ML20202J690
| ML20202J690 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 02/04/1999 |
| From: | Warren C WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20202J698 | List: |
| References | |
| WO-99-0004, WO-99-4, NUDOCS 9902090213 | |
| Download: ML20202J690 (9) | |
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WQLF CREEK , NUCLEAR OPERATING CORPORATION Clay C. Warren
= Vice President & Chief Operating Officer FEB 4 1999 WO 99-0004 U. S.-Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop: Pl-137 Washington, D. C. 20555 -
Subject:
Docket No. 50-482: Changes to Wolf Creek Generating Station (WCGS) Radiological Emergency Response Plan and Implementing Procedures Gentlemen:
i In accordance with 10 CFR 50.54 (q) and 10 CFR 50, Appendix E, enclosed is a !
revision to the Wolf Creek Generating Station " Radiological Emergency Response Plan (RERP)," now AP 06-002, Revision 0. The RERP has been reformatted into the WCGS standard procedure numbering system with this revision, and was l effective January 5, 1999. The previous Emergency Action Levels (EAL) forms l are superseded by the new EAL form, APF 06-002-01, Revision 0, also effect3ve j January 5, 1999. This form should be filed with the RERP, as it is a form to l the RERP. Attachment I in this submittal is a change summary for the hERP, AP l
.06-002, Revision O.
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p Attachment II provides a list of emer gency plan implementing procedures and forms which were. revised or deleted on January 5, 1999, or as noted. ]
7 If you have any questions cor.cerning this submittal, please contact me at (316) 364-4048, or Mr. Michael J. Angus at (316) 364-4077.
Very truly yours, .
Cla C. Warren
.CCW/rlr Attachments Enclosure cc: W. D. Johnson (NRC), w/a l E. W. Merschoff I.NRC ) , w/a, w/e (2)
K. M. Thomas (NRC), w/a, w/e Senior Resident Inspector (NRC), w/a -[g
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Region IV Plant Support Branch Chief (NRC), w/a, w/e 1
9902090213 990204 +
PDR ADOCK 05000482 / '
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, PO. Box 411 / Burkngton. KS 66839 / Phone: (316) 364-8831 -
- An Equal Opporturuty Employer M F HC VET I
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Attachmsnt I to WO 99-0004. 1 ;
iW Page 1 of 2.
*- AP 06 002, Revision 0 i Radiological meergency Response Plan (Rr.RP) f Summary of Changes !
This attachment summarizes changes made to.the WCNOC Radiological Emergency Response. Plan (RERP) that were implemented between January 5 and January 19, ,
1999. These changes provide for a more efficient implementation of the RERP -
by. .the'~ emergency: response organization.
. Certain of these changes were
. determined by . Wolf Creek to require NRC approval prior to their ,
implementation. ' These. changes were submitted to the NRC by letter dated i September 18, 1998, = and subsequently. approved by the NRC by letter dated November 17, 1998. !
The RERP has been reformatted, consistent with the format requirements of the Wolf Creek Generating Station, " Procedure Writers. Guide," AP 15C-004. The previous RERP has been superseded by procedure AP 06-002, " Radiological.
- Emergency Response Plan," (RERP), Revision O. Information provided in several ,
sections of the previous RERP has been consolidated into the new BERP. The ;
generic . summaries and overviews . have been deleted. The new RERP format ;
contains a Table of Contents, Attachments, Figures, and proceduro section for l contents, which follow the recommendations of NUREG 0654. ,
The major changes to the content of the RERP are as follows:
- Position titles changed throughout the RERP for new Emergency Response !
Organization (ERO) implamentation. The title changes better define the -
function for each posi*,1on when discussing events with off-site agencies.
- Positions performing the same functions in the Technical Support Center i (TSC) and Emergency Operations Facility (EOF) have been given the same title and will be cross trained to allow personnel to fill positions in ;
either facility. !
- :Certain functions were moved to positions better suited to perform the j functions. The required functions are still being performed, and .the l changes will make the organization more efficient in their implementation 1 of the RERP. i l
The Emergency Classification level for activation of the EOF was changed from !
"SAE or higher" to " Alert or higher " Concurrent' activation of the facilities !
eliminates. concerns with deployment of teams and dose assessment, and '
eliminates the need for duplication of certain functions. For example,;the ;
Emergency Notifications System (ENS) Communicator position at the EOF was eliminated, since the redundant position remains in the TSC, the TSC facility is activated at the same time as the EOF, and plant related data originates in -
the TSC. Similarly, the Heath Physics Network (HPN) communicator position ;
located in the TSC was eliminated, since the radiological data processing +
originates with the EOF, and the EOF HPN position is activated concurrently.
The . functions of these two communicator positions are being performed as ,
recommended in NUREG 0654 and are located in the facilities that can best i provide necessary information to the NRC in the event of an emergency.
Dose Assessment has been moved from the TSC to the EOF because the off-site monitoring is' performed and controlled from that facility. The Dose ,
' Assessment function is started and performed from the EOF. This change j reduces the number . of persons required for the ERO specific positions and ;
allows for better use of' experienced persons in the locations needed for other i radiation monitoring.
l: The. title of Wolf Creek Lake (WCL) was changed to Coffey County Lake (CCL) in l the.RERP. -
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- Vice President Plant Operations was changed to Plant Manager in the RERP due ;
i to earlier organization changes. 'This change provides consistency between the RERP and the Updated Safety Analysis Report.
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, Attachment I to WO 99-0004 2 Page 2 of 2 ie Emergency Action Levels (EALs) have been relocated to form APF 06-002-01, Revision 0, associated to the RERP. To assure that proper regulatory evaluations continue, a comreitment has been included in the RERP commitment section to require an Unreviewed Safety Question Determination and a 50. 54 (q) evaluation to be performed for each change to the EAL form.
The EAL flow charts, Form APF 06-002-01, have four minor changes:
Box 1-RER5 deleted a reference to the Nuclear Plant Information System display and changed from information located on a form to information located in the EAL bases.
- Box 2-SGTF9 changed the "NO result" from "No Action This Category" to "NUE." This change ensures a small Steam Generator (S/G) tube leak will be declared on the SGIR chart.
- Box 3-LRCB1, laat asterisk added "fexcept S/G tube leakage)." The statcment is added to separate S/G tube leakage and Reactor Coolant (RCS) leakage, as S/G leakage should be declared on the SGTR chart.
- Box 10-FR2 added " Hot Machine Shop." The Hot Machine Shop is added because it is connected to the Auxiliary Building, and the NUMARC EAL bases states l connected buildings should be identified in the EAL chart. )
i None of these changes reduce the effectiveness of the EALs. The Bases part of the form was revised to reflect procedure number changes as a res"It of l writer's guide requirements and ERO title changes due to new ERO l implementation.
l Technical Logkeepers and Communicators titles were changed to Administrative l l Assistants. '
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! The Wolf Creek Spokesperson title was changed to the Pubic Information Officer (PIO), and the former PIO position was changed to Public Information Manager (PIM). The new PIO has overall responsibility for the Public Information Organization and the PIM ensures the facilities are activated and function in accordance with procedure.
l This revision did not change the wording of the four non-delegatable duties of the Emergency Managers. The Emergency Managers may not delegate the duties; however, these duties may be divided between the Emergency Managers.
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, Attach:nent II to WO 99-0004 .
Page 1 of 6 Unless otherwise noted, all revisions occurred on January 5, 1999.
1 Control Room Emergency Preparedness Procedures and Forms l
Current l
EPP 06-001, CONTROL ROOM OPERATIONS !
EPF 06-001-01, NOTIFICATION OF UNUSUAL EVENT EMERGENCY ANNOUNCEMENT EPF 06-001-02, ALERT EMERGENCY ANNOUNCHENT l i
EPF 06-001-03, SITE AREA EMERGENCY ANNOUNCEMENT I EPF 06-001-04, GENERAL EMERGENCY ANNOUNCEMENT EPF 06-001-05, RECOVERY / TERMINATION ANNOUNCEMENT EPF 06-001-06, ENS cot +1UNICATOR' S WORKSHEET Deleted / Superseded EPP 01-1.0, CONTROL ROOM ORGANIZATION EP 01-1.0-1, SHIFT SUPERVISOR TASK LIST EP 01-1.0-5, HEALTH PHYSICS TECHNICIAN TASK LIST EP 01-1.0-6, CHEMISTRY TECHNICIAN TASK LIST EP 01-1.0-7, OFFSITE COMMUNICATOR TASK LIST EP 01-1.0-8, NUE ANNOUNCEMENT EP 01-1.0-9, ALERT ANNOUNCEMENT EP 01-1.0-10, SITE AREA EMERGENCY ANNOUNCEMENT ED 01-1.0-11, GENERAL EMERGENCY ANNOUNCEMENT EP 01-1,0-12, RECOVERY / TERMINATION ANNOUNCEMENT EP 01-1.0-13, CONTROL ROOM ENS COMMUNICATOR' S TASK LIST EP 01-1.0-14, ENS COMMUNICATOR' S WORKSHEET TSC Emergency Preparedness Procedures And Forms Current EPP 06-002, TECHNICAL SUPPORT CENTER OPERATIONS EPF 06-002-01, EMERGENCY MANAGER TURNOVER SHEET EPF 06-002-02, OPERATIONS STATUS EPF 06-002-03 SEQUENCE OF EVENTS Deleted / Superseded EPP 01-1.1, TSC/OSC ORGANIZATION EP 01-1.1-3, DUTY EMERGENCY DIRECTOR' S TASK LIST l EP 01-1.1-4, MAINTENANCE EMERGENCY COORDINATOR' S TASK LIST '
EP 01-1.1-5, OPERATIONS EMERGENCY COORDINATOR'S TASK LIST EP 01-1.1-6, RADIOLOGICAL EMERGENCY COORDINATOR' S TASK LIST EP 01-1.1-7, ADMINISTRATIVE EMERGENCY COORDINATOR'S TASK LIST i EP 01-1.1-8, OPERATIONS ASSESSMENT COORDINATOR'S TASK LIST EP 01-1,1-9, TSC OPERATIONS STATUS RECORDER TASK LIST EP 01-1.1-10, ENGINEERING COORDINATOR'S TASK LIST EP 01-1.1-11, TSC ENS COMMUNICATOR' S TASK LIST EP 01-1.1-12, ONSITE SURVEY TEAM DIRECTOR' S TASK LIST I
EP 01-1.1-13, TSC FIELD TEAM COMMUNICATOR'S TASK LIST ;
EP 01-1.1-14, TSC RADIOLOGICAL STATUS RECORDER'S TASK LIST :
f EP 01-1.1-15, DOSE ASSESSMENT COORDINATOR'S TASK LIST I
( EP 01-1.1-16, TSC EDCP OPERATOR' S TASK LIST
! EP 01-1.1-17, HPN COMMUNICATOR' S TASK LIST l
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. Attachment II to WO 99-0004
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i<i ;EP 01-1.1-18, TSC COMMUNICATOR'S TASK LIST 1
.EP 01-1.1-19, TSC ACCOUNTABILITY CLERK'S TASK LSIT '
EP 01-1.1-20,. TSC CLERK LOGKEEPER'S TASK LIST 1 EP 01-1.1-21, OSC SUPERVISOR'S TASK LIST i EP 01-1.1-22, EMERGENCY PLANNER' S TASK LIST EP.01-1.1-23, TSC ENGINEERING TEAM'S TASK LIST i EPP 01-4.1,.TSC/OSC ACTIVATION !
EP 01-4.1-2, OEC'S TSC/OSC ACTIVATION TASK LIST EP 01-4.1-3, REC' S . TSC/OSC ACTIVATION TASK LIST l j
EP 01-4.1-4, AEC'S TSC/OSC ACTIVATION TASK LIST '
EP 01-4.1-5, DED'S TSC/OSC ACTIVATION TASK LIST EP 01-4.1-6, MEC' S TSC/OSC ACTIVATION TASK LIST ;
EP 01-11.2-2, OPERATIONS STATUS '
EP 01-11.2-7, SEQUENCE OF EVENTS )
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EOF Emergency Preparedness Procedures And Forms _
l Current EPP 06-003, EMERGENCY OPERATIONS FACILITY OPEEATIONS EPF 06-003-01, RADIOLOGICAL STATUS Deleted / Superseded EPP 01-1.2, EMERGENCY OPERATION FACILITY ORGANIEATION EP 01-1.2-3, DUTY EMERGENCY MANAGER'S TASK LIST EP 01-1.2-4, TECHNICAL ADVISOR'S TASK LIST EP 01-1.2-5, RADIOLOGICAL ASSESSMENT MANAGER'S TASK LIST EP 01-1.2-6, ADMINISTRATIVE RESOURCE MANAGER' S TASK LIST EP 01-1.2-7, DOSE ASSESSMENT SUPERVISOR'S TASK LIST EP 01-1.2-8, RADIOLOGICAL ASSESSMENT SUPERVISOR'S TASK LIST EP 01-1.2-9, EOF EDCP OPERATOR'S TASK LIST EP 01-1.2-10, EOF FIELD TEAM COMMUNICATOR'S TASK LIST EP 01-1.2-11, EOF COMMUNICATOR'S TASK LIST EP 01-1.2-12, EOF ADMINISTRATIVE ASSISTANT *S TASK LIST FP 01-1.2-13, EOF OPERATIONS STATUS RECORDER' S TASK LIST EP 01-1.2-15, EOF COORDINATOR'S TASK LIST EP 01-1.2-16, EOF HPN COMMUNICATOR' S TASK LIST EP 01-1.2-17, EOF ENS COMMUNICATOR'S TASK LIST EP 01-1.2-18, TECHNICAL LOGKEEPER'S TASK LIST EP 01-1.2-19, REPRESENTATIVE AT THE COUNTY'S TASK LIST EPP 01-4.3, EMERGENCY OPERATIONS FACILITY ACTIVATION EP 01-4.3-2, EOF COORDINATOR'S ACTIVATION TASK LIST EP 01-4.3-3, DUTY EMERGENCY MANAGER' S ACTIVATION TASK LIST EP 01-4. 3-4, ADMINISTRATIVE RESOUCRE MANAGER' S ACTIVATION TASK LIST EP 01-4.3-5, RALIOLOGICAL ASSESSMENT MANAGER'S ACTIVATION TASK LIST EP 01-4.3-6, TECHNICAL ADVISOR' S ACTIVATION TASK LIST i EP 01-4.3-10, DUTY EMERGENCY MANAGER' S AEOF ACTIVATION TASK LIST l EP 01-4.3-11, TECHNICAL ADVISOR'S AEOF ACTIVATION TASK LIST l EP 01-4.3-12, RADIOLOGICAL ASSESSMENT MANAGER'S ACTIVATION TASK LIST EP.01-4.3-13, ADMINISTRATIVE RESOURCE MANAGER' S AEOF ACTIVATION TASK LIST l EP 01-4.3-14, EOF COORDINATOR'S AEOF ACTIVATION TASK LIST l l EP 01-4.3-15, DOSE ASSESSMENT SUPERVISOR'S AEOF ACTIVATION TASK LIST i i EP 01-4.3-16, RADIOLOGICAL ASSESSMENT SUPERVISOR' S AEOF ACTIVATION TASK LIST I l EP 01-4.3-17, EOF EDCP OPERATOR' S AEOF ACTIVATION TASK LIST I l EP 01-4.3-18, EOF FIELD TEAM COMMUNICATOR' S AEOF ACTIVATION TASK LIST ,
i EP 01-4.3-19, EOF COMMUNICATOR'S AEOF ACTIVATION TASK LIST l 3
'EP 01-4.3-20, EOF ADMINIS2RATIVE ASSISTANT'S AEOF ACTIVATION TASK LIST l j EP 01-4.3-21, EOF OPERATIONS STATUS RECORDER'S AEOF ACTIVATION TASK LIST l EP 01-4.3-22, EOF HPN COMMUNICATOR' S AEOF ACTIVATION TASK LIST EP 01-4.3-23, EOF ENS COMMUNICATOR'S AEOF ACTIVATION TASK LIST ,
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, Attachment II to WO 99-0004 Page 3 of 6 F EP 01-4.3-24, TECHNICAL LOGKEEPER'S AEOF ACTIVATION TASK LIST l EP 01-4.3-25, OFFSITE SURVEY TEAM TECHNICIAN'S AEOF ACTIVATION TASK LIST l EP 03-4.3-26, EMERGENCY PLANNER' S AEOF ACTIVATION TASK LIST EP 01-11.2-3, RADIOLOGICAL STATUS Current l'
l EPP 06-004, PUBLIC INFORMATION ORGANIZATION, Rev 2 EPF 06-004-01, PUBLIC INFORMATION ORGANIZATION ACTIVATION CHECKLIST EPF 06-004-02, MEDIA REGISTRATION LOG EPF 06-004-03, NEWS STATEMENT DISTRIBUTION LOG EPF 06-004-04, PHONE TEAM LOG EPF 06-004-05, PUBLIC INFORMATION KCPL RUMOR CONTROL ACTIVATION EPF 06-004-06, RUMOR CONTROL LOG
'EPP 06-005, EMERGENCY CLASSIFICATION Deleted
- EPP 01-2.1, EMERGENCY CLASSIFICATION Current EPP 06-006, PROTECTIVE ACTION RECODMENDATIONS Deleted EPP 01-10.1, PROTECTIVE ACTION RECOMMENDATIONS Current i EPP 06-007, EMERGENCY NOTIFICATIONS (Supplement I/I9/99)
EPF 06-007-01, WOLF CREEK GENERATING STATION EMERGENCY NOTIFICATION EPP 06-008, RE-ENTRY,' RECOVERY AND TERMINATION OPERATIONS Deleted EPP 01-12.1, RECOVERY OPERATIONS ,
EP 01-12.1-3, RADIOLOGICAL EMERGENCY COORDINATOR' S RECOVERY RESPONSIBILITIES l LIST j EP 01-12.1-4, DUTY EMERGENCY MANAGER RECOVERY TASK LIST !
EP 01-12.1-5, TECHNICAL ADVISOR RECOVERY TASK LIST EP 01-12.1-6, RADIOLOGICAL ASSESSMENT MANAGER RECOVERY TASK LIST EP 01-12.1-7, ADMINISTRATIVE RESOURCE MANAGER RECOVERY TASK LIST ,
EP 01-12.1-8, DUTY EMERGENCY DIRECTOR RECOVERY TASK LIST l l
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< i Attachment II to WO 99-0004 i Page '4 ' of" 6 !
'- Current, l .EPP-06-010, PERSONNEL ACCOUNTABILITY.AND EVACUATION
, EPF 06-010-01,' ACCOUNTABILITY LOG l <
EPF 06-010-02,- SECURITY E-PIAN RESPONSIBILITIES CHECKSHEET l
l' t Deleted i 1 !
EPP 01-6.1, PERSONNEL ACCOUNTABILITY AND EVACUATION !
EP 01-6.1-1, ACOUNTABILITY LOG EP 01-6.1-2, SECURITY E-PLAN RESPONSIBILITIES CHECKSHEET t
l' L Current l
EPP 06-011, EMERGENCY TEAM FORMATION AND CONTROL l EPF 06-011-01, PLANT TEAM BRIEF
( EPF 06-011-02, FIELD TEAM BRIEF EPF 06-011-03, AIRBORNE RADIOACTIVITY CALCULATION 1
l EPF 06-011-04, RADIOLOGICAL MONITORING LOG i EPF 06-011-05, TENH DEBRIEF l
l Deleted EP 01-8.2-1, AIRBORNE RADIQACTIVITY CALCULATIONS EP 01-8.2-3, RADIOLOGICAL SAMPLE INVENTORY LOG EP 01-8.2-8, FIELD TEAM MESSAGE FORM EP 01-9.4-1, EMERGENCY TEAM BRIEFING CHECKLIST EP 01-9.4-2, DEBRIEFING CHECKLIST EP 01-9.4-8, REPAIR TEAM BRIEF EPP 01-8.2, OFF-SITE RADIOLOGICAL MONITORING EPP 01-9.4, ERDC/SEACH & RESCUE TEAM FORMATION l
l Current EPP 06-012, DOSE ASSESSMENT Deleted
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EPP 01-7.2, COMPUTER DOSE CALCULATION Current EPP 06-013, EXPOSURE CONTROL AND PERSONNEL PROTECTION I EPF 06-013-01, EMERGENCY EXPOSURE TRACKING LOG l EPF 06-013-02, EMERGENCY EXPOSURE AUTHORIZATION j EPF 06-013-03, THYROID DOSE EQUIVALENT WORKSHEET EPF 06-013-04, POTASSIUM IODIDE ISSUE RECORDER I-l Deleted EP 01-9.1-2, EMERGENCY EXPOSURE AUTHORIZATION 1 EP 01-9.1-4, EMERGENCY TRACKING LOG EP 01-9.3-1, POTASSIUM IODIDE ISSUE RECORD .
', EP 01-9.3.2, THYRIOD DOSE EQUIVALENT WORKSHEET EPP 01-9.1, EXPOSURE CONTROL AND PERSONNEL PROTECTION EPP 01-9.3, RADIOPROTECTIVE DRUGS u
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-f Attachment II to WO 99-0004
-Page 5 of 6 Current EPP 06-015, EMERGENCY RESPONSE ORGANIZATION CALLOUT EPF 06-015-01,. EMERGENCY RESPONSE ORGANIEATION CALLOUT LOG
-EPF 06-015-02, EMERGENCY CALLOUT MESSAGE Deleted EPP 01-13.1,. EMERGENCY RESPONSE ORGANIZATION CALLOUT EP 01-13.1-1, NON-RESPONDING EMERGENCY COMMUNICATORS (NRECs) CALLOUT TASK LIST EP 01-13.1-2,- EMERGENCY RESPONSE ORGANIZATION ACTIVATION LOG EP 01-13.1-3, EMERGENC'l RESPONSE ORGANIZATIONMANUAL CALLOUT LOG EP 01-13.1-4,. COMPUTER CALLOUT TASK LIST EP 01-13.1-5, EMERGENCY CALLOUT MESSAGE Currep1 EPP 06-016, ACCIDENT ASSESSMENT AND MITIGATION Deleted EPP 01-2.3, ACCIDENT ASSESSMENT AND MITIGATION Current EPP 06-017, CORE DAMAGE ASSESSMENT METHODOLOGY EPF 06-017-01, CORE DAMhGE ASSESSMENT CALCUIATIONS Deleted EPP 01-2.4, CORE DAMAGE ASSESSMENT METHODOLOGY Current EPP 06-021, TRAINING PROGRAMS Deleted EPP 02-1.2, TRAINING PROGRAMS f
Current EPP 06-022, TONE ALERT RADIO MAINTENANCE / COMPENSATING MEASURES Deleted i
EPP 02-1.7, TONE ALERT RADIO MAINTENANCE / COMPENSATING MEASURES EPP 01-11.2, STATUS BOARDS / Ret 9 j EP 01-11.2-5, TEAM ASSIGNMENTS / Rev 1 EP'01-11.2-6, SURVEY INFORMATION / Rev 1 EPP 02-1.4, MAINTENANCE OF WCGS EMER PI PROGRAM / Rev 8 l l l-i
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Attachment II to WO 99-0004
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APF 06-002-01, EMERGENCY ACTION LEVELS Deleted RADIOLOGICAL EMERGENCY RESPONSE PLAN (RERP) )
EP 01-2.1-1, EMERGENCY ACTION LEVELS '
EP 01-2.1-3, EALs EXPLANATIONS / BASES EP 01-2.1-4, AREA RAD MONITORS AVERAGE i i
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Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLRN AP 06-002 I (RERP) e Reference Use Page 1 of 83 m
C TABLE OF CONTENTS SECTION TITLE PAGE 1 4
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A 1.0 PURPOSE 3 !
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2.0 SCOPE 3
3.0 REFERENCES
AND COMMITMENTS 4 4.0 DEFINITIONS f 5.0 RESPONSIBILITIES 6.0 PRCCEDURE 5
9 11 i
] 6.1 Site Description 11 6.2 Emergency Classifications l 12 ;
6.3 Emergency Measures 13 1 6.4 Emergency Facilities 17 l 6.4.1 Control Room Facilities 17 6.4.2 Technical Support Center Facilities 17 6.4.3 Operations support Center 19 6.4.4 Emergency Operations Facility (EOF) 19 6.4.5 Public Information Facilities 20 6.4.6 Onsite Medical Facility 21 6.4.7 State and County Facilities 22 6.5 Control Room Organization 23 6.6 Technical Support Center (TSC) Organization 24 6.7 Operations Support Center (OSC) Organization 29 ;
6.8 Emergency Operations Facility (EOF) Organization 29 6.9 Public Information Organization 33 6.10 Local Offsite Organizations 36 ,
6.10.2 Coffey County Commissioners 37 l 6.10.3 Coffey County Sheriff's Office 37 6.10.4 Coffey County Fire District #1 (CCFD) 38 6.10.5 Off-site Medical Treatment 38 6.10.6 Coffey County Ambulance Service 39 l 6.10.7 Radiological Emergency Assistance Center / Training Site (REAC/TS) 39 i 6.11 State Organizations 39 6.11.3 Kansas Division of Emergency Management (KDEM) 40 6.11.4 Kansas Department of Health and Environment (KDHE) 40 6.11.5 Kansas Highway Patrol (KHP) 41 6.11.6 Kansas National Guard 41 6.11.7 Kansas Department of Transportation (KDOT) 42 6.12 Federal Organizations 42 6.12.2 Federal Emergency Management Agency (FEMA) 42 '
6.12.3 Department of Energy (DOE) 42 6.12.4 Nuclear Regulatory Commission (NRC) 42 6.13 Additional Support Agencies 43 6.13.1 Vendor and Architect / Engineers (A/E) 43 6.13.2 Regional Utility Support 43 6.13.3 Institute of Nuclear Power Operations (INPO) 44 6.13.4 American Nuclear Insurers (ANI) 44 6.14 Plant Monitoring 44 6.14.1 Nuclear Plant Information System (NPIS) 44 6.14.2 Onsite Radiological Monitors 45 6.14.3 Meteorological Monitoring System 46
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6.14.4 Seismic Monitoring System 46 !
6.14.5 Hydrologic Monitoring 46 I f 6.14.6 Fire Protection 46
} 6.14.7 Laboratory Facilities 6.15 Emergency Supplies 46 g 47 s 6.16 Communications 47 2 6.16.1 Communication Equipment 47 g- 6.16.2 Communication Dissemination 48 6.17 Emergency Plan Training 49 6.18 Emergency Plan Drills 49 6.19 Emergency Planning Exercises 50 6.20 Emergency Plan And Procedures Administrative Controls 51 6.21 Recovery Plan 52 7.0 RECORDS 53 8.0 FORMS 53 ,
ATTACHMENT A EFFECTIVE 10-MILE EPZ POPULATION CENTERS 54 ATTACHMENT B SUBZONE EVACUATION TIMES 55 ATTACHMENT C CROSS REFERENCE BETWEEN NUREG 0654, RERP, AND WCGS PROCEDURES 58 ;
ATTACHMENT D WCGS MINIMUM STAFFING FOR EMERGENCIES 66 l ATTACHMENT E EPA / KANSAS PROTECTIVE ACTION GUIDES 67 !
ATTACHMENT F USAR CHAPTER 15 POSTULATED EVENTS 71 ATTACHMENT G LETTERS OF AGREEMENT 72 ATTACHMENT H REPORTING OF INCIDENTS PER 10 CFR 20 73 l FIGURE 1 EFFECTIVE 10 MILE EPZ, SUBZONES AND EVACUATION ROUTES 74 FIGURE 2 MINIMUM SHIFT COMP.LEMENT 75 FIGURE 3 TSC/OSC ORGANIZATION 76 FIGURE 4 EOF ORGANIZATION 77 FIGURE 5 PUBLIC INFORMATION ORGANIZATION 78 i FIGURE 6 EMERGENCY ORGANIZATIONS INTERFACES 79 l FIGURE 7 WCGS EMERGENCY RESPONSE FACILITIES 80 FIGURE 8 DIRECT RADIATION PATHWAY SAMPLING LOCATIONS 81 FIGURE 9 WATERBORNE PATHWAY SAMPLING LOCATION 82 FIGURE 10 FIXED SIREN SIGHTING 83 i
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U 1.O PURPOSE
, 1.1 The purpose of the Wolf Creek Generating Station (WCGS) l }, Radiological Emergency Response Plan (RERP) is to classify g emergencies, assign responsibilities for actions, and to g
establi.,h the lines of authority and communications to protect
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l the public and plant personnel in the event of an emergency.
U g 2.0 SCOPE d 2.1 The RERP has been developed in accordance with 10CFR Part 50, Paragraph 50.47 and Appendix E, Regulatory Guide 1.101 and generally follows the guidelines of NUREG 0696 and 0654. The RERP is sensitive to a broad spectrum of emergency conditions j
which have been postulated for a commercial pressurized water reactor. Although the probability of an accident is low, the RERP is maintained to assure the safety and well-being of plant personnel and members of the public in the vicinity of WCGS.
l 2.2 The RERP interfaces with several related documents such as the Administrative Procedures (APs) and Emergency Plan Procedures (EPPs). Detailed instructions necessary to support the RERP are included in these procedures.and are available for training, drill, and actual emergency use. The RERP references the WCGS Fire and Security Plans, Vendor contingency plans as well as j those of medical support facilities and the Institute of Nuclear Power Operations (INPO). This document has been designed to coordinate with the State Emergency Operations Plan and the Coffey County Contingency Plan for Incidents Involving Commercial Nuclear Power, which govern the activities of these support groups in response to events at WCGS.
2.3 The RERP is based on a graduated, escalating level of emergency response which is activated as conditions at the plant warrant.
This approach provides the flexibility necessary to ensure adequate emergency response to a spectrum of possible events.
The RERP is designed to control emergency response activities ranging from initial event detection, classification of the event, notification of off-site authorities and providing protective action recommendations to the county and state.
! 2.4 The RERP reflects three chief phases of activation. First the
! response is dominated solely by the site staff, next the onsit'e i
and off-site public information facilities are jointly activated, and finally the recovery efforts are performed by j
site, public information facilities, vendor, and other critical support groups.
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2.5 The WCGS normal operating organization and its functional responsibilities are described in the WCGS Technical Specifications, Administrative Procedures, Human Resources o [
company organization charts and the WCGS Updated Safety "snalysis i
- p. Report (USAR). No further discussion of the normal operating i ' organization is contained within the RERP. i g 2.6 The WCGS design bases accidents and various plant systems are
, x listed and described in the WCGS Technical Specifications and !
USAR. No further discussion of these accidents or systems is i (c - contained within the RERP.
l 3.O REFERENCES AND CChe(ITMDTTS
- 3.1 References t
3.1.1 Coffey County Contingency Plan for Incidents Involving !
l Commercial Nuclear Power (County Plan) 3.1.2 State of Kansas, Appendix 12, Nuclear Facilities Incidents Response Plan to Annex N, Nuclear Emergencies 1
of the State Emergency Operations Plan (State Plan) l l 3.1.3 Updated Safety Analysis Report (USAR)
! 3.1.4 NUREG 0654, Criteria For Preparation And Evaluation Of Radiological Emergency Response Plans And Preparedness I In Support Of Nuclear Power Plants i 1
3.1.5 NUREG 0696, Functional Criteria For Emergency Response Facilities >
3.1.6 NUREG 0737, Clarification Of TMI Action Plan l Requirementa l \
l 3.1.7 Title 10, Code Of Federal Regulations, Part 50 '
3.1.8 Regulatory Guideline 1.101 3.1.9 Regulatory Guide 1.145 3.2 Commitments 3.2.1 RCMS #93-325, Emergency Action Levels Converted To NUMARC EALs 3.2.2 APF 06-002-01, EMERGENCY ACTION LEVELS, required to have a USQD and a 50.54 (g) review performed for each revision.
3.2.3 RCMS #96-076, Administrative EAL Changed To Reflect NUMARC/NESP-007 Definitions 4
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C 3.2.4 RCMS #96-077, System Malfunction EAL Changed To Provida Better Guidance For Loss Of Equipment Needed In Modes
, One Through Four 2
g 3.2.5 RCMS #96-078, Natural Phenomena EAL Changed To Cover
\ Ice And Other Natural Occurrences Which Could Impact Safety Systems tJ g 4.0 DEFINITIONS h 4.1 Administrative Procedures (APs) 4.1.1 Procedures which provide programmatic responsibilities and are typically used to solve problems, assemble documentation, process information, and present results of administrative functions.
4.1.2 Administrative procedures control activities affecting quality or nuclear safety.
4.2 As Low As Reasonably Achievable (ALARA) 4.2.1 Making every reasonable effort to maintain exposures to radiation as far below dose limits as is practical, consistent with the purpose for which the licensed activity is undertaken, taking into account the state of technology, the economics of improvements in relation to benefits to the public henith safety, and other societal and socioeconomic considerations.
4.3 Alert 4.3.1 Events are in process or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant. Any releases are expected to be limited to small fractions of the Environmental Protection Agency (EPA) Protective Action Guideline (PAG) exposure levels.
4.4 Assessment Actions 4.4.1 Those actions taken during or after an accident to obtain and process information that is necessary to make decisions to implement specific emergency measures.
4.5 Coffey County Emergency Operations Center (County EOC) 4.5.1 The base of operations for the Coffey County Emergency Response Organization.
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C 4.6 Consultant / Vendor n 4.6.1 The Nuclear Steam System Supplier (NSSS),
7 Architect / Engineer, and other organizations who have available multidiscipline teams ready to support g emergency response and Recovery Operations. )
h 4.7 Control Room
_ 4.7.1 The location at the WCGS from which the reactor and its g auxiliary systems are normally controlled. l 4.8 Drill l
4.8.1 A supervised activity used to develop and maintain j skills. On the spot correction of erroneous !
performance is permitted.
4.9 Emergency Action Levels (EALs) 4.9.1 Radiological dose rates; specific contamination levels of airborne, waterborne or surface-deposited 1 concentrations of radioactive materials; or specific i instrument indications that may be used as thresholds for designating a particular class of emergency.
4.10 Emergency Alert System (EAS) 4.10.1 A coordinated network of broadcasters (e.g. Radio, Television, Cable) that allows the President to address the nation, Governors to address their State and public i safety officials to address local citizens with i emergency information. ;
4.11 Emergency Classification 4.11.1 A system used to define the severity of emergencies into one of four categories based upon projected or confirmed emergency action levels. Classifications listed in order of increasing severity are Notification of Unusual Event (NUE), Alert, Site Area (SAE) and General Emergency (GE).
4.12 Emergency Operations Facility (EOF) 4.12.1 This facility serves as a base of operations for all l emergency plant support activities, site environmental surveillance, communications with supporting agencies, and the WCGS Emergency Organization.
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4.13 Emergench Plan Procedures (EPPs) n 4.13.1 Specific procedures providing step-by-step actions to
} implement the WCGS Radiological Emergency Response and g Recovery Plans, and to provide guidance to improve or g terminate an emergency situation.
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[ 4.14 Evacuatian Registration Centers !
I i; 4.14.1. Facilities designated for receiving personnel m evacuating the Emergency Planning Zone (EPZ) for :
accountability, contamination monitoring and !
decontamination.
1 4.15 Exclusion Area 4.15.1 That area within a 1200-meter radius of the Containment Building in which WCGS has the authority to determine all activities including exclusion or removal of persons and property from the area.
l 4.16 Executive Management 4.16.1 Those members of WCGS management at the vice president level and above.
4.17 Exercise 4.17.1 An event that simulates a radiological emergency condition, incorporates the integrated capability of the basic elements existing within the Radiological Emergency Response Plan (RERP). These events are normally evaluated by FEMA / NRC.
4.18 General Emergency (GE) 4.18.1 Events are in process or have occurred which involve actual or imminent substantial core degradation with potential for loss of containment integrity. Releases can reasonably be expected to exceed EPA Protective Action Guideline exposure levels off-site for more than the immediate site area.
4.19 Immediate Notification 4.19.1 Notification made to State of Kansas and Coffey County authorities within 15 minutes of a declared emergency at WGCS.
4.20 Information Clearinghouse (IC) 4.20.1 The facility where news statement and news conference materials for the media are prepared.
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! 4 21 Kansas State Emergency Operations Center (State EOC) 1 l'
, 4.21.1 The command-and-control center for the state. 1
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4.22 Licensed Operators 4.22.1 l WCGS Reactor Operators and Senior Reactor Operators who y
are licensed under 10CFR55 and who stand watches on x shift and report to the Shift Supervisor.
$3 4.23 Media Center (MC) i 4.23.1 Facility utilized as a focal point for giving information to the media through news conferences.
4.24 Notification of Unusual Event 4.24.1 Events in process, or have occurred, which indicate a potential degradation of the level of safety of the i plant. No releases of radioactive material requiring I off-site response or monitoring are expected unless further degradation of safety systems occurs.
4.25 Off-site l
4.25.1 Any area outside the Exclusion Area of WCGS.
4.26 Onsite 4.26.1 Any area inside the Exclusion Area of WCGS. l i
4.27 Operations Support Center (OSC) 4.27.1 A staging area for emergency teams to support the emergency response effort.
1 4.28 Protective Actions !
1 4.28.1 Those emergency measures taken before or after a release of radioactive material has occurred for the purpose of preventing or minimizing radiological exposures to personnel.
4.29 Protective Action Guides (PAGs) l 4.29.1 Guides promulgated by the Environmental Protection
! Agency (EPA) which set dose limits for the evacuation of the public during an accident condition at a nuclear i power plant.
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U 4.30 Radiologically Controlled Area (RCA) ,
y 4.30.1 An area to which access is controlled by WCGS for purposes of protection of individuals from exposure to
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radiation or radioactive materials. l l 4.31 Recovery 4.31.1 Post-emergency efforts initiated to restore WCGS to full operation or place the plant in a safe shutdown ;
e condition until full operation can be resumed. I l
4.32 Site Area Emergency (SAE) !
4.32.1 Events are in process or have occurred which involve actual or likely major failures of plant functions needed for protection of the public. Any releases are not expected to result in exposure levels which exceed EPA Protective Action Guideline exposure levels except near the site boundary.
4.33 Technical Support Center (TSC) 4.33.1 The TSC serves as a center outside of the Control Room that acts in support of the command-and-control function and houses the OSC organization. Plant status I and diagnostic information are available at this location for use by technical and management personnel in support of reactor command-and-control functions.
5.0 RESPONSIBILITIES 5.1 Site Emergency Director 5.1.1 Assumes command and control of the emergency and directs onsite response to stabilize plant conditions.
5.2 Off-site Emergency Manager 5.2.1 Assumes command and control of the emergency and interfaces with off-site agencies.
5.3 Superintendent Emergency Planning 5.3.1 Ensures the Emergency Planning Program is implemented and maintained as required to protect the health and safety of the public.
5.3.2 Ensures changes to the overall Emergency Planning Program meets the standards of 10CFR50.47(b) and the requirements of 10CFR50, Appendix E.
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l- Nuclear Safety' Review Committee (NSRC) 5.4.1 Ensures a review of the WCGS Emergency Preparedness 2
Program will be performed at least once every' twelve j months in accordance with 10CFR ' 50.54 (t) . i
_' - President and Chief Executive Officer 5.5 i
N l l g. 5.5.1 Maintains overall authority and responsibility for the !
_ WCGS Emergency Preparedness Program. l
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- 5.6 Public Information Officer (PIO) l l 5.6.1 The PIO has the authority and responsibility for the WCGS Public Information Organization and all plant ,
information disseminated to the media. l l
5.7 shift Supervisor (SS) 1 5.7.1 The Senior Reactor Operator designated by WCGS l management with immediate onsite authority and i responsibility for the safe and proper operation of the i
plant. This position is staffed at all times. The SS !
is responsible for the initial evaluation of any l abnormal or emergency situation and for directing the appropriate response. He assumes. responsibilities of ]1 the Emergency Manager until relieved. I l
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U 6.0 PROCEDURE ,
6.1 Site Description t
6.1.1 WCGS is a Pressurized Water Reactor (PWR) nuclear fl generating station operated by Wolf Creek Nuclear Operating Corporation (WCNOC).
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! g 6.1.2 WCGS'is located near the center of Coffey County, 2 Kansas (KS), about 3.5 miles northeast of Burlington, i g the county seat, 90 miles southwest of Kansas City, MO l and 55 miles south of the state capital Topeka, KS.
I 6.1.3 The immediate site environs are sparsely populated.
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' Burlington and New Strawn are the major population r centers. John Redmond Reservoir (JRR) and Coffey County Lake (CCL) are the major recreational facilities. Most-of the seasonal or daily shifts in population are associated with recreational areas around JRR and CCL. Apprcximately 70% of the annual visitors to the John Redmond Reservoir and Coffey County Lake come to the area during the summer months.
l 6.1.4 Coffey County totally encompasses the 10-mile Plume Exposure Emergency Planning Zone (EPZ) which forms a major consideration in the RERP.
6.1.5 The total population of the effective 10-mile EPZ is shown in ATTACHMENT B, SUBZONE EVACUATION TIMES. With the exception of Burlington and the other population ;
centers listed in ATTACHMENT A, EFFECTIVE 10-MILE '
POPULATION CENTERS, the population density of the effective-10-mile EPZ is approximately 4.4 persons per square mile. Other than the WCGS, there are no large industries in the area.
6.1.6 Principal geographical features within the effective 10-mile EPZ are the Neosho River, JRR, and CCL. The land around WCGS is flat with scattered low hills.
Dense vegetation in the form of large trees exists on the banks of the river and in recreational areas.
There are no topographical features within the effective 10-mile EPZ that significantly influence the design of the Alert and Notification System.
4 1 1. Sparsely populated farm land comprises the majority of the effective 10-mile EPZ.
- 2. The site also demonstrates favorable topography, demography, and meteorology, which have been factored into many analyses that support the emergency planning effort.
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- 3. The Neosho River is oriented northwest-southeast and extends to within 3 miles southwest of the p ant.
- 4. The main dam of the John Redmond Reservoir is 3.5
(; It.les west of the plant. This water conservation pool is approximately 4 miles in diameter with a g
surface area of 15 square miles. i l
2 5. The Coffey County Lake is approximately 7 miles g long with a normal surface area of 8 square miles.
6.1.7 Approximately 99% of the 10-mile EPZ is located within Coffey County and 1% within Anderson County. The EPZ has been defined by developing sub-zones based upon natural and political subdivisions. These have been described for evacuation zones approximating 2, 5 and 10-mile radial rings. This distribution allows ready identification of areas to be evacuated and facilitates
! public recognition of subzones in which they work or i reside. FIGURE 1, EFFECTIVE 10 MILE EPZ, SUBZONES AND
! EVACUATION ROUTES, presents the 2, 5 and 10-mile radial t
zones and subzones which provides the basis for the design of an alert and notification system. l l
6.1.8 The meteorological conditions within the effective 10- )
mile EPZ is characterized by a distinctly continental '
climate with warm humid summers and highly variable winter weather. Maritime tropical air originating over l
the Gulf of Mexico is the dominant air mass from June i through August. This air mass is quite humid resulting i
in considerable thunderstorm activity. From November l through February, continental polar air dominates the climate.
6.2 Emergency Classifications 6.2.1 10 CFR Part 50, Appendix E, Section IV.C, requires a classification scheme of four specific levels of emergencies. NUMARC/NESP 007 is identified within REGULATORY GUIDE 1.101 and is considered by the NRC as an acceptable alternative method to that described in Appendix 1 to NUREG 0654. [ Commitment Step 3.2.1]
i 6.2.2 An emergency class is a qualitative estimate of the status of the plant. Inputs to the emergency classification system include the status of plant systems and the levels of radiation in plant areas and effluents. However, an emergency class does not give a qualitative or quantitative estimate of the subsequent status of the plant or radioactive release.
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6.2.3 The emeror,cy classes are used by off-site authorities to dete~aine the level of preplanned actions to be ,
taken by their emergency organizations. Protective '
,f actions taken on behalf of members of the public are
{ the legal responsibility of state and local government.
- 1. The functional interfaces between WCGS and other y emergency organizations are shown in FIGURE 6, g
EMERGENCY ORGANIZATIONS INTERFACES.
g 6.2.4 The classification system used at WCGS is an approach that ranges from primarily event-based for Unusual '
Event to primarily symptom or barrier-based for General l Emergencies. This is to better assure that timely i recognition and notification occurs, that events j occurring during refueling and cold shutdown are j appropriately covered, and that multiple events can be i effectively treated. The Emergency Action Levels I (EALs) are contained in APF 06-002-01, EMERGENCY ACTION LEVELS. [ Commitment Step 3.2.1] ;
6.3 Emergency Measures 6.3.1 Protective actions to minimize personnel exposure are taken when an incident has occurred, or may occur, 1 which could result in a fission product barrier challenge or breach. In addition, protective actions are taken for personnel onsite for situations such as l fires or flooding, where personnel safety is '
threatened.
i 6.3.2 Emergency measures consist of assessment, corrective, i and protective actions. The Shift Supervisor and '
Senior Reactor Operators assume immediate responsibility for accident assessment and mitigation.
The RERP and detailed emergency actions are based on the assumption that, in an emergency, licensed operators take appropriate measures to maintain or return the facility to a safe condition, in accordance with operating license conditions and the technical specifications.
6.3.3 EPPs provide the mechanism for providing information to state and local authorities for their use in making decisions for ordering off-site protective actions.
6.3.4 Actions to protect the general public, and criteria for their implementation, are described in the State Plan.
' Protective action recommendations are made to the County and State authorities.
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- 1. ATTACHMENT E, EPA / KANSAS PROTECTIVE ACTION GUIDES, illustrates the EPA / Kansas PAGs for members of the
, public in the vicinity of WCGS and contains
, information typical of what may be used for the PAR
{ guidelines. The Attachment provides guidelines and ;
g' action levels to be used to develop protective action recommendations. Actions taken off-site are
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the responsibility of County and State officials.
_ 2. Evacuation is the normally anticipated off-site g protective action. Sheltering may be the preferred protective action when it will provide protection equal to or greater than evacuation. ATTACHMENT B, SUBZONE EVACUATION, contains evacuation times for ;
the gene,ral and transient public. l 6.3.5 Contact points for information concerning the County Plan, protective measures, and special needs of the '
handicapped are the County Emergency Preparedness Office.
6.3.6 Additional resources available for accident assessment include the Post Accident Sampling System, accident monitoring, and in-plant iodine instrumentation under accident conditions. Detailed discussions of these resources and their capabilities are found in the USAR.
I 6.3.7 The Emergency Dose Calculation Program (EDCP) is a I computerized method to provide dose estimates using i actual or estimated meteorological data (wind speed, wind direction, degree of cloud cover, day or night determination) and radiological effluent data (actual measurements, estimated values based upon USAR source terms, or field measurements). EDCP is designed to: l
[ Reference Step 3.1.9]
- 1. Use radiological and meteorological information to provide an estimate of off-site exposure.
- 2. Be capable of estimating release rates and off-site exposures from off-site field team data.
- 3. Be capable of estimating release rates and off-site exposures f3r an unmonitored, pressure driven containment release using the Containment High Area Radiation Monitor readings and changes in containment pressure.
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- 4. Off-site dose predictions when combined with actual release duration information and meteorological data during an event, provide sufficient data to i estimate the cumulative population dose resulting from the event. The actual off-site population
[/ dose is confirmed by off-site monitoring, sampling
) and analysis, f 6.3.8 Radiological monitoring teams have a goal of 60 minutes 2 from the declaration of Alert or greater emergency to g be ready for deployment to confirm effluent readings i and verify plume emission and locations.
6.3.9 FIGURE 7, WCGS EMERGENCY RESPONSE FACILITIES, provides a view of the off-site area, showing the location of the EOF. FIGURE 8, DIRECT RADIATION PATHWAY SAMPLING LOCATIONS, shows the fixed air sampling and TLD {
locations. FIGURE 9, WATERBORNE PATHWAY SAMPLING l LOCATIONS, shows similar information for the critical j receptor bioassay measurements that are taken.
]
1 6.3.10 At an Site Area Emergency, General Emergency, or when accountability is required, all personnel not responding to an Emergency Response Facility report to an assembly area for accountability and additional information. ERO personnel report to their assigned ,
emergency facility. Security reports the results of accountability to the TSC.
6.3.11 If the Exclusion Area is evacuated, then Security shall l c'treet an inspection of the lake and land area within Ine Exclusion Area but outside of the Protected Area to ensure that all personnel not responding to an )
l Emergency Response Facility are evacuated from the Exclusion Area.
6.3.12 WCGS procedures contain decontamination instructions and guidelines. Methods for determining if the individual is a potential inhalation or ingestion contamination case are also provided. The Radiological
- Coordinator or appropriate Health Physics supervisory personnel will review the records generated by l decontamination procedures.
l 6.3.13 Respiratory protective devices and protective clothing are stored at several locations onsite and at the EOF.
The use of protective clothing and respiratory protection equipment is governed by normal WCGS procedures.
6.3.14 A supply of potassina iodide (KI) is maintained at the Control Room, TSC and the EOF to be used in the event that an individual .nay be exposed to radiciodine.
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C 6.3.15 There are suggested levels of exposure to be accepted in emergencies. Immediate reentry may be nececsary to save a life, account for missing personnel, or secure
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vital equipment. The Emergency Managers are ultimately responsible for exposure control and can permit the f receiving of up to 5 REM per person for work i activities, 10 REM for saving valuable equipment and 25 o REM for lifesaving after consulting with the NRC, if
{ feasible. Exposure which might exceed 25 REM, for l 2 lifesaving activities, must be approved by an Emergency g' Manacer. Although EPA and NRC does not provide I specific guidance for the upper bounds for lifesaving l exposure, WCGS has chosen to use the following l criteria: 1
- 1. Emergency Managers shall not knowingly permit an individual's exposure to exceed 25 REM, unless it is for lifesaving activities or protection of large populations. Emergency Managers shall not .
knowingly permit an individual to enter a high dose l area if the projected Total Effective Dose !
Equivalent (TEDE) is expected to exceed 75 REM.
o Those individuals designated to exceed 25 REM must be volunteers and be fully aware of the risks involved.
- 2. Emergency Managers should obtain the advice and concurrence of the Radiological Coordinators in approving additional exposure.
6.3.16 Under emergency conditions, normal exposure controls are maintained. This is ensured by the on-shift Health Physics Technician (HP) in the Control Room, the Team Directors in the TSC and EOF.
6.3.17 The Radiological Coordinator has responsibility for maintaining exposure control for site activities, including establishment of access control at alternate locations. Strict exposure control of individuals passing through the access point is maintained on a 24-hour-per-day basis.
6.3.18 In order to enhance the exposure control process and to
, provide dosimetry for an expanded number of people, l dosimetry vendors are available to expedite shipment of extra dosimetry devices to supplement existing onsite supplies of dosimetry equipment and to supply personnel to assist in onsite appraisal of exposures.
6.3.19 When activated, the Emergency Response Team covers emergency sampling, surveying, analysis, and hazard evaluation.
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- O 6.3.20 The Post Accident Sampling System (PASS) accomplishes automatic, remote-controlled reactor coolant system and containment atmosphere sampling while minimizing j personnel exposure.
f' 6.3.21 Personnel, instruments, and equipment are to be monitored at the access control point. Personnel and equipment decontamination is controlled in accordance l
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[ 6.3.22 WCGS maintains control over the Exclusion Area as necessary, restoring affected onsite areas to acceptable conditions for access.
I l 1. Reentry into affected areas is a controlled i
evolution. Surveys are performed, environmental samples are obtained and analyzed, and areas posted l or decontaminated.
! 6.3.23 Contamination limits for food supplies and drinking
! water are based upon the State of Kansas Protective l
i Action Guides, as presented in ATTACHMENT E, EPA / KANSAS PROTECTIVE ACTION GUIDES.
6.4 Emeroency Facilities j 6.4.1 Control Room Facilities
- 1. The Control Room is designed to be habitable under emergency conditions. The Control Room contains controls, instruments, and communications equipment necessary for operation of the plant under both normal and emergency conditions. The ventilation system, shielding, and structures are designed and built to permit continuous occupancy during a postulated design basis accident.
- 2. Equipment available in the Control Room gives early warning and continuous evaluation of potential emergency situations. Portable radiation survey instruments are readily available within the Control Room.
- 3. Access to the Control Room is controlled by the Shift Supervisor.
6.4.2 Technical Support Center Facilities
- 1. The TSC is a brisk 2 minutes and 15 seconds walk from the Control Room. This is sufficiently close to permit face-to-face interaction between personnel in the Control Room and the TSC, should telephone communications become inoperable.
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C 2. The TSC is activated in the event of an Alert or higher emergency. The TSC may also be activated during an NUE at the discretion of the Shift j Supervisor.
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- 3. The TSC is designed to the seismic criteria of the Uniform Building Code. It is designed to withstand g 100-year-recurrence winds and is located above the !
g probable maximum flood level.
l g a. The manually activated single-train, non-seismic !
Category I TSC ventilation system utilizes high-efficiency particulate air and charcoal filters. ,
The radioiodine monitoring equipment in the TSC j provides a designed minimum detectable level of !
1.0E-07 uCi/cc radiciodine. A radiation monitor i (including the monitor for radiciodines) alarms :
to alert TSC personnel if radiation levels may 1 affect the habitability of the TSC.
- b. Portable radiation monitoring equipment, is provided in the TSC for backup radiation monitoring capability.
- c. Equipment for Emergency Response Teams is available in the TSC. This equipment includes protective clothing, dosimetry, survey meters and respirators. )
- d. A diesel generator is available to provide backup power to the TSC. Until the diesel is loaded, batteries are available for Nuclear Plant Instrument System (NPIS),
- e. The TSC is sized to accommodate a minimum of 25 i persons and has the same radiological I habitability as the Control Room under accident conditions.
- 4. Personnel in the TSC have access to the following materials:
o WCGS USAR, Environmental Report, and Technical Specifications o Plant operating and emergency procedures o WCGS, State, and Coffey County emergency response plans o System drawings, schematics, and diagrams l
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O 6.4.3 operations Support Center
L whenever the TSC is activated.
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- 2. The OSC serves as an assembly area for plant personnel immediately serving in emergency repair
{s or Health Physics support capacity during an event.
The OSC functions include the coordination, 2 formation and dispatch of Emergency Response Teams.
- 3. The basement of the Security Building has been identified as an alternate location for the OSC function. It contains telephones and a Gai-Tronic call box, which will allow direct communications with the other emergency centers. Portable radios are available to key personnel to further provide communications with other emergency centers.
6.4.4 Emergency Operations Facility (EOF)
- 1. The EOF is located approximately 2.8 miles north northwest of WCGS, in the Dwight D. Eisenhower Learning Center, and is activated at an Alert or higher emergency. Following facility activation, overall emergency response is managed from the EOF.
- a. This facility serves as a center for evaluation and coordination of environmental activities related to the emergency including radiological assessment and the evaluation of potential or actual radioactive releases from the plant.
- 2. The EOF design life is equivalent to that of the plant and engineered such that a protection factor of greater than 5 is provided to attenuate 0.7 MeV gamma radiation,
- a. The EOF is provided with a manually activated, single-train, non-seismic Category I ventilation system which incorporates a HEPA filter system and fixed radiation monitors, including an alarming monitor for radiciodines (with a minimum detectable level of 1.0E-07 uCi/cc).
l b. A diesel generator is available to provide backup power to the EOF. Until the diesel is loaded, batteries are available for NPIS equipment use upon loss of AC power.
- c. The EOF is sized to accommodate at least 35 persons.
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- 3. Accommodations and telephones are provided for a limited number of state and federal personnel.
j Facilities are provided for staging field survey efforts from the EOF.
( 4. The EOF serves as the base of operations for 2 evacuation assessments and for communications with g federal, state, and local response organizations.
g Radio and telephone links are available to the TSC, and Control Room.
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- 5. Personnel in the EOF have access to the following materials:
o WCGS USAR, Environmental Report, and Technical Specifications o Plant operating and emergency procedures o WCGS, State, and Coffey County emergency response plans o System drawings, schematics, and diagrams
- 6. Arrangements have been made to use the Kansas Power and Light (KPL) Customer Business Office located at 210 E. 2nd, Emporia, KS as the backup EOF. This facility is located approximately 28 air miles west of the plant. Telephones available at this location ensure the provision for continuity in decision-making functions and for communications supporting dose projections.
6.4.5 Public Information Facilities
- 1. At an NUE or Alert the Information Clearinghouse (IC) is established in the Dwight D. Eisenhower Learning Center. The Phone Team and Media Center (MC) are activated when needed. The IC, Media Center and Phone Team are kept in close proximity to each other to facilitate coordination of information in the form of news statements, news conferences or telephone conversations.
- a. If a radioactive release requires that the i
Public Information Organization be relocated, they will be moved to the Kansas State Defense Build 2ng, 2000 Topeka Ave., in Topeka, KS.
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- b. Dedicated telephone lines allow contact between the IC, TSC, and the EOF. The IC contains status boards, appropriate office supplies, j computer (s), printer (s), faxing and photocopy g capabilities, and outside telephone lines.
N 2 2. The Wolf Creek PIO, the State PIO and Coffey County g PIO communicate with the IC to obtain technical x information. The PIOS prepare news statements at the IC and coordinate their efforts.
M
- 3. The MC accommodates news conferences. The MC and Media Room is established in the Dwight D.
e Eisenhower Learning Center. The MC is activated by 3
the Public Information Manager when needed during an NUE or Alert, and will be activated for an Site Area or General Emergency.
- a. If radioactive releases require that the MC be re-located, the MC will be moved to the Nickell Memorial Armory, 2722 S. Topeka Ave., Topeka, KS. The Topeka facility will accommodate several hundred media representatives in an auditorium and adjoining Media Room.
- b. The Media Room is a facility setup to provide the media with a work area, audio / visual material, outside telephone lines and public information status boards.
- 4. The Kansas City Power and Light (KCPL) General Office (GO) is where the Media Monitoring Team performs rumor control functions for WCGS, the State and Coffey County. The KCPL GO contains equipment and supp?ies, and has fax and telephone communications with the IC, All approved news statements and informution are transmitted to the KCPL GO after the IC is activated.
- a. The Media Monitoring Team reports to the Rumor Control Coordinator. This team notifies the Rumor Control Coordinator of any rumors or misinformation heard or observed from their monitoring of the media.
6.4.6 Cnsite Medical Facility
- 1. A medical facility located in the Clyde Cessna building, is staffed with a full time Physicians Assistant. This facility is equipped to provide basic medical response capabilities.
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- 2. First aid kits are located throughout the site. ,
, Emergency supplies and equipment are also available
, to ensure that assistance can be provided to
] contaminated personnel.
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- 3. Shift personnel, trained in first aid, are available onsite 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day. Priority should g be given to treating those with the most urgent g medical needs.
, 4. In the case of contamination, efforts are made to decontaminate injured personnel onsite, as soon as practicable. However, first aid or removal of the individual from a hazardous environment, takes precedence over decontamination efforts. If decontamination is not possible, the victim is covered in such a manner as to avoid any spread of contamination until medical aid can be obtained or hospitalization accomplished.
- 5. Personnel leaving the RCA are monitored for contami. nation. All personnel are monitored for contamination before leaving the site.
- a. Personnel found to be contaminated must undergo decontamination under the direction of health ;
physics personnel using health physics supplies i and equipment available during routine i activities. Release limits for personnel l decontamination are found in the Radiation Protection Manual.
6.4.7 State and County Facilities
- 1. Coffey County Emergency Operations Center (County EOC) is located in the Coffey County Courthouse, Burlington, KS. The County EOC is a command center for county agencies and a mustering area for personnel who arrive in the WCGS area in response l to an emergency. The County EOC is activated at 1 the Alert level with the additional support staff l activated upon declaration of an SAE or GE. Other '
centers are established as the emergency needs dictate.
- 2. Kansas State Emergency Operations Center (State EOC), located in the State Defense Building, 2800 South Topeka Avenue, Topeka, KS, is the command-and-control center for the State.
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- 3. The State Forward Staging Area is located about 11 miles north of WCGS in the roadside park at the intersection of Old Highway 50 and U.S. 75. When i it becomes necessary for the State to dispatch y( emergency personnel to the plume exposure pathway emergency planning zone (EPZ), the State activates the State Forward Staging Area to serve as a y secondary base of operations for state personnel g and a local contact point with Coffey County.
h 6.4.8 Evacuation Registration Centers
- 1. People in the EPZ evacuating to Emporia on I-35, 1 should exit I-35 at Merchant Street and go to the j Emporia State University Physical Education ,
building at 18th and Merchant.
- 2. People in the EPZ evacuating to Garnett should use 12th Rd, 16th Rd, Hwy. 31 or Hwy. 57 East to go to the Anderson County Jr/Sr High School.
l 6.5 Control Room Organization 6.5.1 The Shift Supervisor is responsible for the initial evaluation and classification of any abnormal situation and for directing the appropriate response, including initial activation of a callout.
1
- 1. Control Room personnel are on shift 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day. {
The shift complement is shown in Figure 2, MINIMUM SHIFT COMPLEMENT.
6.5.2 Upon declaration of an emergency, the SS assumes the duties of Emergency Manager. The SS normally goes to and remains in the Control Room unless it is necessary for him to leave the Control Room in order to perform specific assessment, corrective, or protective actions.
The SS performs the following actions:
o Initiate appropriate technical measures to mitigate the event o Determine if releases have occurred, make the necessary assessment of the off-site concentration of radioactivity resulting from a release, and evacuate non-essential personnel if necessary o Direct the activities of the Control Room Emergency Notification System (ENS) and Off-site Communicators
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c) o Ensure immediate and follow-up notifications are '
made which provide sufficient information on
, emergency classification, plant status, off-site
, dose projections or measurements, and issue g recommendations for off-site protective actions to 2
g authorities responsible for off-site emergency measures M 1
- g. o Ensure notifications are made to the NRC i
immediately and within 60 minutes of classification l g of an emergency in accordance with 10CFR50.72 (a) (3) '
o Ensure other notifications are made in accordance with EPPs o Activate onsite emergency teams if required o Notify plant personnel of the change in plant status 6.5.3 off-site Communicator
- 1. The Off-site Communicator reports to the SS, performs initial notifications, and initiates callout of the ERO.
- a. Non-Responding Emergency Communicators (NREC) assist in the manual callout of personnel to staff the ERO if the Automatic Dialing System (ADS) is not functioning.
6.5.4 Emergency Notification System (ENS) Communicator
6.5.5 Initial emergency response to the major functional areas is within the capabilities of the minimum ;
operations shift complement. i 6.5.6 On-shift staff augmentation is available, when deemed i necessary, in accordance with ATTACHMENT D, WCGS I MINIMUM STAFFING FOR EMERGENCIES. l 6.6 Technical Support Center (TSC) Organization !
6.6.1 TSC activation will be performed as soon as practical I and within the times as stated in the following:
s I
- 1. During off-normal working hours, it is the goal to activate the TSC within 75 minutes of a declaration of an Alert or nigher classification.
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- 2. During normal working hours, it is the goal to activate the TSC within 30 minutes of a declaration of an Alert or higher classification.
S 6.6.2 The TSC is considered activated when the following I positions are present, the Site Emergency Manager determines the facility is ready to activate, and y declares the facility activated:
i i l [ o Site Emergency Manager c) i o TSC Operations Coordinator I o TSC Administrative Coordinator l 1
o TSC Radiological Coordinator '
o Maintenance Coordinator 6.6.3 The TSC organization is shown in FIGURE 3, TSC/OSC ORGANIZATION.
6.6.4 Additional personnel to support repair efforts and recovery functions will be added as necessary.
Personnel reporting from off-site may initially report to the Dwight D. "isenhower Learning Center, and then proceed to the TSC as plant / site conditions allow. '
6.6.5 Site Emergency Manager
- 1. The assigned Site Emergency Manager will assume command-and-control functions and will be the top !
line manager responsible for the emergency. An assigned Site Emergency Manager is available 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day. The assigned Site Emergency Manager may assume command-and-control functions from the SS during an NUE if so requested by the SS.
- 2. The SS will transfer the Site Emergency Manager duties to the assigned Site Emergency Manager in accordance with EPPs. The SS resumes Control Room duties and reports to the Site Emergency Manager.
- 3. The Site Emergency Manager directs the onsite emergency effort, implements the applicable EPPs and, as appropriate, performs the following:
o Assess and verify the situation and assure that appropriate mitigating efforts are being taken o Review initial event classification and reclassify as appropriate
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o Determine the necessity for evacuation of personnel onsite
{; o If a release has occurred, make the necessary assessment of the off-site concentration of g radioactivity resulting from a release i
_'_ i g o Ensure immediate and follow-up notifications are g made which provide sufficient information on d emergency classification, plant status, off-site ;
g dose projections or measurements, and issue l recommendations for off-site protective actions :
to authorities responsible for off-site i emergency measures i 1
- 4. The following responsibilities are those of the i Emergency Managers and may not be delegate. These
- responsibilities may be divided between the Site and Off-site Emergency Managers o Classification of the emergency I j o Protective action recommendations l
' l i
o Authorization for notification of off-site !
authorities i t
o Authorization of emergency exposure in excess of 10CFR20 linits t 6.6.6 TSC Operations Coordinator
- 1. The TSC Operations Coordinator reports to the Site l Emergency Manager and is responsible for the j following: I o Supervise reactor plant operations, the Engineering Coordinator, and ENS Communicator l
- o Keep the Site Emergency Manager advised of plant l conditions and operational manipulations i
1 6.6.7 Engineering Coordinator 1
- 1. The Engineering Coordinator reports to the TSC Operations Coordinator and directs the activities of the Engineering Team to technically assess plant j status and the severity of emergency conditions.
. . - -- - . - - .- - . - = . - . - . - - . - - . - . _ . _ - -
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m C) 6.6.8 Engineering Team
- 1. The Engineering Team reports to the Engineering Coordinator. The Team evaluates current and -
historical plant parameters, assesses the severity f g
of the emergency conditions and magnitude of fuel !
damage, and recommends corrective or preventive !
g actions.
i
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j 6.6.9 TSC Emergency Notification System (ENS) Communicator
- 1. The TSC ENS Communicator reports to the TSC Operations Coordinator and maintains communications with the NRC.
6.6.10 TSC Radiological Coordinator i
- 1. The TSC Radiological Coordinator reports to the Site Emergency Manager and is responsible for I
preventing or minimizing direct exposure to, or ingestion / inhalation of, radioactive materials during a rediological emergency. Responsibilities are as follows:
l o Monitoring Dose rates and dose projections o Monitoring Radiological survey teams' results o Assists the On-site Emergency Manager in the l formulation of recommended protective actions i
o Monitoring Personnel radiation exposures to ensure they are maintained in accordance with 10CFR 20 limits unless otherwise authorized by the Emergency Manager
- 2. The TSC Radiological Coordinator will transfer off-site duties to the EOF when the EOF is activated.
6.6.11 TSC Administrative Coordinator
- 1. The TSC Administrative Coordinator reports to and assists the Site Emergency Manager to ensure that i emergency notifications are performed. The TSC
' Administrative Coordinator is responsible for logistical support in the areas of TSC personnel, Control Room, procurement and warehouse support, communications support and equipment repair 3 services.
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- beyond onsite staff capabilities to the EOF B Administrativa Coordinator.
6.6.12 TSC Team Director
- radiological safety matters concerning Emergency g Response Team activities.
6.6.13 Maintenance Coordinator
- 1. The Maintenance Coordinator reports to the Site Emergency Manager and directs the Maintenance Assistant in the coordination of emergency team activities,_ including PASS team. The Maintenance Coordinator also directs the' formation of teams to be assigned to search and rescue.
6.6.14 Operations Communicator
- 1. Provides data, progress and plant conditions from the Control Room via the Operations Recorders, 6.6.15 Additional Personnel i
- 1. The following are examples of positions that are not needed for activation and operation of the TSC but supplement those personnel which are essential l to an emergency response:
o Operations Recorder maintains the Operations Status Board current.
o Team Communicator reports to the Team Director and is responsible for communicating with Onsite Teams.
- o. Onsite Survey Team Technicians perform tasks as ,
l assigned by the Maintenance Assistant. )
o Administrative Assistants perform facility l accountability, assist the Emergency Manager, faxing and copying, log keeping, and off-site ;
notifications and communications as directed. !
9 e
- _ _ _ _ . _ . . _ . _ _ - . _ ... _ . _ . _ _ _ _ _ m . _ ..._ m _ _ _ .. __
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Operations Support Center (OSC) Organization l l '
l 6.7.1 Maintenance Assistant 2
J
- 1. The Maintenance Assistant reports to the !
?) Maintenance Coordinator and coordinates emergency
\
repair and damage control activities, coordinates ;
{g deployment of onsite teams, and coordinates the activities of the Maintenance Engineers. ;
I t
I 6.7.2 .Epergency Response Team (ERT)
- 1. The ERT personnel may be selected from Health Physics Technicians (Tech), Chemistry Tech, and j Instrumentation and Control, Mechanical, or !
Electrical maintenance. The ERT reports to the Maintenance Assistant and is responsible for l repairs, surveys, sampling, analysis, and search and rescue. i i i 6.7.3 Additional Personnel l 1. The following are examples of positions that are ! l not needed for activation and operation of the OSC ! l but supplement those personnel which are essential ! to an emergency response. o Chemistry Technicians perform emergency chemical sampling and provide post-accident sample : analysis. i o Maintenance Planners develop repair plans for { use by the emergency repair and damage control I teams. l o Warehouse Support Personnel assist in locating and securing parts and equipment from the warehouse. 6.8 Emergency Operations Facility (EOF) Organization 6.8.1 EOF activation will be performed as soon as practical and within a goal of 90 minutes of a declaration of an Alert or higher Emergency.
- 1. The EOF is considered activated when the following positions are present, the Off-site Emergency
; Manager determines facility readiness, and declares j the facility activated:
! o Off-site Emergency Manager o EOF Operations Coordinator I
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# i Co o EOF Facility Technician ! ~
- 2. The complete EOF organization is shown in FIGURE 4, g EOF ORGANIZA.lON. *
} 6.8.2 Off-site Emergency Manager CG !
- 1. The Off-site Emergency Manager will assume the f command-and-control functions and direct the !
emergency from EOF. An assigned off-site Emergency ; Manager is available 24 hours a day. t
- 2. The Off-site Emergency Manager is the official WCGS interface with government authorities.
Responsibilities include the following:
- a. Supports and provides resources or performs tasks as requested by the Site Emergency Manager !
- b. Directs all WCGS personnel in the EOF i
- c. Obtains personnel and coordinates the efforts of !
the following: l o Emergency response personnel who perform off-site radiological surveys, plus any other personnel deemed useful for the emergency response effort o Outside contractors and vendors, such as consultants, laboratories under contract, ) j the Nuclear Steam Supply System (NSSS) - vendor, the Architect / Engineer, and regional utilities o Additional technical resources may be called in during the emergency for further support or shift assignment onsite.
- d. Coordinates with the Administrative Coordinator in the logistics effort to supply the plant with the necessary personnel and equipment
- e. Briefs WCGS Executive Management on matters related to the emergency
- f. Coordinates with the Onsite and Off-site Public Information Coordinators (PICS) in providing technical input for news statements l
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i o EOF Radiological Coordinator i D-
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to o EOF Facility Technician i
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- 2. The complete EOF organization is shown in FIGURE 4, !
h) EOF ORGANIZATION. :
}
6.8.2 Off-site Emergency Manager i 03
- 1. The Off-site Emergency Manager will-assume the command-and-control functions and direct the i emergency from EOF. An assigned Off-site Emergency Manager is available 24 hours a day.
- 2. The Off-site Emergency Manager is the official WCGS ,
interface with government authorities. l Responsibilities in ~ de the following: 5
- a. Supports and provides resources or performs !
tasks as requested by the Site Emergency Manager :
- b. Directs all WCGS personnel in the EOF
- c. Obtains personnel and coordinates the efforts of the following: ,
o Emergency response personnel who perform { off-site radiological surveys, plus any ! other personnel deemed useful for the ! emergency response effort ! o Outside contractors and vendors, such as consultants, laboratories under contract, I the Nuclear Steam Supply System (NSSS) vendor, the Architect / Engineer, and regional utilities o Additional technical resourcas may be called in during the emergency for further support or shift assignment onsite.
- d. Coordinates with the Administrative Coordinator in the logistics effort to supply the plant with the r.scessary personnel and equipment
- e. Briefs WCGS Executive Management on matters related to the emergency
- f. Coordinates with the Onsite and Off-site Public !
Information Coordinators (PICS) in providing technical input for news statements
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- 5, n
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- g. Ensure immediate and follow-up notifications are l _ , made which provide sufficient information on
, emergency classification, plant status, off-site
, dose projections or measurements, and issue ;
g protective actions recommendations to off-site g authorities responsible for off-site emergency measures M g h. Requests federal assistance through state officials per the State Plan m
- 3. The following responsibilities are those of the Emergency Managers and may not be delegate. These responsibilities may be divided between the Site and Off-site Emergency Managers:
o Emergency classification o Protective action recommendations o Authorization for notification of off-site authorities o Authorization of emergency exposure in excess of 10CFR 20 1 6.8.3 EOF Radiolocical Coordinator l
- 1. The EOF Radiological Coordinator reports to the Off-site Emergency Manager and is responsible for !
radiological monitoring and dose assessment ! activities off-site. Responsibilities are as follows: o Directs and coordinates activities of the Dose Assessment Coordinator and staff o Assists the Off-site Emergency Manager in the formulation of recommended protective actions o Provides the PIC with an assessment of radiological conditions o Requests through the EOF Administrative Coordinator additional radiation monitoring l equipment, instrumentation and Health Physics support personnel as necessary o Interfaces with State and County emergency response personnel who are assigned to the EOF
- regarding matters related to off-site radiological assessment
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- 1. The EOF Team Director assumes responsibility for 2
3 authorizing and supervising Off-site Monitoring Teams. The EOF Team Director directs Emergency C0 Response Teams and advises the EOF Radiological
\ Coordinator on radiological conditions encountered by the Teams.
U
\
- a. Off-site Monitoring Team authorization should be made promptly upon activation of the EOF.
co
- b. Monitoring teams are specially trained in field sampling techniques. Each team will be equipped with equipment capable of detecting and measuring radioiodine concentrations in the air at levels as low as 10-' uCi/cc.
6.8.5 EOF Facility Technician
- 1. Reports to the EOF within a goal of 60 minutes of declaration of an Alert or higher classification to ensure the EOF is prepared and functional.
6.8.6 Dose Assessment Coordinator
- 1. Reports to the EOF Radiological Coordinator and is responsible for directing / assisting with dose projection and protective action recommendation activities.
- 2. Ensures the Radiological Status Board is maintained current.
6.8.7 Emergency Dose Calculation Program (EDCP Operator)
- 1. Reports to and is responsible for providing completed off-site dose projections to the Dose Assessment Coordinator.
6.8.8 HPN Communicator
- 1. The HPN Communicator reports to th'e EOF Radiological Coordinator and maintains communications with the NRC via the Health Physics Network (HPN) telephone, i
6.8.9 EOF Operations Coordinator l
- l. Reports to and briefs the Emergency Manager on j plant conditions and mitigative strategies.
i y Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 i a - - L (RERP) Reference Use Page 33 of 83 O m o 6.8.10 EOF Administrative Coordinator
- 1. The Administrative Coordinator is responsible for 2
a coordinating, directing, and responding to requests to from the ERO for administrative and logistical support. The techniques and procedures used during
's this effort are adapted from normal WCGS procurement practices. The Administrative U
Coordinator also ensures notifications to off-site
} authorities are made.
M 6.8.11 Representative At County
- 1. The Representative at the County is located in the County Emergency Operations Center in Burlington, KS, and reports to the Off-site Emergency Manager.
The Representative responds to requests from County personnel for clarification or verification of data received from the TSC or EOF. 6.8.12 Additional Personnel l
- 1. The following are examples of positions that are not needed for activation and operation of the EOF but supplement those personnel which are essential to an emergency response.
o Team Communicators communicate with Off-site 3 Monitoring Teams. I o Operations Recorders maintain the Operations Status Board current. o Administrative Assistants perform facility ! accountability, assist the Emergency Manager, faxing and copying, log keeping, and Off-site i notifications and communications as directed. l 6.9 Public Information Oroanization 6.9.1 Wolf Creek Public Information Officer (WC PIO)
- 1. The WC PIO is the public voice for plant information. The WC PIO is responsible for ensuring the timely issuance of accurate information to the public and media during an emergency at WCGS. Public interaction may be as a l formal news conference or a telephone call. I 1
\ l 2. The WC PIO position is activated at an NUE or higher emergency to coordinate the development and release of news statements. I
D' Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 I (RERP) Reference Use Page 34 of 83 O m o 3. The WC PIO has overall responsibility for the Public Information Organization. J 6.9.9 Wolf Creek Public Information Manager 2 M 1.
' The Wolf Creek Public Information Manager position is activated at an NUE or higher emergency. The M
Wolf Creek Public Information Manager works closely
\
with the WC PIO, the Onsite PIC, the Off-site PIC and the Technical Support staff to ensure that [ W information provided the public is timely and accurate.
- 2. The Wolf Creek Public Information Manager has responsibility for ensuring the Public Information Organization is activated and functions as directed in EPPs.
- 3. During a declared emergency the Public Information Manager determines and coordinates the activation of Rumor Control, Information Clearinghouse, Media Center and the Phone Team. The Public Information Manager operates from the appropriate Information Clearinghouse.
- 4. The complete Public Information organization is shown in FIGURE 5, PUBLIC INFORMATION ORGANIZATION.
6.9.2 Onsite Public Information Coordinator (PIC)
- 1. The PIC gathers and transmits technical information to the Wolf Creek Public Information Officer for use in news statements following the declaration of any emergency classification.
6.9.3 off-site Public Information Coordinator (PIC)
- 1. During an SAE or GE, the PIC is responsible for gathering all information related to the health and safety of the public. The PIC transmits this information to the WC PIO at the Information Clearinghouse. The PIC operates from the EOF.
6.9.4 Media Center Manager (MC Manager)
- 1. The MC Manager is located at the Media Center and reports to the WC PIO. Responsibilities include j set-up of the Media Center, leadership for the Media Registrar and Media Liaison and management of the media news conferences. The Media Center Manager maintains contact with the Information Clearinghouse to provide news conference schedules.
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l A C 6.9.5 Media Liaison '
- i 1
- 1. Media Liaison is located in the Media Center and E
reports to the MC Manager. Responsibilities include managing the media crowd at the Media l {(
' Center and assisting the media with registration and facility orientation, providing general Wolf
+
I Creek background information or approved emergency- : Y related information, arranging individual l
\
interviews, and announcing and coordinating
] scheduled news conferences. >
l 6.9.6 News Writer ; l 1. The News Writer reports to and provides support for the WC PIO. The News Writer provides support to l the PIO including: answering telephones, writing i and distributing news statements, updating the > status log, maintaining the media status' board and l faxing news statements. The News Writer maintains ! a chronological log of the events and news l statements. i I 6.9.7 Phona Team Manager
- 1. The Phone Team Manager reports to the WC PIO and coordinates the rumor control activities of the Phone Team.
6.9.8 Rumor Control Coordinator i
- 1. The Rumor Control Coordinator is located in the KCPL General Office and reports to the WC PIO.
Rumor Control monitors news statements or news conferences to identify misinformation being released to the public. 6.9.10 Technical Support
- 1. The Technical Support staff discusses technical details of the news statement with EOF staff to I ensure accuracy, provides technical interpretation for the WC PIO, the Public Information Officer for Coffey County and the State of Kansas. Technical Support gathers information from the Emergency l Facilities to communicate plant, health and safety issues to the public.
l l
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- 1. The following are examples of additional personnel E
1 used to fill ERO positions such as clerical, log keeping, or status board posting. Staffing of f these positions does not affect the activation of _' the facility. f
~ ~
o Media Center Registrar monitors access to the Media Center, records news conference W attendance, provides media packets, provides directions for telephone use and work space information to the media representatives. o Audio / Visual Support records on video and audio tape the proceedings of news conferences presented in the Media Center. o Information Messenger performs clerical and administrative duties at the direction of the Public Information Manager. o The Phone Team may make initial media notifications at PIO discretion, addresses media and public questions to the extent possible and reports rumors or misinformation to the Phone Team Manager. o The Media Monitoring Team notifies the Rumor Control Coordinator of any rumors or misinformation heard or observed from their monitoring of the media. 6.10 Local Off-site Organizations 6.10.1 The Coffey County Contingency Plan for Incidents Involving Commercial Nuclear Power describes the authorities, responsibilities, and agreements to which various county agencies are a party in their response to emergencies at WCGS. Information is provided therein about the various agencies' interrelationships and support roles provided to WCGS. l 1 o The County Plan contains the formulas for calculating evacuation times for each subzone. l 4
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{ Reference Use Page 37 of 83 m C 6.10.2 Coffey County Commissioners l
- 1. The Coffey County Board of Commissioners maintains A
the executive authority and responsibi'ity for 3 planning and coordinating the county response.
? '
They have delegated responsibilities and tasks to i the local support agencies and have established ! operating _ procedures. '
- 2. After declaring a State of Local Disaster
# Emergency, the Chairman of the Coffey County Commissioners is responsible for making the decision to activate the alert and notification system. Emergency authority, as stated in County Plan, is given in an established line of succession. i 1
- 3. If a State of Emergency has not been declared, after receipt of notification and in accordance with the County Plan, the Chairman decides which protective actions would be appropriate.
o When a protective action is decided upon, the County notifies the State to activate EAS. 6.10.3 Coffey County Sheriff's Office
- 1. The Coffey County Sheriff's Office provides local notification, access centrol, and law enforcement support in accordance with the Coffey County Plan.
- 2. If time does not permit, or if he is unable to j contact the Chairman or other members of the County Emergency Response Organization, the County Sheriff has the authority to make protective action decisions based upon recommendations by WCGS.
- 3. The County Dispatcher contacts the Kansas Division of Emergency Management to activate EAS.
- 4. Specific services provided by the Coffey County Sheriff's Office include:
o Perform notifications as defined within the County Plan and associated implementing procedures o Provide a 24 hour per day manning of communications links between the County and l WCGS, and between the County and State
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{ Reference Use Page 38 of 83 m C o Implement off-site protective actions as necessary and as specified in the County Plan implementing procedures s 3 o Initiate warning and initial notification of the population o Direct the evacuation of specific subzones of the EPZ upon the decision to evacuate o Provide traffic control and roadblocks per U implementing procedures o Obtain additional assistance as necessary to secure the evacuated areas o Control access to the County EOC 6.10.4 Coffey County Fire District #1 (CCFD)
- 1. Contractual arrangements have been made with the Board of Trustees of Fire District No. 1, Coffey County, KS, for the provision of fire fighting support. Services contracted are summarized in the Letter of Agreement and maintained in an Emergency Planning file.
- 2. The WCGS Fire Brigade Leader is also responsible for directing all fire fighting activities onsite.
Once onsite, Fire District members and equipment I shall be escorted by Security. j 6.10.5 Off-site Medical Treatment
- 1. Coffey County Hospital and Newman Memorial Hospital l each have developed emergency procedures to provide guidance in the rendering of medical treatment to contaminated patients.
- 2. Coffey County Hospital, located in Burlington, KS, approximately 9 road miles from the WCGS site, has agreed to provide aid to injured / contaminated personnel.
- 3. Newman Memorial Hospital serves as a backup to Coffey County Hospital and is located in Emporia, KS, approximately 40 miles from WCGS.
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Contaminated injured personnel transported from WCGS to off-site medical facilities are attended by 1 personnel qualified in radiological practices. 2 Once the patient (s) has been stabilized, WCGS personnel survey patient (s), attending personnel, < f vehicles, and equipment to ensure they have been I i decontaminated in accordance with WCGS procedures. h'\ 6.10.6 Coffey County Ambulance Service h, 1. Coffey County Ambulance Service provides medical assistance and transports victims to medical facilities for personnel requiring treatment for injuries, exposure to radiation, and contamination. WCGS notifies the Ambulance Service by telephone or though the Coffey County Sheriff's Office. 3
- 2. If conditions warrant, any vehicle at WCGS may be used to transport affected personnel.
6.10.7 Radiological Emergency Assistance Center / Training Site (REAC/TS)
- 1. REAC/TS maintains a 24 hour Hospital Disaster Network. Consultation is available for medical energencies involving radiologically contaminated patients.
6.11 State Organizations 6.11.1 The Governor, by law, is the Chief Executive Officer of l the State of Kansas and is responsible for the safety ; and well-being of all citizens within the State. The j State Plan describes the responsibilities of local, ! federal, state, and volunteer agencies during nuclear i emergencies. Upon declaration of a State of Disaster Emergency the State has primary responsibility for responding to an off-site nuclear emergency. i Activation of the State EOC, located in the lower level ' of the State Defense Building, Topeka, KS, is the responsibility of the Governor or authorized j representatives, depending on the nature of the l emergency. The Kansas Division of Emergency l Management, Technological Hazards Section, provides overall coordination as the responding state agency during a Fixed Nuclear Facilities Incident. ; i
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D Reference Use Page 40 of 83 m O 6.11.2 Appendix 12 to Annex N of the Kansas State Emergency :
- Operations Plan describes in detail, the authorities, I responsibilities, and agreements to which various state J agencies of their response to emergencies at WCGS.
Reference to this document is made for detailed f information on each agency's interrelation and support j _- role provided to WCGS. Y 1. Upon declaration of an SAE or GE representatives of
~ Kansas Department Emergency Management (KDEM) and " Kansas Department of Health and Environment (KDHE) go to the EOF. They act as the interface between WCGS, the County, and the State.
6.11.3 Kansas Division of Emergency Management (KDEM)
- 1. The KDEM provides the following assistance:
- a. Evaluates information presented by WCGS to decide off-site protective actions
- b. Coordinates nuclear incident response planning, training, and notification. Activities include:
o Notification of KDHE o Notification of Key federal and state agencies o Notification of the Governor's Office o Provides radiological monitoring coordination o Requests federal assistance and coordinates federal and state support on behalf of affected areas o Provides 24 hour per day point of contact to receive notification o Activates the State EOC o Activates the Kansas Emergency Alert System 6.11.4 Kansas Department of Health and Environment (KDHE) l 1. The KDHE provides assistance as described below: o Acts as the lead state agency for operational ! radiological emergency response o Conducts radiological monitoring in affected areas
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i m i O : o Provides radiological advice to hospitals i f h o Develops and establishes State PAGs E o 1 M Provides information and guidance to the public ! 1 l \ about protective actions, via the KDEM l
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I o Assesses off-site contamination of the U l
- \ environment
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U o Provides technical guidance and coordination in recovery activities l i o Supports the development and conduct of i I radiological response training ! o Reviews, evaluates, and maintains dosimetry records for non-licensee emergency workers and other affected individuals 6.11.5 Kansas Highway Patrol (KHP)
- 1. The KHP provides communications and notification support including backup notification means for the following:
o Coffey County Sheriff's Office o KDEM, Technological Hazards Section o The Governor's Office l 2. The KHP augments local law enforcement in securing the area and establishing evacuation routes and providing traffic control.
- 3. The KHP provides self-support radiological I monitoring.
l 4. The KHP maintains emergency communications systems l
- 24 hours per day. l 6.11.6 Kansas National Guard
- 1. The Kansas National Guard may be directed by the !
Governor to provide assistance as needed such as the following- l
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o Evacuation of communities 4 3 o Area security ! L o Providing Media Center Security i
i M y Revision: 0 7 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 (RERP) l { Reference Use Page 42 of 83 m O 6.11.7 Kansas Department of Transportation (KDOT) 2
- 1. KDOT provides assistance as follows:
E o Provides emergency traffic barriers and signs to ; o Supplements emergency traffic control 1 o Supplies construction equipment o Provides communications support G 6.12 Federal Organizations 6.12.1 Should an emergency situation or accident occur at WCGS, notification and reports must be made to various federal agencies and organizations, and requests for assistance may also be made. 6.12.2 Federal Emergency Management Agency (FEMA)
- 1. FEMA is the lead agency supporting implementation of the state and local emergency plans. Region VII FEMA response time is estimated to be four hours.
6.12.3 Department of Energy (DOE)
- 1. The DOE Radiological Assistance Program provides monitoring assistance and radiological consultation {
to the KDHE. The DOE provides assistance under the ' Federal Radiological Emergency Response Plan (FRERP) and responds to authorized requests for ! assistance by the KDHE. The DOE Albuquerque Operations Office maintains a team of specialists which are dispatched to the incident site for radiological hazard evaluation within 48 hours. 6.12.4 Nuclear Regulatory Commission (NRC)
- 1. The NRC provides advice to other federal, state, and local agencies on the radiological health consequences of various emergency protective actions. The NRC requires notification and reports as indicated in ATTACHMENT H, REPORTING OF j INCIDENTS PER 10CFR20 and as specified in the WCGS Technical Specifications. NRC Region IV response time is estimated to be 12 hours.
( 6.12.5 Licensee resources available to support the federal response include the following: i i o Space and equipment in the TSC and EOF provided for ) key federal personnel l l
j Revision: 0 ' RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 m - (RERP) { Reference Use Page 43 of 83 m C' o Telecommunications equipment at these centers is
. available to federal personnel for use o Parking space adjacent to the EOF provides an area I 3
for the location of federcl response vehicles, with l fs power and sanitary services available at the EOF i
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l o Open fields south of the parking lot at the EOF fs provide access for helicopters , g o Coffey County Airport is available for air traffic 6.13 Additional Support Agencies ! 6.13.1 Vendor and Architect / Engineers (A/E)
- 1. NSSS supplier, Westinghouse, is the chief vendor who may be involved with emergency response for WCGS. Westinghouse has emergency response plans which are activated upon notice and is expected to provide the following services:
o Personnel with expertise in various areas o ! Technical analysis i o Operational analysis o Accident / transient analysis o Recommendations l 6.13.2 Regional Utility Support l l
- 1. WCGS shares the SNUPPS power-block design with the Union Electric Callaway Plant. Because of this l design concept and similarity with the WCGS layout, assistance from Union Electric is possible. A j specific mutual aid agreement between WCGS and l Union Electric Company has been established. While '
this assistance may be available within a short i period of time, it shows greatest promise in the I case of a prolonged emergency where extended, around the clock coverage is required. The DEM may authorize the temporary use of this resource, should staff augmentation be necessary. Union Electric Company is a signatory of the INPO FIXED ; FACILITY EMERGENCY RESPONSE VOLUNTARY ASSISTANCE AGREEMENT.
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m 7 6.13.3 Institute of Nuclear Power Operations (INPO)
- 1. WCGS has signed the INPO FIXED FACILITY EMERGENCY I
I RESPONSE VOLUNTARY ASSISTANCE AGREEMENT. This ! agreement is by and among electric utilities which {3 - have responsibility for the construction and operation of commercial U.S. nuclear power plants. { Assistance may be requested from any of the signatory companies in the form of. technical and administrative aid or personnel, facility, or
.g equipment resources. Requested assistance is rendered according to the agreement.
6.13.4' American Nuclear Insurers (ANI) !
- 1. ANI is notified at emergency classifications of Alert or higher. ANI is available to provide ,
insurance services as necessary. 6.14 Plant Monitoring f 6.14.1 Nuclear Plant Information System (NPIS)
- 1. The integration and display of selected and critical data is performed by NPIS which is a non- '
safety, non-Class lE system. Isolation is provided to ensure that NPIS does not degrade the performance of safety system equipment or displays. , t
- 2. NPIS provides data storage and recall capability. l
- 3. Certain parameters are also transmitted to the NRC Operations Center via the Emergency Response Data System (ERDS) link of NPIS. ERDS is activated through NPIS within 60 minutes of an Alert or ;
higher classification. '
- 4. The NPIS computer feeds key plant parameters to individual terminals in the Control Room, TSC, and EOF which display data identical in accuracy, resolution, and reliability. Support personnel may assist the Control Room staff to analyze and diagnose plant abnormalities so that corrective action may be taken and then monitored.
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l m C SI The Safety Parameter Display System (SPDS) provides for continuous indication of plant parameters or i A derived variables representative of the safety 1 status of the plant. The primary function of the SPDS is to aid the user in the rapid detection of f ' abnormal operating conditions. As a plant safety
~ information and diagnostic tool, SPDS concentrates on a minimum set of plant parameters from which the g plant safety status can be assessed. ~
0) 6.14.2 Onsite Radiological Monitors
- 1. Process monitors monitor the radiation intensity of !
materials within plant systems. These monitors continuously measure, indicate and record the radioactive material concentrations located within systems being monitored. Each monitor includes an , adjustable alarm to provide indication of a l significant change or the existence of a concentration of radioactive material above pre-selected values. The USAR, Chapter 11.5, includes ! a listing and range of plant monitors. '
- 2. The Area Radiation Monitoring System monitors provide information about radiation intensity at specific plant locations. These monitors provide the following:
- a. Warnings of excessive gamma radiation levels in areas where nuclear fuel is stored or handled
- b. Control Room personnel with a continuous indication of gamma radiation levels at selected locations within the various plant buildings
- c. Assistance in detecting unauthorized or inadvertent movement of radioactive material in the plant, including the radwaste area
- d. Supplementation of other systems, such as process radiation monitoring or leak detection, in detecting abnormal migrations of radioactive material
- e. Local alarms to warn personnel in the area
- 3. Effluent monitors provide information about the concentration of radioactive material in plant effluent pathways. Each significant effluent pathway from the plant includes an effluent monitor to enable the quantification of the radioactive
[ material concentration exiting the plant. i
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{ Reference Use Page 46 of 83 m o 6.14.3 Meteorological Monitoring System
- 1. The Meteorological Monitoring System is composed of E
0 a 90-meter instrument tower and a temperature controlled shelter at the base of the tower housing f\ associated instrumentation and equipment.
- 2. The function of the meteorological system is to (J monitor and record meteorological conditions.
M
- 3. Information provided by instruments at the meteorological tower is available from the NPIS computer system.
- 4. Time interval measurements are used in calculating 15-minute averages for all parameters.
- 5. When needed, Meteorological data can be obtained from the National Weather Service.
6.14.4 Seismic Monitoring System
- 1. The seismic warning panel in the Control Room provides local visual and audible indication when a seismic event has occurred.
6.14.5 Hydrologic Monitoring
- 1. Hydrologic monitoring is not required as WCGS is a
" dry site" as defined by Regulatory Guide 1.102.
The plant site is located above the design basis flood level. 6.14.6' Fire Protection
- 1. WCGS is protected by an independent fire protection system consisting of two subsystems, a detection / alarm system and a suppression system.
- 2. Activation of the fire systems results in an audible alarm throughout the plant. Alarms are also displayed in the Control Room.
6.14.7 Laboratory Facilities
- 1. A radiochemistry (hot) laboratory, radwaste laboratory, and turbine building chemistry laboratory are located in the power block. The chemistry shop laboratory is located in the Walter P. Chrysler Building. Further information on onsite laboratory equipment can be found in USAR, Chapter 12.5.
b Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 7 (RERP) { Reference Use Page 47 of 83 m C 2. The environmental laboratory at the EOF may be used for processing of routine and emergency field 3 samples. The Kansas Health and Environmental
- Laboratory in Topeka, KS, is available to further W augment the processing of emergency samples.
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- 3. Private laboratories under contract to WCGS or 1aboratories of neighboring utilities who are h signatories of the INPO Voluntary Assistance
] Agreement may be considered for use.
U 6.15 Emergency supplies 6.15.1 Emergency supplies include protective, communications, and radiological monitoring equipment, check sources, and other supplies. The EPPs list emergency supplies and their locations. 6.15.2 Emergency supplies are maintained, inventoried, and inspected on a regular basis in accordance with EPPs. The EPPs contain an inventory list of WCGS equipment for emergency supplies. This equipment may be augmented by other onsite equipment. 6.15.3 Instruments are calibrated in accordance with WCGS Health Physics Procedures. For any items removed from the emergency supplies for calibration or repair, an operable equivalent instrument is used to replace it. Sufficient quantities of spare instruments / equipment are onsite to provide replacements. 6.16 Communications 6.16.1 Communication Equipment
- 1. Telephones provide primary communications contact with the State and County EOCs. Systems in the Olive Beech Building and the Dwight D. Eisenhower Learning Center are powered by their own battery and charger. The battery will supply the system if the charger fails,
- a. The Federal Telephone System (PTS 2000) is used for NRC communications.
- b. Trunk lines are available for communications with outside agencies.
Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 (RERP) [- Reference Use Page 48 of 83-m C 2. Radio communications provide backup communications with the State and County EOCs. Fixed AC-powered E transmitter / receiver units and a number of portable 2 and hand-held units are also capable of providing M fixed and mobile communications to joint
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radiological monitoring teams.
- 3. A paging system is used for initial notification of f\- key personnel. Pager coverage is provided in and
~ around ;he cities of Burlington, Emporia, Topeka, Ottawa and Lawrence.
6.16.2 Communication Dissemination
- 1. The methods of employee communications may be employee meetings, announcements, or literature handouts.
- 2. The Public Informatica Organization is responsible for interfacing with the media. Communication between WCGS and media organizations are performed in accordance with EPPs.
- 3. Annually, WCGS offers the news media with the following information:
o Information concerning the emergency plan o Information=concerning radiation o Facilities available for media o Points of contact for statements of public information o Differences between normal and emergency plant operations
- 4. Standardiz'ed public announcements for broadcast during an emergency have been written by the state, county, and WCGS and are found in the State Plan.
- 5. WCGS, state, and local emergency organizations provide members of the public, including transients, public education information on how they are notified and what their initial actions should be during an emergency.
- a. Emergency planning information is provided within loca1' telephone directories. The information, developed jointly by WCGS, Coffey County and the State of Kansas, is distributed to residences of the EPZ.
~ - - - . - - . . . . - - - - - . - - . - - - . - . - - . . -h Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002
{ (RERP) g Reference Use' Page 49 of 83 m G. .b. Information includes educational facts on radiation, protective measures, special needs of 3 the handicapped and the points.of contact for s additional information. M
\ c. An annual mail-out to the public provides information regarding operation of Tone Alert
{ .. Radios.
) 6. Emergency planning information, displayed on y~ information boards, is provided for transients in the public use areas of John Redmond Reservoir lJRR), Coffey County Lake (CCL), and other WCGS controlled areas. Transients have access to emergency plan information within motel rooms and telephone books.
6.17 Emergency Plan Training 6.17.1 WCGS has developed an emergency preparedness training program which meets the requirements of 10CFR50, Appendix E, Section IV. F. 6.17.2 The Superintendent Emergency Planning ensures required training is provided for ERO personnel in accordance with plant procedures. 6.17.3 Personnel receive general RERP training as a portion of Plant Access Training prior to receiving unescorted access to WCGS. 6.17.4 Training associated with each off-site response organization's emergency support role is offered annually. Training is coordinated with KDEM and the Coffey County Emergency Preparedness Office. 6.17.5 Where Letters of Agreement exist between WCGS and local agencies, training is offered annually. Training is also effered to the participants in the Interlocal Agreements between Coffey County and host counties, Anderson and Lyon. 6.17.6 Drills are considered part of the Emergency Plan Training Program. Drills ensure that the ERO is capable of executing the crucial tasks necessary to ; detect emergency conditions, assess and mitigate the ; l consequences, notify key licensee and non-licensee ' personnel and organizations, perform appropriate l response and protective actions, and recommend off-site
- protective actions to state and local agencies. ,
i l 6.18 Emergency Plan Drills 1 l t l
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(RERP) f Reference Use Page 50 of 83 i m C 6.18.1 Annual communication drills between WCGS, State and County EOCs, and field assessment teams ensure that
} contact can be made and that messages are comprehended.
- 1. Monthly communication tests verify communications f with the local County and State authorities. l
} Communications tests are made with the NRC (
g Headquarters via the FTS 2000. These tests are g performed in accordance with EPPs. i y', 6.18.2 Fire drills are conducted in accordance with plant administrative procedures. ; 6.18.3 ! Annual medical emergency drills include transportation ' and treatment of simulated contaminated individuals by l ambulance and off-site medical treatment facilities, i 6.18.4 Annual radiological monitoring drills include ; l collection and' analysis of sample media, field ) activities, and provisions for communications and i record keeping. l I 6.18.5 Semi-annual Health Physics drills involve response to and analysis of simulated elevated airborne and liquid ' samples and direct radiation measurements in the ! environment.
- 1. Annually, analysis of in-plant liquid samples using the post-accident sampling system (PASS) is included in a Health Physics drill.
6.18.6 Each calendar quarter, a callout drill is conducted to verify the operability of the notification system. l 6.18.7 Critiques should be conducted following each drill to i identify and correct noted deficiencies. 6.19 Emergency Planning Exercises i 6.19.1 In accordance with 10CFR50 Appendix E, Section IV.F, emergency exercises will test the adequacy of timing and content of implementing procedures and methods, test emergency equipment and communication networks, I test the public notification system, and ensure that ' ERO personnel are familiar with their duties. 6.19.2 Exercises will be conducted biennially to test the on-site and off-site emergency plans. 6.19.3 To meet NRC and FEMA requirements, the exercises are varied so as to test, at least once every six years, all major components of the WCGS, State, and County plans and response organizations.
i l 1-1 - 3 Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP'06-002 3 (RERP) g Reference Use Page 51 of 83 m C 1. Exercises should be conducted under various weather conditions. 2 2. 1 At least once every six years an unannounce'd co exercise is initiated between 6:00 p.m. and 4 a.m.
'\ -
- 3. At least once every six years an ingestion pathway
{ exercise shall be conducted.
} 6.19.4 Designated observers from federal, state, local governments, and WCGS observe the required exercises.
M Certain of these observers also evaluate the exercise.
- 1. The Superintendent Emergency Planning has the lead responsibility for ensuring corrective actions associated with emergency planning are initiated.
- 2. Critiques are conducted following each exercise to identify and correct noted deficiencies.
6.19.5 Prior to an exercise a scenario package is prepared which contains the following: o Basic objective of each exercise and appropriate evaluation criteria l o Simulated events l o Dates, time periods, places, and participating organizations l o Time schedule of all initiating events o Descriptive scenario addressing the conduct of the exercise which should include public information activities, off-site fire department assistance, simulated casualties, rescue of personnel, use of protective clothing and radiological monitoring teams i o Description of the arrangements for, and advance materials to be provided to official observers l 6.20 Emergency Plan And Procedures Administrative Controls ! ! 6.20.1 The NSRC is responsible for assuring that a review of the WCGS Emergency Preparedness Program will be i performed, at least once every twelve months, in accordance with 10CFR 50. 54 (t) . i
- 1. Personnel performing this review will have no I direct responsibility for implementation of the Emergency Preparedness Program.
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4 Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 3 (RERP) ! g Reference Use Page 52 of 83 i M C 2. The review should evaluate interfaces with state !
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and local governments, licensee drills, exercises, l 2 capabilities, procedures and emergency facilities. l 2
- 3. The results of the review are reported to owner ?
M representatives and WCGS Senior Management and ;
} shall be retained for at least five years.
M
- 4. Correction of review findings are evaluated and implemented using normal WCGS procedures. [
t M
- 5. The applicable portions of the review shall be made l
available to the State and local governments, j 6.20.2 The Superintendent Emergency Planning ensures the { coordination and documentation of RERP reviews and
- revisions. The RERP is revised annually to incorporate changes identified during drills, exercises and the 10CFR 50.54 (t) review. l l 6.20.3 Action items required to be performed in a time period !
l are allowed a 1.25 times frequency grace period to ! f complete the item. : i 6.21 Recovery Plan 6.21.1 The Recovery Plan is activated in a progressive manner when the Site or Off-site Emergency Manager determine stabilized plant conditions warrant the transition of the emergency response efforts to the recovery phase. 5.21.2 If a General Emergency has been reached, NBC and KDEM concurrence shall be obtained prior to downgrading. 6.21.3 The EPPs provide the general plans for reentry and recovery and describe the means by which decisions to : relax protective measures are reached.
- 1. Evaluation of the status of the three fission product barriers is used for de-escalation. As the situation improves and barriers are restored, the next lower level of event may be declared.
! 2. De-escalation may also occur if conditions have i stabilized such that the potential for l re-escalation to a higher level has been removed and a controlled situation exists. A declaration I of de-escalation is provided by the Emergency
- Manager based on known information and recommendations of the ERO.
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Revision: 0 7 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 (RERP) { Reference Use Page 53 of 83 m C 3. Guidelines are provided for Reentry Team (s) to + perform surveys and monitoring activities to be ! employed for initial reentry. - h 6.21.4 During the recovery process the normal procedures f employed for configuration control, reporting, f interfaces with regulatory agencies and support groups, {g exposure control, environmental monitoring, and procurement of supplies and services shall be utilized. l
]- 6.21.5 The Recovery Plan utilizes the necessary technical, 9
i administrative, managerial and support personnel that ; may be required for the recovery phase of emergency ; response,.as determined by Site or Off-site Emergency l Managers. The responsibilities and functions of the Emergency Managers and staff are detailed in the EPPs. ., { 7.0 RECORDS ! i 7.1 None i i 8.0 FORMS ! 1 I 8.1 APF-06-002-01, EMERGENCY ACTION LEVELS :
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_, Reference Use Page 54 of 83 m O ATTACHMENT A (Page 1 of 1) 2 EFFECTIVE 10-MILE EPZ POPULATION CENTERS h in
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Distance (miles) And
]' Significant Population Centers Approximate Direction From The Site Population Subzone To Population Center l
Burlington, KS 2,735 SW-1 3.5 Southwest New Strawn, KS 428 W-1 3.4 West-Northwest Waverly, KS 618 NE-2 11.5 North-Northeast LeRoy, KS 568 SE-3 11.1 South-Southeast ' Aliceville, KS 40 SE-2 9.3 Southeast Ottumwa, KS 20 NW-1 6.8 West-Northwest Sharpe, KS 10 N-1 2.4 North Jacob's Creek 70 W-2 10.0 West The population numbers were taken from the 1990 census. 1
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H Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN m AP 06-002 (RERP) i { Reference Use Page 55 of 83 m ! O ATTACHMENT B
.(Page 1 of 3) .0 SUBZONE EVACUATION TIMES l' !
0) B.1 Table B.1 lists each subzone and the population in that subzone. ' TABLE B.1 d POPUIATION BY SUREONE ; Evacuation Subzone Evacuation Zone Population
\ ._ Center (CTR) 0-2 75 W North-1 (N-1) 2-5 65 Northeast-1 (NE-1) 2-5 53 East-1 (E-1) 2-5 53 Southeast-1 (SE-1) 2-5 40 i South-1 (S-1) 2-5 40 Southwest-1 (SW-1) i 2-5 2,779 ~
West-1 (W-1) 2-5 450 Northwest-1 (NW-1) 2-5 82 i North-2 (N-2) 5 - 10 121 , Northeast-2 (NE-2) 5 - 10 697 Northeast-3 (NE-3) 5 - 30 132 East-2 (E-2) 5 - 10 70 Southeast-2 (SE-2) 5 - 10 128 Southeast-3 (SE-3) 5 - 10 634 Southeast-4 (SE-4) 5 - 10 53 South-2 (S-2) 5 - 10 88 Southwest-2 (SW-2) 5 - 10 88 West-2 (W-2) 5 - 10 132 Northwest-2 (NW-2) 5 - 10 114 B.2 Total Coffey County population equals 8,404 persons (1990 census). Effective 10-Mile Emergency Planning Zone Subtotals are as follows: , o Effective 0 mile zone = 75 persons Effective 2 mile zone = 3,562 persons o i o Effective 5 mile zone = 2,257 persons o Effective 0 mile zonn - 5,894 persons B.3 Table B.2 lists evacuation confirmation time parameters. TABLE B.2 l EVACUATION CONFIRMATION TIME PARAMETERS Speed Vehicles EPZ Miles Number of Between Effort in Assumed Confirmation l Location Traveled Houses Houses Vehicle Available Time l Burlington 36 1,183 5 mph 105 Hrs 11 9.5 Hrs l New Strawn 3 229 5 mph 20 Hrs 3 6.6 Hrs LeRoy 9 289 5 mph 43 Hrs 5 8.6 Hrs . Waverly 7 280 5 mph 33 Hrs 4 8.3 Hrs l Rcmaining 289 649 30 mph 80.5 Hrs 8 10.3 Hrs EPZ* 1 i Includes the evacuation confirmation of the U.S. Army Corps of Engineers areas at John Redmond Reservoir, Coffey County Lake, and the U.S. Fish and Wildlife Service area north of the Neosho River. I 1 l
_f Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 m (RERP) g Reference Use Page 56 of 83 i m C ATTACHMENT B (Page 2 of 3) SUBZONE EVACUATION TIMES
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.c B.4 Table B.3 lists Ambulances and Funeral Directors (FD) who may ;
o3 assist with transportation fer non-ambulatory persons, distance
\ to travel, time to travel, capacity of each vehicle, and an accumulative total of person capacity.
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\ TABLE B.3 l TRANSPORTATION FOR NON-AMBUIATORY PERSONS l (O Availability Due To Weather Accumulated l Location Distance Capacity Good Adverse (minutes) Capacity (persons) !
(miles) (minutes) (persons) Coffey Co Ambu 10 Imnediate Immediate 10 Yates Center FD 23 4 30 40 14 Allen Co Ambu 49 6 47 67 20 Lyon Co Ambu 40 12 48 68 32 Emporia FD 40 4 48 68 36 Franklin Co Ambu 46 9 55 79 45 Chanute FD 50 6 60 86 51 Garnett FD 30 3 36 52 54 Eureka FD 55 4 66 94 58 McPherson FD 122 2 132 210 60 Osawatomie FD 70 4 78 120 64 Lyndon FD 28 3 30 48 67 LIFESTAR 50 (air) 2 30 Limited by 69 I ceiling and visibility I l 1 Anderson Co Ambu 30 8 25 45 77 l B.5 Tables B.4 and B.5 lists the 10-mile evacuation time for average ! and adverse weather conditions. l TABIE B . 4 l 10 MII2 EVACUATION TIMES FOR AVERAGE WEATHFR CONDITIONS (HOURS)
- i l
Subzone Effective 2-mile Effective 5-mile Effective 10-mile I CTR 0.7 0.9 1.1 l CCL 2.5 2.5 2.5 JRR 2.5 2.5 2.5 N-1 - 0.8 1.1 NE-1 - 0.9 1.1 E-1 - 0.9 0.9 SE-1 - 0.8 1.0 S-1 - 0.9 1.2 SW-1 - 1.4 1.5 W-1 - 1.0 1.1 ! NW-1 - 0.8 1.0 I N-2 - - 0.9 ! NE-2 - - 1.0 NE-3 - - 0.9 E-2 - - 0.8 SE-2 - - 0.9 SE-3 - - 1.0 SE-4 - - 0.7 S-2 - - 0.9 SW-2 - - 0.9 W-2 - - 0.8 NW-2 - - 0.7
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O Reference Use Page 57 of 83 1 rn C ATTACHMENT B (Page 3 of 3) )' SUBZONE EVACUATION TIMES
.c I TABLE B.5 CO \ 10 MILE EVACUATION TIMES FOR ADVERSE WEATHER CONDITIONS (HOURS) l Effective Effective Etfective l l --
Subzone 2-mile 5-mile 10-mile ' tJ CTR 0.7 1.0 1.3 1 g' CCL 2.5 2.5 2.5 j JRR 2.5 2.5 2.5 N-1 - 0.9 1.3 IO NE-1 - 1.0 1.1 ! E-1 - 1.0 1.1 SE-1 - 0.9 1.1 S-1 - 0.9 1.4 SW-1 - 1.7 1.8 W-1 - 1.1 1.3 NW-1 - 0.9 1.1 N-2 - - 1.0 NE-2 - 1.1 NE-3 - - 1.0 E-2 - - 0.9 SE-2 - - 1.0 SE-3 - - 1.1 SE-4 - - 0.8 S-2 - - 1.0 SW-2 - - 0.9 W-2 - - 0.9 NW-2 - - 1.0 NOTE: For all transportation-dependent people, including the non-ambulatory occupants of the Golden Age Lodge, Sunset Manor Nursing Home and the Coffey County Hospital, an evacuation time of 2.5 hours is estimated using area resources. Evacuation times are based on the population from the 1980 census. The 1980 population was larger than the population determined from the 1990 census. Since the evacuation times are based on a greater population than what is l presently in Coffey County, and because the condition of some of the evacuation routes has improved (e.g. paving), the times are considered to be conservative. i l
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$ Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN 'AP 06-002 i (RERP) j
{ Reference Use Page 58 of 83 m C ATTACHMENT C I ! (Page 1 of 8) CROSS REFERENCE BETWEEN NUREG 0654, RERP, AND WCGS PROCEDURES
- .D
.0 0654 RERP Comments Procedure
\ Section Section A. -
ARSIGtteFT OF RESPONSIBILITY (Organisation Control) g 1. a 6.5, 6. 6, WCGS onsite and off- EPP 06-002, TECHNICAL SUPPORT l 6.7, 6.8, site organizations CENTER OPERATIONS g 6.9 EPP 06-003, EMERGENCY OPERATION l FACILITY OPERATIONS EPP 06-004, PUBLIC INFORMATION ORGANIZATION 1.a 6.10, Outside organizations 6.11, 6.12, j 6.13 i 1.b 6.5 - l 6.13 1.c FIGURE 6 1.d 6.5, 6.6, EPP 06-001, CONTROL ROOM 6.7, 6.8, OPERATIONS l
- 6. 9 EPP 06-002, TECHNICAL SUPPORT I CENTER OPERATIONS EPP 06-003, EMERGENCY OPERATION FACILITY OPERATIONS 1.e 6.5.2 Notifications are made from the centrol l room, at the i direction of the Site Emergency Manager. !
2.a & 2.b N/A l
- 3. ATTACH. G i
- 4. 6.8.2 Off-site Emergency EPP 06-003, EMERGENCY OPERATION Manager FACILITY OPERATIONS l 6.8.11 Administrative EPP 06-003, EMERGENCY OPERATION Manager FACILITY OPERATIONS B. - ONSITE EMERGENCY ORGANIEATION
- 1. 6.5
- 2. 6.5.2 Site Emergency EPP 06-001, CONTROL MOOM Manager OPERATIONS
- 3. 6.5.2, Transfer of control EPP 06-001, CONTROL ROOM l 6.6.5, from the SS to the OPERATIONS l l 6.8.2 Site Emergency EPP 06-002, TECHNICAL SUPPORT l Manager. CENTER OPERATIONS
( EPP 06-003, EMERGENCY OPERATION ! FACILITY OPERATIONS l
u W Revision: 0 u RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 ! 3 (REhP) ! o Reference Use Page 59 of 83 i A ;
-O t ATTACHMENT C ~
(Page 2 of 8) CROSS REFERENCE BETWEEN NUREG 0654, RERP, AND WCGS PROCEDURES JJ ; D ! 0654 RERP Comments l N Procedure ! Section Section
+
B. [
~
- ONSITE ENERGENCY ORGANIEATION '
- 4. 6.5.2, Responsibilities of EPP 06-001, CONTROL ROOM '
i , s.. 6.6.5, the SS, DED, DEM OPERATIONS 6.8.2 EPP 06-002, TECHNICAL SUPPORT C0 CENTER OPERATIONS EPP 06-003, EMERGENCY OPERATION i FACILITY OPERATIONS 2 5 6.5, 6. 6, Major ERO positions EPP 06-001, CONTROL ROOM 6.7, 6.8, and their functions OPERATIONS I 6.9 EPP 06-002, TECHNICAL SUPPORT , CENTER OPERATIONS $ EPP 06-003, EMERGENCY OPERATION . FACILITY OPERATIONS 1
- 6. 6.5, 6.6, Interfaces between j 6.7, 6.8, WCGS and outside 6.9, Fig. organizations l 5& 6 '
7a. 6.8.11 Administrative EPP 06-003, EMERGENCY OPERATION Resources Manager FACILITY OPERATIONS 7b. 6.21 Recovery Plan EPP 06-003, EMERGENCY OPERATION FACILITY OPERATIONS i 7c. 6.8.2 Duty Emergency EPP 06-003, EMERGENCY OPERATION ' Manager FACILITY OPERATIONS 7.d 6.9 On-site & Off-site EPP 06-002, TECHNICAL SUPPORT Public Information CENTER OPERATIONS Coordinator & Wolf EPP 06-003, EMERGENCY OPERATION Creek Public TACILITY OPERATIONS Information Officer EPP 06-004, PUBLIC INFORMATION ORGANIZATION
- 8. 6.13 Specify contractors /
organizations available on request
- 9. 6.10 Identify local support agencies C. - EMERGENCY RESPONSE SUPPORT AND RESOURCES i
1.a 6.8.2 Persons authorized to j request assistance 1.b 6.12 Expected Federal resources 9
b 2 Revision: 0 RADIOLOGICAL EMERGENCY RESPOMSE PLAN AP 06-002 (RERP) Li Reference Use Page 60 of 83 m ! O ATTACHMENT C (Page 3 of 8) CROSS REFERENCE BETWEEN NUREG 0654, RERP, AND WCGS PROCEDURES _C I 0654 RERP Comments Procedure f Section- Section C. - EMERGENCY RESPONSE SUPPORT AND RESOURCES
] ~
l 1.c 6.4.1, Space is prov!ded for p( 6.4.2, NRC personnel in the 6.4.4, Control Room, TSC, and { 6.12.5 EOF. The EOF also has limited space for state and local personnel. 2a. N/A 2.b 6.8.12
- 3. 6.*4.7 Identify radiological laboratories
- 4. 6.13 and Identify other ATTACH G facilities and organizations which could assist D. - EMERGENCY CIASSIFICATION SYSTEM
- 1. 6.2 Emergency EPP 06-2.1, EMERGENCY Classifications CLASSIFICATION
- 2. 6.2 Initiating conditions EPP 06-2.1, EMERGENCY CLASSIFICATION
- 3. & 4. N/A E. - NOTIFICATION METHODS AND PROCEDURES
- 1. 6.5.2, Notifications EPP 06-007, EMERGENCY NOTIFICATIONS 6.6.5, 6.8.2
- 2. 6.16.1, Notification of EPP 06-015, EMERGENCY RESPONSE 6.5.3 responding personnel ORGANIZATION CALLOUT
- 3. 6.5.2, Initial notifications EPP 06-007, EMERGENCY NOTIFICATIONS 6.6.5, 6.8.2 4.a 6.5.2, Follow-up Notifications EPP 06-007, EMERGENCY NOTIFICATIONS thru 6.6.5, j
4.n 6.8.2 I
- 5. N/A
- 6. Attach B Evacuatior times 1
- 7. N/A i l F. - EMERGENCY CCDe40NICATIONS 1.a 6.5 l 1.b 6.5.2 1.c 6.5.2, l 6.5.4, i
l 6.6.5, ' l 6. 6. 9, t 6.8.2 l 1.d 6.4.4, 6.16
l l n l
, Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAM AP 06-002 I m .I (RERP)
Reference Use { Page 61 of 83 ! m j O i ATTACHMENT C i (Page 4 Of 8) h CROSS REFERENCE BETWEEN NUREG 0654, RERP, AND WCGS PROCEDURES I 0654 RERP Comments Procedure f Section Section F. - EMERGENCY CGGRINICATIONS g 1.e 6.5.3, ERO Callout EPP 06-015, EMERGENCY RESPONSE s 6.16.1
) 1.f 6.4.4, 6.5.2, ORGANIZATION CALLOUT EPP 06-001, CONTROL ROOM g,, OPERATIONS 6.5.4, EPP 06-002, TECHNICAL SUPPORT 6.6.9, CENTER OPEPATIONS !
6.16.1 EPP 06-003, EMERGENCY OPERATION i FACILITY OPERATIONS i
- 2. 6.10.6 Coffey County ambulances are in radio contact with !
the County Sheriff
- 3. 6.15, EPP 06-018, MAINTENANCE OF 6.18.1, EMERGENCY FACILITIES AND !
6.18.6 EQUIPMENT / COMMUNICATION CHECKS G. - PUBLIC EDUCATION AND INNORMATION
- 1. 6.17.5, L;'T.6
- 2. . 5, t .6 3.a 6.! .
EPP 06-004, PUBLIC INFORMATION 16.6.2 ORGANIZATION 3.b 6.4.5 i ! 4.a 6.9.10 EPP 06-004, PUBLIC INFORMATION ORGANIZATION 4.b 6.9.1, EPP 06-004, PUBLIC INFORMATION 6.9.10 ORGANIZATION 4.c 6.4.5, EPP 06-004, PUBLIC INFORMATION 1 6.9.8 ORGANIZATION
- 5. 6.16.2 H. - EMERGENCY FACILITIES AND EQUIPRENT
- 1. 6.4.2, EPP 06-002, TECHNICAL SUPPORT 6.4.3, CENTER OPERATIONS
- 6. 6, 6.7 j
- 2. 6.4.4, EPP 06-003, EMERGENCY OPERATION l 6.8 FACILITY OPERATIONS ;
l
- 3. 6.8 Establish EOF.
i 4. 6.6.1, . 6.8.1, Fig.2,3,4 4 ATTACH. D I
__ _ __. _. . _ .. __ . - . . . . - _ _ _ . _ _ . _ _ _ _ . . . _ _ . . m._.__ 1 1 Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 f
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Reference Use Page 62 of 83 l m-O ATTACHMENT C (Page 5 of 8) CROSS REFERENCE BETWEEM.NUREG 0654, RERP, AND WCGS PROCEDURES {
.D 2 l 0654 RERP Comments Procedure CO Section Section H. - EMERGENCY FACILITIES AND EQUIPMENT g 5.a 6.14.3, g 6.14.4, 6.14.5 5.b 6.14.2 EPP 06-011, EMERGENCY TEAM FORMATION AND CONTROL 5.c 6.14.2 5.d 6.14.6 6.a 6.14.1 6.b 6.14.1 i EPP 06-011, EMERGENCY TEAM and FORMATION AND CONTROL Figure B 6.c 6.14.7 7 6.15 EPP 06-011, EMERGENCY TEAM 1
i FORMATION AND CONTROL
- 8. 6.14.3
- 9. 6.4.3 EPP 06-002, TECHNICAL SUPPORT CENTER OPERATIONS
- 10. 6.15 EPP 06-018, MAINTENANCE OF EMERGENCY FACILITIES AND EQUIPMENT / COMMUNICATION CHECKS l 11. 6.15 l 12. 6.14.7 EPP 06-011, EMERGENCY TEAM FORMATION AND CONTROL I. - ACCIDENT ASSESSMENT
- 1. 6.2 APF 06-002-01, EMERGENCY ACTION l LEVELS
! 2. 6.3.20, EPP 06-017, CORE DAMAGE 6.14.2 ASSESSMENT METHODOLOGY 3.a 6.3.7 EPP 06-012, DOSE ASSESSMENT 3.b 6.3.7 EPP 06-012, DOSE ASSESSMENT
- 4. 6.3.7 EPP 06-012, DOSE ASSESSMENT
- 5. 6.14.3
- 6. 6.3.7 EPP 06-012, DOSE ASSESSMENT
- 7. 6.3.8, EPP 06-011, EMERGENCY TEAM 6.8.4 FORMATION AND CONTROL
- 8. 6.3.7, 6.5.2, l 6.6.5, 6.8.2 a
t : M . y. t t - Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 i r .. (RERP) , y Reference Use Page 63 of 83 l A ~~ l l 0 ATTACHMENT C l l (Page 6 of 8) ! CROSS REFERENCE BETWEEN NUREG 0654, RERP, AND WCGS PROCEDURES l _0 i A 0654 RERP Comments Procedure f f Section -Section I. - ACCIDENT ASSESSMENT i
- 9. 6.4.2, Lower bound for g 6.4.4 iodine measurement [
_. capability is 1.0E- l' g 7uci/ce.
- 10. 6.3.7 EPP 06-012, DOSE ASSESSMENT 11, !
6.3.8. EPP 06-011, EMERGENCY TEAM FORMATION AND CONTROL J. - PROTECTIVE RESPONSE ! 1.a thru 6.3.10, EPP 06-010, PERSONNEL I 1.d 6.3.11, ACCOUNTABILITY AND EVACUATION I 6.6.5
- 2. 6.3.10, j Fioure 1
- 3. 6. 3. 9, 6.3.12
- 4. 6. 3. 9, 6.3.12 )
- 5. 6.3.10, EPP 06-010, PERSONNEL /
j 6.3.11, ACCOUNTABILITY AND EVACUATION 6.6.5 l 6.a thru 6.3.13, EPP 06-013, EXPOSURE CONTROL AND 6.c 6.3.14 f PERSONNEL PROTECTION ' EPP 06-011, EMERENCY TEAM FORMATION AND CONTROL 7 6.3.3, A EPP 06-006, PROTECTIVE ACTION RECOMMENDATION
- 9. N/A 10.a & Fig. I 10.b 10.c 6.1. 6, 6.1.7, 6.10.2 10 d & N/A 10.1 10.m Attach. E EPP 06-006, PROTECTIVE ACTION RECOMMENDATION l
- 11. & 12. N/A K. - RADIOLOGICAL EXPOSURE CONTROL l 1.a thru 6. 4 . 6, 1.g 6.10.5, i 6.10.6 1
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h Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 (RERP) { Reference Use Page 64 of 83 m C ATTACHMENT C (Page 7 of 8)
,c, CROSS REFERENCE BETWEEN NUREG 0654, RERP, AND WCGS PROCEDURES 2 0654 RERP Comments M Procedure Section Section \ 2. 6.3.16, - EPP 06-001, CONTROL ROOM 6.5.2, OPERATIONS U 6.6.5, '\
EPP 06-002, TECHNICAL SUPPORT 6.B.2 CENTER OPERATIONS CG EPP 06-003, EMERGENCY OPERATION FACILITY OPERATIONS 3.a & 3.b 6.3.17, 6.4.2, 6.15.1
- 4. N/A 5.a & 5.b 6.3.21, i 6.3.23 l 6.a thru 6.3.22, 6.c 6.3.23, ATTACH. E
- 7. 6.3.13, 6.4.6 L. - NEDICAL AND PUBLIC MEALTH SUPPORT
- 1. ~~"
6.10.5
- 2. 6.4.6 1
- 3. N/A'
- 4. 6.10.6 i M. - RECOVERY AND REENTRY PIANNING AND POST-ACCIDENT OPERATIONS 1.0 6.21
{ 2, 6.21 EPP 06-008, RE-ENTRY, RECOVERY, {
- 3. 6.21 AND TERMINATION OPERATIONS
- 4. l 6.3.7 This is not specifically {
l identified as a post-accident function l N. - EXERCISES AND DRILLS ' 1.a & l'. b 4.17, 6.18 l 2.a 6.18 I 2.b 6.18.2 2.c 6.18.3
- 2.d 6.18.4 EPP 06-009, DRILL AND EXERCISE
[ 2. e (1) 6.18.5 REQUIREMENTS 2.e(2) 6.18.5 3.a thru 6.19.5 3.f 1
- 4. 6.19.4
- 5. 6.19.4 I
, U Revision: 0 i
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! O Reference Use Page 65 of 83 M 1 O ATTACHMENT C (Page 8 of 8) CROSS REFERENCE BETWEEN NUREG 0654, RERP, AND WCGS PROCEDURES ) _D ! C ] 0654 RERP Comments ! D3 Procedure ! Section Section
\ 0. - RADIOIDGICAL EMERGENCY RESPONSE TRAINING l 1.a g 6.17 g 1.b N/A j 2. 6.17.2, , EPP 06-021, TRAINING PROGRAMS i
to 6.17.6 3. 6.4.6
- 4. 6.17.2
- 5. 6.17 P. - RESPONSIBILITY FOR THE PIANNING EFFORT: DEVELOPIENT, PERIODIC REVIEW AND DISTRIBUTION OF EMERGENCY PLANS l 1. '
6.17
- 2. 5. 3, 6.17.2
- 3. 6.20.2
- 4. 6.20.2 !
i
- 5. 6.20.3
- 6. 6.10, 6.11
- 7. ATTACH. C
- 8. Table of Contents i and ATTACH. C i
- 9. 6.20.1 10, 6.20.2
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I i M l Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 I 3 (RERP) kJ Reference Use Page 66 of 83 m-O ATTACHMENT D (Page 1 of 1) h WCGS MINIMUM STAFFING FOR EMERGENCIES
,,[i 93 Capability For g '
Additions: **
] FUNCTIONAL AREA POSITION TITLE OR EXPERTISE Ott SWIFT 60 mine 90 mina b Plant Operations & Shift Supervisor (SRO)' ' 1 - -
t Assessment of Supervising Operator (SRO) 1 - - Operational Aspects Reactor Operator (RO) 2 - - g) Nuclear Station Operator 4 - - Emergency Direction and Duty Emergency Director 1* - - Control Notification / Emergency Communicator 1* 3 - Communication Radiological Accident DEM and staff - - 5 Assessment & Support of Operational Accident Sr. Health Physics (HP) Assessment Expertise - 1 -
)
HP Personnel 1 B - Chemistry Personnel 1 1 - Plant System Shift Technical Advisor 1 - - Engineering, Repair & Corrective Actions Core / Thermal Hydraulics Eng. - 1 - Electrical Eng. - 1 - Mechanical Eng. - 1 - Radwaste Operator 1 Mechanical Maint. . 2 - Electrical Maint. 2 - 1 I&C Technician . 1 - Protective Actions (In- HP Personnel le 4 _ Plant) Fire fighting = Tire -- FB per Tech Local Local Brigade (FB) Specs Support Support Rescue Operations and -- 2* Local Local First Aid Support Support All per Site Access Control and Security Personnel Security Accountability Plan TOTAL 10 25 5 May be provided by shift personnel assigned to other functions. ! It is a goal to add, in accordance with this table, to the on-shift capabilities I when determined necessary after a declared Emergency.
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i Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN E AP 06-002 i (RERP) { Reference Use Page 67 of 83 I m-C ATTACHMENT E ! (Page 1 of 4) l _c EPA / KANSAS PROTECTIVE ACTION GUIDES I f E.1 Table E.1 lists the exposure limits in accordance with t {2 EPA-400-R-92-001, May 1992, and KANSAS PROTECTIVE ACTION GUIDES. ! I y TABLE E.1 i EXPOSURE LIMITS A. Whole Body Exposure Pro 3ected TEDE i [ W
- 1. General Population 1 to 5 REM
- I 2 Emergency Workers 5 REM
- 3. Lifesaving Activities >25 REM **
1 B. Exposure to Radioiodines in a Plume Proiected Thyroid Committed Dose l l E,quivalent (CDE) !
- 1. Emergency Workers and Immobile Populations
>25 REM )
- 2. Lifesaving Activities No specific upper REM limit *** l C. Exposure from Surface Water Containing Radioactive Materials Concentration Level ;
- 1. General Population Concentration in excess of Kansas i Radiation Protection Guidelines, App. l A, Table II, Column II
- 2. Emergency Workers N/A l
The lowest value should be used if there are no major local constraints in providing protection at that level, especially to sensitive populations. Local constraints may make lower values impractical to use, but in no case should the higher value be exceeded in determining the need for protective action. EPA-400 provides a limit of >25 REM, with no upper bounds for lifesaving activities. Consistent with RTM-93, WCGS has chosen to establish an upper limit of ~/5 REM. No specific upper limit is given for thyroid dose since in lifesaving l activities, complete thyroid loss might be an acceptable sacrifice if a life can be saved. However, this should not be necessary if respirators and/or thyroid protection for rescue personnel are available as a result of adequate planning. E.2 Table E.2 lists recommended protective actions for exposure to a gaseous plume and controlling relocation / return. TABLE E.2 RECCle(ENDED PROTECTIVE ACTIONS EXPOSURE TO A GASEOUS PLUME Projected Dose (REM) Actions Considered Comments General Population: No specific action required. Monitoring will be continued Considerations may be given until the extent of the TEDE <1 to: incident can be determined
- 1. An advisory to seek and the situation fully shelter and await further evaluated.
instructions. l 2. Voluntary evacuation. i 3. Monitor environmental l radiation levels. l l
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0 I l ATTACHMENT E ' (Page 2 of 4) A EPA / KANSAS PROTECTIVE ACTION GUIDES General Population: Evacuation should be Monitoring 1s performed so I initiated. Shelter may be the projected dose can be c) TEDE 1 preferable in some g situations, determined and initial i __' Thyroid CDE 5 actions re-evaluated for ! possible adjustments. Re- ! U. evaluation will be 1
\ continuous as more data )
becomes available. ! General Population: Administration of stable Monitoring is performed to (o iodine. This requires Thyroid CDE 25 and confirm the evacuation area above approval of State officials. or as a basis for necessary adjustments in the evacuation area. Emergency Team Control exposure of For non-lifesaving emergency Workers: emergency team members tasks. through the use of time, TEDE 5 distance, shielding, job assignment, prophylactics and respirators. Emergency Team Workers Control exposure of (Lifesaving) emergency team workers through use of time and task , TEDE 25 assignment. CONTROLLING RELOCATION / RETURN Projected Dose (REM) Actions Considered Comments General Population: No action required. Public Monitoring will be performed TEDE <2 REM /lst year announcements of monitoring to determine that projected or results and time required concentrations do not result
<0.5 REM /for any for passage of peak in doses exceeding PAGs.
other year concentration may be made. General Population: Do not allow return or Initial actions (if time relocate those that are 1 permits) and re-evaluation l TEDE greater than present. of initial actions will be I above, based upon monitoring of { water directly from the supply and after treatment. Use of KI is not planned for general population in Kansas. l i 4 I i I
m y R: vision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN 7 AP 06-002 (RERP) a Reference Use Page 69 of 83 m C ATTACHMENT E (Page 3 of 4) I EPA / KANSAS PROTECTIVE ACTION GUIDES E.3 Table E.3 lists recommended protective actions for different I accident phases. (O
\ - TABLE E.3 N RECCHENDED PROTECTIVE ACTIONS FOR DIFFERENT ACCIDENT PHASES Accident Phase Exposure Pathway Examples Of Recommended Actions Emergency Phase (1) Inhalation of gases, Evacuation, shelter, access 0.5 to 24 hours
- radio-iodine, or control, respiration protection, c) particulate ,
prophylaxis (thyroid protection) ! Direct whole body Evacuation, shelter, access exposure ! control ! Ingestion of milk Take cows off pasture, prevent cows from drinking surface water, discard contaminated milk, or divert to stored products such as cheese { j Intermediate Phase (2) Ingestion of fruits Wash all produce, or impound 24 hours to 30 d3ys* produce, delay harvest until l l approved uncontaminated produce ' can be substituted Ingestion of water Cut off contaminated supplies, substitute from other sources, i filter, demineralize i External exposure and Relocation decontamination, access inhalation control l Long term phase (3) Ingestion of food and Decontamination, condemnation, or over 30 days
- water contaminated destruction of food; deep plowing, from the soil either condemnation, or alternate use of by resuspension or land l
uptake through roots External exposure from Relocation, access control, deposition material or decontamination, deep plowing inhalation of resuspended material (1) Emergency Phase - Time period of major release and subsequent plume exposure (2) Intermediate Phase - Time period of moderate continuous release with plume ' exposure and contamination of environment i (3) Long Term Phase - Recovery period l
" Typical" Post-Accident time periods l
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.{ Reference Use Page 70 of 83 l
m CY ATTACHMENT E (Page 4 of 4) l EPA / KANSAS PROTECTIVE ACTION GUIDES ; _D f E,4 Protective action guides for ground contamination ingestion ! g exposure pathway are as follows.
\
l 2 Action Levels Recommended Protective Actions ( g 1. Projected whole body dose above the 1. Evacuation of affected areas. j ground - 1 REM. 2. Restriction of entry to contaminated !
\ 2. Ground contamination levels = 200 ~
offsite areas until radiation level uCi/m2 at t = 1 hr post-accident. has decreased to State approved ! M 3. Exposure rate = 12 MREM /hr at 1 meter levels. f above ground at t = 1 hr post- ! accident. E.5 Protective action guides for food contamination ingestion l' exposure pathway are as follows: Action Levels Concentration In Milk Pacture Grass Total Intake Via all ; Food Pathways ! 0.5 REM WB 5 REM WB or bone; or bone; 1.5 REM 15 REM i Thyroid Thyroid Nuclide* Preventive Emergency Preventive Emergency Preventive Emergency l' (pCi/L) (pC1/L) (pCi/kg) (pCi/kg) (pCi) (pCi) I-131 0.015 0.15 0.05 0.5 0.09 0.9 I (Thyroid) CS-137- 0.24 2.4 1.3 13 7 70 (WB) Sr-90 0.009 0.09 0.18 1.8 0.2 2 l (Bone) - Sr-89 0.14 1.4 3 30 2.6 26 (Bone) Recommended Protective Actions l Preventive Emergency l l 1. Removal of lactating dairy cows from Isolate food from its introduction into { contaminated pasture and substitution commerce after considering: l of uncontaminated stored feed. 1. Availability of other possible 1
- 2. Substitute source of uncontaminated actions.
water. 2. Importance of particular food in
- 3. Withhold contaminated milk from market nutrition.
to allow radioactive decay. 3. Time and effort to take action. l
- 4. Divert fluid milk to production of 4. Availability of other foods. l dry whole milk, butter, etc. '
- If other nuclides are present, Reg. Guide 1.109 will be used to calculate the i doss to the critical organ (s). Infants are the critical segment of the l population, j +
References:
U.S. Food and Drug Administration, Federal Register, Vol. 47, No. 205, october 22, 1982.
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.0 USAR CHAPTER 15 POSTULATED EVENTS 3
0) _Feedwater system malfunctions that result in decrease of feedwater temperature-
\_ Feedwater system malfunctions that result in increase of feedwater system flow Excessive increase in secondary steam flow 9 Inadvertent opening and failure to close of SG ARV or safety viv g Steam system piping failure (inside containment)
Steam system piping failure (outside containment)
~~
02 Loss of external load (Main Generator trip) ! Turbine Trip
]
Inadvertent closure of MSIVs j Loss of condenser vacuum & other events resulting in turbine trip 1 Loss of non-emergency AC power to station auxiliaries Loss of normal feedwater Feedwater system pipe break Partial loss of forced RCS flow Complete loss of forced RCS flow RCP shaft seizure (locked rotor) RCP shaft break Uncontrolled RCCA bank withdrawal from a suberitical of low power startup condition Uncontrolled RCCA withdrawal at power RCCA misalignment Startup of inactive RCP at an incorrect temperature CVCS malfunction resulting in a decrease in the boron concentration in the RCS Inadvertent loading and operation of a fuel assembly in improper position RCCA ejection accidents Inadvertent ECCS operation at power CVCS malfunction that increases RCS inventory' Inadvertent opening, with failure to close, of pressurizer safety or relief valve l Break in instrument line or other lines from RCS pressure boundary,that penetrate containment i SG tube rupture l LOCA spectrum i Radioactive waste gas decay tank failure l Postulated radioactive releases due to liquid tank failure Fuel handling accident (inside containment)
.ruel handling accident (ruel Building)
Spent fuel cask drop ! Anticipated transients without scram
- END -
l l i I i
_ . _ . . . _ _ _ _ _ _ - . . _ - _ _ _ . ~ ._ .. __._ _.. .- . . _ _ _ __ H ! 3 Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 f 3 (RERP). l 3 Reference Use Page 72 of 83 i m O ATTACHMENT G (Page 1 of 1)
.c LETTERS OF AGREEMENT D
to i
)
j Party: I U i
\
The Coffey County Sheriff's Office Board of Trustees-Fire District No'. 1, Coffey County, KS Newman Memorial Hospital Coffey County Hospital and Ambulance Service l l Topeka Air Ambulance Inc. (d.b.a. Life Star) Wolf Creek Nuclear Operating Corporation / Union Electric Co. Emergency Mutual Assistance Agreement INPO (Support During an Emergency) Department of Energy ** Nuclear Regulatory Commission ** j National Weather Service *** l l EPRI/INPO/NEI/ Member Utilities Coordination Agreement on l Emergency Information Westinghouse As of January 1, 1987, the Letters of Agreement in this Supplement are transferred from Kansas Gas and Electric Company to the Wolf Creek Nuclear operating Corporation. These Letters of Agreement are maintained on file and { l may be reviewed upon request. ' These LOAs will not be updated. They have been superseded by the publication of the " Federal Radiological Emergency Response Plan" in the Federal Register j on 11/8/85. ! As of 8/25/93, the National Weather Service stated in writing that a Letter f of Agreement with WCGS is unnecessary. Their " National Plan for Radiological I i Emergencies at Commercial Nuclear Power Plants," November 1982, remains in effect.
- END - I 4 i l
1 l i
L.
;f~ Revision: 0-RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 '3 u (RERP)
D Reference Use Page 73 of 83 rri
' C1 ATTACHMENT H
* (Page 1 of 1)
REPORTING OF INCIDENTS PER 10 CFR 20
. 0
.D CO
.2202 l Tek;;is & Tek ,;. .2203 Wrinen
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-c Immedsste Notification 24 Hour Notificanon .30 Day Notification RADIATION VALUES WCGS NRC KDEM N INCIDENTS WCGS NRC KDEM WCGS NRC. KDEM
\
TEDE 25 REM (.25 Sv) X X X X -X ' X. (0 S REM (.05 Sv) X X X X X. X MPE.1201 X X X X Shallow dose to 250 Rad X X X X X X-skin or extremities 50 REM X X X X X X in excess of MPE .1201 X X X X To the eye 75 REM (.75 Sv) X X 15 REM (.15 Sv) X X X MPE .1201 X X X Emuent release 5 ALI X X- X X X X excess of I ALI - X X X X X X MPE.1201 X X X' X X = Indicates' noti?.'ication is required MPE = Maximum Permir,sible Exposure DAC = Derived Air Concentration WCGS = Wolf Crees Generating Station NRC = Nuclear Regulatory Commission KDEM -= Kansas Division of Emergency Management ALI = Annual Limit on Intake 1
, , ,. ,, ,. ,, - , , --c ,w. g-
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RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 (RERP) { Reference Use Page 74 of 83 m O FIGURE 1 EFFECTIVE 10 MILE EPZ, SUBZONES AND EVACUATION ROUTES
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Y Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 f (RERP) - y Reference Use Page 75 of 83 in C FIGURE 2 MINIMUM SHIFT COMPLEMENT o
.I SHIFT SUPERVISOR (SS)
(0 (1 SRO)
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M s., , SHIFT ENGINEER (SE) (1) {ij 1P
.._ ._ SUPERVISING OPERATOR (SO)
(1 SRO) ir REACTOR OPERATORS (RO) . STATION OPERATORS (2) (4) CHEMISTRY TECHNICIAN (1) HEALTH PHYSICS TECHNICIAN (1)
- Direction
-- Technical Guidance SRO = Senior Reactor Operator STA = Shift Technical Advisor NOTE:
The SE or an SRO meeting the STA requirements of the NRC must be on shift in Modes 1 thru 4
r-H Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002
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C FIGURE 3 TSC/OSC ORGANIZATION
.D 2 SITE EMERGENCY MANAGER (0
\
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RADIOLOGICAL MAINTENANCE ADMNSTRATNE OPERATIONS COORDINATOR COORDINATOR COORDINATOR COORDINATOR
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FACluTY MAINTENANCE ADMINISTRATWE
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ENS TECHNICIAN PLANNER ASSISTANT COMMUNICATOR TEAM DIRECTOR WA USE OPERATIONS
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- EMERGENCY **** 3 ENGINEERING RESPONSE TEAM j TEAM
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OPERATIONS COMMUNICATOR l
. . = . _ . . . . - _ - . . . - _ _ . . - - . . . . . . . . _ . . - . - - - . . . . . . -.-
r.a - y Ravision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002
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(G e i OPERATIONS i RADIOLOGICAL ADMINISTRATIVE COORDINATOR ! COORDINATOR COORDINATOR
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OPERATIONS HPN FACluTY ADMINISTRATIVE RECORDER COMMUNICATOR TECHNICIAN ASSISTANT
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I l DOSE ASSESSMENT TEAM DIRECTOR l COORDINATOR l ! DOSE g l i COMMUNICATOR i TECHNICIAN l l l LOCATED AT COUNTY EOC EMERGENCY i T RESPONSE TEAM REPRESENTATIVE AT COUNTY J 1 l
.. - - - . .. . . - - - _ . . - . . - . . _ - . - - - . - - - ~ .
H Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 7 (RERP) y
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Reference Use Page 78 of.83 rri D. FIGURE 5 PUBLIC INFORMATION ORGANIZATION 0 COFFEY COUNTY WOLF CREEK STATE OF KANSAS FEMA _D NRC KGE/KCPUKEPCo PUBUC PUBLIC PUBUC PUBUC PUBUC py REPRESENTATIVE INFORMATION INFORMATION INFORMATION INFORMATION INFORMATION g (IC) OFFICER OFFICER OFFICER
- OFFICER OFFICER OC) DC) (IC)
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VOLF CREEK (0 PUBUC INFORMATION MANAGER OC) TECHNICAL INFORMATiON SUPPORT M MITER ONSITE PUBUC INFO. OC) MESSENGER COORDINATOR (IC) OC) (TSC) PHONE TEAM MEDIA CENTER RUMOR CONTROL OFFSITE PUBUC INFO. ! MANAGER MANAGER COORDINATOR COORDINATOR ! OC) (MC) (KCPL GO) l (EOF) i PHONE TEAM MEDIA UAISON IN (KCPL GO) MEDLA REGISTRAR I (MC) AUDIO VISUAL { SUPPORT (MC) i c
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- n m EMERGENCY ORGANIZATIONS INTERFACES $ 3.
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- yj yQ d" 38.<
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- Any of these functions may be activated at any emergency classification level.
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Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 l f m Reference Use (RERP) Page 80 of 83 ' l C FIGURE 7 i WCGS EMERGENCY RESPONSE FACILITIES 11 l CG l
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l y Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 , 1 (RERP) t Reference Use Page 82 of 83 rn C FIGURE 9 WATERBORNE PATHWAY SAMPLING LOCATION 1 J l
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H y Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 7 (RERP) g Beference Use Page 83 of 83 m O FIGURE 10 FIXED SIREN SIGHTING ?s llll///lll////llII// //// A e e - M == # 1 , L .p w l--r.- Tam ), n, m
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I i Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 E (RERP) l g Referenca Use Page 1 of 83 j m ' O TABLE OF CONTENTS j i SECTION TITLE 2 PAGE 3 1.0 PURPOSE 3 f 2.0 SCOPE 3 i
3.0 REFERENCES
AND COMMITMENTS 4 ; 4.0 DEFINITIONS 5 l p( 5.0 RESPONSIBILITIES 9 l 2 6.0 PROCEDURE 11 l g~ 6.1 Site Description 11 ; 6.2 Emergency Classifications 12
^
6.3 Emergency Measures 13 6.4 Emergency Faciiities 17 ! 6.4.1 Control Room Facilities 17 6.4.2 Technical Support Center Facilities 17 6.4.3 Operations Support Center 19 6.4.4 Emergency Operations Facility (EOF) 19 6.4.5 Public Information Facilities 20 6.4.6 Onsite Medical Facility 21 6.4.7 State and County Facilities 22 6.5 Control Room Organization 23 6.6 Technical Support Center (TSC) Organization 24 6.7 Operations Support Center (OSC) Organization 29 )
,_ 6.8 Emergency Operations Facility (EOF) Organization 29
( ) 6.9 Public Information Organization 33
\_/ 6.10 Local Offsite Organizations 36 6.10.2 Coffey County Commissioners 37 6.10.3 Coffey County Sheriff's Office 37 6.10.4 Coffey County Fire District #1 (CCFD) 38 6.10.5 off-site Medical Treatment 38 6.10.6 Coffey Cct .4ty Ambulance Service 39 6.10.7 Radiological Emergency Assistance Center / Training Site (REAC/TS) 39 6.11 State Organizations 39 6.11.3 Kansas Division of Emergency Management (KDEM) 40 6.11.4 Kansas Department of Health and Environment (KDHE) 40 6.11.5 Kansas Highway Patrol (KHP) 41 6.11.6 Kansas National Guard 41 6.11.7 Kansas Department of Transportation (KDOT) 42 6.12 Federal Organizations 42 6.12.2 Federal Emergency Management Agency (FEMA) 42 6.12.3 Department of Energy (DOE) 42 6.12.4 Nuclear Regulatory Commission (NRC) 42 6.13 Additional Support Agencies 43 6.13.1 Vendor and Architect / Engineers (A/E) 43 6.13.2 Regional Utility Support 43 6.13.3 Institute of Nuclear Power Operations (INPO) 44 6.13.4 American Nuclear Insurers (.A NI) 44
(__
\_/
) 6.14 Plant Monitoring 44 6.14.1 Nuclear Plant Information System (NPIS) 44 6.14.2 Onsite Radiological Monitors 45 6.14.3 Meteorological Monitoring System 46
i 7 Revision: 0' RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 L3 (RERP) ! g Reference Use Page 2 of 83 i m
\
TABLE OF CONTENTS
/ SECTION TITLE 3 PAGE t
1 6.14.4 Seismic Monitoring System 46
- 6.14.5 Hydrologic Monitoring 46
\ 6.14.6 Fire Protection 46 6.14.7 Laboratory Facilities 46
{ s 6.15 Emergency Supplies 6.16 Communications 47 j 47 t 6.16.1 Communication Equipment 47 g~ 6.16.2 Communication Dissemination 48 6.17 Emergency Plan Training 49 6.18 Emergency Plan Drills 49 6.19 Emergency Planning Exercises 50 6.20 Emergency Plan And Procedures Administrative Controls 51 6.21 Recovery Plan 52 7.0 RECORDS 53 8.0 FORMS 53 ATTACHMENT A EFFECTIVE 10-MILE EPZ POPULATION CENTERS 54 ATTACHMENT B SUBZONE EVACUATION TIMES 55 ATTACHMENT C CROSS REFERENCE BETWEEN NUREG 0654, RERP, AND WCGS PROCEDURES 58 ATTACHMENT D WCGS MINIMUM STAFFING FOR EMERGENCIES 66 ATTACHMENT E EPA / KANSAS PROTECTIVE ACTION GUIDES 67 ATTACHMENT F USAR CHAPTER 15 POSTULATED EVENTS 71 O ATTACHMENT G LETTERS OF AGREEMENT ATTACHMENT H REPORTING OF INCIDENTS PER 10 CFR 20 72 73 ' FIGURE 1 EFFECTIVE 10 MILE EPZ, SUBZONES AND EVACUATION ROUTES 74 FIGURE 2 MINIMUM SHIFT COMPLEMENT 75 i FIGURE 3 TSC/OSC ORGANIZATION 76 l FIGURE 4 EOF ORGANIZATION 77 j FIGURE 5 PUBLIC INFORMATION ORGANIZATION 78 i FIGURE 6 EMERGENCY ORGANIZATIONS INTERFACES 79 ) FIGURE 7 WCGS EMERGENCY' RESPONSE FACILITIES 80 ' FIGURE 8 DIRECT RADIATION PATHWAY SAMPLING LOCATIONS 81 FIGURE 9 WATERBORNE PATHWAY SAMPLING LOCATION 82 FIGURE 10 FIXED SIREN SIGHTING 83 1 I I i l l' lO
h Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 2> i (RERP)
- n. Reference Use Page 3 of 83 m
U 1.O PURPOSE O
\
b /. 1.1 The purpose of the Wolf Creek Generating Station (WCGS) i g Radiological Emergency Response Plan (RERP) is to classify g{ emergencies, assign responsibilities for actions, and to establish the lines of authority and communications to protect the public and plant personnel in the event of an emergency. ; M - g 2.0 SCOPE
) 2.1 The RERP has been developed in accordance with 10CFR Part 50, Paragraph 50.47 and Appendix E, Regulatory Guide 1.101 and '
generally follows the guidelines of NUREG 0696 and 0654. The ; RERP is sensitive to a broad spectrum of emergency conditions which have been postulated for a commercial pressurized water reactor. Although the probability of an accident is low, the RERP is maintained to assure the safety and well-being of plant personnel and members of the public in the vicinity of WCGS. 2.2 The RERP interfaces with several related documents such as the Administrative Procedures (APs) and Emergency Plan Procedures (EPPs). Detailed instructions necessary to support the RERP are included in these procedures and are available for training, drill, and actual emergency use. The RERP references the WCGS Fire and Security Plans, Vendor contingency plans as well as (~N those of medical support facilities and the Institute of Nuclear i Power Operations (INPO). This document has been designed to coordinate with the State Emergency Operations Plan and the Coffey County Contingency Plan for Incidents Involving Commercial Nuclear Power, which goverv the activities of these support groups in response to events at WCGS. 2.3 The RERP is based on a graduated, escalating level of emergency response which is activated as conditions at the plant warrant. This approach provides the flexibility necessary to ensure adequate emergency response to a spectrum of possible events. The RERP is designed to control emergency response activities ranging from initial event detection, classification of the event, notification of off-site authorities and providing protective action recommendations to the county and state. 2.4 The RERP reflects three chief phases of activation. First the response is dominated solely by the site staff, next the onsite and off-site public information facilities are jointly activated, and finally the recovery efforts are performed by site, public information facilities, vendor, and other critical ( support groups. I O r
7 Revision: 0 3 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 (RERP) D Reference Use Page 4 of 83 m C 2.5 The WCGS normal operating organization and its functional responsibilities are described in the WCGS Technical (/} 3, Specifications, Administrative Procedures, Human Resources
, company organization charts and the WCGS Updated Safety Analysis Report (USAR). No further discussion of the normal operating i g( organization is contained within the RERP.
y 2.6 The WCGS design bases accidents and various plant systems are g listed and described in the WCGS Technical Specifications and , USAR. No further discussion of these accidents or systems is l co contained within the RERP. ) 3.O REFERENCES AND CObMITNENTS 3.1 References 3.1.1 Coffey County Contingency Plan for Incidents Involving Commercial Nuclear Power (County Plan) 3.1.2 State of Kansas, Appendix 12, Nuclear Facilities Incidents Response Plan to Annex N, Nuclear Emergencies of the State Emergency Operations Plan (State Plan) 3.1.3 Updated Safety Analysis Report (USAR) e' 3.1.4 NUREG 0654, Criteria For Preparation And Evaluation Of Radiological Emergency Response Plans And Preparedness l In Support Of Nuclear Power Plants 3.1.5 NUREG 0696, Functional Criteria For Emergency Response Facilities I 3.1.6 NUREG 0737, Clarification Of TMI Action Plan Requirements 3.1.7 Title 10, Code Of Federal Regulations, Part 50 3.1.8 Regulatory Guideline 1.101 3.1.9 Regulatory Guide 1.145 3.2 Commitments 3.2.1 RCMS #93-325, Emergency Action Levels Converted To NUMARC EALs
- 3.2.2 APF 06-002-01, EMERGENCY ACTION LEVELS, required to I
l have a USQD and a 50.54 (q) review performed for each ( revision.
) 3.2.3 RCMS #96-076, Administrative EAL Changed To Reflect
-' NUMARC/NESP-007 Definitions 1
$h Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN m AP 06-002 (RERP) n Reference Use Page 5 of 83 m
U 3.2.4 RCMS #96-077, System Malfunction EAL Changed To Provide Better Guidance For Loss Of Equipment Needed In Modes One Through Four [g 3.2.5 RCMS #96-078, Natural Phenomena EAL Changed To Cover Ice And Other Natural Occurrences Which Could Impact Safety Systems M i 4.0 DEFINITIONS to 4.1 Administrative Procedures (APs) i 4.1.1 Procedures which provide programmatic responsibilities i and'are typically used to solve problems, assemble ! documentation, process information, and present results ' of administrative functions. i 4.1.2 Administrative procedures control activities affecting quality or nuclear safety. 4.2 As Low As Reasonably Achievable (ALARA) 4.2.1 Making every reasonable effort to maintain exposures to radiation as far below dose limits as is practical, consistent with the purpose for which the licensed activity is undertaken, taking into account the state I O' of technology, the economics of improvements in relation to benefits to the public health safety, and l other societal and socioeconomic considerations. l l 4.3 Alert 4.3.1 Events are in process or have occurred which invol-actual or potential substantial degradation of the level of safety of the plant. Any releases are j expected to be limited to small fractions of the Environmental Protection Agency (EPA) Protective Action ! Guideline (PAG) exposure levels. 4.4 Assessment Actions 4.4.1 Those actions taken during or after an accident to obtain and process information that is necessary to j make decisions to implement specific emergency measures. l 4.5 Coffey County Emergency Operations Center (County EOC) a 4.5.1 The base of operations for the Coffey County Emergency j Response Organization. 4 1 I
2 R$ vision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 m (RERP) a Rnferenc3 Uso Page 6 of 83 m C 4.6 Consultant / Vendor I I yc/ 4.6.1 The Nuclear Steam System Supplier (NSSS), l 7 Architect / Engineer, and other organizations who have [ available multidiscipline teams ready to support ) [ emergency response and Recovery Operations. 4.7 Control Room j 4.7.1 The location at the WCGS from which the reactor and its g auxiliary systems are normally controlled. l 4.8 Drill 4.8.1 A supervised activity used to develop and maintain skills. On the spot correction of erroneous ' performance is permitted. 4.9 Emergency Action Levels (EALs) l 4.9.1 Radiological dose rates; specific contamination levels l of airborne, waterborne or surface-deposited l concentrations of radioactive materials; or specific l instrument indications that may be used as thresholds l for designating a particular class of emergency. l (_,) 4.10 Emergency Alert System (EAS) 4.10.1 A coordinated network of broadcasters (e.g. Radio, Television, Cable) that allows the President to address the nation, Governors to address their State and public safety officials to address local citizens with emergency information. 4.11 Emergency Classification 4.11.1 A system used to define the severity of emergencies into one of four categories based upon projected or confirmed emergency action levels. Classifications listed in order of increasing severity are Notification of Unusual Event (NUE), Alert, Site Area (SAE) and General Emergency (GE). 4.12 Emergency Operations Facility (EOF) 4.12.1 This facility serves as a base of operations for all emergency plant support activities, site environmental surveillance, communications with supporting agencies, and the WCGS Emergency Organization. k N_. l l
Z Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 m (RERP) 1 a Reforcnc3 Usa Page 7 of 83 l m 3, 4.13 Emergency Plan Procedures (EPPs) l f J; y 4.13.1 Specific procedures providing step-by-step actions to I c. implement the WCGS Radiological Emergency Response and [ Recovery Plans, and to provide guidance to improve or ( terminate an emergency situation. 4.14 Evacuation Registration Centers
\
4.14.1. Facilities designated for receiving personnel g evacuating the Emergency Planning Zone (EPZ) for , l accountability, contamination monitoring and decontamination. 4.15 Exclusion Area 1 4.15.1 That area within a 1200-meter radius of the Containment Building in which WCGS has the authority to determine all activities including exclusion or removal of 4 persons and property from the area. l 4.16 Executive Management 1 4.16.1 Those members of WCGS management at the vice president 7, level and above. () 4.17 Exercise i 4.17.1 An event that simulates a radiological emergency condition, incorporates the integrated capability of the basic elements existing within the Radiological Emergency Response Plan (RERP). These events are normally evaluated by FEMA / NRC. 4.18 General Emergency (GE) ! 4.18.1 Events are in process or have occurred which involve actual or imminent substantial core degradation with potential for loss of containment integrity. Releases can reasonably be expected to exceed EPA Protective l Action Guideline exposure levels off-site for more than l the immediate site area. 4.19 Immediate Notification 4.19.1 Notification made to State of Kansas and Coffey County authorities within 15 minutes of a declared emergency at WGCS. 4.20 Information Clearinghouse (IC)
\' ~ '
/
4.20.1 The facility where news statement and news conference materials for the media are prepared.
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? 4.21 Kansas State Emergency Operations Center (State EOC) } g/ 4.21.1 The command-and-control center for the state.
n [ 4.22 Licensed Operators 2 4.22.1 WCGS Reactor Operators and Senior Reactor Operators who y are licensed under 10CFR55 and who stand watches on y shift and report to the Shift Supervisor. h, 4.23 Media Center (:MC) 4.23.1 Facility utilized as a focal point for giving information to the media through news conferences. 4.24 Notification of Unusual Event 4.24.1 Events in process, or have occurred, which indicate a potentia) Jegradation of the level of safety of the plant. D> releases of radioactive material requiring off-site response or monitoring are expected unless further degradation of safety systems occurs. 4.25 off-site i y 4.25.1 Any area outside the Exclusion Area of WCGS. 4.26 Onsite 4.26.1 Any area inside the Exclusion Area of WCGS. 4.27 Operations Support Center (OSC) 4.27.1 A staging area for emergency teams to support the emergency response effort. 4.28 Protective Actions 4.28.1 Those emergency measures taken before or after a release of radioactive material has occurred for the purpose of preventing or minimizing radiological exposures to personnel. 4.29 Protective Action Guides (PAGs) 4.29.1 Guides promulgated by the Environmental Protection l Agency (EPA) which set dose limits for the evacuation of the public during an accident condition at a nuclear power plant. 7 3
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I Revision: 0 3 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 (RERP) o Referenca Use Page 9 of 83 m U 4.30 Radiologically Controlled Area (RCA) (l 4.30.1 An area to which access is controlled by WCGS for purposes of protection of individuals from exposure to [ radiation or radioactive materials.
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l 4.31 Recovery u
? 4.31.1 hast-emergency efforts initiated to restore WCGS to full operation or place the plant in a safe shutdown g condition until full operation can be resumed.
4.32 Site Area Emergency (SAE) 4.32.1 Events are in process or have occurred which involve actual or likely major failures of plant functions needed for protection of the public. Any releases are not expected to result in exposure levels which exceed EPA Protective Action Guideline exposure levels except near the site boundary. 4.33 Technical Support Center (TSC) 4.33.1 The TSC serves as a center outside of the Control Room that acts in support of the command-and-control g- function and houses the OSC organization. Plant status (3~') and diagnostic information are available at this location for use by technical and management personnel in support of reactor command-and-control functions. 5.0 RESPONSIBILITIES 5.1 Site Emergency Director 5.1.1 Assumes command and control of the emergency and directs onsite response to stabilize plant conditions. 5.2 Off-site Emergency Manager 5.2.1 Assumes command and control of the emergency and interfaces with off-site agencies. 5.3 Superintendent Emergency Planning 5.3.1 Ensures the Emergency Planning Program is implemented and maintained as required to protect the health and safety of the public. 5.3.2 Ensures changes to the overall Emergency Planning Program meets the standards of 10CFR50.47 (b) and the (v) requirements of 10CFR50, Appendix E.
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# Program will be performed at least once every twelve !
months in accordance with -10CFR 50.54 (t) .
) 5.5 President and Chief Executive Officer 5.5.1 Maintains overall authority and responsibility for the WCGS Emergency Preparedness Program.
5.6 Public Information Officer (PIO) 5.6.1 The PIO-has the authority and responsibility for the WCGS Public Information Organization and all plant. information disseminated to the media. 5.7 Shift Supervisor (SS) 5.7.1 The Senior Reactor Operator designated by WCGS management with immediate onsite authority and responsibility for the safe and proper operation of-the plant. This position is staffed at all times. The SS is responsible for the initial evaluation of any abnormal or emergency situation and for directing the appropriate response. O He assumes responsibilities of the Emergency Manager until relieved. l l l 1 1 s i iO l l i
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. 6.0 PROCEDURE
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'l g- 6.1 Site Description 6.1.1 WCGS is a Pressurized Water Reactor (PWR) nuclear f( generating station operated by Wolf Creek Nuclear Operating Corporation (WCNOC).
M 6.1.2 WCGS is located near the center of Coffey County, Kansas (KS), about 3.5 miles northeast of Burlington,
,a the county seat, 90 miles southwest of Kansas City, MO and 55 miles south of the state capital Topeka, KS.
6.1.3 The immediate site environs are sparsely populated. Burlington and New Strawn are the major population centers. John Redmond Reservoir (JRR) and Coffey County Lake (CCL) are the major recreational facilities. Most of the seasonal or daily shifts in ; population are associated with recreational areas ' around JRR and CCL. Approximately 70% of the annual visitors to the John Redmond Reservoir and Coffey County Lake come to the area during the summer months. 6.1.4 Coffey County totally encompasses the 10-mile Plume Exposure Emergency Planning Zone (EPZ) which forms a / t
~'} major consideration in the RERP. % ,J 6.1.5 The total population of the effective 10-mile EPZ is shown in ATTACHMENT B, SUBZONE EVACUATION TIMES. With the exception of Burlington and the other population centers listed in ATTACHMENT A, EFFECTIVE 10-MILE POPULATION CENTERS, the population density of the effective 10-mile EPZ is approximately 4.4 persons per square mile. Other than the WCGS, there are no large industries in the area.
6.1.6 Principal geographical features within the effective 10-mile EPZ are the Neosho River, JRR, and CCL. The land around WCGS is flat with scattered low hills. Dense vegetation in the form of large trees exists on the banks of the river and in recreational areas. There are no topographical features within the effective 10-mile EPZ that significantly influence the design of the Alert and Notification System.
- 1. Sparsely populated farm land comprises the majority of the effective 10-mile EPZ.
- 2. The site also demonstrates favorable topography,
'r3) demography, and meteorology, which have been factored into many analyses that support the emergency planning effort.
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- 3. The Neosho River is oriented northwest-southeast (K/') and extends to within 3 miles southwest of the x plant.
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- 4. The main dam of the John Redmond Reservoir is 3.5
{' miles west of the plant. This water conservation pool is approximately 4 miles in diameter with a g surface area of 15 square miles. _ 5. The Coffey County Lake is approximately 7 miles g long with a nonnal surface area of 8 square miles. 6.1.7 Approximately 99% of the 10-mile EPZ is located within Coffey County and 1% within Anderson County. The EPZ has been defined by developing sub-zones based upon natural and political subdivisions. These have been described for evacuation zones approximating 2, 5 and 10-mile radial rings. This distribution allows ready identification of areas to be evacuated and facilitates public recognition of subzones in which they work or reside. FIGURE 1, EFFECTIVE 10 MILE EPZ, SUBZONES AND EVACUATION ROUTES, presents the 2, 5 and 10-mile radial zones and subzones which provides the basis for the design of an alert and notification system.
;} The meteorological conditions within the effective 10-6.1.8
(/ mile EPZ is characterized by a distinctly continental climate with warm humid summers and highly variable winter weather. Maritime tropical air originating over the Gulf cf Mexico is the dominant air mass from June through August. This air mass is quite humid resulting in considerable thunderstorm activity. From November through February, continental polar air dominates the climate. 6.2 Emergency Classifications 6.2.1 10 CFR Part 50, Appendix E, Section IV.C, requires a classification scheme of four specific levels of emergencies. NUMARC/NESP 007 is identified within REGULATORY GUIDE 1.101 and is considered by the NRC as an acceptable alternative method to that described in Appendix 1 to NUREG 0654. [ Commitment Step 3.2.1] 6.2.2 An emergency class is a qualitative estimate of the status of the plant. Inputs to the emergency classification system include the status of plant l systems and the levels of radiation in plant areas and ( effluents. However, an emergency class does not give a (~} qualitative or quantitative estimate of the subsequent (/ status of the plant or radioactive release.
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6.2.3 The emergency classes are used by off-site authorities O to determine the level of preplanned actions to be a
# taken by their emergency organizations. Protective j actions taken on behalf of members of the public are i the legal responsibility of state and local government. ;
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- 1. The functional interfaces between WCGS and other
{ ss emergency organizations are shown in FIGURE 6, I EMERGENCY ORGANIZATIONS INTEREACES. l i ! $ 6.2.4 The classification system used at WCGS is an approach that ranges from primarily event-based for Unusual Event to primarily symptom or barrier-based for General Emergencies. This is to better assure that timely recognition and notification occurs, that events occurring during refueling and cold shutdown are I appropriately covered, and that multiple events can be effectively treated. The Emergency Action Levels (EALs) are contained in APF 06-002-01, EMERGENCY ACTION LEVELS. [ Commitment Step 3.2.1] 6.3 Emergency Measures 6.3.1 Protective actions to minimize personnel exposure are i taken when an incident has occurred, or may occur, ) which could result in a fission product barrier , challenge or breach. In addition, protective actions l are taken for personnel onsite for situations such as fires or flooding, where personnel safety is i threatened. 6.3.2 Emergency measures consist of assessment, corrective, and protective actions. The Shift Supervisor and j Senior Reactor Operators assume immediate responsibility for accident assessment and mitigation. 'l The RERP and detailed emergency actions are based on the assumption that, in an emergency, licensed operators take appropriate measures to maintain or l return the facility to a safe condition, in accordance with operating license conditions and the technical specifications. 6.3.3 EPPs provide the mechanism for providing information to state and local authorities for their use in making decisions for ordering off-site protective actions. l 6.3.4 Actions to protect the general public, and criteria for j their implementation, are described in the State Plan. Protective action recommendations are made to the County and State authorities.
3 Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 3 (RERP) g Reference Use Page 14 of 83 m C[ 1. ATTACHMENT E, EPA / KANSAS PROTECTIVE ACTION GUIDES, ( 'T illustrates the EPA / Kansas PAGs for members of the is/ 7 public in the vicinity of WCGS and contains information typical of what may be used for the PAR guidelines. The Attachment provides guidelines and t(' action levels to be used to develop protective action recommendations. Actions taken off-site are {\ the responsibility of County and State officials. _ 2. Evacuation is the normally anticipated off-site l n protective action. Sheltering may be the preferred ' protective action when it will provide protection equal to or greater than evacuation. ATTACHMENT B, SUBZONE EVACUATION, contains evacuation times for the general and transient public. 6.3.5 Contact points for information concerning the County Plan, protective measures, and special needs of the handicapped are the County Emergency Preparedness Office. 6.3.6 Additional resources available for accident assessment include the Post Accident Sampling System, accident monitoring, and in-plant iodine instrumentation under accident conditions. Detailed discussions of these rescurces and their capabilities are found in the USAR. (~/) \_ 6.3.7 The Emergency Dose Calculation Program (EDCP) is a computerized method to provide dose estimates using actual or estimated meteorological data (wind speed, wind direction, degree of cloud cover, day or night determination) and radiological effluent data (actual measurements, estimated values based upon USAR source terms, or field measurements). EDCP is designed to: [ Reference Step 3.1.9)
- 1. Use radiological and meteorological information to provide an estimate of off-site exposure.
- 2. Be capable of estimating release rates and off-site exposures from off-site field team data.
- 3. Be capable of estimating release rates and off-site exposures for an unmonitored, pressure driven containment release using the Containment High Area Radiation Monitor readings and changes in containment pressure.
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- 4. Off-site dose predictions when combined with actual O
release duration information and meteorological data during an event, provide sufficient data to l estimate the cumulative population dose resulting l [ 1 from the event. The actual off-site population dose is confirmed by off-site monitoring, sampling 2 and analysis. l 6.3.8 Radiological monitoring teams have a goal of 60 minutes _- from the declaration of Alert or greater emergency to g be ready for deployment to confirm effluent readings l and verify plume emission and locations. 6.3.9 ! FIGURE 7, WCGS EMERGENCY RESPONSE FACILITIES, provides i l a view of the off-site area, showing the location of i .the EOF. FIGURE 8, DIRECT RADIATION PATHWAY SAMPLING LOCATIONS, shows the fixed air sampling and TLD locations. FIGURE 9, WATERBORNE PATHWAY SAMPLING LOCATIONS, shows similar information for the critical 1 receptor bioassay measurements that are taken. 6.3.10 At.an Site Area Emergency, General Emergency, or when accountability is required, all personnel not responding to an Emergency Response Facility report to an assembly area for accountability and additional O information. ERO personnel report to their assigned emergency facility. Security reports the results of l accountability to the TSC. 1' l 6.3.11 If the Exclusion Area is evacuated, then Security shall direct =an inspection of the lake and land area within i the Exclusion Area but outside of the Protected Area to ensure that all personnel not responding to an Emergency Response Facility are evacuated from the Exclusion Area. 6.3.12 WCGS procedures contain decontamination instructions and guidelines. Methods for determining if the individual is a potential inhalation or ingestion contamination case are also provided. The Radiological Coordinator or appropriate Health Physics supervisory personnel will review the records generated by decontamination procedures. 6.3.13 Respiratory protective devices and protective clothing are stored at several locations onsite and at the EOF. The use of protective clothing and respiratory protection equipment is governed by normal WCGS procedures. 6.3.14 A supply of potassium iodide (KI) is maintained at the Control Room, TSC and the EOF to be used in the event that an individual may be exposed to radiciodine.
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l Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 l 7, (RERP) g Reference Use Page 16 of 83 m O 6.3.15 There are suggested levels of exposure to be accepted ( ')
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in emergencies. Immediate reentry may be necessary to save a life, account for missing personnel, or secure vital equipment. The Emergency Managers are ultimately ! responsible for exposure control and can permit the ( receiving of up to 5 REM per person for work activities, 10 REM for saving valuable equipment and 25 l g REM for lifesaving after consulting with the NRC, if ; ( feasible. Exposure which might exceed 25 REM, for ' lifesaving activities, must be approved by an Emergency g Manager. Although EPA and NRC does not provide I specific guidance for the upper bounds for lifesaving ' exposure, WCGS has chosen to use the following criteria: l i 1. Emergency Managers shall not knowingly permit an individual's exposure to exceed 25 REM, unless it is for lifesaving activities or protection of large populations. Emergency Managers shall not knowingly permit an individual to enter a high dose area if the projected Total Effective Dose Equivalent (TEDE) is expected to exceed 75 REM. o Those individuals designated to exceed 25 REM must be volunteers and be fully aware of the risks involved. [}
- 2. Emergency Managers should obtain the advice and concurrence of the Radiological Coordinators in approving additional exposure.
6.3.16 Under emergency conditions, normal exposure controls are maintained. This is ensured by the on-shift Health Physics Technician (HP) in the Control Room, the Team Directors in the TSC and EOF. 6.3.17 The Radiological Coordinator has responsibility for maintaining exposure control for site activities, including establishment of access control at alternate locations. Strict exposure control of individuals passing through the access point is maintained on a 24- . hour-per-day basis. ! 6.3.18 In order to enhance the exposure control process and to provide dosimetry for an expanded number of people, dosimetry vendors are available to expedite shipment of extra dosimetry devices to supplement existing onsite i supplies of dosimetry equipment and to supply personnel to assist in onsite appraisal of exposures. 1 f~ 6.3.19 When activated, the Emergency Response Team covers emergency sampling, surveying, analysis, and hazard evaluation. i
i Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 N'$ g Reference Use (RERP) Page 17 of 83 m O 6.3.20 The Post Accident Sampling System (PASS) accomplishes O 2 automatic, remote-controlled reactor coolant system and containment atmosphere sampling while minimizing D personnel exposure. (
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6.3.23 Personnel, instruments, and equipment are to be monitored at the access control point. Personnel and equipment decontamination is controlled in accordance with WCGS procedures. 6.3.22 WCGS maintains control over the Exclusion Area as necessary, restoring affected onsite areas to acceptable conditions for access. 1
- 1. Reentry into affected areas is a controlled evolution. Surveys are performed, environmental samples are obtained and analyzed, and areas posted or decontaminated.
6.3.23 Contamination limits for food supplies and drinking water are based upon the State of Kansas Protective Action Guides, as presented in ATTACHMENT E, EPA / KANSAS PROTECTIVE ACTION GUIDES. 6.4 Emergency Facilities
) 6.4.1 Control Room Facilities
- 1. The Control Room is designed to be habitable under emergency conditions. The Control Room contains controls, instruments, and communications equipment l necessary for operation of the plant under both ;
normal and emergency conditions. The ventilation ' system, shielding, and structures are designed and built to permit continuous occupancy during a i postulated design basis accident.
- 2. Equipment available in the Control Room gives early '
warning and continuous evaluation of potential ' emergency situations. Portable radiation survey instruments are readily available within the l Control Room.
- 3. Access to the Control Room is controlled by the Shift Supervisor.
6.4.2 Technical Support Center Facilities l l 1. The TSC is a brisk 2 minutes and 15 seconds walk i .s(~ from the Control Room. This is sufficiently close to permit face-to-face interaction between i personnel in the Control Room and the TSC, should telephone communications become inoperable.
I Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PL N AP 06-002 (RERP) g Reference Use Page 18 of 83 m , l Ci 2. The TSC is activated in the event of an Alert or higher emergency. l
'. The TSC may also be activated during an NUE at the discretion of the Shift I
i x Supervisor. P 3. The TSC is designed to the seismic criteria of the Uniform Building Code. It is designed to withstand 100-year-recurrence winds and is located above the {[ probable maximum flood level. g a. The manually activated single-train, non-seismic Category I TSC ventilation system utilizes high-efficiency particulate air and charcoal filters. The radiciodine monitoring equipment in the TSC provides e designed minimum detectable level of 1.0E-07 uCi/cc radiciodine. A radiation monitor (including the monitor for radiciodines) alarms to alert TSC personnel if radiation levels may affect the habitability of the TSC.
- b. Portable radiation monitoring equipment, is provided in the TSC for backup radiation monitoring capability.
- c. Equipment for Emergency Response Teams is
/^' ) available in the TSC. This equipment includes
(,,/ protective clothing, dosimetry, survey meters and respirators.
- d. A diesel generator is available to provide backup power to the TSC. Until the diesel is loaded, batteries are available for Nuclear Plant Instrument System (NPIS).
- e. The TSC is sized to accommodate a minimum of 25 persons and has the same radiological habitability as the Control Room under accident conditions.
- 4. Personnel in the TSC have access to the following materials:
o WCGS USAR, Environmental Report, and Technical Specifications o Plant operating and emergency procedures o WCGS, State, and Coffey County emergency response plans (\) o System drawings, schematics, and diagrams
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O 6.4.3 Operations Support Center
- 1. The OSC is housed in the TSC and is activated
'_0 . 0 whenever the TSC is activated.
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- 2. The OSC serves as an assembly area for plant
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personnel immediately serving in emergency repair { g or Health Physics support capacity during an event. The OSC functions include the coordination, j formation and dispatch of Emergency Response Teams. U
- 3. The basement of the Security Building has been-identified as an alternate location for the OSC
' function. It contains telephones and a Gai-Tronic call box, which will allow direct communications with.the other emergency centers. Portable radios are available to key personnel to further provide ,
communications with other emergency centers. l 6.4.4 Emergency Operations Facility (EOF) '
- l. The EOF is located approximately 2.8 miles north northwest of WCGS, in the Dwight D. Eisenhower Learning Center, and is activated at an Alert or higher emergency. Following facility activation, fg overall emergency response is managed from the EOF.
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- a. This facility serves as a center for evaluation and coordination of environmental activities related to the emergency including radiological assessment and the evaluation of potential or actual radioactive releases from the plant.
- 2. The EOF design life is equivalent to that of the 1 l
plant and engineered such that a protection factor i of greater than 5 is provided to attenuate 0.7 MeV l gamma radiation.
- a. The EOF is provided with a manually activated, single-train, non-seismic Category I ventilation
' system which incorporates a HEPA filter system and fixed radiation monitors, including an alarming monitor for radioiodines (with a minimum detectable level of 1.0E-07 uCi/cc).
- b. A diesel generator is available to provide i backup power to the EOF. Until the diesel is !
} loaded, batteries are available for NPIS equipment use upon loss of AC pover. () c. The EOF is sized to accommodate at least 35 persons.
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- 3. Accommodations and telephones are provided for a O limited number of state and federal personnel.
Facilities are provided for staging field survey efforts from the EOF. f 4. The EOF serves as the base of operations for 2 evacuation assessments and for communications with g federal, state, and local response organizations. g Radio and telephone links are available to the TSC, and Control Room. 0)
- 5. Personnel in the EOF have access to the following materials:
o WCGS USAR, Environmental Report, and Technical Specifications o Plant operating and emergency procedures o WCGS, State, and Coffey County emergency response plans o System drawings, schematics, and diagrams
- 6. Arrangements have been made to use the Kansas Power O and Light (KPL) Customer Business Office located at 210 E. 2nd, Emporia, KS as the backup EOF. This facility is located approximately 28 air miles west of the plant. Telephones available at this location ensure the provision for continuity in decision-making functions and for communications supporting dose projections.
6.4.5 Public Information Facilities
- 1. At an NUE or Alert the Information Clearinghouse (IC) is established in the Dwight D. Eisenhower Learning Center. The Phone Team and Media Center (MC) are activated when needed. The IC, Media Center and Phone Team are kept in close proximity to each other to facilitate coordination of information in the form of news statements, news conferences or telephone conversations.
- a. If a radioactive release requires that the Public Information Organization be relocated, they will be moved to the Kansas State Defense Building, 2000 Topeka Ave., in Topeka, KS.
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- b. Dedicated telephone lines allow contact between O. the IC, TSC, and the EOF. The IC contains status boards, appropriate office supplies, j computer (s), printer (s), faxing and photocopy g capabilities, and outside telephone lines.
) 2. The Wolf Creek PIO, the State PIO and Coffey County g PIO communicate with the IC to obtain technical ; information. The PIOS prepare news statements at 2 the IC and coordinate their efforts.
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- 3. The MC accommodates news conferences. The MC and Media Room is established in the Dwight D.
Eisenhower Learning Center. The MC is activated by the Public Information Manager when needed during an NUE or Alert, and will be activated for an Site Area or General Emergency.
- a. If radioactive releases require that the MC be re-located,.the MC will be moved to the Nickell Memorial Armory, 2722 S. Topeka Ave., Topeka, l KS. The Topeka facility will accommodate several hundred media representatives in an auditorium and adjoining Media Room. I
( b. The Media Room is a facility setup to provide the media with a work area, audio / visual material, outside telephone lines and public information status boards.
- 4. The Kansas City Power and Light (KCPL) General Office (GO) is whare the Media Monitoring Team performs rumor contrc.. functions for WCGS, the State and Coffey County. The KCPL GO contains equipment and supplies, and has fax and telephone communications with the IC. All approved news statements and information are transmitted to the KCPL GO after the IC is activated. !
- a. The Media Monitoring Team reports to the Rumor Control Coordinator. This team notifies the Rumor Control Coordinator of any rumors or l
i misinformation heard or observed from their monitoring of the media. l ' f 6.4.6 Onsite Medical Facility 1
; 1. A medical facility located in the Clyde Cessna building, is staffed with a full time Physicians ^
Assistant. This facility is equipped to provide basic medical response capabilities. l 4 4
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- 2. First aid kits are located throughout the site.
Si) Emergency supplies and equipment are also available ('d 1 to ensure that assistance can be provided to
] contaminated personnel.
I) 3. shift personnel, trained in first aid, are 2 available onsite 24 hours per day. Priority should g be given to treating those with the most urgent medical needs. g~ 4. In the case of contamination, efforts are made to decontaminate injured personnel onsite, as soon as practicable. However, first aid or removal of the individual from a hazardous environment, takes precedence over decontamination efforts. If decontamination is not possible, the victim is covered in such a manner as to avoid any spread of contamination until medical aid can be obtained or hospitalization accomplished.
- 5. Personnel leaving the RCA are monitored for contamination. All personnel are monitored for contamination before leaving the site. I
- a. Personnel found to be contaminated must undergo
- k. decontamination under the direction of health m
physics personnel using health physics sts nlies and equipment available during routine activities. Release limits for personnel decontamination are found in the Radiation Protection Manual. 6.4.7 State and County Facilities
- 1. Coffey County Emergency Operations Center (County EOC) is located in the Coffey County Courthouse, Burlington, KS. The County EOC is a command center i for county agencies and a mustering area for l personnel who arrive in the WCGS area in response to an emergency. The County EOC is activated at the Alert level with the additional support staff activated upon declaration of an SAE or GE. Other centers are established as the emergency needs dictate.
- 2. Kansas State Emergency Operations Center (State EOC), located in the State Defense Building, 2800 South Topeka Avenue, Topeka, KS, is the command-and-control center for the State.
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- 3. The State Forward Staging Area is located about 11
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k )/ miles north of WCGS in the roadside park at the s-intersection of Old Highway 50 and U.S. 75. When i it becomes necessary for the State to dispatch emergency personnel to the plume exposure pathway f emergency planning zone (EPZ), the State activates i the State Forward Staging Area to serve as a
\y secondary base of operations for state personnel and a local contact point with Coffey County.
h 6.4.8 Evacuation Registration Centers
- 1. People in the EPZ evacuating to Emporia on I-35, should exit I-35 at Merchant Street and go to the Emporia State University Physical Education building at 18th and Merchant.
- 2. People in the EPZ evacuating to Garnett should use 12th Rd, 16th Rd, Hwy. 31 or Hwy. 57 East to go to the Anderson County Jr/Sr High School. l l
6.5 Control Room Organization 6.5.1 The Shift Supervisor is responsible for the initial evaluation and classification of any abnormal situation (} (_f and for directing the appropriate response, including initial activation of a callout.
- 1. Control Room personnel are on shift 24 hours a day.
The shift complement is shown in Figure 2, MINIMUM SHIFT COMPLEMENT. 6.5.2 Upon declaration of an emergency, the SS assumes the duties of Emergency Manager. The SS normally goes to ! and remains in the Control Room unless it is necessary for him to leave the Control Room in order to perform specific assessment, corrective, or protective actions. The SS performs the following actions: o Initiate appropriate technical measures to mitigata the event o Determine if releases have occurred, make the necessary assessment of the off-site concentration of radioactivity resulting from a release, and l evacuate non-essential personnel if necessary o Direct the activities of the Control Room Emergency Notification System (ENS) and Off-site i f-~S Communicators l l
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o Ensure immediate and follow-up notifications are made which provide sufficient information on ps/ emergency classification, plant status, off-site
} dose projections or measurements, and issue g( recommendations for off-site protective actions to authorities responsible for off-site emergency measures IJ g o Ensure notifications are made to the NRC immediately and within 60 minutes of classification a of an emergency in accordance with 10CFR50.72 (a) (3) o Ensure other notifications are made in accordance with EPPs o Activate onsite emergency teams if required j o Notify plant personnel of the change in plant status 6.5.3 Off-site Communicator l
- 1. The Off-site Communicator reports to the SS, l
performs initial notifications, and initiates callout of the ERO. () a. Non-Responding Emergency Communicators (NREC) assist in the manual callout of personnel to staff the ERO if the Automatic Dialing System (ADS) is not functioning. l 6.5.4 Emergency Notification System (ENS) Communicator
- 1. The ENS Communicator reports to the SS and maintains communications with the NRC.
6.5.5 Initial emergency response to the major functional areas is within the capabilities of the minimum operations shift complement. 6.5.6 On-shift staff augmentation is available, when deemed necessary, in accordance with ATTACHMENT D, WCGS MINIMUM STAFFING FOR EMERGENCIES. 6.6 Technical Support Center (TSC) Organization 6.6.1 TSC activation will be performed as soon as practical and within the times as stated in the following: 7- 1. During off-normal working hours, it is the goal to ('~ ) activate the TSC within 75 minutes of a declaration of an Alert or higher classification.
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- 2. During normal working hours, it is the goal to
>/ activate the TSC within 30 minutes of a declaration x of an Alert or higher classification.
6.6.2 The TSC is considered activated when the following [? positions are present, the Site Emergency Manager determines the facility is ready to activate, and y declares the facility activated:
\
_ o Site Emergency Manager to o TSC Operations Coordinator o TSC Administrative Coordinator o TSC Radiological Coordinator o Maintenance Coordinator 6.6.3 The TSC organization is shown in FIGURE 3, TSC/OSC ORGANIZATION. 6.6.4 Additional personnel to support repair efforts and recovery functions will be added as necessary. Personnel reporting from off-site may initially report (~~} to the Dwight D. Eisenhower Learning Center, and then (_j proceed to the TSC as plant / site conditions allow. 6.6.5 Site Emergency Manager
- 1. The assigned Site Emergency Manager will assume command-and-control functions and will be the top line manager responsible for the emergency. An assigned Site Emergency Manager is available 24 hours a day. The assigned Site Emergency Manager may assume command-and-control functions from the SS during an NUE if so requested by the SS.
- 2. The SS will transfer the Site Emergency Manager duties to the assigned Site Emergency Manager in accordance with EPPs. The SS resumes Control Room duties and reports to the Site Emergency Manager.
- 3. The Site Emergency Manager directs the onsite emergency effort, implements the applicable EPPs and, as appropriate, performs the following:
o Assess and verify the situation and assure that appropriate mitigating efforts are being taken i ( ~~' ) o Review initial event classification and reclassify as appropriate
Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 3 (RERP) g Reference Use Page 26 of 83 m S_s o Determine the necessity for evacuation of (
) personnel onsite J
j o If a release has occurred, make the necessary 7 assessment of the off-site concentration of radioactivity resulting from a release g o Ensure immediate and follow-up notifications are
- 3. made which provide sufficient information on i emergency classification, plant status, off-site 3 dose projections or measurements, and issue recommendations for off-site protective actions to authorities responsible for off-site emergency measures
- 4. The following responsibilities are those of the Emergency Managers and may not be delegate. These responsibilities may be divided between the Site and Off-site Emergency Managers:
o Classification of the emergency o Protective action recommendations o Authorization for notification of off-site (^'s authorities (s_- ! o Authorization of emergency exposure in excess of 10CFR20 limits 6.6.6 TSC Operations Coordinator
- 1. The TSC Operations Coordinator reports to the Site Emergency Manager and is responsible for the following:
o Supervise reactor plant operations, the g Engineering Coordinator, and ENS Communicator o Keep the Site Emergency Manager advised of plant conditions and operational manipulations
- 2. The TSC Operations Coordinator may supervise other positions as directed by WCGS procedures.
6.6.7 Engineering Coordinator
- 1. The Engineering Coordinator reports to the TSC Operations Coordinator and directs the activities
,- of the Engineering Team to technically assess plant
(. ,
) status and the severity of emergency conditions.
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'E
- 1. The Engineering Team reports to the Engineering
# Coordinator. The Team evaluates current and
- historical plant. parameters, assesses the severity
\ of the emergency conditions and magnitude of fuel
~ damage, and recommends corrective or preventive actions.
\
_. 6.6.9 TSC Emergency Notification System (ENS) Communicator to
- 1. The TSC ENS Communicator reports to the TSC Operations Coordinator and maintains communications with the NRC.
6.6.10 'TSC Radiological Coordinator j
- 1. .The TSC Radiological Coordinator reports to the Site Emergency Manager and is responsible for '
preventing or minimizing direct exposure to, or ! ingestion / inhalation of, radioactive materials I during a radiological emergency. Responsibilities ' l are as follows: l o Monitoring Dose rates and dose projections () o Monitoring Radiological survey teams' results L o Assists the On-site Emergency Manager in the formulation of recommended protective actions o Monitoring Personnel radiation exposures to ensure they are maintained in accordance with l 10CFR 20 limits unless otherwise authorized by the Emergency Manager
- 2. The TSC Radiological Coordinator will transfer off-site duties to the EOF when the EOF is activated.
! 6.6.11 TSC Administrative Coordinator l l
- 1. The TSC Administrative Coordinator reports to and assists the Site Emergency Manager to ensure that emergency notifications are performed. The TSC l
Administrative Coordinator is responsible for logistical support in the areas of TSC personnel, ! Control Room, procurement and warehouse support, 4. communications support and equipment repair services. i O l I
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- 2. After EOF activation, the TSC Administrative
('^, Coordinator directs requests for logistical support (j_) beyond onsite staff capabilities to the EOF Administrative Coordinator. 6.6.12 TSC Team Director
] 1. The TSC Team Director reports to the TSC b Radiological Coordinator and provides advise on 1 radiological safety matters concerning Emergency g Response Team activities.
6.6.13 Maintenance Coordinator
- 1. The Maintenance Coordinator reports to the Site Emergency Manager and directs the Maintenance Assistant in the coordination of emergency team l activities, including PASS team. The Maintenance !
Coordinator also directs the formation of teams to be assigned to search and rescue. l 6.6.14 Operations Communicator l
- 1. Provides data, progress and plant conditions from the Control Room via the Operations Recorders.
e s ,-
) 6.6.15 Additional Personnel
- 1. The following are examples of positions that are not needed for activation and operation of the TSC l but supplement those personnel which are essential to an emergency response:
- o Operations Recorder maintains the Operations Status Board current.
o Team Communicator reports to the Team Director and is responsible for communicating with Cnsite Teams. 1
- o. Onsite Survey Team Technicians perform tasks as assigned by the Maintenance Assistant.
l o Administrative Assistants perform facility accountability, assist the Emergency Manager, faxing and copying, log keeping, and Off-site notifications and communications as directed. t8
\j
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.g Reference Use. Page 29 of 83 m
O 6.7 Operations Support Center (OSC) Organization 6.7.1 Maintenance Assistant A 1.
" The Maintenance Assistant reports to the
\ Maintenance Coordinator and coordinates emergency l
- repair and damage control activities, coordinates
~ deployment of onsite teams, and coordinates the Y activities of the Maintenance Engineers.
\
6.7.2 Emergency Response Team (ERT) 1 l i
- 1. The ERT personnel may be selected from Health Physics Technicians (Tech), Chemistry Tech,-and ]
Instrumentation and Control, Mechanical, or Electrical maintenance. The ERT reports to the Maintenance Assistant and is responsible for , l repairs, surveys, sampling, analysis, and search ! and rescue. I 6.7.3 Additional Personnel
- 1. The following are examples of positions that are not needed for activation and operation of the OSC but supplement those personnel which are essential to an emergency response.
o Chemistry Technicians perform emergency chemical sampling and provide post-accident sample analysis. o Maintenance Planners develop repair plans for use by the emergency repair and damage control teams. o Warehouse Support Personnel assist in locating and securing parts and equipment from the warehouse. 6.8 Emergency Operations Facility (EOF) Organization 6.8.1 EOF activation will be performed as soon as practical ! and within a goal of 90 minutes of a declaration of an L Alert or higher Emergency. i
- 1. The EOF is considered activated when the following l positions are present, the Off-site Emergency j Manager determines facility readiness, and declares i the facility activated
() o Off-site Emergency Manager o EOF Operations Coordinator l l i i . _ . . _ _ - _ _ _ , . . , , _ . .
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- 2. The complete EOF organization is shown in FIGURE 4, M EOF ORGANIZATION.
s
] 6.8.2 Off-site Emergency Manager M
- 1. The Off-site Emergency Manager will assume the command-and-control functions and direct the emergency from EOF. An assigned Off-site Emergency Manager is available 24 hours a day.
I
- 2. The Off-site Emergency Manager is the official WCGS !
interface with government authorities. Responsibilities include the following: l
- a. Supports and provides resources or performs tasks as requested by the Site Emergency Manager
- b. Directs all WCGS personnel in the EOF r~N c. Obtains personnel and coordinates the efforts of
) the following:
o Emergency response personnel who perform off-site radiological surveys, plus any other personnel deemed useful for the emergency response effort o Outside contractors and vendors, such as consultants, laboratories under contract, the Nuclear Steam Supply System (NSSS) vendor, the Architect / Engineer, and regional utilities o Additional technical r3 sources may be called in during the emergency for further support or shift assignment onsite.
- d. Coordinates with the Administrative Coordinator in the logistics effort to supply the plant with the necessary personnel and equipment
- e. Briefs WCGS Executive Management on matters related to the emergency n
( '
) f. Coordinates with the Onsite and Off-site Public Information Coordinators (PICS) in providing technical input for news statements l
l
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- g. Ensure immediate and follow-up notifications are j made which provide sufficient information on .
emergency classification, plant status, off-site ! j dose projections or measurements, and issue l l g protective actions recommendations to off-site g authorities responsible for off-site emergency _ measures , M i
-g h. Requests federal assistance through state :
officials per the State Plan i M I
- 3. The following responsibilities are those of the !
Emergency Managers and may not be delegate. These l responsibilities may be divided between the Site ! and Off-site Emergency Managers. i o l Emergency classification i i o Protective action recommendations o Authorization for notification of off-site authorities o Authorization of emergency exposure in excess of , 10CFR 20 6.8.3 EOF Radiological Coordinator
- 1. The EOF Radiological Coordinator reports to the Off-site Emergency Manager and is responsible for l radiological monitoring and dose assessment activities off-site. Responsibilities are as follows:
o Directs and coordinates activities of the Dose ! Assessment Coordinator and staff o Assists the Off-site Emergency Manager in the formulation of recommended protective actions o Provides the PIC with an assessment of ! radiological conditions ! o Requests through the EOF Administrative Coordinator additional radiation monitoring equipment, instrumentation and Health Physics support personnel as necessary 4 o Interfaces with State and County emergency [ . response personnel who are assigned to the EOF regarding matters related to off-site radiological assessment
IIA ' Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 i 3 (RERP) o Reference Use Page 32 of 83 m o_ g 6.8.4 EOF Team Director b~- 1. The EOF Team Director assumes responsibility for 2 authorizing and supervising Off-site Monitoring 1 3 Teams. 03 The EOF Team Director directs Emergency l
\
Response Teams and advises the EOF Radiological l Coordinator on radiological conditions encountered ; by the Teams. M ! i
- a. Off-site Monitoring Team authorization should be !
made promptly upon activation of the EOF. I
- 0) l
- b. Monitoring teams are specially trained in field i sampling techniques. Each team will be equipped l with equipment capable of detecting and measuring radiciodine concentrations in the air at levels as low as 10 uCi/cc.
6.8.5 EOF Facility Technician
- 1. Reports to the EOF within a goal of 60 minutes of l I
declaration of an Alert or higher classification to ensure the EOF is prepared and functional. 6.8.6 Dose Assessment Coordinator (_,e 1, Reports to the EOF Radiological Coordinator and is responsible for directing / assisting with dose l projection and protective action recommendation i activities.
- 2. Ensures the Radiological Status Board is maintained current.
6.8.7 Emergency Dose Calculation Program (EDCP Operator)
- 1. Reports to and is responsible for providing 1 completed off-site dose projections to the Dose l Assessment Coordinator.
6.8.8 HPN Communicator
- 1. The HPN Communicator reports to the EOF Radiological Coordinator and maintains communications with the NRC via the Health Physics !
Network (HPN) telephone. 6.8.9 EOF Operations Coordinator
- 1. Reports to and briefs the Emergency Manager on j plant conditions and mitigative strategies. '
l
[ R$ vision: 0 o - RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 I (RERP) R ference Use Page 33 of 83 D ; m o- 6.8.10 EOF Administrative Coordinator i A. / 1. The Administrative Coordinator is responsible for a coordinating, directing, and responding to requests a from the ERO for administrative and logistical to support. The techniques and procedures used during l
\ this effort are adapted from normal WCGS procurement practices. The Administrative U
Coordinator also ensures notifications to off-site
} authorities . ire made.
M 6.8.11 Representative At County
- 1. The Representative at the County is located in the County Emergency Operations Center in Burlington, KS, and reports to the Off-site Emergency Manager.
The Representative responds to requests from County personnel for clarification or verification of data received from the TSC or EOF. 6.8.12 Additional Personnel
- 1. The following are examples of positions that are not needed for activation and operation of the EOF but supplement those personnel which are essential r~3 to an emergency response.
u l o Team Communicators communicate with Off-site Monitoring Teams. o Operations Recorders maintain the Operations Status Board current. o Administrative Assistants perform facility accountability, assist the Emergency Manager, faxing and copying, log keeping, and Off-site notifications and communications as directed. 6.9 Public Information Organization 6.9.1 Wolf Creek Public Information Officer (WC PIO)
- 1. The WC PIO is the public voice for plant information. The WC PIO is responsible for ensuring the timely issuance of accurate information to the public and media during an emergency at WCGS. Public interaction may be as a formal news conference or a telephone call.
-s 2. The WC PIO position is activated at an NUE or
(
) higher emergency to coordinate the development and release of news statements.
[ ' Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 L (RERP) 0 Reference Use Page 34 of 83 m o 3. The WC PIO has overall responsibility for the
%)
[~} Public Information Organization. 2 h 6.9.9 Wolf Creek Public Information Manager (G
- 1. The Wolf Creek Public Information Manager position
\
is activated at an NUE or higher emergency. The U Wolf Creek Public Information Manager works closely
\
with the WC PIO, the Onsite PIC, the Off-site PIC and the Technical Support staff to ensure that W[ information provided the public is timely and accurate.
- 2. The Wolf Creek Public Information Manager has responsibility for ensuring the Public Information Organization is activated and functions as directed in EPPs.
- 3. During a declared emergency the Public Information Manager determines and coordinates the activation of Rumor Control, Information Clearinghouse, Media Center and the Phone Team. The Public Information Manager operates from the appropriate Information Clearinghouse.
f N., 4. The complete Public Information organization is i s ,) shown in FIGURE 5, PUBLIC INFORMATION ORGANIZATION. 6.9.2 Onsite Public Information Coordinator (PIC)
- 1. The PIC gathers and transmits technical information to the Wolf Creek Public Information Officer for use in news statements following the declaration of any emergency classification.
6.9.3 Off-site Public Information Coordinator (PIC)
- 1. During an SAE or GE, the PIC is responsible for gathering all information related to the health and safety of the public. The PIC transmits this information to the WC PIO at the Information Clearinghouse. The PIC operates from the EOF.
6.9.4 Media Center Manager (MC Manager)
- 1. The MC Manager is located at the Media Center and reports to the WC PIO. Responsibilities include set-up of the Media Center, leadership for the Media Registrar and Media Liaison and management of the media news conferences. The Media Center (f s) Manager maintains contact with the Information Clearinghouse to provide news conference schedules.
1 \
y Rsvision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 { (RERP) g R2ference Use Page 35 of 83 m l l O_ 6.9.5 Media Liaison 1
- 1. Media Liaison is located in the Media Center and I
y reports to the MC Manager. Responsibilities include managing the media crowd at the Media (t ' Center and assisting the media with registration
~ and facility orientation, providing general Wolf '
Creek background information or approved emergency-f related information, arranging individual 2 interviews, and announcing and coordinating l g scheduled news conferences. 6.9.6 News Writer
- 1. The News Writer reports to and provides support for the WC PIO. The News Writer provides support to the PIO including: answering telephones, writing and distributing news statements, updating the status log, maintaining the media status board and faxing news statements. The News Writer maintains a chronological log of the events and news statements.
6.9.7 Phone Team Manager
's
) 1. The Phone Team Manager reports to the WC PIO and coordinates the rumor control activities of the Phone Team.
6.9.8 Rumor Control Coordinator
- 1. The Rumor Control Coordinator is located in the KCPL General Office and reports to the WC PIO.
Rumor Control monitors news statements or news conferences to identify misinformation being released to the public. 6.9.10 Technical Support
- 1. The Technical Support staff discusses technical details of the news statement with EOF staff to ensure accuracy, provides technical interpretation for the WC PIO, the Public Information Officer for Coffey County and the State of Kansas. Technical Support gathers information from the Emergency Facilities to communicate plant, health and safety issues to the public.
'x l
l l
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/\ i
- s' 1.
E The following are examples of additional personnel I 2 used to fill ERO positions such as clerical, log l M keeping, or status board posting. Staffing of l
\ these positions does not affect the activation of the facility.
o Media Center Registrar monitors access to the
- Media Center, records news conference I U attendance, provides media packets, provides directions for telephone use and work space information to the media representatives.
o Audio / Visual Support records on video and audio l tape the proceedings of news conferences presented in the Media Center. l o Information Messenger performs clerical and administrative duties at the direction of the Public Information Manager. o The Phone Team may make initial media notifications at PIO discretion, addresses media and public questions to the extent possible and
, } reports rumors or misinformation to the Phone
_j Team Manager, o The Media Monitoring Team notifies the Rumor Control Coordinator of any rumors or misinformation heard or observed from their monitoring of the media. l l 6.10 Local Off-site Organizations l 6.10.1 The Coffey County Contingency Plan for Incidents Involving Commercial Nuclear Power describes the authorities, responsibilities, and agreements to which various county agencies are a party in their response l to emergencies at WCGS. Information is provided therein about the various agencies' interrelationships and support roles provided to WCGS. I o The County Plan contains the formulas for calculating evacuation times for each subzone. U
{ (RERP) O Reference Use Page 37 of 83 l i Di __ 1 G 6.10.2 Coffey County Commissioners
.C\ i U
A
- l. The Coffey County Board of Commissioners maintains
\
{ 3 the executive authority and responsibility for l 03 planning and coordinating the county response.
\ They have delegated responsibilities and tasks to ~ the local support agencies and have established )
operating procedures.
\
j 2. After declaring a State of Local Disaster
*3 Emergency, the Chairman of the Coffey County l Commissioners is responsible for making the '
decision to activate the alert and notification system. Emergency authority, as stated in County Plan, is given in an established line of succession.
- 3. If a State of Emergency has not been declared, after receipt of notification and in accordance with the County Plan, the Chairman decides which protective actions would be appropriate. 1 I
o When a protective action is decided upon, the County notifies the State to activate EAS. I Cs 6.10.3 Coffey County Sheriff's Office U l
- 1. The Coffey County Sheriff's Office provides local ;
notification, access control, and law enforcement l support in accordance with the Coffey County Plan. !
- 2. If time does not permit, or if he is unable to contact the Chairman or other members of the County i l
Emergency Response Organization, the County Sheriff l has the authority to make protective action 1 decisions based upon recommendations by WCGS. l 3. The County Dispatcher contacts the Kansas Division l of Emergency Management to activate EAS.
- 4. Specific services provided by the Coffey County Sheriff's Office include: i o Perform notifications as defined within the County Plan and associated implementing l i procedures o Provide a 24 hour per day manning of communications links between the County and l WCGS, and between the County and State '
h Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 3 (RERP) g Reference Use Page 38 of 83 m i j O o Implement off-site protective actions as t l necessary and as specified in the County Plan ! i h implementing procedures ! l l E o ' Initiate warning and initial notification of the ! 0) population i
\
~
Direct the evacuation of specific subzones of l o l ~ @ the EPZ upon the decision to evacuate
~
\ ]
63 o Provide traffic control and roadblocks per implementing procedures I o 'Obtain additional assistance as necessary to l
- secure the evacuated areas l o Control access to the County EOC (6.10.4 Coffey County Fire District #1 (CCFD) i
- 1. Contractual arrangements have been made with the Board of Trustees of Fire District No. 1, Coffey County, KS, for the provision of fire fighting l
l support. Services contracted are summarized in the Letter of Agreement and maintained in an Emergency Planning file. ;
- 2. The WCGS Fire Brigade Leader is also responsible for directing all fire fighting activities onsite.
Once onsite, Fire District members and equipment shall be escorted by Security. 6.10.5 Off-site Medical Treatment !
- 1. Coffey County Hospital and Newman Memorial Hospital j each have developed emergency procedures to provide i guidance in the rendering of medical treatment to I contaminated patients.
1
- 2. Coffey County Hospital, located in Burlington, KS, approximately 9 road miles from the WCGS site, has agreed to provide aid to injured / contaminated personnel.
- 3. Newman Memorial Hospital serves as a backup to
- Coffey County Hospital and is located in Emporia,
{ KS, approximately 40 miles from WCGS. 4 i iO I i
)
{ L Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 (RERP) g Reference Use Page 39 of 83 m O
- 4. Contaminated injured personnel transported from
(~)
\_j' WCGS to off-site medical facilities are attended by personnel qualified in radiological practices.
{ Once the patient (s) has been stabilized, WCGS i personnel survey patient (s), attending personnel, 7 ! vehicles, and equipment to ensure they have been !
] decontaminated in accordance with WCGS procedures.
f 6.10.6 Coffey County Ambulance Service
*, 1. Coffey County Ambulance Service provides medical assistance and transports victims to medical facilities for personnel requiring treatment for !
injuries, exposure to radiation, and contamination. j WCGS notifies the Ambulance Service by telephone or though the Coffey County Sheriff's Office. i l
- 2. If conditions warrant, any vehicle at WCGS may be used to transport affected personnel.
6.10.7 Radiological Emergency Assistance Center / Training Site (REAC/TS)
- 1. REAC/TS maintains a 24 hour Hospital Disaster Network. Consultation is available for medical
() f'N emergencies involving radiologically contaminated patients. 6.11 State Organizations 6.11.1 The Governor, by law, is the Chief Executive Officer of the State of Kansas and is responsible for the safety and well-being of all citizens within the State. The State Plan describes the responsibilities of local, federal, state, and volunteer agencies during nuclear emergencies. Upon declaration of a State of Disaster Emergency the State has primary responsibility for responding to an off-site nuclear emergency. Activation of the State EOC, located in the lower level of the State Defense Building, Topeka, KS, is the responsibility of the Governor or authorized representatives, depending on the nature of the emergency. The Kansas Division of Emergency Management, Technological Hazards Section, provides overall coordination as the responding state agency during a Fixed Nuclear Facilities Incident. l l [ t n/
y Revision: 0
~ RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 I' (RERP) 0 Reference Use Page 40 of 83 m
!O 6.11.2 Appendix 12 to Annex N of the Kansas State Emergency l Operations Plan describes in detail, the authorities, E responsibilities, and agreements to which various state ! A agencies of their response to emergencies at WCGS. M Reference to this document is made for detailed .
\ information on each agency's interrelation and support ! ~
role provided to WCGS. l f' 1. Upon declaration of an SAE or GE representatives of
- Kansas Department Emergency Management (KDEM) and M Kansas Department of Health and Environment (KDHE) i go to the EOF. They act as the interface between 4
j WCGS, the County, and the State. j 6.11.3 Kansas Division of Emergency Management (KDEM) l 1. The KDEM provides the following assistance:
- a. Evaluates information presented by WCGS to j decide off-site protective actions
! b. Coordinates nuclear incident response planning, l training, and notification. Activities include: l o Notification of KDHE l () o Notification of Key federal and state agencies o Notification of the Governor's Office o Provides radiological monitoring coordination o Requests federal assistance and coordinates federal and state support on behalf of affected areas 1 l o Provides 24 hour per day point of contact to receive notification o Activates the State EOC i o Activates the Kansas Emergency Alert System l l l 6.11.4 Kansas Department of Health and Environment (KDHE) { 1. The KDHE provides assistance as described below: j o Acts as the lead state agency for operational l i () radiological emergency response o Conducts radiological monitoring in affected areas
h Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 (RERP) { Reference Use Page 41 of P3 m 9- o Provides radiological advice to hospitals (
'w/) o Develops and establishes State PAGs D
J o Provides information and guidance to the public ( about protective actions, via the KDEM { o Assesses off-site contamination of the environment y o Provides technical guidance and coordination in recovery activities o Supports the development and conduct of radiological response training o Reviews, evaluates, and maintains dosimetry records for non-licensee emergency workers and other affected individuals 6.11.5 Kansas Highway Patrol (KHP)
- 1. The KHP provides communications and notification support including backup notification means for the following:
( ) o Coffey County Sheriff's Office o KDEM, Technological Hazards Section o The Governor's Office
- 2. The KHP augments local law enforcement in securing the area and establishing evacuation routes and providing traffic control.
- 3. The KHP provides self-support radiological monitoring.
- 4. The KHP maintains emergency communications systems 24 hours per day.
6.11.6 Kansas National Guard
- 1. The Kansas National Guard may be directed by the Governor to provide assistance as needed such as the following:
o Evacuation of communities j j o Area security LJ o Providing Media Center Security 1
n Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 [7 (RERP) g Reference Use Page 42 of 83 m 3., 6.11.7 Kansas Department of Transportation (KDOT) i S
}/ 1. KDOT provides assistance as follows:
3 o Provides emergency traffic barriers and signs 03 1 i o Supplements emergency traffic control h o Supplies construction equipment w o Provides communications support 6.12 Federal Organizations 6.12.1 Should an emergency situation or accident occur at WCGS, notification and reports must be made to various federal agencies and organizations, and requests for assistance may also be made. 6.12.2 Federal Emergency Management Agency (FEMA)
- 1. FEMA is the lead agency supporting implementation of the state and local emergency plans. Region VII FEMA response time is estimated to be four hours.
,ess 6.12.3 Department of Energy (DOE)
'~
- 1. The DOE Radiological Assistance Program provides monitoring assistance and radiological consultation to the KDHE. The DOE provides assistance under the Federal Radiological Emergency Response Plan (FRERP) and responds to authorized requests for assistance by the KDHE. The DOE Albuquerque Operations Office maintains a team of specialists which are dispatched to the incident site for radiological hazard evaluation within 48 hours.
6.12.4 Nuclear Regulatory Commission (NRC) l 1. The NRC provides advice to other federal, state, and local agencies on the radiological health consequences of various emergency protective actions. The NRC requires notification and reports l as indicated in ATTACHMENT H, REPORTING OF l INCIDENTS PER 10CFR20 and as specified in the WCGS Technical Specifications. NRC Region IV response time is estimated to be 12 hours. 6.12.5 Licensee resources available to support the federal
,3 response include the following:
)
o Space and equipment in the TSC and EOF provided for key federal personnel
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- 7. -
(RERP) { Reference Use Page 43 of 83 m O
,_ o Telecommunications equipment at these centers is
( ) available to federal personnel for use
%l 2
o Parking space adjacent to the EOF provides cn area 1 for the location of federal response vehicles, with f 1 power and sanitary services available at the EOF o Open fields south of the parking lot at the EOF ( provide access for helicopters w, o Coffey County Airport is available for air traffic 6.13 Additional Support Agencies 6.13.1 Vendor and Architect / Engineers (A/E)
- 1. NSSS supplier, Westinghouse, is the chief vendor who may be involved with emergency response for WCGS. Westinghouse has emergency response plans which are activated upon notice and is expected to provide the following services:
o Personnel with expertise in various areas o Technical analysis g ( ,) o Operational analysis o Accident / transient analysis o Recommendations 6.13.2 Regional Utility Support
- 1. WCGS shares the SNUPPS power-block design with the Union Electric Callaway Plant. Because of this design concept and similarity with the WCGS layout, assistance from Union Electric is possible. A specific mutual aid agreement between WCGS and Union Electric Company has been established. While this assistance may be available within a short period of time, it shows greatest promise in the case of a prolonged emergency where extended, around the clock coverage is required. The DEM may authorize the temporary use of this resource, should staff augmentation be necessary. Union Electric Company is a signatory of the INPO FIXED FACILITY EMERGENCY RESPONSE VOLUNTARY ASSISTANCE l
AGREEMENT. \ ,/ Y..,]
E Revision: 0 f, RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 (RERP) y Reference Use Page 44 of 83 m O (y 6.13.3 Institute of Nuclear Power Operations (INPO) 1. I_) WCGS has signed the INPO FIXED FACILITY EMERGENCY I RESPONSE VOLUNTARY ASSISTANCE AGREEMENT. This agreement is by and among electric utilities which f ' have responsibility for the construction and operation of commercial U.S. nuclear power plants. E Assistance may be requested from any of the f ' signatory companies in the form of technical and administrative aid or personnel, facility, or
]
equipment resources. Requested assistance is rendered according to the agreement. 6.13.4 American Nuclear Insurers (ANI)
- 1. ANI is notified at emergency classificaticns of Alert or higher. ANI is available to provide insurance services as necessary.
6.14 Plant Monitoring 6.14.1 Nuclear Plant Information System (NPIS)
- 1. The integration and display of selected and critical data is performed by NPIS which is a non-
-'y safety, non-Class lE system. Isolation is provided i
,) to ensure that NPIS does not degrade the performance of safety system equipment or displays.
- 2. NPIS provides data storage and recall capability.
- 3. Certain parameters are also transmitted to the NRC Operations Center via the Emergency Response Data System (ERDS) link of NPIS. ERDS is activated through NPIS within 60 minutes of an Alert or higher classification.
- 4. The NPIS computer feeds key plant parameters to individual terminals in the Control Room, TSC, and EOF which display data identical in accuracy, resolution, and reliability. Support personnel may assist the Control Room staff to analyze and diagnose plant abnormalities so that corrective action may be taken and then monitored.
i -
)
$A Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 (RERP)
Reference Use Page.45 of 83 m i cLs 5. The Safety Parameter Display System (SPDS) provides ! (s- >) for continuous indication of plant parameters or ! A derived variables representative of the safety status of the plant. The primary function of the 3 SPDS is to aid the user in the rapid detection of f ' abnormal operating conditions. As a plant safety information and diagnostic tool, SPDS concentrates on a minimum set of plant parameters from which the i {( plant safety status can be assessed. EUJ 6.14.2 Onsite Radiological Monitors
- 1. Process monitors monitor the radiation intensity of materials within plant systems. These monitors l
continuously measure, indicate and record the radioactive material concentrations located within systems being monitored. Each monitor includes an adjustable alarm to provide indication of a significant change or the existence of a l concentration of radioactive material above pre-i selected values. The USAR, Chapter 11.5, includes l a listing and range of plant monitors. l 2. i'he Area Radiation Monitoring System monitors provide information about radiation intensity at (~h specific plant locations. These monitors provide the following: l a. Warnings of excessive ganna radiation levels in areas where nuclear fuel is stored or handled
- b. Control Room personnel with a continuous indication of gamma radiation levels at selected locations within the various plant buildings
- c. Assistance in detecting unauthorized or inadvertent movement of radioactive material in the plant, including the radwaste area
- d. Supplementation of other systems, such as process radiation monitoring or leak detection, i in detecting abnormal migrations of radioactive material
- e. Local alarms to warn personnel in the area
- 3. Effluent monitors provide information about the concentration of radioactive material in plant effluent pathways. Each significant effluent
(~T pathway from the plant includes an effluent monitor (_) to enable the quantification of the radioactive material concentration exiting the plant.
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- 6.14.3 Meteorological Monitoring System
- 1. The Meteorological Monitoring System is composed of 2
1 a 90-meter instrument tower and a temperature f controlled shelter at the base of the tower housing associated instrumentation and equipment. ~
- 2. The function of the meteorological system is to 9 monitor and record meteorological conditions.
- a. Information provided by instruments at the meteorological tower is available from the NPIS computer system.
- 4. Time interval measurements are used in calculating 15-minute averages for all parameters.
- 5. When needed, Meteorological data can be obtained from the National Weather Service.
6.14.4 Seismic Monitoring System
- 1. The seismic warning panel in the Control Room provides local visual and audible indication when a
,~ seismic event has occurred.
( ) 6.14.5 Hydrologic Monitoring
- 1. Hydrologic monitoring is not required as WCGS is a
" dry site" as defined by Regulatory Guide 1.102.
The plant site is located above the design basis flood level. 6.14.6 Fire Protection
- 1. WCGS is protected by an independent fire protection system consisting of two subsystems, a detection / alarm system and a suppression system.
- 2. Activation of the fire systems results in an audible alarm throughout the plant. Alarms are also displayed in the Control Room.
6.14.7 Laboratory Facilities
- 1. A radiochemistry (hot) laboratory, radwaste laboratory, and turbine building chemistry laboratory are located in the power block. The chemistry shop laboratory is located in the Walter
,s -
P. Chrysler Building. Further information on ( ) onsite laboratory equipment can be found in USAR,
'~'
Chapter 12.5.
a
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Reference Use Page 47 of 83 m ci
- 2. The environmental laboratory at the EOF may be used f\
A/ # for processing of routine and emergency field samples. The Kansas Health and Environmental 1
# Laboratory in Topeka, KS, is available to further augment the processing of emergency samples. \ ~
- 3. Private laboratories under contract to WCGS or laboratories of neighboring utilities who are signatories of the INPO Voluntary Assistance
] Agreement may be considered for use.
6.15 Emergency Supplies 6.15.1 Emergency supplies include protective, communications, and radiological monitoring equipment, check sources, and other supplies. The EPPs list emergency supplies and their locations. 6.15.2 Emergency supplies are maintained, inventoried, and inspected on a regular basis in accordance with EPPs. The EPPs contain an inventory list of WCGS equipment for emergency supplies. This equipment may be augmented by other onsite equipment. 6.15.3 Instruments are calibrated in accordance with WCGS N Health Physics Procedures. For any items removed from f(_sl the emergency supplies for calibration or repair, an operable equivalent instrument is used to replace it. Sufficient quantities of spare instruments / equipment are onsite to provide replacements. 6.16 Communications 6.16.1 Communication Equipment
- 1. Telephones provide primary communications contact with the State and County EOCs. Systems in the Olive Beech Building and the Dwight D. Eisenhower Learning Center are powered by their own battery and charger. The battery will supply the system if the charger fails.
- a. The Federal Telephone System (PTS 2000) is used for NRC communications.
- b. Trunk lines are available for communications with outside agencies.
O(h
D1 Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 I' (RERP) Beference Use Page 48 of 83 a m ! g, 2. Radio communications provide backup communications ( ') with the State and County EOCs. Fixed AC-powered A/ transmitter / receiver units and a number of portable I I and hand-held units are also capable of providing fixed and mobile communications to joint f radiological monitoring teams. 1
- 3. A paging system is used for initial notification of Y, key personnel. Pager coverage is provided in and
- around the cities of Burlington, Emporia, Topeka, 0:
Ottawa and Lawrence. 6.16.2 Communication Dissemination
- 1. The methods of employee communications may be employee meetings, announcements, or literature handouts.
- 2. The Public Information Organization is responsible for interfacing with the media. Communication between WCGS and media organizations are performed in accordance with EPPs.
- 3. Annually, WCGS offers the news media with the following information:
m ' ( (_)' o Information concerning the emergency plan o Information concerning radiation o Facilities available for media o Points of contact for statements of public information o Differences between normal and emergency plant operations
- 4. Standardized public announcements for broadcast during an emergency have been written by the state, county, and WCGS and are found in the State Plan.
- 5. WCGS, state, and local emergency organizations provide members of the public, including transients, public education information on how they are notified and what their initial actions should be during an emergency.
l
- a. Emergency planning information is provided 73 within local telephone directories. The f
'~'
) information, developed jointly by WCGS, Coffey County and the State of Kansas, is distributed to residences of the EPZ.
m 7 Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 7 (RERP) { Referenca Use Page 49 of 83 m O
- b. Information includes educational facts on
,') radiation, protective measures, special needs of K_ / the handicapped and the points of contact for i
L additional information. M
- c. An annual mail-out to the public provides !
information regarding operation of Tone Alert I { Radios. [ 6. Emergency planning information, displayed on g~ information boards, is provided for transients in the public use areas of John Redmond Reservoir J (JRR), Coffey County Lake (CCL), and other WCGS l controlled areas. Transients have access to emergency plan information within motel rooms and ; telephone books. l 6.17 Emergency Plan Training 6.17.1 WCGS has developed an emergency preparedness training program which meets the requirements of 10CFR50, Appendix E, Section IV. F. 6.17.2 The Superintendent Emergency Planning ensures required training is provided for ERO personnel in accordance (^) L ,/ with plant procedures. 6.17.3 Personnel receive general RERP training as a portion of Plant Access Training prior to receiving unescorted access to WCGS. 6.17.4 Training associated with each off-site response organization's emergency support role is offered annually. Training is coordinated with KDEM and the Coffey County Emergency Preparedness Office. 6.17.5 Where Letters of Agreement exist between WCGS and local agencies, training is offered annually. Training is also offered to the participants in the Interlocal Agreements between Coffey County and host counties, Anderson and Lyon. 6.17.6 Drills are considered part of the Emergency Plan Training Program. Drills ensure that the ERO is capable of executing the crucial tasks necessary to detect emergency conditions, assess and mitigate the consequences, notify key licensee and non-licensee personnel and organizations, perform appropriate response and protective actions, and recommend off-site f
~]; protective actions to state and local agencies.
( 6.18 Emergency Plan Drills r
_ _ _ . _ . . . _ - _ _ . - - - ~ - - - ^ Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 { 3 Reference Use (RERP) D Page 50 of 83 m O 6.18.1 Annual communication drills between WCGS, State and [ County EOCs, and field assessment teams ensure that
.D contact can be made and that messages are comprehended.
1
- 1. Monthly _ communication tests verify communications f '
with the local County and State authorities. Communications tests are made with the NRC Headquarters via the FTS 2000. These tests are performed in accordance with EPPs.
~
6.18.2 Fire drills are conducted in accordance with plant administrative procedures. i 6.18.3 Annual medical emergency drills include transportation and treatment of simulated contaminated individuals by ambulance.and off-site medical treatment facilities. 6.18.4 Annual radiological monitoring drills include ; collection and analysis of sample media, field activities, and provisions for communications and record keeping. 6.18.5 Semi-annual Health Physics drills involve response to and analysis of simulated elevated airborne and liquid samples and direct radiation measurements in the i environment. '
- 1. Annually, analysis of in-plant liquid samples using the post-accident sampling system (PASS) is l
. included in a Health Physics drill.
6.18.6 Each calendar quarter, a callout drill is conducted to .; verify the operability of the notification system. 1 6.18.7 Critiques should be conducted following each drill to identify and correct noted deficiencies. 6.19 Emergency Planning Exercises 6.19.1 In accordance with 10CFR50 Appendix E, Section IV.F, emergency exercises will test the adequacy of timing and content of implementing procedures and methods, test emergency equipment and communication networks, i test the public notification system, and ensure that ERO personnel are familiar with their duties. 6.19.2 Exercises will be conducted biennially to test the on-site and off-site emergency plans. 6.19.3 To meet NRC and FEMA requirements, the exercises are l l varied so as to test, at least once every six years, l l all major components of the WCGS, State, and County plans and response organizations.
2 Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 3 (RERP) i g Reference Use Page 51 of 83 A i C 1. () A Exercises should be conducted under various weather conditions. l l
- 2. At least once every six years an unannounced j 2
to exercise'is initiated between 6:00 p.m. and 4 a.m. !
\ 3. At least once every six years an ingestion pathway M exercise shall be conducted. i i \
i
~
6.19.4 Designated observers from federal, state, local U governments, and WCGS observe the required exercises. l Certain of these observers also evaluate the exercise. 1 i
- 1. The Superintendent Emergency Planning has the lead responsibility for ensuring corrective actions associated with emergency planning are initiated.
- 2. Critiques are conducted following each exercise to identify and correct noted deficiencies.
6.19.5 Prior to an exercise a scenario package is prepared which contains the following: o Basic objective of each exercise and appropriate evaluation criteria o Simulated events o Dates, time periods, places, and participating organizations o Time schedule of all initiating events o Descriptive scenario addressing the conduct of the exercise which should include public information activities, off-site fire department assistance, l simulated casualties, rescue of personnel, use of ' protective clothing and radiological monitoring teams o Description of the arrangements for, and advance materials to be provided to official observers 6.20 Emergency Plan And Procedures Administrative Controls
- 6.20.1 The NSRC is responsible for assuring that a review of the WCGS Emergency Preparedness Program will be performed, at least once every twelve months, in l accordance with 10CFR 50.54 (t) . i j
l () 1. Personnel performing this review will have no direct responsibility for implementation of the Emergency Preparedness Program. i
s y Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 2 (RERP) [ Reference Use Page 52 of 83 m ! OL-i () l'
- 2. The review should evaluate interfaces with state and local governments, licensee drills, exercises, capabilities, procedures and emergency facilities.
l'
- 3. The results of the review are reported to owner M
representatives and WCGS Senior Management and
) shall be retained for at least five years.
M
- 4. Correction of review findings are evaluated and
) implemented using normal WCGS procedures.
M
- 5. The applicable portions of the review shall be made available to the State and local governments.
6.20.2 The Superintendent Emergency Planning ensures the coordination and documentation of RERP reviews and revisions. The RERP is revised annually to incorporate changes identified during drills, exercises and the 10CFR 50. 54 (t) review. 6.20.3 Action items required to be performed in a time period are allowed a 1.25 times frequency grace period to complete the item. 6.21 Recovery Plan s_/ 6.21.1 The Recovery Plan is activated in a progressive manner when the Site or Off-site Emergency Manager determine stabilized plant conditions warrant the transition of the emergency response efforts to the recovery phase. 6.21.2 If a General Emergency has been reached, NRC and KDEM concurrence shall be obtained prior to downgrading. 6.21.3 The EPPs provide the general plans for reentry and recovery and describe the means by which decisions to relax protective measures are reached.
- 1. Evaluation of the status of the three fission product barriers is used for de-escalation. As the i situation improves and barriers are restored, the next lower level of event may be declared.
- 2. De-escalation may also occur if conditions have !
stabilized such that the potential for re-escalation to a higher level has been removed and a controlled situation exists. A declaration of de-escalation is provided by the Emergency Manager based on known information and recommendations of the ERO. l O 1
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- 3. Guidelines are provided for Reentry Team (s) to perform surveys and monitoring activities to be employed for initial reentry.
i S i 6.21.4 During the recovery process the normal procedures i f\ employed for configurer . M1 control, reporting, i interfaces with regulatory agencies and support groups, j exposure control, environmental monitoring, and ; s i i procurement of supplies and services shall be utilized. j 6.21.,5 g~ The Recovery Plan utilizes the necessary technical, administrative, managerial and support personnel that may be required for the recovery phase of emergency response, as determined by Site or Off-site Emergency Managers. The responsibilities and functions of the Emergency Managers and staff are detailed in the EPPs. 7.0 RECORDS 7.1 None 8.0 FORMS 8.1 APF-06-002-01, EMERGENCY ACTION LEVELS
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h Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 3 (RERP) l g Reference Use Page 54 of 83 m O ATTACHMENT A ('"'N ; (Page 1 of 1) s.__/ EFFECTIVE 10-MILE EPZ POPULATION CENTERS 2 x (O
\
U
\
Significant Distance (miles) And
]' Population Centers Approximate Direction From The Site Population Subzone To Population Center Burlington, KS 2,735 SW-1 3.5 Southwest New Strawn, KS 428 W-1 3.4 West-Northwest Waverly, KS 618 NE-2 11.5 North-Northeast LeRoy, KS 568 SE-3 11.1 South-Southeast Aliceville, KS 40 SE-2 9.3 Goutheast Ottumwa, KS 20 NW-1 6.8 West-Northwest ,~,
i \
't.,/ Sharpe, KS 10 N-1 2.4 North Jacob's Creek 70 W-2 10.0 West The population numbers were taken from the 1990 census.
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r, 7 R: vision: 0 7. RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 (RERP) f^ Reference Use Page 55 of 83 rn O ATTACHMENT B [^')
's (Page 1 of 3)
.D SUBZONE EVACUATION TIMES 2 En B.1 Table B.1 lists each subzone and the population in that subzone. j TABLE B.1 POPULATION BY SUBZONE Evacuation Subzone Evacuation Zone Population 1 Center (CTR) 0-2 75 "a North-1 (N-1) 2-5 65 Northeast-1 (NE-1) 2-5 53 East-1 (E-1) 2-5 53 Southeast-1 (SE-1) 2-5 40 South-1 (S-1) 2-5 40 Southwest-1 (SW-1) 2-5 2,779 West-1 (W-1) 2-5 450 Northwest-1 (NW-1) 2-5 82 North-2 (N-2) 5 - 10 121 Northeast-2 (NE-2) 5 - 10 697 Northeast-3 (NE-3) 5 - 10 132 East-2 (E-2) 5 - 10 70 Southeast-2 (SE-2) 5 - 10 128 Southeast-3 (SE-3) 5 - 10 634 Southeast-4 (SE-4) 5 - 10 53 South-2 (S-2) 5 - 10 88 Southwest-2 (SW-2) 5 - 10 88 West-2 (W-2) 5 - 10 132 ('^ h. Northwest-2 (NW-2) 5 - 10 114 \ ] B.2 Total Coffey County population equals 8,404 persons (1990 census). Effective 10-Mile Emergency Planning Zone Subtotals are as follows: o Effective 0 mile zone = 75 persons o Effective 2 mile zone = 3,562 persons o Effective 5 mile zone = 2,257 persons o Effective 0 mile zone = 5,894 persons B.3 Table B.2 lists evacuation confirmation time parameters. TABLE B.2 EVACUATION CONFIRMATION TIME PARAMETERS Speed Vehicles EPZ Miles Number of Between Effort in Assumed Confirmation Location Traveled Houses Houses Vehicle Available Time Burlington 36 1,183 5 mph 105 Hrs 11 9.5 Hrs New Strawn 3 229 5 mph 20 Hrs 3 6.6 Hrs LeRoy 9 289 5 mph 43 Hrs 5 8.6 Hrs Waverly 7 280 5 mph 33 Hrs 4 8.3 Hrs Remaining 299 649 30 mph 80.5 Hrs 8 10.3 Hrs EPZ* [ ] Includes the evacuation confirmation of the U.S. Army Corps of Engineers areas w/ at John Redmond Reservoir, Coffey County Lake, and the U.S. Fish and Wildlife Service area north of the Neosho River.
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- o ATTACHMENT B 1 f- (Page 2 of 3) !
SUBZONE EVACUATION TIMES
.D 2 B.4 Table B.3 lists Ambulances and Funeral Directors (FD) who may (0 assist with transportation for non-ambulatory persons, distance
\ to travel, time to travel, capacity of each vehicle, and an accumulative total of person capacity.
U
\ TABLE B.3 TRANSPORTATION FOR NON-AMBUIATORY PERSONS (O j Availability Due To Weather Accumulated Location Distance Capacity Good (persons)
Adverse (minutes) Capacity ! (miles) (minutes) (persons) ! Coffey Co Ambu 10 Immediate Immediate 10 } Yates Center FD 23 4 30 40 14 Allen Co Ambu 49 6 47 67 20 Lyon Co Ambu 40 12 48 68 32 Emporia FD 40 4 48 68 36 Franklin Co Ambu 46 9 55 79 45 Chanute FD 50 6 60 86 51 Garnett FD 30 3 36 52 54 Eureka FD 55 4 66 94 58 McPherson FD 122 2 132 210 60 osawatomie FD 70 4 78 120 64 Lyndon FD 28 3 30 48 67 LIFESTAR 50 (air) 2 30 Limited by 69 ! O Anderson Co Ambu 30 8 25 ceiling and visibility 45 77 l I i B.5 Tables B.4 and B.5 lists the 10-mile evacuation time for average l and adverse weather conditions. l TABLE B.4 10 MILE EVACUATION TIMES FOR AVERAGE WEATHER CONDITIONS (HOURS)
- Subzone Effective 2-mile Effective 5-mile Effective 10-mile CTR 0.7 0.9 1.1 CCL 2.5 2.5 2.5 l JRR 2.5 2.5 2.5 N-1 -
0.8 1.1 NE-1 - 0.9 1.1 E-1 - 0.9 0.9 SE-1 - 0.8 1.0 S-1 - 0.9 1.2 SW-1 - 1.4 1.5 l W-1 - 1.0 1.1 NW-1 - 0.8 1.0 N-2 - - 0.9 NE-2 - - 1.0 NE-3 - - 0.9 l E-2 - - 0.8 SE-2 - - 0.9 SE-3 - - 1.0 i SE-4 - [. 0.7
, S-2 - -
0.9 ( SW-2 - - 0.9 ' W-2 - - 0.8 NW-2 - - 0.7 i
ii . l 7 Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 r, (RERP) o Reference Use Page 57 of 83 m c( ATTACHMENT B
') (Page 3 of 3)
L/ SUBZONE EVACUATION TIMES _O 2 TABLE B.5 CO 10 MILE EVACUATION TIMES EVR ADVERSE WEATHER CONDITIONS (HOURS) Effective Effective Effective Subzone 2-mile 5-mile 10-mile h) CTR 0.7 1.0 1.3 x CCL 2.5 2.5 2.5 JRR 2.5 2.5 2.5 N-1 - 0.9 1.3 C0 NE-1 - 1.0 1.1 E-1 - 1.0 1.1 SE-1 - 0.9 1.1 S-1 - 0.9 1.4 SW-1 - 1.7 1.8 W-1 - 1.1 1.3 NW-1 - 0.9 1.1 N-2 - - 1.0 NE-2 - - 1.1 NE-3 - - 1.0 E-2 - - 0.9 SE-2 - - 1.0 SE-3 - - 1.1 SE-4 - - 0.8 S-2 - - 1.0 SW-2 - - 0.9 W-2 - - 0.9
/~'N NW-2 - -
1.0 ( l
~
NOTE: For all transportation-dependent people, including the non-ambulatory occupants of the Golden Age Lodge, Sunset Manor Nursing Home and the Coffey County Hospital, an evacuation time of 2.5 hours is estimated using area resources. Evacuation times are based on the population from the 1980 census. The 1980 population was larger than the population determined from the 1990 census. Since the evacuation times are based on a greater population than what is presently in Coffey County, and because the condition of some of the evacuation routes has improved (e.g. paving), the times are considered to be conservative.
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; (Page 1 of 8)
CROSS REFERENCE BETWEEN NUREG 0654, RERP, AND WCGS PROCEDURES D 0 m
;' 0654 RERP Comments Procedure Section Section A. - ASSIGNMENT OF RESPONSIBILITY (Organization Control) 1.a 6.5, 6. 6, WCGS onsite and off- EPP 06-002, TECHNICAL SUPPORT 6.7, 6.0, site organizations CENTER OPERATIONS g 6.9 EPP 06-003, EMERGENCY OPERATION FACILITY OPERATIONS EPP 06-004, PUBLIC INFORMATION ORGANIZATION 1.a 6.10, Outside organizations 6.11, 6.12, 6.13 1.b 6.5 -
6.13 1.c FIGURE 6 1.d 6.5, 6. 6, EPP 06-001, CONTROL ROOM 6.7, 6.8, OPERATIONS 6.9 EPP 06-002, TECHNICAL SUPPORT CENTER OPERATIONS EPP 06-003, EMERGENCY OPERATION l )
FACILITY OPERATIONS 1.e 6.5.2 Notifications are made from the control room, at the direction of the Site Emergency Manager.
2.a & 2.b N/A
- 3. ATTACH. G
- 4. 6.8.2 Off-site Emergency EPP 06-003, EMERGENCY C'PERATION Manager FACILITY OPERATIONS 6.8.11 Administrative EPP 06-003, EMERGENCY OPERATION Manager , FACILITY OPERATIONS B. - ONSITE EMERGENCY ORGANIZATION
- 1. 6.5
- 2. 6.5.2 Site Emergency EPP 06-001, CONTROL ROOM Manager OPERATIONS
- 3. 6.5.2, Transfer of control EPP 06-001, CONTROL ROOM 6.6.5, from the SS to the OPERATIONS 6.8.2 Site Emergency EPP 06-002, TECHNICAL SUPPORT Manager. CENTER OPERATIONS EPP 06-003, EMERGENCY OPERATION FACILITY OPERATIONS LI
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- o ATTACHMENT C l
l~ (Page 2 of 8)
,D T) CROSS REFERENCE BETWEEN NUREG 0654, RERP, AND WCGS PROCEDURES i
1 E 0654 RERP Comments Procedure ! E' Section Section
\ j l B. - ONSITE EMRGENCY ORGANIEATION
~
{
- 4. 6.5.2, Responsibilities of EPP 06-001, CONTROL ROOM l y' 6.6.5, the SS, DED, DEM OPERATIONS
- 6.8.2 t
- EPP 06-002, TECHNICAL SUPPORT -
i (0 CENTER OPERATIONS EPP 06-003, EMERGENCY OPERATION FACILITY OPERATIONS 5 6.5, 6.6, Major ERO positions EPP 06-001, CONTROL ROOM , 6.7, 6.8, and their functions OPERATIONS ' 6.9 EPP 06-002, TECHNICAL SUPPORT CENTER OPERATIONS EPP 06-003, EMERGENCY OPERATION FACILITY OPERATIONS
- 6. 6.5,.6.6, Interfaces between 6.7, 6.8, WCGS and outside 6.9, Fig. organizations 5& 6 7a. 6.8.11 Administrative EPP 06-003, EMERGENCY OPERATION Resources Manager FACILITY OPERATIONS 7b. 6.21 Recovery Plan EPP 06-003, EMERGENCY OPERATION l FACILITY OPERATIONS (w 7c. 6.8.2 Duty Emergency EPP 06-003, EMERGENCY OPERATION Manager FACILITY OPERATIONS 7.d 6.9 On-site & Off-site EPP 06-002, TECHNICAL SUPPORT i
Public Information CENTER OPERATIONS Coordinator & Wolf EPP 06-003, EMERGENCY OPERATION , Creek Public FACILITY OPERATIONS i Information Officer EPP 06-004, PUBLIC INFORMATION j i ORGANIZATION ! l 8. 6.13 Specify contractors / j organizations available on request i l 9. 6.10 Identify local { j support agencies J C. - EMERGENCY RESPONSE SUPPORT AND RESOURCES 1.a 6.8.2 Persons authorized to request assistance l 1.b 6.12 Expected Federal resources L l l , . - - - , - - - -
Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002
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.. (Page 3 of 8) m,I CROSS REFERENCE BETWEEN NUREG 0654, RERP, AND WCGS PROCEDURES 1
E 0654 RERP Comments Procedure 03 Section Section i C. - EMERGENCY RESPONSE SUPPORT AND RESOURCES 1.c 6.4.1, Space is provided for y 6.4.2, NRC personnel in the 6.4.4, Control Room, TSC, and 6.12.5 EOF. The EOF also has limited space for state and local personnel. 2a. N/A 2.b 6.8.12
- 3. 6.14.7 Identify radiological laboratories
- 4. 6.13 and Identify other ATTACH G facilities and organizations which could assist D. - EMERGENCY CLASSIFICATION SYSTEM
- 1. 6.2 Emergency EPP 06-2.1, EMERGENCY Classifications CLASSIFICATION
- 2. 6.2 Initiating conditions EPP 06-2.1, EMERGENCY f'"^x CLASSIFICATION
!v) 3. & 4.
E. N/A
- NOTIFICATION METHODS AND PROCEDURES
- 1. 6.5.2, Notifications EPP 06-007, EMERGENCY NOTIFICA'rIONS 6.6.5, 6.8.2
- 2. 6.16.1, Nocification of EPP 06-015, EMERGENCY RESPONSE 6.5.3 responding personnel ORGANIZATION CALLOUT
- 3. 6.5.2, Initial notifications EPP 06-007, EMERGENCY NOTIFICATIONS 6.6.5, 6.8.2 4.a 6.5.2, Follow-up Notifications EPP 06-007, EMERGENCY FOTIFICATIONS thru 6.6.5, 4.n 6.8.2
- 5. N/A
- 6. Attach B Evacuation times
- 7. N/A F. - EMERGENCY CCetiUNICATIONS 1.a 6.5 1.b 6.5.2 1.c 6.5.2, 6.5.4, 6.6.5,
- 6. 6. 9,
,m 6.8.2 i
( ) 1.d 6.4.4, ! V' 6.16
Rnvision: 0 f g Reference Use RADIOLOGICAL EMERGENCY RESPONSE PLAN (RERP) AP 06-002 Page 61 of 83 m O ATTACHMENT C [ ') (Page 4 of 8) _./ CROSS REFERENCE BETWEEN NUREG 0654, RERP, AND WCGS PROCEDURES h 0 0654 RERP Comments Procedure f Section Section F. - EMERGENCY CCH4UNICATIONS g 1.e 6.5.3, ERO Callout EPP 06-015, EMERGENCY RESPONSE 6.16.1 ORGANIZATION CALLOUT j 1.f 6.4.4, EPP 06-001, CONTROL ROOM 3.*] 6.5.2, OPERATIONS 6.5.4, EPP 06-002, TECHNICAL SUPPORT
- 6. 6. 9, CENTER OPERATIONS 6.16.1 EPP 06-003, EMERGENCY OPERATION FACILITY OPERATIONS
- 2. 6.10.6 Coffey County ambulances are in radio contact with the County Sheriff
- 3. 6.15, EPP 06- 018, MAINTENANCE OF 6.18.1, EMERfiENCY FACILITIES AND 6.18.6 EOUiPMENT/ COMMUNICATION CHECKS G. - PUBLIC EDUCATION AND INFORMATION
- 1. 6.17.5, 6.17.6
,7~'s 2. 6.17.5, 6.17.6 3.a 6.4.5, EPP 06-004, PUBLIC INFORMATION 16.6.2 ORGANIZATION 3.b 6.4.5 4.a 6.9.10 EPP 06-004, PUBLIC INFORMATION ORGANIZATION 4.b 6.9.1, EPP 06-004, PUBLIC INFORMATION 6.9.10 ORGANIZATION 4.c 6.4.5, EPP 06-004, PUBLIC INFORMATION 6.9.8 ORGANIZATION
- 5. 6.16.2 H. - EMERGENCY FACILITIES AND EQUIPMENT
- 1. 6.4.2, EPP 06-002, TECHNICAL SUPPORT 6.4.3, CENTER OPERATIONS 6.6, 6.7
- 2. 6.4.4, EPP 06-003, EMERGENCY OPERATION 6.8 FACILITY OPERATIONS
- 3. 6.8 Establish EOF.
- 4. 6.6.1, 6.8.1, Fig.2,3,4 ATTACH. D gs
( ) Lj'
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' ") (Page 5 of 8) m CROSS REFERENCE BETWEEN NUREG 0654, RERP, AND WCGS PROCEDURES l'
1 0654 RERP Comments Procedure Section Section H. - EMERGENCY FACILITIES AND EQUIPMENT 73 5.a 6.14.3,
, 6.14.4, 6.14.5 5.b 6.14.2 EPP 06-011, EMERGENCY TEAM FORMATION AND CONTROL 5.c 6.14.2 5.d 6.14.6 6.a 6.14.1 6.b 6.14.1 EPP 06-011, EMERGENCY TEAM and FORMATION AND CONTROL Figure 8 6.c 6.14.7 7 6.15 EPP 06-011, EMERGENCY TEAM FORMATION AND CONTROL
- 8. 6.14.3
- 9. 6.4.3 EPP 06-002, TECHNICAL SUPPORT CENTER OPERATIONS
- 10. 6.15 EPP 06-018, MAINTENANCE OF
, ~] EMERGENCY FACILITIES AND ( ! EQUIPMENT / COMMUNICATION CHECKS
- 11. 6.15
- 12. 6.14.7 EPP 06-011, EMERGENCY TEAM FORMATION AND CONTROL I. - ACCIDENT ASSESSMENT
- 1. 6.2 APF 06-002-01, EMERGENCY ACTION LEVELS
- 2. 6.3.20, EPP 06-017, CORE DAMAGE 6.14.2 ASSESSMENT METHODOLOGY 3.a 6.3.7 EPP 06-012, DOSE ASSESSMENT 3.b 6.3.7 EPP 06-012, DOSE ASSESSMENT
- 4. 6.3.7 EPP 06-012, DOSE ASSESSMENT
- 5. 6.14.3
- 6. 6.3.7 EPP 06-012, DOSE ASSESSMENT
- 7. 6.3.8, EPP 06-011, EMERGENCY TEAM 6.8.4 FORMATION AND CONTROL
- 8. 6.3.7, 6.5.2, 6.6.5, 6.8.2 q
\ _ ,_,/
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O ATTACHMENT C (Page 6 of 8)
\\ CROSS REFERENCE BETWEEN NUREG 0654, RERP, AND WCGS PROCEDURES
_D [ 0654 RERP Comments Procedure [ . Section Section I. - ACCIDENT ASSESSMENT g 9. 6.4.2, Lower bound for s 6.4.4 iodine measurement capability is 1.0E-7uci/ce.
- 10. 6.3.7 EPP 06-012, DOSE ASSESSMENT
- 11. 6.3.8 EPP 06-011, EMERGENCY TEAM FORMATION AND CONTROL J. - PROTECTIVE RESPONSE 1.a thru 6.3.10, EPP 06-010, PERSONNEL 1.d 6.3.11, ACCOUNTABILITY AND EVACUATION 6.6.5
- 2. 6.3.10, Figure 1
- 3. 6. 3. 9, 6.3.12
- 4. 6. 3. 9, 6.3.12
- 5. 6.3.10, EPP 06-010, PERSONNEL
,' ~T 6.3.11, ACCOUNTABILITY AND EVACUATION
) 6.6.5 6.a thru 6.3.13, EPP 06-013, EXPOSURE CONTROL AND 6.c 6.3.14 PERSONNEL PROTECTION EPP 06-011, EMERENCY TEAM
~ FORMATION AND CONTROL
- 7. 6.3.3, A EPP 06-006, PROTECTIVE ACTION RECOMMENDATION
- 8. Attach. B
- 9. N/A 10.a & Fig. I 10.b 10.c 6.1.6, 6.1.7, 6.10.2 10.d & N/A 10.1 10.m Attach. E EPP 06-006, PROTECTIVE ACTION RECOMMENDATION
- 11. & 12. N/A K. - RADIOIDGICAL EXPOSURE CONTROL l 1.a thru 6. 4 . 6, 1.g 6.10.5, 6.10.6 7
J4
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)
h CROSS REFERENCE BETWEEN NUREG 0654, RERP, AND WCGS PROCEDURES A 0654 RERP Comments E0 Procedure Section Section
\ 2. 6.3.16,
- EPP 06-001, CONTROL ROOM 6.5.2, OPERATIONS U 6.6.5, ; EPP 06-002, TECHNICAL SUPPORT l 6.8.2 CENTER OPERATIONS C0 EPP 06-003, EMERGENCY OPERATION i FACILITY OPERATIONS ' 3.a & 3.b 6.3.17, 6.4.2, ' 6.15.1
- 4. N/A 5.a & 5.b 6.3.21, 6.3.23
- 6. a 6' >ru 6.3.22, j 6.c 6.3.23, ATTACH. E
- 7. 6.3.13, 6.4.6 L. - MEDICAL AND PUBLIC HEALTH SUPPORT
- 1. 6.10.5 7.-
- 2. 6.4.6
- 3. N/A
' .- ')
x
- 4. 6.10.6 M.
- RECOVERY AND REENTRY PLANNINC AND POST-ACCIDENT OPERATIONS 1.0 6.21
- 2. 6.21 EPP 06-008, RE-ENTRY, RECOVERY,
- 3. 6.21 AND TERMINATION OPERATIONS
- 4. 6.3.7 This is not specifically identified as a post-accident function N. - EXERCISES AND DRILLS 1.a & 1.b 4.17, 6.18 2.a 6.18 2.b 6.18.2 2.c 6.18.3 2.d 6.18.4 EPP 06-009, DRILL AND EXERCISE
- 2. e (1) 6.18.5 REQUIREMENTS 2.e(2) 6.18.5 3.a thru 6.19.5 3.f
- 4. 6.19.4
- 5. 6.19.4
,-~.
_m ... . ... . . _ D Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN {
# AP 06-002 l # 'RERP)
O Reference Use Page 65 of 83 1 i m-( O ATTACHMENT C
. (Page 8 of 8) {
CROSS REFERENCE BETWEEN NUREG 0654, RERP, AND WCGS PROCEDURES
.D 1 0654 RERP Cr = = arat s Procedure 2
Section section __
] o. - RADIOIDGICAL EMERGENCY RESPONSE TRAINING g 1.a 6.17
.g 1.b N/A
,,_ 2. 6.17.2, EPP 06-021, TRAINING PROGRAMS g 6.17.6
- 3. 6.4.6
- 4. 6.17.2
- 5. 6.17 P. - RESPONSIBILITY FOR THE PLANNING EFFORT: DEVELOPMENT, PERIODIC REVIEW AND DISTRIBUTION OF EMERGENCY PLANS
- 1. 6.17
- 2. 5.3, 6.17.2 )
- 3. 6.20.2 j
- 4. 6.20.2 '
- 5. 6.20.3
- 6. 6.10, l l
6.11
- 7. ATTACH. C I
- 8. Table of Contents and ATTACH. C
- 9. 6.20.1
- 10. 6.20.2
- END -- I l
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/ (Page 1 of 1)
C ') WCGS MINIMUM STAFFING FOR EMERGENCIES
.D h
03 i Capability For Additions: ** FUNCTIONAL AREA POSITION '1ITLE OR EXPERTISE ON SHIFT 60 mins 90 mins Plant Operations & Shift Supervisor (SRO) 1 - - l Assessment of Supervising Operator (SRO) 1 - - Operational Aspects Reactor Operator (RO) 2 - - l ,.. Nuclear Station Operator 4 - - Emergency Direction and Duty Emergency Director 1* - - Control Notification / Emergency Communicator 1* 3 - Communication Radiological Accident DEM and staff - - 5 Assessment & Support of Operational Accident Sr. Health Physics (HP) Assessment Expertise - 1 - HP Personnel 1 8 - Chemistry Personnel 1 1 - Plant System Shift Technical Advisor 1 - - Engir eering, Repair &
/' 'N \
Corrective Actions Core / Thermal Hydraulics Eng. - 1 -
) Electrical Eng. -
1 - Mechanical Eng. - 1 - Radwaste Operator - - 1 Mechanical Maint. _ 2 - Electrical Maint. 2 - 1 I&C Technician _ 1 - Protective Actions (In- HP Personnel 1* 4 - Plant) Fire fighting = Fire -- FB per Tech Local Local Brigade (FB) Specs Support Support Rescue Operations and -- 2* Local Local First Aid Support Support All per Site Access Control and Security Personnel Security Accouncability Plan TOTAL 10 25 5 May be provided by shift personnel assigned to other functions. It is a goal to add, in accordance with this table, to the on-shift capabilities when determined necessary after a declared E.mergency. l
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' ATTACHMENT E (Page 1 of 4)
.D EPA / KANSAS PROTECTIVE ACTION GUIDES U E.1 Table E.1 lists the exposure limits in accordance with fs EPA-400-R-92-001, May 1992, and KANSAS PROTECTIVE ACTION GUIDES. g TABLE E.1 g EXPOSURE LIMITS ~ A. Whole Body Exposure Projected TEDE !
- 1. General Population M 1 to 5 REM
- 2 Emergency Workers 5 REM
- 3. Lifesaving Activities >25 REM **
B. Exposure to Radioiodines in a Plume Projected Thyroid Committed Dose j Equivalent (CDE)
- 1. Emergency Workers and Immobile i Populations
>25 REM I
- 2. Lifesaving Activities No specific upper REM limit ***
C. Exposure from Surface Water l Containing Radioactive Materials Concentration Level I l
- 1. General Population Concentration in excess of Kansas !
Radiation Protection Guidelines, App. l A, Table II, Column II
- 2. Emergency Workers N/A The lowest value should be used if there are no major local constraints in providing protection at that level, especially to sensitive populations. l s Local constraints may make lower values impractical to use, but in no case d
} should the higher value be exceeded in determining the need for protective ;
action. EPA-400 provides a limit of >25 REM, with no upper bounds for lifesaving activities. Consistent with RTM-93, WCGS has chosen to establish an upper limit of ~15 REM. No specific upper limit is given for thyroid dose since in lifesaving activities, complete thyroid loss might be an acceptable sacrifice if a life can be saved. However, this should not be necessary if respirators and/or ' i thyroid planning. protection for rescue personnel are available as a result of adequate E.2 Table E.2 lists recommended protective actions for exposure to a gaseous plume and controlling relocation / return. TABLE E.2 RECOM4 ENDED PROTECTIVE ACTIONS EXPOSURM TO A GASEOUS PLUME Projected Dose (REM) Actions Considered Comments General Population: No specific action required. Monitoring will be continued Considerations may be given until the extent of the TEDE <1 to: incident can be determined i
- 1. An advisory to seek and the situation fully shelter and await further evaluated.
instructions.
- 2. Voluntary evacuation.
- 3. Monitor environmental radiation levels.
O l
i$ Pevision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 { (RERP) gp Reference Use. Page 68 of 83 l l m D ATTACHMENT E * (N . (Page 2 of 4) l A l EPA / KANSAS PROTECTIVE ACTION GUIDES 1 General Population: l Evacuation should be Monitoring is performed so 1 initiated. Shelter may be the projected dose can be (o TEDE 1 preferable in some i determined and initial j j Thyroid CDE 5 situations. actions re-evaluated for possible adjustments. Re-l U evaluation will be
\ continuous as more data becomes available.
General Population: Administration of stable Monitoring is performed to Oy iodine. This requires confirm the evacuation area ! Thyroid CDE 25 and approval of State officials. or as a basis for necessary l above
- adjustments in the evacuation area.
Emer'gency Team Control exposure of Workers: For non-lifesaving emergency emergency team members tasks. through the use of time, TEDE 5 distance, shielding, job assignment, prophylactics and respirators. Emergency Team Workers Control exposure of (Lifesaving) emergency team workers through use of time and task i TEDE 25- assignment.
~~
j CONTROLLING RELOCATION / RETURN l Projected Dose (REM) Actions Considered Comments General Population: No action required. Public Monitoring will be performed TEDE <2 REM /lst year announcements of monituring to determine that projected or results and time required concentrations do not result
<0.5 REM /for any for passage of peak in doses exceeding PAGs.
other year concentration may be made. General Population: Do not allow return or Initial actions (if time relocate those that are permits) and re-evaluation ! TEDE greater than present. of initial actions will be l above. based upon monitoring of water directly from the supply and after treatment. Use of KI is not planned for general population in Kansas. i iO
. ._ .y
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u Reference Use Page 69 of 83 m O - ATTACHMENT E 7 3 ' (Page 3 of 4) EPA / KANSAS PROTECTIVE ACTION GUIDES l I E.3 Table E.3 lists recommended protective actions for different ' accident phases. O
\
TABLE E.3 U RECOMMENDED PROTECTIVE ACTIONS FOR DIFFERENT ACCIDENT PHASES Accident Phase Exposure Pathway Examples Of Recommended Actions l Emergency Phase (1) Inhalation of gases, Evacuation, shelter, access 0.5 to 24 hours
- radio-iodine, or control, respiration protection, g particulate prophylaxis (thyroid protection)
Direct whole body Evacuation, shelter, access exposure control Ingestion of milk Take cows off pasture, prevent cows from drinking surface water, discard contaminated milk, or divert to stored products such as cheese Intermediate Phase (2) Ingestion of fruits Wash all produce, or impound 24 hours to 30 days
- produce, delay harvest until approved uncontaminated produce can be substituted Ingestion of water Cut off contaminated supplies, substitute from other sources, filter, demineralize External exposure and Relocation decontamination, access inhalation control
,m Long term phase (3) Ingestion of tood and Decontamination, condemnation, or over 30 days *
(V) water contaminated destruction of food; deep plowing, from the soil either condemnation, or alternate use of by resuspension or land uptake through roots External exposure from Relocation, access control, deposition material or decontamination, deep plowing inhalation of resuspended material (1) Emergency Phase - Time period of najor release and subsequent plume exposure (2) Intermediate Phase - Time period of moderate continuous release with plume exposure and contamination of environment (3) Long Term Phase - Recovery period
" Typical" Post-Accident time periods i
/-~
v l
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'j EPA / KANSAS PROTECTIVE ACTION GUIDES 1r f E.4 Protective action guides for ground contamination ingestion
) exposure pathway are as follows:
_ Action Levels Recommended Protective Actions
- p. 1. Projected whole body dose above the 1. Evacuation of affected areas.
f ground - 1 REM. 2. Restriction of entry to contaminated
\
- 2. Ground contamination levels = 200 offsite areas until radiation level 03 uCi/m2 at t = 1 hr post-accident. has decreased to State approved
- 3. Exposure rate = 12 MREM /hr at 1 meter levels-above ground at t = 1 hr post-accident.
E.5 Protective action guides for food contamination ingestion { exposure pathway are as follows: 1 l Action Levels Concentration In Milk Pasture Grass Total Intake Via all l Food Pathways 0.5 REM WB 5 REM WB or bone; or bone; 1.5 REM 15 REM Thyroid Thyroid Nuclide* Preventive Emergency Preventive Emergency Preventive Emergency (pC1/L) (pCi/L) (pCi/kg) (pCi/kg) (pCi) (pCi)
,, I-131 0.015 0.15 0.05 0.5 0.09 0.9 / \ (Thyroid) i ) CS-137 0.24 2.4 1.3 13 7 70 (WB)
Sr-90 0.009 0.09 0.18 1.8 0.2 2 (Bone) Sr-89 0.14 1.4 3 30 2.6 26 (Bone) Recommended Protective Actions Preventive Emergency
- 1. Removal of lactating dairy cows from Isolate food from its introduction into contaminated pasture and substitution commerce after considering:
of uncontaminated stored feed. 1. Availability of other possible
- 2. Substitute source of uncontaminated actions.
water. 2. Importance of particular food in
- 3. Withhold contaminated milk from market nutrition.
to allow radioactive decay. 3. Time and effort to take action.
- 4. Divert fluid milk to production of 4. Availability of other foods.
dry whole milk, butter, etc. If other nuclides are present, Reg. Guide 1.109 will be used to calculate the dose to the critical organ (s). Infants are the critical segment of the population.
+
References:
U.S. Food and Drug Administration, Federal Register, Vol. 47, No. 205, Oc,tober 22, 1982.
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V
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' ATTACHMENT F (Page 1 of 1)
.O
.USAR CHAPTER 15 POSTULATED EVENTS
_G C0
\
Feedwater system malfunctions that result in decrease of feedwater temperature Feedwater system malfunctions that result in increase of feedwater system flow Excessive increase in secondary steam flow gy Inadvertent opening and failure to close of SG ARV or safety viv g Steam system piping failure (inside containment)
- Steam system piping failure (outside containment)
DD Loss of external. load (Main Generator trip) Turbine Trip Inadvertent closure of MSIVs Loss of condenser vacuum & other events resulting in turbine trip Loss of non-emergency AC power to station auxiliaries Loss of normal feedwater Feedwater system pipe break Partial loss of forced RCS flow Complete loss of forced RCS flow RCP shaft seizure-(locked rotor) RCP shaft break Uncontrolled RCCA bank withdrawal from a suberitical of low power.startup condition Uncontrolled RCCA withdrawal at power RCCA misalignment Startup of ire tive RCP at an incorrect temperature s CVCS malfunction resulting in a decrease in-the boron concentration in the RCS 1: Inadvertent loading and operation of a fuel assembly in improper position RCCA ejection accidents Inadvertent ECCS operation at power CVCS malfunction that increases RCS inventory l
.valve Inadvertent opening, with failure to close, of pressurizer safety or relief t
Break in instrument line or other lines from RCS pressure boundary that penetrate containment SG tube rupture LOCA spectrum l Radioactive waste gas decay tank failure l Postulated radioactive releases due to liquid tank failure i Fuel handling accident (inside containment) Fuel handling accident (Fuel Building) Spent fuel cask drop Anticipated transients without scram i
- END -
! i d e I 4 l l t
g _ ; _ _ _~_3_ ;_ _ _ _7 - 7 Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 h g Reference Use (RERP) I Page 72 of 83 m , n ATTACHMENT G (Page 1 of 1) , D LETTERS OF AGREEMENT ' D l c0
\
Party: I P The Coffey County Sheriff's Office
\ , ~
i (o Board of Trustees Fire District No. 1, Coffey County, KS . Newman Memorial Hospital Coffey County Hospital and Ambulance Service Topeka Air Ambulance Inc. (d.b.a. Life Star) Wolf Creek Nuclear Operating Corporation / Union Electric Co. Emergency Mutual Assistance Agreement INPO (Support During an Emergency) Department of Energy ** L Nuclear Regulatory Commission ** National Weather Service *** EPRI/INPO/NEI/ Member Utilities Coordination Agreement on Emergency Information Westinghouse As of January 1, 1987, the Letters of Agreement in this Supplement are transferred from Kansas Gas and Electric Company to the Wolf Creek Nuclear Operating Corporation. These Letters of Agreement are maintained on file and may be reviewed upon request. These LOAs will not be updated. They have been superseded by the publication of the " Federal Radiological Emergency Response Plan" in the Federal Register on 11/8/85. As of 8/25/93, the National Weather Service stated in writing that a Letter of Agreement with WCGS is unnecessary. Their " National Plan for Radiological Emergencies at Commercial Nuclear Power Plants," November 1982, remains in effect.
- END -
t O
-$ Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 % Reference Use' (RERP) -
g Page 73 of 83 m ! O ATTACHMENT H (Page 1 of 1) U REPORTING OF INCIDENTS PER 10 CFR 20
.0 0 .
CO
.2202 l Telephone & Telegraph .2203 Written immediate Notification 24 Hour Notification 30 Day Notification
( i RADIATION VALUES WCGS NRC KDEM WCGS NRC KDEM id WCGS NRC KDEM l INCIDENTS
\
_ TEDE 25 REM (.25 Sv) X X X X X X gg 5 REM (.05 Sv) X X X X X X MPE .1201 X X X X { Shallow dose to 250 Rad X X X X X X skin or extremities 50 REM X X X X X X in excess of MPE .1201 X X X X To the eye 75 REM (.75 Sv) X X X f 15 REM (.15 Sv) X X MPE .1201 X X X Emuent release 5 ALI X X X O excess of 1 ALI MPE .1201 X X X X X X X X X X X X X l X = Indicates notification is required MPE = Maximum Permissible Exposure DAC = Derived Air Concentration WCGS = Wolf Creek Generating Station NRC = Nuclear Regulatory Commission KDEM = Kansas Division of Emergency Management ALI = Annual Limit on Intake l \
(; Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002
" (RERP) o Reference Use Page 74 of 83 f71 O FIGURE 1 /~T EFFECTIVE 10 MILE EPZ, SUBZONES AND EVACUATION ROUTES !v!
A 4' y' 4 w ' " iN Y, (75 (]3 ) TO GMNETT - Y T REGISTRATION .7, h) TO EMPORIA NM '
'1N'k,I' '.p .'y CENTER g
AREGISMATION CENTER f . A;;;y >([Yg f yWa% 13J, > 77, ,,,7
, y, ys y Y ~
g Y2 ' m, ,, ,
- ' ', ', ' \
Hartford :, .3,$h. M N N ',20TH' RD'. ,'A ' '
' ', ?
,,,'YM ' b; A ) ?. New Q f M Strawny/h :,'- ' ' TO GARNETT
.. . fK >X 16TH RD. ,, /' ,
f CI' R .X'[';<'T<Ms;TJ RD.x fry y ([ y's__,/ [
~FRTW y$
[Wll yy' < '>g" 9 99 ,/ y < ^ N/ A ,...V1.3 E 1 , ? < >' - ' 12m RD. .
.4
[ 'on CCI f 3
'X[ ')>,'niRD})
?12 ReGETETWN CENTER
[NI '/. . ..,,,[
' ~
" 7Y X X' >['X'){
g 'l'. I) - g b,'enf!SWli;ss;gp]b1!W
' ' ' ~
' 10TH RD. 31',0.,/h M SE15^ME2}(;'
/ ',' [
V X 'y^V V V t s,s
..y yy'
'y'
- j)/. % y
% Vf Ql
$ m? <f/3.. $, ;),'?
$ >8m AD.
s ?SW 2 gd/ $ ,{q];g(x;x;xy. TOEMPORAq 87 $, 3 . fy$'bTf 2hk k '/ h' 2 h'y'V'> < Y! TO GARNETT REGISTRATlON REGISTRATION s s 2' ? ' ,' '( 'y'< X X CENTER CENTER '
'E u, _
L " g7'. p { Coffey County jf1 L.eRoy % f ; TO EMPORA
._J
[ TO GARNETT
,/ -~x v
Revision: 0 Y RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 (RERP) - y Reference Use Page 75 of 83 m O FIGURE 2 (') (/ MINIMUM SHIFT COMPLEMENT
.D
_c
- 0) SHIFT SUPERVISOR (SS)
(1 SRO)
\
h) SHIFT ENGINEER (SE) 2 ' (1) to V SUPERVISING OPERATOR (SO) (1 SRO) v REACTOR OPERATORS (RO) .' STATION OPERATORS (2) (4) - CHEMISTRY TECHNICIAN
-q (1)
HEALTH PHYSICS TECHNICIAN (1)
- Direction Technical Guidance SRO = Senior Reactor Operator STA = Shift Technical Advisor NOTE:
The SE or an SRO meeting the STA requirements of the NRC must be on shift in Modes 1 thru 4 /'N J
7 Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN 7' AP 06-002
' (RERP)
D Reference Use Page 76 of 83 m O FIGURE 3
/^ TSC/OSC ORGANIZATION
\
.D -
.D SITE EMERGENCY MANAGER (0
\.
IJ
\
(0 RADIOLOGICAL MAINTENANCE ADMINISTRATIVE OPERATIONS COORDINATOR COORDINATOR COORDINATOR COORDINATOR
- FACILITY MAINTENANCE ADMINIS*RATIVE
- ENS TECHNICIAN PLANNER ASSISTANT COMMUNICATOR M DRECTM - WAREHOUSE OPERATIONS SUPPORT RECORDER TEAM i ENGINEERING COMMUNICATOR j ; COORDINATOR
; : i a
l EMERGENCY :
- "** ! ENGINEERING RESPONSETEAM l TEAM
.. . 9 7ED.IN C,OlmtOL,lt00M,, ,
OPERATIONS COMMUNICATOR i i l l l I
. , . . . . . . _ _ . . _ . - . _ - = -
I Revision: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 1 (RERP) D Reference Use Page 77 of 83 m O FIGURE 4 EOF ORGANIZATION D A OFF-SITE EMERGENCY 03 MANAGER
\
l IJ l \ i (0 { { I OPERATIONS RADIOLOGICAL ADMINISTRATIVE { COORDINATOR COORDINATOR COORDINATOR I i i-l l OPERATIONS j HPN FACILITY ADMINISTRATIVE RECORDER g COMMUNICATOR TECHNICIAN ASSISTANT I s l . l DOSE ASSESSMENT TEAM DIRECTOR COORDINATOR l l , DOSE j ASSESWEW - TN
! TECHNICIAN COMMUNICATOR l
! i LOCATED ATCOUNTY EOC EMERGENCY RESPONSE TEAM REPRESENTATIVE AT COUNTY j 1 J 8 l l l l l
~ H~
j 7 Revision: 0
-' RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 l lE 1 D Reference Use (RERP)
Page 78'of 83 TTI . o FIGURE 5 PUBLIC INFORMATION ORGANIZATION O COFFEY COUNTY WOLF CREEK STATE OF KANSAS _D FEMA' NRC KGE/KCPUKEPCo PUBUC PUBUC PUBUC PUBUC PUBUC p) REPRESENTATIVE INFORMATION . INFORMATION INFORMATION INFORMATION INFORMATION (IC) OFFICER OFFICER
\ OFFICER OFFICER OFFICER OC) OC) - OC) (IC) (IC)
M
\
WOLF CREEK U PUBUC INFORMATION MANAGER (IC) TECHNICAL SUPPORT M MITER INFORMATION ONSITE PUBUC INFO. (IC) MESSENGER COORDINATOR OC) (IC) (TSC) PHONE TEAM MEDLA CENTER RUMOR CONTROL OFFSITE PUBUC INFO. MANAGER MANAGER COORDINATOR COORDINATOR (IC) (MC) (KCPL GO) (EOF) PHONE TEAM MEN UAIM MEDIA MONITORING OC) (MC) (KCP GO) MEDIA REGISTRAR
)
(MC) ' AUDIO VISUAL i' SUPPORT (MC) l l l
O O "*"O""' x w EMERGENCY ORGANIZATIONS INTERFACES $
; E (AT UNUSUAL EVENT LEVEL) l l g o
, TECHNICAUOPERATIONS S(ATJLEglEgl) . ,
SUPPORT CENTER 8 M Z h o ONSITE ONSITE y y
~ ~~
OFFSITE ~~ OFFSITE e a e RUMOR PHONE E O 8 CONTROL
- TEAM
- Q M 8 (AT SITE AREA OR GEF ERAL EMERGENCY LEVEL) O 8 EMERGENCY OPERATIONS INFORMATION CLEARINGHOUSE
- gM g
FACILITY (EOF) MEDIA CENTER
- y@ QQ
- 1
- sg gm .<
H M (n COUNTY STATE EMERGENCY OPERATIONS EMERGENCY OPERATIONS USNRC OFSE SUPPORT kM O z SUPPORT w CENTER CENTER cn e M s OTHER & SUPPORT FEMA STATE AGENCIES m NORMAL INTERFACE 4 e k TEMPORARY INTERFACE o @ EOF may be activated at Alert level. [ h
- Any of these functions may be activated at any emergency classification level. w N
g'. Revicion: 0 RADIOLOGICAL EMERGENCY RESPONSE PLAN AP 06-002 '
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O Reference Use Page 80 of-83 i til ; ! O FIGURE 7 ! WCGS EMERGENCY RESPONSE FACILITIES { z : l .0 (0
\ . '
td "*7 f i
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