ML20213G776
| ML20213G776 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 10/30/1986 |
| From: | Julie Ward SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| JEW-86-737, NUDOCS 8611180324 | |
| Download: ML20213G776 (25) | |
Text
{{#Wiki_filter:. F.ORM KMF-32 REV. 8/85 Date: /C - / 7 - A(n Sheet: 1 of 1 NUCLEAR DEPARTMENT POLICY / PROCEDURE MANUAL C REMOVE AND INSERT INSTRUCTION REMOVE INSERT I MX;S RADIOLOGICAL EMERGENCY RESPONSE PLAN IMPLEMENTING PROCEDURES N0fE: Please refer to the transmittal for pertinent hmts to be removed and/or inserted into the manual. j
- 1) Renove EPP TofC, Rev.19 (3 pages) 1) Insert EPP TofC, Rev. 20 (3 pages) i
- 2) None 2) Insert 'ICN No. 01-1.1-2 (2 pages) in front of EPP 01-1.1, Rev. S I
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f. EPP TofC UNG"> 5 0 REV. 20 DC20 e n-% , WCGS EMERGENCY PLAN IMPLEMENTING PROCEDURES i TABLE OF CONTENTS OCTOBER 14, 1986 l PROCEDURE NO. TITLE REV. EPP 01-1.1 TCN No. 01-1.1-2 5 l EPP 01-1.1 TCN No. 01-1.1-1 5 EPP 01-1.1 WCGS Organization 5 EPP 01-1.2 Emergency Operation Facility Emergency 4 Organization EPP 01-1.3 Home Office Emergency Center Organization 1
#F*~ EPP 01-1.4 Public Information Organization 3 EPP 01-2.1 Emergency Classification 2 EPP 01-2.2 Activation of Emergency Plan / Organization 3
. EPP 01-2.3 Accident Assessment and Mitigation 1 EPP 01-2.4 Core Damage Assessment Methodology 0 EPP 01-3.1 Immediate Notifications 4 EPP 01-3.2 Followup Notifications 3 EPP 01-3.3 Offsite Support Notification 2 EPP 01-3.4 TCN No. 01-3.4-1 2 EPP 01-3.4 Onsite Emergency Response Organization 2 Manual Call-Out EPP 01-3.5 EOF, HOEC and Public Information Emergency 4 Response Organization Manual Call-Out EPP 01-3.6 KG&E Emergency Response Organization 0 Automatic Call-Out EPP 01-4.1 Technical Support Center Activation 4 EPP 01-4.2 Operations Support Center Activation / 4 Operation s_ EPP 01-4.3 Emergency Operations Facility Activation 4
' EPP . 01-4.4 Home Office Emergency Center Activation 1' Page 1 of 3
~ ' EPP TofC I REV. 20 PROCEDURE NO. TITLE REV. EPP 01-4.5 General office Activation 3 EPP 01-4.6 Information Clearinghouse / Media Release 3 Center Activation EPP 01-4.7 Emergency Response Facility Information 0 System (ERFIS) EPP 01-5.1 Exclusion Area Evacuation 2 EPP 01-6.1 TCN No. 01-6.1-1 3EPP 01-6.1 Personnel Accountability 3 EPP 01-7.1 Radiological Release Information System 3 d.. (RRIS) EPP 01-7.2 Manual Determination of Release Rate 5 EPP 01-7.3 Manual Dose Projection Determination 5 EPP 01-8.1 Onsite Radiological Monitoring 4 EPP 01-8.2 Offsite Radiological Monitoring 3 EPP 01-8.3 Joint Radiological Monitoring Team 1 Formation and Operation EPP 01-9.1 Exposure Control and Personnel Protection 3 EPP 01-9.2 Personnel Decontamination 3 EPP 01-9.3 Radioprotective Drugs 3 EPP 01-9.4 Emergency Team Formation 4 EPP 01-9.5 Aid to Contaminated / Injured Personnel 3 EPP 01-10.1 Protective Action Recommendations 2 EPP 01-10.2 Preparation of News Releases 2 EPP 01-10.3 Release of Emergency-Related Information 2 Information to the Public EPP 01-11.1 Communications 2 TPP 01-11.2 Status Boards 2 ,
~~EPP D1-11.3 Logs and~ Record Keeping 1 ,
Page 2 of 3
EPP TofC REV. 20 PROCEDURE NO. TITLE REV. EPP 01-12.1 Reentry and Recovery Operations 3 EPP 02-1.1 Emergency Preparedness Program 3 Maintenance s EPP 02-1.2 TCN No. 02-1.2-3 4 EPP 02-1.2 TCN No. 02-1.2-2 4 EPP 02-1.2 Training Programs 4 EPP 02-1.3 Drills and Exercises 3 EPP 02-1.4 Public Education 1 EPP 02-1.5 TCN No. 02-1.5-1 5 jp, EPP 02-1.5 Maintenance of Emergency Facilities 5 and Equipment EPP 02-1.6 Communications Tests 2 ( EPP 02-1.7 EPP 02-1.8 Tone Alert Radio Maintenance and Compensating Measures Testing and Maintenance of Alert 0 2
\
and Notification System Sirens l Page 3 of 3
i n-U FORM EP 02-3 . TMPORARY PROCEDORE CHANGE WElC2 REV. 0 1 p/l,gr--- of 2 57 b y' p N i a . is 6 t, C 8 V (. ppnPFn0RZ TITLE: PROCEDURE NO./ REVISION 'ICN NO.
. . T'PP 01-1.1 / 5 01-1.1-2 l NCGS Organization -- -
RElt.ON FOR 'ICN: Further clarification of Bnerger.9/ Duties k-AFFBCTDDSTEPS: 4.2, 4.10, 4.25, 4.32, 4.33, 'ICN 01-1.1-1 ,. CHANGE REQUIRED: d' - C;mnge step number *4.2 9" to "4.2.1C^.
- 1 Add the following new sdep 4.2.9; - e 4.2.9 The DED/GS will provide instructions ;'_o, and verify accountability of, all on-duty I. ids. All on-duty NL0s will report to the Control Ibom and renaln C under the diro:tica of the Shift Supervisor unless otherwise directed by the DED.
- 3enove the fi at sentence fmn 4.10.1. -
- Add the following new steps 4.32 ani .4.32.1: '
4.32 ON-SHIFT HEAL'IH PHYSICS TECPSICIAN 4.32.1 'Ihe on-shift Health Physics Tedinician should report ' to the Ocntrol Roan and take direction h.an the DED/ Shift Supervisor. Other on-duty Health Physics Technicians.shall report to access control. As needed, the DED/SS raay require the on-shift Health Physics Technician to report to access control. hult'd on next page) PREPAPjD BY:
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D6TE APPRD* BY EIC: N A 5 sip'ITIRE l /'DATE AIF!!ORTTFD BY VZn 4mPDAR:
//RnFd SIGE'tDRE DATE DC29 I O 8(,
'ICN 01-1.1-2 Sheet 2 of 2
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g IEQUIRED (cont'd):
- Renove the secord sentence frca 4.25.1.
- Add the following new steps 4.33 and 4.33.1:
4.33 ON-SHIFT CHEMISTRY TECHNICIAN 4.33.1 'Ihe on-shift Chemistry Technician should report to the Control acam and take direction from the DED/SS. Other on-duty Chemistry Technicians should report to access control.
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FORK 10f-32 REY. 8/85 Date: /O-3D-8b 1 1 Sheet: of
~
NUCLEAR DEPARTMENT POLICY / PROCEDURE MANUAL REMOVE AND INSERT INSTRUCTION REMOVE INSERT NCGS RADIOEDGICAL EMERGENCY RESPONSE PLAN IMPLEMENTING PROCEDURES NOTE: Please refer to the transmittal for pertinent documents to be renoved and/or inserted into the manual. Renove EPP TofC, Rev. 20 (3 pages) 1) Insert EPP TofC, Rev. 21 (3 pages) 1)
- 2) Ranove EPP 02-1.1, Rev. 3 (22 pages) 2) Insert EPP 02-1.1, Rev. 4 (23 pages)
- 3) Renove EPP 02-1.8, Rev. 2 (7 pages) 3) Insert EPP 02-1.8, Rev. 3 (13 pages) 1 t
4
% EPP TofC
[ . REV. 21 DC29 so-so-8u l WCGS EMERGENCY PLAN IMPLEMENTING PROCEDURES TABLE OF CONTENTS OCTOBER 31, 1986 PROCEDURE NO. TITLE REV. EPP 01-1.1 TCN No. 01-1.1-2 5 EPP 01-1.1 TCN No. 01-1.1-1 5 EPP 01-1.1 WCGS Organization 5 EPP 01-1.2 Emergency Operation Facility Emergency 4
%- Organization EPP 01-1.3 Home Office Emergency Center Organization 1 EPP 01-1.4 Public Information Organization 3 EPP 01-2.1 Emergency Classification 2 EPP 01-2.2 Activation of Emergency Plan / Organization 3
'7;} EPP 01-2.3 Accident Assessment and Mitigation 1 EPP 01-2.4 Core Damage Assessment Methodology 0 EPP 01-3.1 Immediate Notifications 4 i
EPP 01-3.2 Followup Notifications 3 EPP 01-3.3 offsite Support Notification 2
, EPP 01-3.4 TCN No. 01-3.4-1 2 EPP 01-3.4 Onsite Emergency Response Organization 2 Manual Call-Out EPP 01-3.5 EOF, HOEC and Public Information Emergency 4 Response Organization Manual Call-Out EPP 01-3.6 KG&E Emergency Response Organization 0 Automatic Call-Out EPP 01-4.1 ,
Technical Support Center Activation 4 EPP 01-4.2 Operations Support Center Activation / 4 Operation EPP 01-4.3 Emergency Operations Facility Activation 4 EPP 01-4.4 Home Office Emergency Center Activation 1 Page 1 of 3
i s EPP TofC gS I REV. 21 PROCEDURE NO. TITLE REV. EPP 01-4.5 General Office Activation 3 EPP 01-4.6 Information Clearinghouse / Media Release 3 Center Activation EPP 01-4.7 Emergency Response Facility Information 0 System (ERFIS) EPP 01-5.1 Exclusion Area Evacuation -2 EPP 01-6.1 TCN No. 01-6.1-1 3 EPP 01-6.1 Personnel Accountability 3 EPP 01-7.1 Radiological Release Information System 3 (RRIS) EPP 01-7.2 Manual Determination of Release Rate. 5 EPP 01-7.3 Manual Dose Projection Determination 5 EPP 01-8.1 Onsite Radiological Monitoring 4 EPP 01-8.2 Offsite Radiological Monitoring 3 EPP 01-8.3 Joint Radiological Monitoring Team 1 Formation and Operation EPP 01-9.1 Exposure Control and Pe.rsonnel Protection 3 EPP 01-9.2 Personnel Decontamination 3 EPP 01-9.3 Radioprotective Drugs 3 EPP 01-9.4 Emergency Team Formation 4 EPP 01-9.5 Aid to Contaminated / Injured Personnel 3 EPP 01-10.1 Protective Action Recommendations 2 EPP 01-10.2 Preparation of News Releases 2 EPP 01-10.3 Release of Emergency-Related Information 2 Information to the Public EPP 01-11.1 Communications 2 EPP 01-11.2 Status Boards 2 EPP 01-11.3 Logs and Record Keeping 1 l Page 2 of 3
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EPP TofC [ REV. 21 l V) PROCEDURE NO. TITLE REV. EPP 01-12.1 Reentry and Recovery Operations 3 EPP 02-1.1 Emergency Preparedness Program 4 l Maintenance EPP 02-1.2 TCN No. 02-1.2-3 4 EPP 02-1.2 TCN No. 02-1.2-2 4 i EPP 02-1.2 Training Programs 4 EPP 02-1.3 Drills and Exercises 3 EPP 02-1.4 Public Education 1 EPP 02-1.5 TCN No. 02-1.5-1 5 EPP 02-1.5 Maintenance of Emergency Facilities 5 and Equipment EPP 02-1.6 Communications Tests 2 l EPP 02-1.7 Tone Alert Radio Maintenance and 0 Compensating Measures EPP 02-1.8 Testing and Maintenance of Alert 3 l and Notification System Sirens l l l l i Page 3 of 3 I
l l l l KANSAS GAS & ELECTRIC COMPANY WOLF CREEK GENERATING STATION RADIOLOGICAL EMERGENCY RESPONSE PLAN IMPLEMENTING PROCEDURE EMERGENCY PREPAREDNESS PROGRAM MAINTENANCE EPP 02-1.1 Revision 4 l O
- / a f EMERGENCY 'PLANNINtr Wuu ORDIN OR REVIEW
&/u DATE / /
Nm Ss ,am EMERGENCY PLANNING ADMINISTRATOR REVIEW WJO/8d DATE/ / Afd n l0-d PSRC APPROVAL RECOMMENDATION DATE O l0 Ei U V.P. NUCLEp APPROV L DATE / / RELEASED 501aoiB6 DATE 0 t
'l
. 1.0 PURPOSE s
This procedura defines the duties of the individuals responsible for emergency preparedness for the Wolf J Creek Generating Station (WCGS). It also provides guidelines for the updating of the Emergency Response Organization (ERO) Duty Roster; for the format, content, approval, review and revision requirements of the WCGS Radiological Emergency Response Plan (Plan) and Implementing Procedures (EPPs) ; and for the tracking of corrective actions. 2.0 APPLICABILITY This procedure applies to the Emergency Planning Coordinator (EPC) , Emergency Planning Administrator (EPA), and those personnel assigned responsibility for maintaining emergency preparedness for the WCGS.
; 3.0 DEFINITIONS 3.1 WCGS RADIOLOGICAL EMERGENCY RESPONSE PLAN IMPLEMENTING PROCEDURES (EPPs)
Written procedures which implement requirements of the Plan and specify actions to be taken by the ERO in the l event of a radiological emergency condition or a potential radiological emergency condition at WCGS. 3.2 ORIGINAL COPY Original copy is the word processed procedure which contains the actual review and approval signatures. I 3.3 RADIOLOGICAL EMERGENCY TELEPHONE DIRECTORY (RETD) l The directory of telephone numbers for all emergency
- response personnel and support organizations.
3.4 OPEN ITEMS l } Those items, which if left uncorrected, could impact
- the effectiveness of the emergency planning program.
These items are usually generated by the NRC, or Emergency Planning Group. 1 l l EPP 02-1.1 Rev. 4 Page 1 of 22 i
l
. 3.5 IMPROVEMENT ITEMS l !
Those items, which if left uncorrected, would not
. reduce the effectiveness of the emergency planning l program. These items, if corrected, would enhance the emergency planning program.
4.0 RESPONSIBILITIES 4.1 VICE PRESIDENT - NUCLEAR (VP - NUCLEAR) 4.1.1 The VP - Nuclear is responsible for assuring the development, maintenance and implementation of the WCGS radiological emergency preparedness program. He l
- has delegated the responsibility and authority for
, carrying out the responsibilities listed in Sections
} 4.2 and 4.3 to the EPC and EPA respectively. 4.2 EMERGENCY PLANNING COORDINATOR (EPC) -
- 4.2.1 The EPC is responsible for
i 4.2.1.1 Coordinating the overall Emergency Preparedness Program and developing and maintaining the offsite
- portion of the Emergency Preparedness Program 4.2.1.2 Developing and maintaining the Plan 4.2.1.3 Developing the EPPs that affect the Emergency Operations Facility (EOF), Information Clearinghouse
'~
(IC) , Media Release Center (MRC) , General Office (GO) , Systems Operation (SO), and Home Office Emergency Center (HOEC) 4.2.1.4 Maintaining the EPPs 4.2.1.5 Interfacing with the Manager, Nuclear Training in accordance with EPP 02-1.2, " Training Programs" i 4.2.1.6 Developing and implementing an Emergency Preparedness Drill and Exercise Program in accordance with EPP 02-1.3, " Drills and Exercises" 4.2.1.7 Developing and maintaining a Public Education and Information Program in accordance with EPP 02-1.4, "Public Education" 4.2.1.8 Assuring offsite emergency facilities (HOEC, GO, IC, and MRC), systems, equipment and supplies are l maintained. I EPP 02-1.1
- Rev. 4 Page 2 of 22 l
l 1
i 4.2.1.9 Assuring periodic reviews of the Plan and EPPs are j completed as required by 10 CFR 50.47(b),, 10 CFR 50.54(t) and 10 CFR 50.54 (q) 4.2.1.10 Assuring the appropriate personnel approve the Plan and EPPs 4.2.1.11 Maintaining the WCGS Radiological Emergency Preparedness Program associated files and documents for the above items, and Plan /EPP distribution control 4.2.1.12 Assigning personnel to the Emergency Response l Organization for the EOF, GO, IC, MRC and HOEC. 4.2.1.13 Assuring the tracking and closure of Open Items identified during drills, exercises, audits or appraisals. 4.2.1.14 Assuring the letters of agreement (LOAs) are reviewed annually and updated every two (2) years. 1 4.3 EMERGENCY PLANNING ADMINISTRATOR (EPA) 4.3.1 The EPA is responsible for: 4.3.1.1 Developing and maintaining the onsite portion of the j Emergency Preparedness Program, associated files and i documents 4.3.1.2 Technical review of the Plan to assure the onsite portion of the Emergency Preparedness Program is accurately reflected i 4.3.1.3 Developing the EPPs that affect the Control Room (CR), Technical Support Center (TSC) , Operations Support Center (OSC) and Security. 1 4.3.1.4 Reviewing technical content of all EPPs 4.3.1.5 Performing a 10 CFR 50.59 review for all revised EPPs and the Plan. 4.3.1.6 Developing and implementing an Emergency Preparedness l Drill and Exercise Program in accordance with EPP 02-
~1.3, " Drills and Exercises" l 4.3.1.7 Interfacing with the Manager, Nuclear Training in accordance with EPP 02-1.2, " Training Programs" 4.3.1.8 Maintaining onsite and near-site Emergency Response Facilities (Control Room, TSC, OSC and EOF), systems, equipment, supplies and performing inventory and I
i i EPP 02-1.1 ! \, Rev. 4 Page 3 of 22 i
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1 operability checks in accordance with EPP 02-1.5,
" Maintenance of Emergency Facilities and Equipment" 4.3.1.9 Assigning WCGS personnel to the Emergency Response l
! Organization for the Control Room, TSC and OSC and assuring Security provides personnel to the ERO 5.O PROCEDURE FORMAT AND CONTENT 5.1 The EPPs are divided into two groups, the 01-series and the 02-series. r i 5.1.1 The 01-series EPPs provide sufficient detail to guide emergency response personnel through specific actions during actual or potential emergencies. 5.1.2 The 02-series EPPs provide guidelines for the maintenance of the various aspects of emergency ( preparedness (e.g. program, training, emergency facilities, drills and exercises and alert and notification system). 5.2 All 01-series and 02-series EPPs shall contain the following elements and be written in accordance with l the format presented in Attachment 1.0. l l 5.2.1 Title - A page stating the title and incorporating the 4 following information: 1 5.2.1.1 " Wolf Creek Generating Station" l l 5.2.1.2 " Radiological Emergency Response Plan Implementing l Procedure" l The procedure title 1 5.2.1.3 5.2.1.4 The procedure identifying number The procedure revision number I 5.2.1.5 5.2.1.6 The EPC's signature and date of review I 5.2.1.7 The EPA's signature and date of review l 5.2.1.8 The Plant Safety Review Committee's recommendation for l approval and date 5.2.1.9 The VP - Nuclear's. signature and date of approval l 5.2.1.10 The release date (the date the procedure is issued by l Management Systems - Document Control) EPP 02-1.1 Rev. 4 Page 4 of 22 l
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. 5.2.2 Purpose - a brief statement describing the purpose of the EPP 5.2.3 Applicability - This section states when the EPP is used and designates the individuals or groups responsible for implementation.
5.2.4 Definitions - Define in this section any applicable term that may clarify the EPP. If there are none, designate by placing "NONE" in this section. 5.2.5 Instructions - The guidance to initiate or complete an activity and may include precautions, initial actions ! and subsequent actions as applicable. For 02-series EPPs, paragraphs 5.2.6 through 5.2.8 may be omitted. 5.2.6 Precautions - Note any important precautions or comments in this section. 5.2.7 Initial Actions - Identify those actions to be taken by the designated emergency response personnel upon activation of the EPP. 5.2.8 Subsequent Actions - Identify those actions to be taken by the designated emergency response personnel to ensure the emergency task is continued, as required, and aids in the recovery to normal j conditions. 5.2.9 References - List references used in the EPP in the order given below. If there are none, designate by placing "NONE" in this section. 5.2.9.1 WCGS Radiological Emergency Response Plan 5.2.9.2 Other EPPs 5.2.9.3 Other WCGS Procedures 5.2.9.4 Other Procedures / Documents 5.2.10 Records - Identify, by number and title, the forms to be retained, the length of the retention time, the i place of retention and if the records are QA or non-QA records. If there are none, designate by placing "NONE" in this section. 5.2.11 Attachments - Include applicable charts, drawings, data sheets, lists, forms and maps. If there are none, designate by placing "NONE" in this section. EPP 02-1.1 O Rev. 4 Page 5 of 22 I
5.3 With the exception of the title page, each page of an EPP shall contain the following information in the lower right hand corner of the page (as shown in [s Attachment 1.0 of this EPP) : 5.3.1 Procedure Identifying Number 5.3.2 Procedure Revision Number 5.3.3 Page number as part of the entire EPP, including its attachments. 5.4 The attachments contained in each EPP shall contain the following information at the top of each page: 5.4.1 Attachment number 5.4.2 Attachment page number as part of the entire attachment (as required) 5.4.3 Attachment title 5.4.4 If the attachment is a form, a form number and revision number shall appear at the upper left hand corner of the form. 6.0 REVIEW 6.1 A review of the emergency preparedness program shall be conducted at least every 12 months by persons who s- have no direct responsibility for implementation of the emergency preparedness program. This review is required by 10 CFR 50.54(t). 6.1.1 The review shall include the evaluation of: 6.1.1.1 Interfaces with State and local governments 6.1.1.2 Drills and exercises 6.1.1.3 Capabilities 6.1.1.4 EPPs 6.1.1.5 Emergency equipment 6.1.1.6 Discussions with emergency response personnel concerning their responsibilities during an emergency. EPP 02-1.1 Rev. 4 Page 6 of 22 l B L- _ -- - - - - - - --
.-- . -. . = . . _ - . . - . . -
6.1.2 Results of the review, along with recommendations for improvements shall be documented and reported to the eN Vice President - Nuclear and the Director - Nuclear
- Operations.
6.1.3 The review report shall be retained for a period of five years. 6.1.4 The part of the review involving the evaluation for adequacy of interface with State and local governments shall be available to the appropriate State and local governments. 6.2 A review of the Plan and EPPs, for possible revision, may occur at any time by a member of the ERO. 6.3 The EPC should conduct a review upon publication of changes to regulatory requirements or when significant changes are identified at WCGS which impact emergency preparedness capabilities, such as: i 6.3.1 Organizational changes l 6.3.2 Changes made to the State of Kansas Disaster Emergency Plan and to the Coffey County Contingency Plan for Incidents Involving Commercial Nuclear Power j 6.3.3 Changes to equipment used for emergency communications
) 6.3.4 Changes in the design of the WCGS or to the design of i
) emergency response facilities
, 6.3.5 Changes to the letters of agreement and related I documents
- 6.3.6 Changes made to the Radiological Emergency Telephone Directory (RETD) .
7.0 REVISION AND APPROVAL i 7.1 Any reviews of the Plan or EPPs may result in a request for revision of the document (s). ! 7.2 When a change to an EPP or the Plan is requested, the originator of the request (if outside the Emergency Planning Group) shall include it in a memo to the EPC. l l 7.2.1 The EPC reviews the change to determine its merit and urgency, and assures completion of the appropriate sections of the E Plan /EPP Change Request Form, Form EPP 02-1.1 Rev. 4 Page 7 of 22 1
.. _ . _ . . = _ -- __. . _ - _ - _ - _- -- _ .- - .- . - - . . . ,e s EP 02-2. A number is assigned to the change request consisting of two digits indicating the year, two digits indicating the month, and two digits indicating the sequential number for that request (i.e. 86/01-08). If the request must be incorporated immediately, the EPC will initiate an Emergency Procedure Change Notice (EPCN) to the EPP in accordance with Step 7.3.
No EPCNs are issued for the Plan. 7.2.2 If the change is not urgent, it will be placed in the file for that particular EPP or for the Plan and will be incorporated at the next revision. ! 7.2.3 A revision should be initiated when five EPCN's have l i been issued against an EPP, or at the EPC's
- discretion. Change requests from the file will be
, incorporated and the appropriate revision bars and arrows will be included. A Quality Compliance Verification Matrix Data Form (for EPPs only) and a ! EPP/E-Plan Revision Review Form will be attached to , i the proposed revision. f 4 7.2.4 The revision will be routed to the appropriate review , groups for comments. After comment incorporation, the ! revision will again be routed for review until no } further comments are received. The Lead in each review group will then sign and date the appropriate line on the Revision Review Form. 7.2.5 The revision package will be routed to the EPA for a i review in accordance with 10 CFR 50.59. The EPA will then route the package to the EPC, after signing the Revision Review Form and the title page of the EPP or E Plan. l 7.2.6 The EPC is responsible for a review in accordance with 10 CFR 50.54(q) and for obtaining the signature (s) of I the EPA, EPC, PSRC and the Vice President - Nuclear on the title page of the EPP or the E-Plan. [ NOTE: If any of the review group (s) request addi-tional revision (s) or indicate the proposed revision is unnecessary, the Revision Package is immediately forwarded to the EPC. Then the revision process is again initiated with Step i 7.2. l l 7.3 Minor revisions to EPPs are incorporated through the i use of an Emergency Procedure Change Notice (EPCN), l Attachment 4.0, Form EP 02-3. . 7.3.1 The EPC is responsible for issuing all EPCNs to EPPs. l l 5 EPP 02-1.1 Rev. 4 Page 8 of 22 i i
l e 7.3.2 EPCN numbers are assigned by, and reserved with, the Management Systems Document Control. The EPCN numbers shall include the EPP number, revision number, and the appropriate serial number (e.g. EPP 01-1.5 - Rev. 3-1, , EPP 01-1.5 - Rev. 3-2, ....). The serial numbers start over after each procedure revision. 7.3.3 The completed EPCN is routed to the EPA for review. l 7.3.4 The EPC shall approve the EPCN. I i 7.3.5 The Vice President - Nuclear authorizes the EPCN to be l released. t 7.3.6 Upon release, EPCNs are placed in front of the title l page of the affected EPP. 7.3.7 Upon release of a EPCN, revision of the affected EPP l will commence soon afterwards. 7.3.8 When five (5) EPCNs have been issued, a complete revision, incorporating all previously-issued EPCNs, should be initiated, or at the EPC's discretion. 7.4 Once all required signatures have been obtained, the revision package is routed to Management Systems l Methods & Procedures and then to Document Control for release. l 7.5 Management Systems Document Control is responsible for l verifying that each revision of the E-Plan, EPPs or
- EPCN is accompanied by a completed Attachment 2.0, l "E-Plan /EPP Revision Review Form," Form EP 02-1; and i that the E-Plan and EPPs are also accompanied by a completed KGF-21 form, " Quality Program Compliance Verification Matrix Data Form."
7.6 Management Systems Document Control is responsible for l releasing the revision and distributing it according i to the matrix maintained in CSARS (Configuration Status Accounting Record System). The CSARS matrix is
; updated by the EPC by using " Distribution Change l Request," Form KMF-3.
I 7.7 After release of the revised EPP or Plan, a copy is i forwarded to Records Management Control Systems - MSDC (RMCS-MSDC) for filming. The original and attached forms are maintained by MSDC. EPP 02-1.1 ( Rev. 4 Page 9 of 22 I
7.8 The EPC should assure that plan and/or procedural I changes which may impact offsite agencies and support organizations are routed to responsible individuals h within such agencies / organizations for their review {~'/
, and comments.
7.9 The call lists referenced in EPP 01-3.1, "Immediate l Notifications," EPP 01-3.2, " Followup Notifications," I and EPP 01-3.3, "Offsite Support Notifications" shall be reviewed at least once per calendar quarter and updated, as required, by the EPC. Attachment 5.0, "Callout List Verification," Form EP 02-18 will be used to document the quarterly review. 8.0 EMERGENCY RESPONSE ORGANIZATION (ERO) MAINTENANCE 8.1 The EPC identifies personnel to ERO positions in the i EOF, GO, IC, MRC and HOEC. Systems Operations notifies the EPC when new Systems Operations personnel need to be trained in emergency response duties. 8.2 The EPA identifies personnel to ERO positions in the l Control Room, TSC, OSC. Security notifies the EPA when new Security personnel need to be trained in emergency response duties. The EPA forwards the names of these candidates to the EPC. 8.3 A Position Acknowledgment Form and Selection and Qualification Form (if applicable) are transmitted to the ERO candidate by the EPC. ' (N
' 8.4 Nuclear Training is notified for which position (s) the candidate needs to receive training.
8.5 When Nuclear Training verifies that the candidate has completed the required training this information is transmitted to the EPC and the candidate's name is submitted for entry on the next revision of the ERO. 8.6 The RETD is updated according to each ERO revision. 9.0 CONTROL AND DISTRIBUTION ! 9.1 The EPC shall update and maintain the WCGS Plan, EPP and Radiological Emergency Telephone Directory (RETD) controlled distribution lists for facilities and personnel. 9.2 Changes in these lists shall be transmitted to Management Systems Document control by using Form KMF-3, "WDCC Distribution Control List Change Request." l EPP 02-1.1 O Rev. 4 Page 10 of 22
______._- ._ _ _ _ _ . _ _ _ __ _-_ m-- . _ _ _ . t
. 9.3 The Management Systems Document Control group shall l maintain:
9.3.1 The controlled distribution lists (CSARS distribution i module) and associated distibution codes r 9.3.2 Original copy of the WCGS Radiological Emergency l l Response Plan r j 9.3.3 Original copy of the RETD I l 9.3.4 Original copies of the EPPs l 9.3.5 Receipt acknowledgments for controlled copies per KP- l 1040, " Control and Release of KG&E Policies,
. Directives, Procedures, Instructions and Forms j 9.3.6 The release record and document control numbers of the Plan, EPPs and RETD (in CSARS) i 9.4 Management Systems shall identify each controlled copy of the Plan, EPPs and RETD with a unique distribution code.
9.4.1 Distribution shall be made using CSARS transmittal / acknowledgements. Acknowledgements shall be main-tained as described in KP-1032, " Distribution Control System." l l 10.0 CORRECTIVE ACTION PROGRAM 10.1 Open Items and Improvement Items may be initiated by:
- NRC Inspection / Exercise Reports Drill / Exercise Reports
- Other documents as identified by EPA or EPC, as necessary j
10.2 As items are identified for corrective action, they are reviewed by the Emergency Planning Group. 10.3 If the item is classified as an Open Item, it is assigned an Open Item Tracking Number. The format for l the number is: 4 "EP-two digits indicating year the item was identified l a three digit I.D. number assigned in chronological i' order" (Example: EP-86-066). Open Items are maintained on the Open Item Tracking List. 10.4 If the item is classified as an Improvemenu Item, the l item may be maintained on the Improvement Item Tracking List. I EPP 02-1.1
- Rev. 4 Page 11 of 22 l
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. 10.5 Each Open Item is assigned:
its source document, if any [ - responsible individual j Q} . - due date status, if any l 1 description of the item 10.6 The Emergency Planning Group informs the responsible l individual of his/her Open Items and/or Improvement l Items. 10.7 The Emergency Planning Group is responsible for incorporating new Open Items / Improvement Items onto their respective lists and deleting those items which have been closed. 10.8 If the response to close an Open Item is to be sent to the NRC, the Emergency Planning Group shall inform Licensing of the item, its response and due date. Licensing is responsible for the formal submittal. 10.9 All Open Item closure responses are reviewed by the EPC, documented and maintained by the Emergency Planning Group.
11.0 REFERENCES
11.1 Wolf Creek Generating Station Radiological Emergency Response Plan l l 11.2 EPP 01-3.1, "Immediate Notifications" 11.3 EPP 01-3.2, " Followup Notifications" 11.4 EPP 01-3.3, "Offsite Support Notifications" 11.5 EPP 02-1.2, " Training Programs" l 11.6 EPP 02-1.3, " Drills and Exercises" 11.7 EPP 02-1.4, "Public Education" l 11.8 EPP 02-1.5, " Maintenance of Emergency Facilities and Equipment" 11.9 KP-1032, " Distribution Control System" l l 11.10 KP-1040, " Control and Release of KG&E Policies, Direc- l tives, Procedures, Instructions and Forms" l 11.11 10 CFR 50 l EPP 02-1,1 Rev. 4 Page 12 of 22 1
l r
, 11.12 10 CFR 50 Appendix E l 12.0 RECORDS 12.1 Form EP 02-1, "E-Plan /EPP Revision Review Form" 12.2 Form EP 02-2, "E-Plan /EPP Change Request Form" 12.3 Form EP 02-3, " Emergency Procedure Change Notice" l 12.4 Form KMF-3, " Distribution Change Request" 12.5 Form KGF-21, " Quality Program Compliance Verification Matrix Data Form" 12.6 The following records shall be retained for at least five (5) years in the WCGS vault:
12.6.1 Records of all audits and appraisals 12.6.2 All drill and exercise reports 12.6.3 Original copies of all EPPs, and their subsequent revisions. 12.7 The Plan, EPP and RETD controlled distribution acknowledgment forms shall be retained for at least six (6) months. j 12.8 The Open Item Tracking List is considered a QA l record. It will be maintained for two years by the i Emergency Planning Group, then transferred to Records l Management for permanent storage. 12.9 The Improvement Item Tracking List shall be considered a non-QA record and maintained by the Emergency Planning Group. As each Improvement Item is closed, l it is deleted from the list. i
- 13.0 ATTACHMENTS 13.1 Attachment 1.0, " Sample Format for the Radiological ,
Emergency Response Plan Implementing . Procedure - Title Page" ( 13.2 Attachment 2.0, "E-Plan /EPP Revision Review Form" i
- 13.3 Attachment 3.0, "E-Plan /EPP Change Request Form" 13.4 Attachment 4.0, " Emergency Procedure Change Notice" l 13.5 Attachment 5.0, "Callout List Verification" l
[ EPP 02-1.1 Rev. 4 ' k Page 13 of 22 i 1
. ATTACHMENT 1.0 (Page 1 of 2)
SAMPLE FORMAT FOR THE RADIOLOGICAL EMERGENCY RESPONSE PLAN IMPLEMENTING PROCEDURE - TITLE PAGE WOLF CREEK GENERATING STATION RADIOLOGICAL EMERGENCY RESPONSE PLAN IMPLEMENTING PROCEDURE PROCEDURE TITLE ( ) PROCEDURE NUMBER EPP ( ) Revision Number ( ) N EMERGENCY PLANNING COORDINATOR REVIEW DATE l l EMERGENCY PLANNING ADMINISTRATOR REVIEW DATE l l l PSRC APPROVAL RECOMMENDATION DATE l l l VP NUCLEAR APPROVAL DATE Released: DATE EPP 02-1.1 - Rev. 4 Page 14 of 22 I
. ATTACHMENT 1.0 '
(Page 2 of 2) SAMPLE FORMAT FOR THE RADIOIAGICAL EMERGENCY RESPONSE PLAN IMPLEMENTING PROCEDURE 1.0 PURPOSE 2.0 APPLICABILITY 3.0 DEFINITIONS 4.O INSTRUCTIONS 4.1 PRECAUTIONS 4.2 IMMEDIATE ACTIONS 4.3 SUBSEQUENT ACTIONS 5.O REFERENCES 6.0 RECORDS 7.O ATTACHMENTS I i l l EPP 02-1.1 Rev. 4 Page 15 of 22 I
l l
}U M EP 02-1 REV. 2 g ATDOBENT 2.0 (Page 1 of 2)
E-PIAN /EPP REVISICH REVIEN IMM Data E-PIAN [ Affected Sections EPP [ Affected EPPs EPCN [ Affected EPP
- 1. m itment Interface Will this incorporate, delete or modify an existing - itment to the NRC or an E-Plan Group Open Item?
Yes No If yes, Ctastitment Number /Open Item Number (If yes to the NRC ocautituent, foward a copy to responsible Licensing Engineer)
- 2. Review Revision to be reviewed by the following puum u 1:
O [ Nuclear Operations Signature of Reviewer /Date Health Physics / Radiological Services Signature of Reviewer /Date [ Nuclear Services Signature of Reviewer / Data t l [E Signature of Reviewer /Date [ Oorporate m w11 cations Signature of Reviewer / Data b Signature of Reviewer /Date l i l EPP 02-1.1 Rev. 4 Page 16 of 22
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e FW M EP 02-1 REV. 2 ATDGMEtc 2.0 (Page 2 of 2) E-PIAN /EPP REVISION REVIDi FWM (Continued)
- 3. M r=ar= *
- a. 'Ihe r - ettru, s - tive revision or change, or anrif fication to which this evaluation is applicable:
Yes No Does this change the facility or r etires from their description in the FSAR? Yes No Does this change involve a test or experiment described in the FSAR? Yes No oxid this change effect nuclear safety in a way not previously evaluated in the FSAR? Yes No Does this change reduce the margin of safety as defined in the Technical Specifications? Yes No Does an envircrimental question exist? If the answer to any of the above questions is "Yes", the Nuclear Safety Evaluation Checklist shall be forwarded to the Results Engineering Supervisor or Supervisor Environmental Managenent for ocsplation of a safety /envisua utal evaluation. If' the answer to all the above are "No", no unreviewed safety / environmental questien exists. l EPA Signature /Date l b. Effactiveness Evaluation [10 CFR 50.54(q)] Yes No Does this pwyr.ed revision decrease the effectiveness of the E-Plan? EPC Signature / Data EPP 02-1.1 Rev. 4 l Page 17 of 22 l l
FCEM EP 02-2 REV.1
- ATDOMENP 3.0 (Page 1 of 2)
't E-PIAN /EPP OiANGE REQUEST FUEM V .
Date
) OiANGE REQUEST NUMBER
[ URGENT (IARET DATE Q NEXT REVISICN E-PIAN [ Affected Sections EPP [ Affected EPPs
- 1. Sauros Prepared By croup
- 2. W! tion of Revisica (Marked up pages should be attached)
O 3. Damarwt for Revisicm: Design Change Correction to PlarVEPP Error Clarification Other (describe) Justification:
- 4. h itzent Interface Will this ir uswiate, delete or modify an existing ocznitment to the NRC or an E-Plan Group Open Item?
Yes No If yes, Ocunitment Number /Open Item Number (If yes to the NRC ocannitment, forward a copy to reeiuriible Licensing Engineer) EPP 02-1.1 Rev. 4 Page 18 of 22 1
FCEM EP 02-2 REV.1 ATDOttENT 3.0 (Page 2 of 2) E-PIAN /EPP OIANGE REQUEST FCEM
- 5. Cicsscut
- a. l l Ir - m ated into rerision #
EPC Signature /Date
- b. p Rejected EPC Signature / Data Raason:
l I Date originator notified of rejection Date .1 l i ? F ,1 r j l i e i I 1 I EPP 02-1.1 j 1 Rev. 4 Page 19 of 22-I
l ATDGMENT 4.0
, (Page 1 of 2) lO l
IEV. I d l moaouis Trrut: Isrvwrer m./suivIsmat ERN ND.
/
RENKN RR EFQt l AFyrmn gatFs amie EeQDInup: l h V l mEPMD M: suaemam om APIWDYED N EPC: suaomas om I mmsztIzso a vP-NUCUAR: i I sunomme om EPP 02-1.1 Rev. 4 1 Page 20 of 22 k l
ATDOBEDE 4.0 ( (Page 2 of 2) INS'5DCITCMS PER CMPIEI'ING PMM EP 02-3 l
- 1. Enter title of g. - - itre.
- 2. Enter p -- twa rumber and revision.
- 3. Enter Emmiupcy Pzrmhnu Change Notice (EPCN) number. l l
- 4. Enter reason for EPCN. l
- S. Enter affected p --ins steps. -
1 j 6. Enter g --tire changes required. I 7. Preparer's signature and date. .
- 8. Eunupcf Planning Coordinator approval signature and date.
- 9. VP - Nuclear authorization signature and date.
l - l l
'. L EPP 02-1.1 Rev. 4 Page 21 of 22
a-- - ---- s - - a _ - - +u ,4a l
- t. ,
V ,;,,. ,f , f
- *' FotM EP 02-18 REV. C-'-
4 ( g ATTACHMENT 5.0 _ e - (Page 1 of 11
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QUARTEHfJ CAI. LOUT LIST VERIFICATION ,, F
- 1. EPP 01-3.1, " Immediate Notification," call lists have been reviewed and " ~ '
updated as required. Reviewed by ' Date Changes incorporated _ , EPP Rev. or EPCN No. or NA (not applicable) Date
.t
- ,4 6 2. EPP 01-3.2, " Followup Not,iffistions," call lists h' ave bfen reviewed'and updated as required.
, ,Raviewed by _ _ _ _
- Date l Changes incorporated' EPP Rev. or EPCN No.,or NA (not applicable) Date
} '3. EPP 01-3.3, "Offairst,Gupport Notifications," call-lists have been i reviewed and upJsted aa required. Reviewed by Date Changes incorporated : SPP Rev. or EPCil No. er NA (not applicable) Date 4 - (,s a E { ' .. w . , s.. I 1
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i EPP 02-1.1 Rev. 4 Page 22 of 22 s 8 1 J f -
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.s D WOLF CREEK GENERATING STATION l
RADIOLOGICAL EMERGENCY RESPONSE PLAN IMPLEMENTING PROCEDURE TESTING AFD MAINTENANCE OF ALERT AND NOTIFICATION SYSTEM SIRENS EPP 02-1.8 Revision 3 l [ O w EsNA1 9A A > Mn EMERG2NCY PLA) NG COORDIN LTUR REVIER DATE / ~/"- Sm EMERGENCY' PLANNING ADMI ISTRATOR REVIEW
/0 -AYSb DATE PSRC APPROVAL RECOMMENDATION lb/kf R DATE .
0khk V.P. NUC APP OVAL
- b.b. Def /o/2.9h6 DATE '
RELEASED C29 f ajg aj,,f, DATE O I
l 4 1.0 PURPOSE 1.1 This procedure provides instruction for the testing and maintenance of the Alert and Notification System sirens.
;2.0 APPLICABILITY
' 2.1 This procedure applies to all WCGS Alert and Notification System Sirens. It is the responsibility l l of the Emergency Planning Administrator (EPA) to initiate the Work Request which implements siren maintenance. Siren maintenance shall be performed on an annual basis.
2.2 This procedure also applies to the Emergency Planning Administrator (EPA) and the Maintenance Communication Group for testing of the Alert and Notification System Sirens. Refer to Attachment 2.0, " Alert and Notification System Siren Annual Maintenance Form," Attachment 3.0, "ANS Siren Two-Week Test Report" and Attachment 4.0, "ANS Siren Full-Cycle Test Report." 3.0 TESTING 3.1 BIWEEKLY TEST 3.1.1 The Maintenance Communication Group shall perform a test of each siren. The sirens are growl tested (verifies proper operation of each siren by activating the siren motor long enough to attain sufficient speed to produce a growl sound) once per month; and silent : tested (verifies operation of the radio control, activating equipment without operating the siren motors) every two weeks, except when growl tested. i 3.1.2 Listed below are the siren identifier, location and approximate test time in the order which they are tested. SIREN SIREN APPROXIMATE l IDENTIFIER LOCATION TEST TIME S-1 (Sharpe) Directly west of the Sharpe 0730 grain elevator W-1 (Waverly) Corner of 7th and Shefield 0800 Streets in Waverly ' JR-2 (Cttumwa) South end of Ottumwa 0845 NS-1 (New Strawn) South of'the old New Strawn 0930 , School JR-1 (Main Dam) Adjacent to the WCGS Make-up 1000 ( Water Screenhouse EPP 02-1.8 l O Rev. 3 Paga 1 of 12
/
I
-,w -r. - - ,,----w. - - - - - , , . -.----,,,-m...--- -..--m.,.-,,--w~r,.,--m----.--w----.--.---e,- . _ , - - ,,--,,1-=- w.. , , , - - --,-,-,,, ,-- w1,,w-,.----,,---
JR-3 (Otter Creek) One-half mile north and one- 1030 quarter mile west of the west i and of JRR Dan JR-4 (Jacobs Creek) Five miles west and three miles 1045 north of Burlington B-2 (Sonic) North edge of Burlington on 1200 Hwy. 75 B-1 (9th & Yubc) Near the alley at 9th & Yuba 1230 Streets in Burlington L-1 (LeRoy) One block south of the LeRoy 1325 High School 3.2 ANNUAL FULL CYCLE TEST 3.2.1 The annual full c;ycle test requires activation of all ten sirens in unison. The Coffey County Sheriff's Department will activate the sirens for this test. 3.2.2 Personnel will be located near each siren location l during the annual test to verify that each siren I functions (uounds (;nd rotates) properly. 3.3 SCHEDULE AND COUNTY COORDINATION 3.3.1 The siren testing schedule will be coordinated with the Coffey County Emergency Preparedness Coordinator (EPC). The Coffey Ccunty EPC is responsible for notifying the public af siren test schedules. Adverse weather say affect thc. schedule. The annual full l
- cycle test is also coordinated with the Coffey County l Sheriff # s Department.
3.4 SIREN ACTIVATION 3.4.1 A portable radio transmitter is used to activate.the individual sirens for tha biweekly tests. See Attachment 1.0, " Instructions for using the Siren i Portable Radio Transmittet" for instructions on using the portable radio transmitter. 3.4.2 The Coffey County Sheriff'c Department instrument console should be used for siren activation for the biweekly testing when the portable radio transmitter is malfunctioning. 3.5 SIREN MALFUNCTIONS 3.5.1 The Coffey County Sheriff's Department will be notified of any siren or group of sirens which fail to operate, so that compensating measure can be taken per Coffey County's Contingency Plan Implementing Procedure No. 42. l , EPP 02-1.8 Rev. 3 Page 2 of 12 l
. 3.5.2 Following repair completion, a growl test will be performed on the repaired siren. Any sound tests will be coordinated with the Coffey County EPC.
3.5.3 The coffey County Sheriff's Department will be notified of the successful test of the siren (s) so that compensating measures may be stopped. 3.6 SIRENS 3.6.1 See Attachment 5.0, " Siren Locations" for locations of the sirens. 4.0 ANNUAL SIREN INSPECTION 4.1 NOTES AND PRECAUTIONS l 4.1.1 Suitably identify and store nuts, bolts, washers, l studs, or any disassembled parts for proper reinstallation. 4.1.2 Wear ear protection if locally testing sirens. l 4.1.3 Deenergize the power at the breaker before performing l any anintenance on the siren. 4.1.4 Follow all " Bucket Truck" safety requirements. l 4.2 PREREQUISITES l O 4.2.1 Obtain a current working copy of this procedure, plus l l a Signoff/ Data Sheet (Attachment 1.0) for each siren to be tested (total of 9). 4.2.2 Obtain a current copy of the Federal Signal ! Corporation Radio-Controlled Public Notification System Service Manual. 4.2.3 Enter the Work Request Number on the Signoff/ Data l Sheet (Attachment 1.0) 4.2.4 The EPA shall notify, as appropriate, the following i before inspection begins: 4.2.4.1 Landowners to obtain permission to enter their l property. 4.2.4.2 Local law enforcement officials that sirens will be l turned off. 4.2.4.3 WCGS Public Information Officer so public l announcements can be made, if necessary. EPP 02-1.8 Rev. 3 Page 3 of 12 l i l
. 4.3 PARTS AND SPECIAL EQUIPMENT 4.3.1 NONE l 4.4 WORK PERFORMANCE INSTRUCTION l NOTE: The applicable paragraphs of the Federal Signal Corporation Radio-Controlled Public Notification System Service Manual are referenced below as "FSC SM Paragraph x-xx."
4.4.1 Remove the screws that hold the blower base channel l space covers on the blower housing, and lift off the blower housing. l 4.4.2 Remove the cover from the rotator housing closest to l the conduit fitting. 4.4.3 Remove the weights from the blower relief valve. l Clean all machined surfaces and cover them with a film ! of SAE 10W40 motor oil. 4.4.4 Examine the blower drive belts for excessive wear. l Depress each belt individually with one finger. The belts should not depress more than approximately 1/2 in. or 13 mm. Replace both belts if either belt is excessively worn or frayed. Tighten belts if they depress more than 1/2 in. or 13 mm. Refer to FSC fiM Paragraph 5-4B.1 for belt tightening and replacement instructions. 4.4.5 Change the oil and grease in the blower. Refer to FSC l SM Paragraph 5-3A.1 for instructions. 4.4.6 Examine the rotator drive belt for excessive wear. l Depress the belt with one finger. The belt should not depress more than approximately 1/2 in. or.13 mm. Replace the belt if it is excessively worn or adjust if it depresses more than 1/2 in. or 13 mm. Refer to FSC SM Paragraph 5-4B.2 for belt tightening and replacement instructions. 4.4.7 Change the oil in the rotator gear reducer. Refer to l FSC SM Paragraph 5-3A.2. 4.4.8 Clean the rotator spur and pinion gears. Apply a l light film of grease: Texaco Regal AFB 2 or equivalent, to the gears. 4.4.9 Inspect the Electrical Control Box gaskets to ensure l water tight integrity and verify that there is no moisture condensation on the box internals. 4.4.10 Replace the rotator and blower housing covers. l EPP 02-1.8 Rev. 3 Page 4 of 12 I
4.4.11 Inspect painted surfaces to determine if repainting is I required. O 4.4.12 Inspect the siren installation to ensure vertical orientation. Siren must not be more than 5 degrees out of plumb. l 4.5 RESTORATION AND RETESTING Energize siren power at the breaker. I 4.5.1 5.O ATTACHMENTS 5.1 Attachment 1.0, " Instructions for Using the Siren Portable Radio Transmitter" 5.2 Attachment 2.0, " Alert and Notification System Siren Annual Maintenance Form," Form EP 02-16 5.3 Attachment 3.0, ANS Siren Two-Week Test Report," Form EP 02-20 5.4 Attachment 4.0, ANA Siren Full Cycle Test Report," Form EP 02-21 5.5 Attachment 5.0, " Siren Locations"
6.0 REFERENCES
l 6.1 EPP 02-1.7, " Tone Alert Radio Maintenance and l Compensating Measures" 6.2 Federal Signal Corporation Radio-Controlled Public l Notification System Service Manual 6.3 MGEE COP-05, Megger Procedure 6.4 Coffey County Contingency Plan Implementing Procedure l No. 42, " Siren Maintenance" 7.0 RECORDS , 7.1 Form EP 02-16, " Alert and Notification System Siren l ! Annual Maintenance Form" 7.2 Form EP 02-20, "ANS Siren Two-Week Test Report" 7.3 Form EP 02-21, "ANS Siren Full Cycle Test Report" 7.4 Records generated by this procedure are maintained by the EPA for a period of at least five years. These records are non-QA records. EPP 02-1.8 O Rev. 3 Page 5 of 12 1
l ATTACHMENT 1.0 h (Pago 1 of 2) INSTRUCTIONS FOR USING THE SIREN l
) PORTABLE RADIO TRANSMITTER The siren portable radio transmitter has a 10-key keyboard similar to a pushbutton phone, having 10 numbered keys and two keys with the "*" and "#" symbols. The transmitter is used to activate the individual sirens by use of a six (6) digit code system.
The first two digits of each code is the " call code." The third and fourth digits will be the siren " address." The last two digits make up the " function" designator which refers to the Attack, Alert, Fire or Cancel mode. See example below. 1-5 - 0-9 - *-3 Function designator Address or group call locations call code, common for all requests Table 1 lists the address and call code for each siren as well as the designator for each function. Example 1: To activate the Waverly siren in the fire mode, key the following sequence: 1-5-0-9-*-3 To cancel sequence is: 1-5-0-9-*-4 Example 2: Cancel can also be achieved by Group Call sequence: 1-5-0-#-*-4 EPP 02-1.8 Rev. 3 Page 6 of 12 l
ATTACHMENT 1.0 (Pags 2 of 2) f s TABLE 1 SIREN ACTIVATION CODES Siren Site Address Group Calls All Call Sharpe 0-1 0-# New Strawn 0-2 Ottumwa 1-3 Otter Creek 1-4 1-# Main Dam 1-5 #-# Jacobs Creek 1-6 (Sheriff's office only) Sonic 2-6 2-# 9th & Yuba 2-7 Leroy 0-8 0-# Waverly 0-9 Function Attack (wail) 1 Alert (steady) 2 Fire (Hi-low) 3 Cancel 4 EPP 02-1.8 Rev. 3 Page 7 of 12 I
REM EP 02-16 REV. 1 ATDORENT 2.0 l-(Page 1 of 2)
. AIERP AND NCTfIFICATICN SYSHM SIREN ANNUAL MAINIDONCE REN
- 1. Work Request No. Dated
- 2. Siren Iocation
- 3. Deanergize siren power at breaker.
- 4. Maintenance Items to be Perfnmari:
Initial Not Action Ocmgalete Applicable A. Blower Relief valve weights cleaned and oiled B. Blower drive belts examined for excessive wear. C. Blower drive belts r elaced. (Yes No ) D. Blower drive belts do not depress more than 1/2 in or 13 m. (Yes No ) E. Blower drive belts tifa'ws.d. (Yes No ) F. Blower oil and grease changed. G. Rotator drive belt / drive chain examined for excessive wear. H. Rotator drive belt / drive chain replaced. (Yes No ) I. Rotator drive belt / drive chain does not depress more than 1/2 in. or 13 m. (Yes No ) J. Rotator drive belt / drive diain tightened. (Yes No ) l K. Rotator gear rait- oil dianged. L. Rotator spur and pinicn gears cleaned and grease applied to gears. M. Electrical Control Dax gasket i W =i and no moisture condensation en internals. N. Collector ring brushes i W =i. i O. Megger 50 hp. siren motors. For Magger g etim reference maintenance p ettm } GEE OOP-05. EPP 02-1.8 l Rev. 3 p Page 8 of 12 i k~ l
ItsM EP 02-16 RN.1 l ATDOMENT 2.0 1 (Page 2 of 2) l Painted surfaces regaLM repainting
) .4.
(Yes No ) If yes, enter Wedt Request Number i 1 for painting job . l 1
- 5. Siren orientation is more than 5 degrees !
from vertical (Yes No ) ! If yes, enter Work Request Number for reorientating siren . 1
- 6. Reenergize siren power at breaker.
l Performed By: Date: Reviewed By: Date: Rmerd copy of 7 1 *=9 fetus to the W Planning Mniniahia. NOTE: 'Ihe 50 hp sirens (JR 1 and JR-4) are --T4 W w thi sealed motor bearings, therefore, it is not r=w'aamary to lubricate these bearirgs.
'Ibese bearings should be replarwi idan conditicais irx11cate the bearings are defective.
O 1 EPP 02-1.8 Rev. 3 g Page 9 of 12 I. yg--7 --
UFM EP 02-20 ATI30tG2rr 3.0 ANS SIREN 'INCHEEK 'IE!rf REPGE
'N The Offsite sirens were testai cm , 19 -. 'Ihm results of these
/ tests are listed below: -
V TET MXE SIREN'S NABE CDemf!B G S BE5Et REMENG Sharps: Waverly: Ott e : New Strum: Main Due: Ottar Creek: Jac2e Creek: Sonic: 9th & Yuba:
\
Ieroy: i rests c.weleted by: NAME DNIE NAME _ DNIE Paviewed by: Data Albert Mcmtague Maintenance Ctasunications NUIE: Any siren failing test requires notification to the following:
- Coffey M ' Sheriff's napa 6
- Phtma 364-2123 Call taken by: Data Tima l
Coffey Ctunty Eu-uwcf Operaticms Cantar: 364-2721 Call taken by: Data Time _ L % c/ Planning Cbordinator: Call taken by: Data Time , I Reported by: Date Time EPP 02-1.8 Bev. 3
\ Page 10 of 12 l
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FG M EP 02-21 ATIACIDENT 4.0
.. ANS SIIEN FUIL CYCIE 'IE!rf RERRE
'Ihe offsite sirens were tested en , 19 _. 'Ihm results of this
(] test is described below: , sharpe: Ozenents: Gamerver: Waverly: ozoenr:ts: Cheerver: Ottumwa: Ozenents: Cheerver: New Stranst: Counnants: Observer: letin Den: Ozenants: Cheerver: otter Creek: cannants: Observer: Jacobs Creek: Czements: Cheerver: Scnic: Czenants: Obmarver: 9th & Yuba: N: Observer: Iaroy: %: Observer: 1%sts verified by: NAME DATE 1 NCTIE: Any siren failing test requires notification to the following: Coffey ctunty Sheriff's %6a.: l Ihone 364-2123 Call taken by: Date Time i Coffey County E-mu p cy Operaticns Center: Fhens 364-2721 Call taken by: Data Time Emergency Plannirq Cbordinator: Call taken by: Data Time Reported by: Date Time EPP 02-1.8 Rev. 3 Page 11 of 12 l
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- 1S FORM KMF-32 REY. 8/85 Date: / / Pg,
' Sheet: of (Q'
, NUCLEAR DEPARTHENT POLICY / PROCEDURE MANUAL 4
i REMOVE AND INSERT INSTRUCTION
/
REMOVE INSERT WCGS RADIOLOGICAL EMERGENCY RESPONSE PLAN IMPLEMENTING PROCEDURES NOTE: Please refer to the transmittal for pertinent h= ants to be removed and/or inserted into the manual.
- 1) Remove EPP TofC, Rev. 21 (3 pages) 1) Insert EPP TofC, Rev. 22 (3 pages)
- 2) Remove TCN No. EPP 01-1.1-2, Rev. 5 2) None (2 pages)
- 3) Ranove TCN No. EPP 01-1.1-1, Rev. 5 3) None (1 page)
[D 4) Renove EPP 01-1.1, Rev. 5 (32 pages) 4) Insert EPP 01-1.1, Rev. 6 (33 pages)
- 5) Renove EPP 01-2.1, Rev. 2 (32 pages) 5) Insert EPP 01-2.1, Rev. 3 (32 pages)
- 6) Remove EPP 01-3.1, Rev. 4 (17 pages) 6) Insert EPP 01-3.1, Rev. 5 (17 pages)
- 7) Renove EPP 01-3.2, Rev. 3 (8 pages) 7) Insert EPP 01-3.2, Rev. 4 (8 pages)
- 8) Renove TCN No. EPP 01-3.4-1, Rev. 2 8) None (1 page)
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- 11) Remove EPP 01-6.1, Rev. 3 (6 pages) 11) Insert EPP 01-6.1, Rev. 4 (6 pages)
- 12) Renove EPP 01-7.2, Rev. 5 (16 pages) 12) Insert EPP 01-7.2, Rev. 6 (22 pages)
- 13) Renove EPP 01-7.3, Rev. 5 (24 pages) 13) Insert EPP 01-7.3, Rev. 6 (26 pages)
- 14) Renove EPP 01-10.1, Rev. 2 (14 pages) 14) Insert EPP 01-10.1, Rev. 3 (17 pages)
- 15) Remove EPP 01-11.2, Rev. 2 (19 pages) 15) Insert EPP 01-11.2, Rev. 3 (20 pages)
- 16) Renove EPP 01-12.1, Rev. 3 (20 pages) Insert EPP 01-12.1, Rev. 4 (20 pages)
{} 16) R+
8 FORM KMF-32 REY. 8/85 Date: l l 7 - ESCO j
' 2 2 Sheet: of
~
, , 3 ,, NUCLEAR DEPARTMENT POLICY / PROCEDURE MANUAL
/ REMOVE AND INSERT INSTRUCTION
/
REMOVE INSERT
- 17) Remove TCN No. EPP 02-1.2-3, Rev. 4 17) None (1 page)
- 18) Remove TON No. EPP 02-1.2-2, Rev. 4 18) None (1 page)
- 19) Remove EPP 02-1.2, Rev. 4 (19 pages) 19) Insert EPP 02-1.2, Rev. 5 (12 pages)
- 20) Remove EPP 02-1.4, Rev.1 (4 pages) 20) Insert EPP 02-1.4, Rev. 2 (4 pages)
- 21) Renove TCN No. EPP 02-1.5-1, Rev. 5 21) None (1 page)
- 22) Remove EPP 02-1.5, Rev. 5 (34 pages) 22) Insert EPP 02-1.5, Rev. 6 (34 pages)
- 23) Renove EPP 02-1.6, Rev. 2 (13 pages) 23) Insert EPP 02-1.6, Rev. 3 (13 pages)
- 24) Remove EPP 02-1.7, Rev. 0 (3 pages) 24) Insert EPP 02-1.7, Rev. 1 (3 pages)
O l l l [ s i .
- EPP TofC
/q DC29 //-7 #4 kj REV.122 WCGS EMERGENCY PLAN IMPLEMENTING PROCEDURES TABLE OF CONTENTS NOVEMBER 7, 1986 PROCEDURE NO. TITLE REV.
EPP 01-1.1 WCGS Organization 6 EPP 01-1.2 Emergency Operation Facility Emergency 4 Organization EPP 01-1.3 Home Office Emergency Center Organization 1 EPP 01-1.4 Public Information Organization 3 EPP 01-2.1 Emergency Classification 3 l EPP 01-2.2 Activation of Emergency Plan / Organization 3
/N EPP 01-2.3 Accident Assessment and Mitigation 1 (N' J EPP 01-2.4 Core Damage Assessment Methodology 0 EPP 01-3.1 Immediate Notifications 5 EPP 01-3.2 Followup Notifications 4 EPP 01-3.3 Offsite Support Notification 2 l
- EPP 01-3.4 Onsite Emergency Response Organization 3 i Manual Call-Out
! EPP 01-3.5 EOF, HOEC and Public Information Emergency 4 Response Organization Manual Call-Out EPP 01-3.6 KG&E Emergency Response Organization 0 l Automatic Call-Out EPP 01-4.1 Technical Support Center Activation 4 EPP 01-4.2 Operations Support Center Activation / 4 Operation EPP 01-4.3 Emergency Operations Facility Activation 4 EPP 01-4.4 Home Office Emergency Center Activation 1 l l Pa'ge 1 of 3
)
EPP TofC O i 1
\s l . REV. 22 PROCEDURE NO. TITLE REV.
EPP 01-4.5 General Office Activation 3 EPP 01-4.6 Information Clearinghouse / Media Release 3 Center Activation EPP 01-4.7 Emergency Response Facility Information 0 System (ERFIS) EPP 01-5.1 Exclusion Area Evacuation 2 EPP 01-6.1 Personnel Accountability 4 EPP 01-7.1 Radiological Release Information System 3 (RRIS) EPP 01-7.2 Manual Determination of Release Rate 6 EPP 01-7.3 Manual Dose Projection Determination 6 [J EPP 01-8.1 Onsite Radiological Monitoring 4 EPP 01-8.2 Offsite Radiological Monitaring 3 EPP 01-8.3 Joint Radiological Monitoring Team 1 Formation and Operation , EPP 01-9.1 Exposure Control and Personnel Protection 3 EPP 01-9.2 Personnel Decontamination 3 , EPP 01-9.3 Radioprotective Drugs 3 EPP 01-9.4 Emergency Team Formation 4 EPP 01-9.5 Aid to Contaminated / Injured Personnel 3 EPP 01-10.1 Protective Action Recommendations 3 EPP 01-10.2 Preparation of News Releases 2 EPP 01-10.3 Release of Emergency-Related Information 2 Information to the Public EPP 01-11.1 Communications 2 O EPP 01-11.2 Status Boards 3 Logs and Record Keeping 1 EPP 01-11.3 Page 2 of 3
e EPP TofC REV. 22 PROCEDURE NO. TITLE REV. EPP 01-12.1 Reentry and Recovery Operations 4 EPP 02-1.1 Emergency Preparedness Program 4 Maintenance i EPP 02-1.2 Training Programs 5 l EPP 02-1.3 Drills and Exercises 3 EPP 02-1.4 Public Education 2 EPP 02-1.5 Maintenance of Emergency Facilities 6 and Equipment EPP 02-1.6 Communications Tests 3 EPP 02-1.7 Tone Alert Radio Maintenance and 1 Compensating Measures O EPP 02-1.8 Testing and Maintenance of Alert and Notification System Sirens 3 4 i l l Page 3 of 3
F k 4 O WOLF CREEK GENERATING STATION I RADIOLOGICAL EMERGENCY RESPONSE PLAN IMPLEMENTING PROCEDURE WCGS ORGANIZATION EPP 01-1.1 Revision 6 l O em EMERCENCY PI 'ING C RDINATOR REVIEW
/D R12%
DA'TE / / A, 46_ o - am EMERGENCY PLANNING ADMINISTRATOR REVIEW DATE l f lm E'$ PSRC APPROVAL RECOMMENDATION
-::-/
DATE
? l/-34L 4L a hak V.P.
a/Ju DATE / NUCLEARAPPROVAL[ l RELEASED DC29 [j-g-g(f. j DATE !O l i
_. _ ~
, 1.0 PURPOSE This procedure describes the WCGS Emergency Response Organization and delineates responsibilities as well
.as provides guidance for key emergency response per-sonnel in the performance of their designated positions.
2.0 APPLICABILITY This procedure is applicable to all onsite WCGS Emergency Response Organization personnel upon decla-ration of an Emergency Classification. Upon declar-ation of Recovery or Re-entry, personnel shall use EPP 01-12.1, " Recovery and Reentry Operations". 3.0 DEFINITIONS NONE 4.0 INSTRUCTIONS 4.1 INITIAL / SUBSEQUENT ACTIONS 4.1.1 Upon notification of an emergency situation, the WCGS Emergency Responsa Organization (Attachment 1.0) shall proceed to and establish operations at their desig-nated emergency response positions. s 4.1.2 Emergency positions are staffed by personnel specified in Attachment 2.0, "WCGS Emergency Organization Staffing Requirements". This attachment designates the primary and alternate normal WCGS positions l required to fill the various emergency response positions. 4.2 DUTY EMERGENCY DIRECTOR (SHIFT SUPERVISOR) NOTE: The following responsibilities for the Duty Emergency Director (DED) Shift Supervisor and later the DED may not be delegated -
- Energency Classification
- Notification of Offsite Authorities
- Protective Acticn Recommendations
- Authorization of Energencf Exposure in excess of 10CFR 20 limits I EPP 01-1.1
'i Rev. 6 Page 1 of 32
4.2.1 Upon recognition that an emergency condition exists, O' the Shift Supervisor shall assess plant parameters and indications to determine the appropriate emergency classification utilizing EPP 01-2.1, " Emergency Classification." 4.2.2 Upon declaration of an emergency classification, the Shift Supervisor shall assume the role of the DED. The Shift Supervisor retains the DED position until relieved by the Plant Manager or designated Call Superintendent or the emergency is terminated. 4.2.2.1 The DED (Shift Supervisor) shall assure that the ! County, State, NRC resident inspector, NRC Headquarters, and System Operations are notified per EPP 01-3.1, "Immediate Notifications." 4.2.2.2 The DED (Shift Supervisor) shall assure that Call-Out l of the WCGS Emergency Responsa Organization is made per EPP 01-3.4, "Onsite Emergency Organization Manual Call-Out." 4.2.2.3 The DED (Shift Supervisor) shall initiate appropriate ! technical measures to mitigate the event. 4.2.2.4 The DED (Shift Supervisor) shall activate onsite emer-gency teams if required. 4.2.2.5 The DED (Shift Supervisor) shall notify plant person- , N-- nel of the change in plant status. 4.2.2.6 The DED (Shift Superviscr) shall assure proper logs are kept. 4.2.2.7 The DED/SS will provide instructions to, and verify accountability of, all on-duty NLOs. All on-duty NLOs
- will report to the Control Room and remain under the direction of the Shift Supervisor unless otherwise directed by the DED.
4.2.2.8 The DED (Shift Supervisor), following transfer of ! responsibility and authority to the DED, functions as the Shift Supervisor and keeps the Operations Emer-i gency Coordinator (OEC) informed of plant status. 4.3 DUTY EMERGENCY DIRECTOR (DED) l 4.3.1 The DED may report to the Control Room to evaluate the declared emergency classification per EPP 01-2.1,
" Emergency Classification."
EPP 01-1.1 Rev. 6 Page 2 of 32 l
-- . - .- - _ - = __
s 4.3.2 At emergency classifications of Alert or more severe the DED reports to the Technical Support Center (TSC) . 4.3.3 The DED shall imp 2ement Attachment 3.0, " Duty Emer-gency Director's Checklist (TSC) ," Form EP 1.1-3. 4.3.4 The DED shall continue to evaluate plant conditions to determine the need for escalating or deescalating emergency classification. 4.3.5 The DED in coordination with the Radiation Emergency Coordinator (REC) shall determine the necessity for evacuation of personnel onsite. 4.3.6 The DED shall determine if radioactive releases have, are, or may occur and assure that radiological assess-ment is performed as necessary per EPP 01-7.0 series. 4.3.7 The DED shall evaluate the extent of protective action recommendations needed to be issued to County and State authorities per EPP 01-10.1, " Protective Action Recommendations." 4.3.8 The DED shall assure that Immediate Notifications and Followup Notifications are made to the County, State, l NRC Headqu'arters, System Operations, and the NRC . Resident Inspector per EPP 01-3.1, "Immediate Notifi-
's cations" and EPP 01-3.2, " Followup Notifications."
4.3.9 The DED in coordination with the REC shall evaluate the need for and authorize emergency workers to exceed 10CFR 20 radiation exposure limits with concurrence from the NRC, if practical. 4.3.10 The DED shall assume all responsibilities and author-ity of the Duty Emergency Manager (DEM) (EPP 01-1.2) until relieved of those responsibilities by the DEM. l 4.3.11 The DED shall direct the WCGS personnel in accident i mitigation per EPP 01-2.3, " Accident Assessment and Mitigation." l 4.3.12 The DED shall evaluate hazardous circumstances and initiate onsite protective actions as appropriate. 4.3.13 The DED shall assure that the Onsite Public l Information Coordinator (PIC) is periodically updated l per EPP 01-10.2, " Preparation of News Releases." 4.3.14 The DED shall notify Home Office Management as l appropriate. b EPP 01-1.1 Rev. 6 Page 3 of 32
.r 4.3.15 The DED shall assure that responsible members of the
[ emergency organization document all significant actions taken. 4.3.16 The DED shall keep the Shift Supervisor informed of all significant information and decisions made. 4.3.17 The DED shall inform station groups from which speci-fic expertise may be required, such as Health Physics, Chemistry, and Security, of emergency status and establish communications. 4.4 OPERATIONS EMERGENCY COORDINATOR (OEC) 4.4.1 At emergency classifications of Alert or more severe, the OEC shall report directly to the TSC and respond to requests from the DED. 4.4.2 The OEC shall implement Attachment 5.0, " Operations Emergency Coordinator's Checklist," Form EP 1.1-5. 4.4.3 The OEC shall maintain a current knowledge of plant status and evaluate proposed operational manipulations. 4.4.4 The OEC shall advise the DED concerning plant condi-tions and operational manipulations. 4.4.5 The OEC shall coordinate the activities of the Control i Room staff as appropriate. 4.4.6 The OEC shall interface with the Maintenance Emergency Coordinator (MEC) and the Technical Support Coordinator to provide maintenance and engineering support to the Control Room staff. [ 4.4.7 The OEC shall be responsible for approving the i Operational Status Sheet and assuring accurate updates of the Operational Status Board per EPP 01-11.2,
" Status Boards."
4.4.8 The OEC may direct the Operations Assessment Coordinator to report to the Control Room. I 4.4.9 The OEC shall call in WCGS personnel as necessary to l supplement the WCGS emergency teams under his control and assure that continuity of appropriate technical resources is maintained. 4.4.10 The OEC shall, through the Shift Supervisor, supervise the activities of the Site Fire Brigade. l O s_e EPP 01-1.1 Rev. 6 Page 4 of 32
4.4.11 Within 10 days af'ter going on containment sump recir-(} culation, evaluate the necessity of isolating the seal ( j injection filters. 4.5 OPERATIONS ASSESSMENT COORDINATOR (OAC) 4.5.1 At emergency classification of Alert or more severe, the Operations Assessment Coordinator (OAC) shall report directly to the TSC and respond to requests from the OEC. The OAC may be directed to report to the Control Room by the OEC. 4.5.2 The OAC shall complete the Operational Status Sheet and advise the OEC regarding plant conditions and operational manipulations. 4.5.3 The OAC shall establish communications between the Control Room and the TSC. 4.5.4 The OAC shall coordinate the activities of the Opera-tions Status Recorder and the Control Room Communica-tor to assure timely and accurate updates are made to the Operational Status Board per EPP 01-11.2, " Status Boards."
~
4.6 CONTROL ROOM COMMUNICATORS es 4.6.1 The Control Room Communicators shall be located in the Control Room. 4.6.2 The Control Room Communicators shall communicate with: . TSC Operations Status Recorder when required (Communicator reports to the person designated by the OEC) NRC, via Emergency Notification System (ENS) (Communicator reports to the DED/ Shift Supervisor) State of Kansas, Coffey County and other support agencies (Communicator reports to the DED/ Shift Supervisor) l 4.7 TECHNICAL SUPPORT COORDINATOR 4.7.1 At emergency classification of Alert or more severe, the Technical Support Coordinator shall report direct-ly to the TSC and respond to requests from the OEC. O EPP 01-1.1 Rev. 6 Page 5 of 32
4.7.2 The Technical Support Coordinator shall direct and coordinate the efforts of the TSC Engineering Team to technically assess plant status and the severity of the emergency conditions per EPP 01-2.3, " Accident Assessment and Mitigation." f 4.7.3 The Technical Support Coordinator shall advise the OEC on technical matters relating to fuel integrity, plant systems and equipment, plant electrical systems, electrical systems and equipment, and plant instrumentation. 4.7.4 The Technical Support Coordinator shall perform an independent assessment of critical plant parameters. 4.7.5 After EOF activation the Technical Support Coordinator shall direct all requests for assistance through the Technical Resources Manager (TRM) in the EOF. 4.8 TECHNICAL SUPPORT CENTER ENGINEERING TEAM (TSC ENGINEERING TEAM)
- 4.8.1 At the emergency classification of Alert or more severe, the TSC Engineering Team shall report directly to the TSC and respond to requests from the Technical Support Coordinator.
t 4.8.2 The TSC Engineering Team shall be composed of at least four (4) members with general knowledge in Mechanical Engineering, Electrical Engineering, Nuclear Engineering, I&C, and Operations. 4.8.3 The TSC Engineering Team shall evaluate current and historical plant parameters, assess the severity of the emergency conditions, and recommend corrective or preventative actions to the Technical Support Coordinator. 4.9 CHEMISTRY COORDINATOR 4.9.1 At emergency classification of Alert or more severe, the Chemistry Coordinator shall report directly to the ! TSC and respond to requests from the OEC. 4.9.2 The Chemistry Coordinator shall provide technical expertise on chemistry related matters to the DED. 4.9.3 The Chemistry Coordinator shall identify. laboratory facilities to be used for sample analysis. i 4.9.4 The Chemistry Coordinator shall assist in evaluating radiochemical analysis results and provide estimates of fuel damage. i ( EPP 01-1.1 Rev. 6 i Page 6 of 32 l
4.10 RADIOLOGICAL EMERGENCY COORDINATOR (REC) b ( 4.10.1 At emergency classification of Alert or more severe, l the REC shall report to the TSC and report directly to the DED. 4.10.2 The REC shall implement Attachment 6.0, " Radiological Emergency Coordinator's Checklist," Form Ep 1.1-6. 4.10.3 The REC shall assume all responsibilities and authority of the Radiological Assessment Manager (RAM) (per EPP 01-1.2) until the RAM arrives and relieves the REC of those responsibilities and authorities. 4.10.4 The REC shall, prior to and after activation of the EOF, supervise in-plant and onsite radiological survey teams, onsite dose projections, and onsite personnel protective action recommendations to the DED. 4.10.5 The REC shall coordinate the activities of the Radiological Assessment Coordinator (RAC) and the Dose Assessment Coordinator (DAC) per EPP 01-7.0 series. 4.10.6 The REC shall assure that personnel radiation exposures are maintained in accordance with 10CFR20.101 limits unless otherwise authorized by the DEM (or DED prior to EOF activation) per EPP 01-9.1,
" Exposure Control and Personnel Protection."
s_/ 4.10.7 The REC shall assist in the coordination of l operations, such as planning search and rescue operations; and transferring injured and non-essential personnel, if radiation or contamination hazards are involved per EPP 01-7.0 series. 4.10.8 The REC shall direct requests for additional support t to the ARM, including any requests for: l ,
- a. Additional radiological monitoring equipment.
i
- b. Engineering evaluations of temporary shielding on l special tools and equipment.
l l l EPP 01-1.1 Rev. 6 Page 7 of 32 f
~ . _ _ _ . _ _ . . _ _ . . .
m c. Additional health physics support personnel. l
- d. Adaitional instrumentation and equipment.
If the EOF has not been activated, the REC shall direct any requests for additional support to the Administrative Emergency Coordinator (AEC). 4.11 RADIOLOGICAL ASSESSMENT COORDINATOR (RAC) 4.11.1 At emergency classification of Alert or more severe, the RAC shall report directly to the TSC and respond to requests from the REC. 4.11.2 The RAC shall advise and assist the REC on matters involving radiological safety. 4.11.3 The RAC shall maintain appropriate records of all onsite radiological emergency response activities per EPP 01-11.3, " Logs and Record Keeping." 4.11.4 The RAC shall be responsible for completion of the Radiological Status Sheet and assuring timely and accurate status updates of the Radiological Status Board by the Radiological Status Recorder per EPP 01-11.2, " Status. Boards." 4.11.5 The RAC shall supervise the TSC Field Team Communicators in directing the activities of Onsite Monitoring Teams, and prior to activation of the EOF, directs the activities of Offsite Monitoring Teams. 4.12 DOSE ASSESSMENT COORDINATOR (DAC) 4.12.1 At emergency classification of Alert or more severe, i the DAC shall report directly to the TSC and respond ,, l to requests from the REC. l
- 4.12.2 The DAC shall coordinate the activities of the j Radiological Release Information System (RRIS)
Operators per EPP 01-7.1, " Radiological Release Information System (RRIS)." 4.12.3 The DAC shall provide the completed Radiological ' Status Sheet to the TSC Radiological Status Recorder. 1 4.13 TSC RADIOLOGICAL RELEASE INFORMATION SYSTEM (RRIS) OPERATORS l 4.13.1 At emergency classification of Alert or more severe, the TSC RRIS Operators shall report directly to the - TSC and respond to requests from the DAC. EPP 01-1.1 Rev. 6 Page 8 of 32 l
?;
4.13.'2 The TSC RRIS Operators shall calculate the projected
/ onsite and offsite doses per EPP 01-7.0l series.
4.13.3 The TSC RRIS Operators shall provide tha' completed dose projections to the DAC for subsequent evaluation. 4.13.4 If required, the TSC RRIS Operators shall obtain information regarding current and forecasted meteor-ological conditions. 4.13.5 ' Ihe T C RRIS Operators shall provide input as required
, for the timely completion of the Radiological Status
! Sheet. .
- \
4.12.s. The TSC RRIS Operators shall, prior to activation of the EOF, perform offdlte dose piojections.
^
4.14 ADMINISTRATIVE EMERGENCY COORDINATOR (AEC)
~
4.14.1 At emergenci classification of. Alert or more severe, 9 - the AEC shqll report directlysto the TSC and respond to requests from the DED. 4.14.2' The AEC shall implement Attachment 7.0, .
" Administrative Emergency Coordinator Checklist."
4.14.3 The AEC shall assume all responsibilities and s authority of the Administrative Rasources Manager (ARM) (per EPP 01-1.2, " Emergency Operaticns Facility Emergenqy Organization",) until relieQad of those responsibilities by the ARM. -
~ ~4.14.4 The AEC shall direct and cocrdi ate the activities of ~
! the TSC communicators and the Security-Emergency' i l Coordinator (SEC). / ! 4.14.5 The AEC shall provide administrative advice to the DED and other members of the TSC 9taff as required. 4.14.6 The AEC shall keep Security informed of plant / radio-logical conditions. [ 4.14.7 The AEC shall arrange / coordinate shift assignments for l , sw relief personnel to ensure a6 equate staffing for the I onsite emergency respcnse organization. p
~
4.14.8 The AEC shall assure that. adequate logistical support is provided both to the onsite and offsite emergency response and recovery efforts. Such logistical
-. support mayfinclude, but is not limited to, the L (.- following: c Il/ Page 9 of 32 A
.h N
,, a. Additional clerical and administrative support
[ j personnel;
\ /
'/ b. Warehouse support, procurement and expediting services;
- c. Essential services (e.g., food, clothing, and sleeping quarters) for onsite emergency response personnel; and
- d. Additional communications support and equipment repair services.
Following the activation of the EOF, the AEC shall direct any requests for logistical support beyond the capabilities of the WCGS plant staff to the ARM. 4.15 TSC COMMUNICATORS 4.15.1 At emergency classification of Alert or more severe, the TSC Communicators shall report to the TSC and perform communications duties as directed by the AEC. 4.15.2 The TSC Communicators shall log all incoming and outgoing communications with individuals, officials and agencies which are related to the emergency response per EPP 01-11.3, " Logs and Record Keeping."
- ( 4.15.3 The TSC Communicators shall assure that the s _/
s verification call back line is properly functional. 4.16 TSC CLERK /LOGKEEPER 4.16.1 At emergency classification of Alert or more severe, the TSC Clerk /Logkeeper shall report directly to the TSC and respond to requests from the DED. 4.16.2 The TSC Clerk /Logkeeper shall perform clerical and administrative duties (e.g., distributing or posting information, and copying documents) as directed by the DED. 4.16.3 The TSC Clerk /Logkeeper shall maintain a log of all pertinent emergency response activities occurring in the TSC per EPP 01-11.3, " Log and Record Keeping." l 4.17 TSC OPERATIONAL STATUS RECORDER 4.17.1 At emergency classification of Alert or more severe, l the TSC Operational Status Recorder shall report l directly to the TSC and respond to requests from the Operation Emergency Coordinator (OEC). i (- EPP 01-1.1 Rev. 6 Page 10 of 32 l i
1 4.17.2 The TSC operational Status Recorder shall complete Operational Status Sheets using ERFIS and update the TSC Operational Status Board periodically. He may require assistance from a member of the TSC Engineer-
) ing Team.
4.17.3 The TSC Operational Status Recorder shall provide one
~
copy of the Operational Status Sheet to the Public Information Coordinator (prior to EOF activation) and i two copies tc the OEC. 4.17.4 The TSC Operational Status Recorder, if ERFIS is non-operational shall update the Operational Status Sheet and Operational Status Board by participating in a three way phone conversation with the Control Room Communicator and EOF Operational Status Recorder (if EOF is activated) . 4.18 TSC RADIOLOGICAL STATUS RECORDER 4.18.1 At emergency classification of Alert or more severe, the TSC Radiological Status Recorder shall report directly to the TSC and respond to requests from the RAC. 4.18.2 The TSC Radiological Status Recorder shall maintain the TSC Radiological Status Board by using the completed Radiological Status Sheets. 4.18.3 The TSC Radiological Status Recorder, upon posting the information provided on the Radiological Status Sheets, shall provide the Radiological Status Sheet to the REC. t 4.19 TSC FIELD TEAM COMMUNICATOR 4.19.1 At emergency classification of Alert or more severe, the TSC Field Team Communicator shall report directly to the TSC and respond to requests from the RAC. 4.19.2 The TSC Field Team Communicator shall establish and maintain communications with the Onsite Survey Team Director and the Onsite Survey Team (s) per EPP 01-11.1, " Communications." 4.19.3 The TSC Field Te,am Communicator shall record any survey and sample data reported by the Onsite Survey Team (s) and provide the completed data sheets to the RAC. O EPP 01-1.1 Rev. 6 Page 11 of 32
4.19.4 Prior to the activation of the EOF, the TSC Field Team [ h Communicator shall establish and maintain communi-( ,) cations with the Offsite Monitoring Teams. The TSC Field Team Communicator shall record data obtained from the Offsite Monitoring Teams until such time that the Radiological Assessment Supervisor and the EOF Field Team Communicator have established operations at the EOF and assumed control of offsite monitoring operations per EPP 01-8.2, "Offsite Radiological Monitoring." 4.19.5 The TSC Radiological Status Recorder, using data provided by the RAC shall plot the current locations ! of the Onsite Survey Team (s) and the Offsite Monitoring Teams, and post the results of any dose rate surveys or air samples taken at those locations. 4.20. SECURITY EMERGENCY COORDINATOR (SEC) 4.20.1 At emergency classification of Alert or more severe, the Security Emergency Coordinator (SEC) shall report to the TSC and respond to requests from the AEC. The Security Shift Lieutenant shall assume duties of the SEC until relieved. 4.20.2 The'SEC shall direct the WCGS Security Force in responding to the emergency.
*bj g 4.20.3 The SEC shall perform accountability checks per EPP
's 01-6.1, " Personnel Accountability."
l 4.20.4 The SEC shall direct accountability and search activities by the Security Force for all areas within the Exclusion Area Boundary (EAB) excluding the Radiation Controlled Areas (RCA). 4.21 EMERGENCY OPERATIONS FACILITY COORDINATOR (EOFC) 4.21.1 At emergency classification of Alert or more severe, the EOFC shall report to the TSC and respond to requests from the DED. 4.21.2 The EOFC shall be dispatched to setup the Emergency Operation Facility (EOF) with the decision to activate that facility per EPP 01-4.3, " Emergency Operation Facility Activation." i EPP 01-1.1 Rev. 6 Page 12 of 32 i'
4.21.3 The EOFC shall arrive at the EOF and have the EOF O functionally operational within 60 minutes post clas-sification of a Site Area Emergency or General Emergency. 4.22 MAINTENANCE EMERGENCY COORDINATOR (MEC) l 4.22.1 At emergency classification of Alert or more severe, the MEC shall report directly to the TSC and respond to requests from the DED. 4.22.2 The MEC shall implement Attachment 4.0, " Maintenance Emergency Coordinator Checklist," Form EP 1.1-4. 4.22.3 The MEC shall direct the Operations Support Center (OSC) Supervisor in the coordination of emergency team activities of the OSC. 4.22.4 The MEC shall advise the OSC Supervisor of changes in plant conditions which may affect emergency team activities. i 4.22.5 The MEC shall determine the scope of needed search and rescue operations for unaccounted personnel in the Radiation Controlled Area (RCA). He shall direct the formation of search and rescue teams in accordance with EPP 01-9.4, " Emergency Team Formation." 4.23 OPERATIONS SUPPORT CENTER SUPERVISOR (OSC Supervisor)
! 4.23.1 At emergency classification of Alert or more severe, ! the OSC Supervisor shall report directly to the OSC and respond to requests from the MEC.
4.23.2 The OSC Supervisor shall implement Attachment 8.0,
" Operations Support Center (OSC) Supervisor Checklist," Form EP 1.1-8.
i' 4.23.3 The OSC Superviser shall initiate and verify the ac-tivation of the OSC per EPP 01-4.2, " Operations Support Center Activation / Operation." 4.23.4 The OSC Super. visor shall interface with the MEC to , coordinate emergency repair and damage control activ-ities. 4.23.5 The OSC Supervisor shall interface with the Onsite Survey Team Director (OSTD) to coordinate the deploy-ment of the Onsite Survey Team (s) and deployment of offsite Monitoring Teams per EPP 01-8.1 and EPP 01-8.2, respectively. EPP 01-1.1 Rev. 6 Page 13 of 32 l
)
I l 4.23.6 The OSC Supervisor shall interface with the Chemistry l
/ Director to coordinate the deployment of Chemistry '
personnel to perform sampling activities. 4.23.7 The OSC Supervisor shall supervies and coordinate the i activities of those personnel assigned to the OSC. ' 4.23.8 The OSC Supervisor shall assign personnel to assure the proper staffing of the emergency repair and damage control teams per EPP 01-9.4, " Emergency Team Formation."
- 4.24 ONSITE SURVEY TEAM DIRECTOR (OSTD) 4.24.1 At emergency classification of Alert or more severe, the OSTD shall report directly to the OSC and respond to requests from the OSC Supervisor.
4.24.2 The OSTD shall assist the OSC Supervisor in accordance with EPP 01-4.2 4.24.3 The OSTD shall direct the deployment of and interface directly with emergency teams. 4.24.4 The OSTD shall confirm plant entry / reentry points and provide technical expertise for radiation protection related matters in preparing the teams for deployment. 4.24.5 The OSTD shall coordinate dosimetry activities. 4.24.6 The OSTD shall interface with the RAC to assess the radiological considerations applied to planning emer-gency repair and damage control activities. 4.24.7 The OSTD shall determine initial and periodic habita-bility of the OSC. l 4.24.8 The OSTD shall, prior to EOF activation, assist the OSC Supervisor in the deployment of offsite monitoring teams. 4.25 CHEMISTRY DIRECTOR l 4.25.1 At emergency classification of Alert or more severe, the Chemistry Director shall report to the Operations l Support Center and assist the OSC Supervisor in organ-izing and dispatching personnel to perform sampling. I i EPP 01-1.1
\
Rev. 6 Page 14 of 32
. . _~ _ _ _ _ _ -
4.25.2 The Chemistry Director shall assure that emergency g sampling procedures are properly implemented. 4.25.3 The Chemistry Director shall provide post-accident i sampling analysis results and technical expertise for chemistry matters to the Chemistry Coordinator. 4.26 DOSIMETRY COORDINATOR 4.26.1 At Emergency Classification of Alert or more severe, the Dosimetry Coordinator shall report directly to the Operational Support Center and respond to direction from the OSTD. 4.26.2 The Dosimetry Coordinator shall coordinate the issue of emergency dosimetry in the OSC and perform emer-gency processing of TLD's. 4.26.3 The Dosimetry Coordinator shall respond to requests for personal exposure histories and maintain exposure records. 4.27 OSC COMMUNICATORS 4.27.1 At emergency classification of Alert or more severe, the OSC Supervisor shall appoint individuals in the - OSC to act as OSC Communicators. 4.27.2 The OSC Communicators shall perform communications
\m duties as directed by the OSC Supervisor.
4.27.3 The OSC Communicators shall log all incoming and out-going communications. 4.28 OSC' CLERKS 4.28.1 At emergency classification of Alert or more severe, the OSC Supervisor shall appoint individuals in the OSC to act as OSC Clerks. 4.28.2 The OSC Clerks shall maintain the OSC Staffing Board; OSC H.P. Activation Task Status Board; OSC Schedule of . Events Board and the OSC Accountability Board per EPP { 01-11.2, " Status Boards." i i 4.28.3 The OSC Clerks shall perform clerical and adminis-trative duties (e.g., distributing or posting informa- ! tion, and copying documents) as directed by the OSC , Supervisor. EPP 01-1.1 l Rev. 6 Page 15 of 32 i 1
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, , . _ _ , . - . . _ _ - - . - - - - - - - , - - - - - . - - _ _ -----+
l 4.29 EMERGENCY TEAMS , i J s ,) 4.29.1 At emergency classification of Alert or more severe, l personnel assigned to the Emergency Team Group shall i report directly to the OSC and respond to requests l from the OSTD. i j 4.29.2 Emergency Teams shall be composed of personnel from, I&C, Electrical, Mechanical, Operations, and Health Physics. 4.29.3 The Emergency Teams, under the direction of the OSC Supervisor, shall effect any repairs or modifications. 4.29.4 The Emergency Teams shall also perform search and rescue operations and provide first aid treatment, as l necessary. 4.30 OSC HEALTH PHYSICS TECHNICIANS 4.30.1 At emergency classification of Alert or more severe, the OSC Health Physics Technicians shall report
- directly to the OSC and respond to requests from the OSTD.
4.30.2 The OSC Health Physics Techn'icians shall sign-in on the "OSC Staffing Status Board" and then begin implementing the tasks assigned to them via the "H.P. (\ Activation Task Status Board." 4.30.3 The OSC Health Physics Technicians shall then await further instructions from the OSTD. 4.31 OSC CHEMISTRY TECHNICIANS 4.31.1 At emergency classification of Alert or more severe,
! the OSC Chemistry Technicians shall report directly to the OSC and respond to requests from the Chemistry Director.
4.31.2 The OSC Chemistry Technicians shall sign-in on the "OSC Staffing Status Board". 4.31.3 The OSC Chemistry Technicians shall perform emergency chemical sampling and provide post accident sampling analysis. l EPP 01-1.1 Rev. 6 l Page 16 of 32 i l l I
4.32 ON-SHIFT HEALTH PHYSICS TECHNICIAN f\s_,) s\ 4.32.1 The on-shift Health Physics Technician should report to the Control Room and take direction from the DED/ Shift Supervisor. Other on-duty Health Physics Technicians shall. report to access control. As needed, the DED/SS may require the on-shift Health Physics Technician to report to access control. 4.33 ON-SHIFT CHEMISTRY TECHNICIAN 4.33.1 The on-shift Chemistry Technician should report to the Control Room and take direction from the DED/SS. Other on-duty Chemistry Technicians should report to access control. 4.34 ONSITE PUBLIC INFORMATION COORDINATOR 4.34.1 The Onsite PIC shall report to the TSC upon declara-tion of an Alert. Upon activation of the EOF, the Onsite PIC shall report to the EOF and assist the Offsite PIC. 4.34.2 The Onsite PIC shall perform duties in accordance with EPP 01-1.4, "Public Information Organization." 4.34.3 The PIC shall gather and transmit technical informa- [ tion by interfacing with the General Office during an emergency situation at WCGS, as per EPP 01-1.4, (~'T )
"Public Information Oragnization."
4.34.4 Assure proper interaction with the WC Public Informa-tion Officer (PIO).
5.0 REFERENCES
5.1 Wolf Creek Generating Station Radiological Emergency Response Plan
- 5. 2 EPP 01-1.2 " Emergency Operation Facility Emergency Organization" 5.3 EPP 01-2.1 " Emergency Classification" 5.4 EPP 01-2.3 " Accident Assessment and Mitigation" 5.5 EPP 01-3.1 "Immediate Notifications" 5.6 EPP 01-3.2 " Followup Notifications" 5.7 EPP 01-3.4 "Onsite Emergency Response Organization Manual Call-Out"
(g EPP 01-1.1 Rev. 6 s/ Page 17 of 32 i _ , _ _ _ . - . _ . _ _ . . - - - , _ . , _ _ - - _ ~
5.8 EPP 01-4.1 " Technical Support Center Activation" 5.9 EPP 01-4.2 " Operations Support Center Activation / (Ns/ Operation" 5.10 EPP 01-4.3 " Emergency Operation Facility Activation" 5.11 EPP 01-4.4 "Home Office Emergency Center Activation" 5.12 EPP 01-4.5 " General Office Activation" 5.13 EPP 01-4.6 "Information Clearinghouse / Media Release Center Activation" 5.14 EPP 01-4.7 " Emergency Response Facility Information System (ERFIS)" 5.15 EPP 01-6.1 " Personnel Accountability" 5.16 EPP 01-7.1 " Radiological Release Information System (RRIS)" 5.17 EPP 01-7.2 " Manual Determination of Release Rate" 5.18 EPP 01-7.3 " Manual Dose Projection Determination" 5.19 EPP 01-8.1 "Onsite Radiological Monitoring" 5.20 EPP 01-8.2 "Offsite Radiological Monitoring" 5.21 EPP 01-9.1 " Exposure Control and Personnel Protection" 5.22 EPP 01-9.3 "Radioprotective Drugs" 5.23 EPP 01-9.4 " Emergency Team Formation"
! 5.24 EPP 01-9.5 " Aid to Contaminated / Injured Personnel" 5.25 EPP 01-10.1 " Protective Action Recommendations" i
5.26 EPP 01-10.2 " Preparation of News Releases" 5.27 EPP 01-11.1 " Communications" , 5.28 EPP 01-11.2 " Status Boards" l 5.29 EPP 01-11.3 " Logs and Record Keeping" 5.30 EPP 01-12.1 " Reentry and Recovery Operations" i I EPP 01-1.1 Rev. 6 Page 18 of 32 i ___m--__-- -_+--t-----_ _ _ _ _
6.0 RECORDS O 6.1 Form EP 1.1-3, " Duty Emergency Director's Checklist (TSC)" 6.2 Form EP 1.1-4, " Maintenance Emergency Coordinator Checklist" 6.3 Form EP 1.1-5, " Operations Emergency Coordinator's 4 Checklist" 6.4 Form EP 1.1-6, " Radiological Emergency Coordinator's Checklist" 6.5 Form EP 1.1-7, " Administrative Emergency Coordinator Checklist" 6.6 Form EP 1.1-8, " Operations Support Center (OSC) j Supervisor Checklist" 6.7 The records generated by this procedure during an actual emergency shall be forwarded to the Emergency Planning Coordinator (EPC) at the termination of the emergency. The EPC forwards the records to Records Management for storage. These records will be retained for the life of the plant. These records shall be considered QA records. , 6.8 The records generated by this procedure during drills i and exercises shall be forwarded to the EPC upon , termination of the drill or exercise. The EPC shall maintain these records for at least one yacr. These records shall be considered non-QA records. 7.0 ATTACHMENTS 7.1 Attachment 1.0, "WCGS Emergency Response Organization 7.2 Attachment 2.0, "WCGS Emergency Responsa Organization Staffing Requirements" 7.3 Attachment 3.0, " Duty Emergency Director's Checklist (TS C) " 7.4 Attachment 4.0, " Maintenance Emergency Coordinator Checklist" < 7.5 Attachment 5.0, " Operations Emergency Coordinator's Checklist" EPP 01-1.1
- Rev. 6 Page 19 of 32
7.6 Attachment 6.0, " Radiological Emergency Coordinator's Checklist" i 7.7 Attachment 7.0, " Administrative Emergency Coordinator Checklist" 7.8 Attachment 8.0, " Operations Support Center (OSC) i Supervisor Checklist" I I i a i i I i l i r l J i l l 1 i
- l l
l l 1 EPP 01-1.1 Rev. 6 Page 20 of 32 i l l
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p
) - -
ATTACHMENT 1.0 (Page I of 2)
! WCCS EMERGENCY RESPONSE ORGANIZATION 1 ! TECHNICAL SUPPORT CENTER (TSC) j Duty Emergency Director (DED)
TSC Clerk / i NRC (5) Logkeeper I I I I Onsite Radiological Administrative Operations Maintenance 4 Public Emergency Emergency Emergency Emergency Information Coordinator Coordinator Coo rdina t o r Coordinator Coordinator (REC) (AEC) (DEC) (MEC) I l Security Operations
; TSC __
Emergency Support i Communicators Coordinator Center
- (2) l 1
- l EOF Coordinator I
i i Radiological Dose Operations Technical Chemistry Assessment Assessment Assessment Support Coordinator Coordinator Coordinator Coordinator Coordinator i
- TSC Field Radiological I RRIS i Operational i Engineering
, Team ~- Status Operators Status ~~ Control Room Team l Communicator Recorder (2) Recorder Communicators (4) i j EPP 01-1.1 i Rev. 6 Page 21 of 32 I i
_ .-.- - . - . . . . ~ , - - - . . - . _ - . - - . _ . . . . . - . _ _ - - - . . . _ . - . _ . _ . . - . - . . . . . ~ . . .- . . _ . ~ . 1 4 l ATTACilMENT l.0 (Page 2 of 2) WCCS EMERCENCY RESPONSE ORGANIZATION OPERATIONS SUPPORT CENTER (OSC) Operations j Support i Center Supervisor ) OSC OSC Communicators Clerks . I (2) (2) , i i ! 1 Onsite l l Chemistry Survey Emergency Director Team Team Director Croup 1 OSC . Chemistry 4 Technicians f f I OSC Dosimetry llealth l Physics Coordinator Technicians i i i i I 8 EPP 01-1.1
- Rev. 6 Page 22 of 32 i
1 1 l 4 l
ATTACHMENT 2.0 (Page 1 of 2) a WCGS EMERGENCY RESPONSE ORGANIZATION STAFFING REQUIREMENTS Normal Operating Position /Titie ( Primary
% Facility Emergency Response Position i Alternate Control Room Duty Emergency Director Shift Supervisor -
(Acting) NRC Consunicator Nuclear Station Nuclear Station Operator Operator Offsite Communicator Shift Clerk Shift Clerk Ops. Status Communicator Nuclear Station Nuclear Operator Station Operator Operations Emergency Supervising Operator -- Coordinator (Acting) 1
' TSC Duty Energency Director Plant Manager Call Superintendent Designated Shift Operations Energency Superintendent of Supervisor / Operations Coordinator Operations Coordinator Maintenance Energency Superintendent of Superintendent of Plant Coordinator Maintenance Support Superintendent of Administrative Energency Regulatory Quality & WCGS Emergency Plan Coordinator Admin. Services Administrator Radiological Energency Site Health Physicist Health Physics Supervisor Coordinator _
Chemistry Coordinator Site Chemist Chemistry Supervisor Operation Assessment Off duty SRO Off duty SRO j Coordinator ! J ' Results Engit.=ering Technical Support Reactor Engineering Coordinator Supervisor Supervisor i Radiological Assessment Health Physics or Health Physic.s or Coordinator Chemistry Supervisor Chemistry Supervisor i i Dose Assessment Coordinator Health Physics or Health Physics or Chemistry Supervisor Chemistry Supervist.r Security Energency Chief of Security Security Operaciuns Coordinator Supe rvisor J Radiological Release Radiation Protection or Radiation Prctection/ Information Systems Operators Chemistry Personnel Chemistry Personnel EPP 01-1.1 Rev. 6 , Page 23 of 32 i L f i i
,, . - _ - _ . _ . . . . , , , . _ - . . _ _ - - - - - _ _ _ - - _ _ _ _ _ _ _ . .. - - - - - - .. -.,_.,,, n ,v,_ _
t 4 ATTAC3 MENT 2.0
* (Page 2 of 2)
WCGS EMERGENCY RESPONSE ORGANIZATION STAFFING REQUIREMENTS Normal Operating Position / Title I
- g Facility Emergency Response Position Primary Alternate l TSC TSC Clerk /Logkeeper Administrative Clerk Administrative Clerk (continued) .
Operational Status Recorder Off duty SRO Off duty SRO/R0 4 1 ! Radiological Status Recorder Health Physics or Health Physics or Chemistry Personnel Chemistry Personnel Engineering Team Results Engineers or Results Engineers or Reactor Engineers Reactor Engineers TSC Consunicators Staff Engineer or Staff Engineer or Training Training Supervisor Clerk TSC Field Team Communicator Health Physics or Health Physics or Chemistry Technician Chemistry Technician 4 EOF Coordinator Health Physics or Simulator Superintendent Chemistry Technician Onsite PIC Licensing Personnel Licensing Personnel OSC OsC Supervisor Maintenance Support Maintenance Service Supervisor ' Supervisor i Onsite Survey Team Director Health Physics Health Physics Supervisor Supervisor Chemistry Supervisor, Chemistry Supervisor, or U Chemistry Director On shift Chemist or On shift Chemist 16C, Electrical Maint., 16C. Electrical Maint., Energency Team Group Mechanical Maint., Mechanical Maint., HP Techs HP Techs I , OSC Clerks Admin Clerk Admin Clerk Dosimetry Coordinator Health Physics Health Physics Personnel Personnel Nuclear Station Nuclear Station OSC Communicators (2) Operator / Health Ope rator/ Health Physics TectSician Physics Technician OSC Health Physics Health Physics Health Physics Technicians Technicians Technicians I I OSC Chemistry Technicians' Chemistry Technicians Chemistry Technicians { J EPP 01-1.1 Rev. 6 Page 24 of 32 i 1 , h. W
, ,,n. ..%-=,,--,..---rr- _w.
. FORM EP 1.1-3 REV. 1 ATDGMENT 3.0
~
DUIY EMERGENCY DIRECIUR'S CHECKLIST (TSC) (Page 1 of 2) AIERT TIME /INIT RENARKS
- 1. Assume duties ard responsibilities /
of the Duty Emuu.pcf Director
- 2. Declaration of Alert /
- 3. Conduct T h iate Notifications to /
County, State, NRC, System Operations per EPP 01-3.1, "T
- 4 ate Notifications"
- 4. Assure Call-out of Emmu.pcy Response /
Organization per EPP 01-3.4, "Onsite Emergency Response Organization Mamal call-Out"
- 5. Assure the TSC and OSC are activated /
per EPP 01-4.1 and EPP 01-4.2
- 6. Continue to a==a== plant ocnditions /
d mh k 7. Assure personnel accountability per / EPP 01-6.1, " Personnel Accour*mhility"
- 8. Initiate onsite protective actions as /
necessary
- 9. Initiate radiological aaaaaminavn /
activities per EPP 01-7.0 Feries
- 10. Provide Followup Notifications per /
EPP 01-3.2, " Followup Notifications" l 11. Escalate Emmu.gscf Classification / per EPP 01-2.1, " Emergency Classification" or
- 12. Close-out Emergency /
/
, Duty Emergency Director Date Time EPP 01-1.1 Rev. 6 Page 25 of 32
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,,m ,w- ,,- r-a >-r,w--, - . - - - - - - - , , . , - , - - eg - - - - - .- - -- ------,-,v.mm n- , - , - - - - - -
. FORM EP 1.1-3 REV.1 ATDCEMENT 3.0 (Continued)
II7IY ENREGENCY DIRECICR'S CHECKLIST (TSC) i (Page 2 of 2) SITE AREA ENERGENCY/ GENERAL ENERGENCY I TIMEVINIT RENARIG
- 1. Assume duties and responsibilities /
of the Duty Empcf Director
- 2. Declaration of Site Area E - ga cy /
or General Emergency
- 3. Perform T h iate Notifications to /
State, County, NRC, System Operations per EPP 01-3.1, "T h iate Notifications"
- 4. Assure that Call-out of Eunu p cf Response /
Organization is perfemnsd per EPP 01-3.4, "Onsite Eunupcy Paspm1se Organization Manual Call-Out"
- 5. Assure that 'ISC, OSC, IDF, ICEC and /
ledia Centers are activated per EPP
- 01-4.0 series I 6. Continue to assess plant ocniition and /
status
- 7. Assure evacuation of non-essential /
personnel and accountability per EPP 01-6.1, " Personnel Accountability"
- 8. Assure that protective action /
ra - ai-ilations are made per EPP 01-10.1, " Protective Action pas... ;-u tions"
- 9. Initiate radiological maama=nant /
per EPP 01-7.0 series
- 10. Provide periodic Followup Notifications /
to State and County per EPP 01-3.2,
" Followup Notifications"
- 11. Turn responsibilities and duties of /
the DEM over to designated individual
/
Duty Emergency Director Date Time EPP 01-1.1 Rev. 6 Page 26 of 32 l l ? __._.,_.,_,_.._-__,_..-___.___.,..__.-_.---__x.- . ,. . . - . _ . _ - _ - _ _ , , _ _ _ _, _ . - .
. FORM EP 1.1-4 REV. O ATIAODENT 4.0 O ManmsmCE neamscr axmDnan am:xr2sr (Page 1 of 1) TnF/INrr REMMUG
- l. Assume the duties and responsibilities of /
the Maintenance 7. .v. wy coordinator (MEC)
- 2. Conduct an initial assessment of plant /
conditions in relaticmship to the Emuy=cy Classificatico
- 3. Establish communications with the /
OSC Supervisor
- 4. Provide the OSC Supervisor with /
an initial emergency classification and plant status briefing
- 5. Obtain the status of all g . s y= cy /
maintenance activities
- 6. Perform an initial manaammarit of the /
need for mouv cf teams. Assure adequate staffire for emergency teams per EPP 01-9.4.
" Emergency Team Formation"
- 7. Provide the DED with the scope and current / _
status of all maintenance activities associated with emergency re p
- 8. Authorize the OSC Supervisor to dispatch /
emergency teams
/
Maintenance Emergency Coordinator Date Time EPP 01-1.1 Rev. 6 Page 27 of 32
ICIE EP 1.1-5 REV.1 ATDOBENT 5.0 OPERATICNS EMERGENCY CDORDDUGUR'S CHECKLIST (Page 1 of 1) TIME /INIT MNAIES
- 1. Assume the duties and responsibilities /
of the Operations Eunupcy Coortiinator
- 2. Verify operability of the Emergency /
Response Facility Informaticri System (ERFIS) J per EPP Cl-4.7, "ERFIS"
- 3. Verify operability of the Safety /
Assessment S3P.am (SPDS)
- 4. Verify r=mmicaticri capability with the /
Control Rocan
- 5. Assess the status of the fissicri /
product barriers /Einupcf Classification per EPP 01-2.1, "Eu-u p cf Classification"
- 6. Perform acx:ident aaamaamarrt and mitigation /
activities for initiating events
- 7. Activate the Operational Status Board /
b per EPP 01-11.2, " Status Boards"
- 8. Evaluate the need to dispatch the /
OAC to the Control Rocan for assistance
- 9. Assure adequate staffing for the /
operational a==a==marit function of the TSC l
/
Operations Emergency Coordinator Date Time EPP 01-1.1 Rev. 6 O Page 28 of 32 ;
FORM EP 1.1-6 REV. 1 ATD4HENT 6.0 RADIOIOGICAL EMERGENCY CDORDDUmR'S CHECKLIST (Page 1 of 2) ' TIME /INIT REMARKS
- 1. Assume the responsibilities ani functions /
of the Radiological Eu-u.p.;y Coordinator 1
- 2. Initiate habitability surveys for the /
Technical Support Center i
- 3. Initiate Onsite Survey Teams and Offsite /
Monitoring Teams and coordinate their dis-patch with the SEC per EPP 01-8.0 series
- 4. Provide HP pw.h..El as required for /
Contaminated / Injured W h ..el per EPP 01-9.5, " Aid to Centaminated/ Injured Personnel"
- 5. Assoss radiological ocnditions per /
i EPP 01-7.0 series
- l. 6. Verify cmmunication(s) links /
\ 7. Verify that an initial dose projection /
has been performed per EPP 01-7.0 series
- 8. Assure input fr m radiological point of /
view into an initial Protective Action Pa_ - =r3ation is performed per EPP 01-10.1,
" Protective Action Pswmnandations" i 9. Assure current and projected meterological /
data has been obtained
- 10. Verify RRIS is functional per EPP 01-7.1, /
- " Radiological Release Information System" l
l EPP 01-1.1 Rev. 6 Page 29 of 32
- j FORM EP 1.1-6 REV. 1 I
ATTACHMENT 6.0 RADIOLOGICAL D4ERGENCY COORDINATOR'S CHECKLIST (Page 2 of 2) TIMF/INIT RENARKS
- 11. Perform an initial assessment to /
j determine the need to issue radioprotective drugs to emergency teams per EPP 01-9.3, "Radioprotective Drugs"
- 12. Perform an initial manpower, equipnent /
e assessment an:1 assure adequate staffing
! 13. Assess the need for exposure increases /
>10CFR20.101 limits per EPP 01-9.1,
" Exposure Control arxl Personnel Protection" 4
l l / i Radiological Bnergency Coordinator Date Time 1 l i d e EPP 01-1.1 Rev. 6 Page 30 of 32 1 1 i
FORM EP 1.1-7 REV. O ATTACHMENT 7.0
, AININISIRATIVE ENERGENCY CDORDINATOR GECKLIST (Page 1 of 1)
, , TIME /INIT RENARKS
- 1. Assume the duties ani responsibilities of the Administrative Emm.p.1 Coordinator /
- 2. Provide administrative advice / support to Duty Emergency Director as required /
- 3. Initiate enemications at TSC /
- 4. Coordinate offsite ambulance support as & ==_q /
- 5. Assure that Tunadiate Notification is ocenunicated to State, County, NRC, t
System Operations per EPP 01-3.1, /
"T w iate Notifications" i
l 6. Provide logistical support o Clerical and administrative support - peu.-.. l / o Warehouse support, procurement and
- expediting respcmse i . . 1 /
o Additional camaznications support
- and equipnent repair services /
l o Personnel, support - h actcrs, etc. i t i
/ l
! Administrative Emergency Coordinator Date Time l EPP 01-1.1 I Rev. 6 f Page 31 of 32 r
'. __ _ - . _ _ _ _ - _ _ _ _ . . - - _ - - - - _ _ - - _ _ _ .- _ _ _ ____._-,_...___- _-.__,- _ -~ .__.-
FORM EP 1.1-8 REV.1 ATDGMDTI 8.0 OPERATIONS SUPPCEtr CDTTER (OSC) SUPERVISCR CHECKLIST (Page 1 of 1) TIME /INIT RDERES
- 1. Assume the duties and responsibilities of the OSC Supervisor /
- 2. Verify that initial habitability /
surveys have been ocupleted with the Onsite Survey Team Director NOTE: Announce that there will be no eating, drinking or smoking until habitability has been established.
- 3. Establish rmentications with the /
Maintenance E-pcy Cocedinator (MEC) at the Technical Support Center (TSC) and verify agn'M operability
- 4. Assign the OSC r==nticator to initiate /
accountability
- 5. Determine the nature and status of the /
declared emergency classificatica1 and k make an initial announcement
- 6. Corduct an initial ammaamman1t on the need / '
for Emm.fucy '14ams with the MEC and assure adequate staffing
- 7. Verify that key OSC positions are staffed /
and that adequate support staff is available
- 8. Assure that the OSC (Eunupcy Response /
and Recenery activities) logbook is maintained ! 9. Synchronize OSC clock with TSC / l 10. Verify designated OSC ocumunications lines / are established and functioning properly
- 11. Declare the OSC activated and notify the MEC / e
/
i Operations Support Center Supervisor Date Time l l EPP 01-1.1 Rev. 6
\, Page 32 of 32 v-
i ' O t. I WOLF CREEK GENERATING STATION RADIOLOGICAL EMERGENCY RESPONSE PLAN IMPLEMENTING PROCEDURE EMERGENCY CLASSIFICATION 4 EPP 01-2.1 Revision 3 l 4 O PAlfA4 l } )$ lW W[n EMfRGl'WCY'P NING CO RDINATOR' REVIEW DATE '/ ' /' ' , . '5 :^ $ e wM 18!A}/fd j EMBRGENCY PLANNING ADMINISTRATOR REVIEW DATE / V A'A ll- 3 k h PSRC XPPROVAL RECOMMEN'DATION DATE l V.P. NUCLEAR b0 PPROVAL AAbm IIl7f/L DATE/ / RELEASED DC29 I I' 7' N DATE
1.0 PURPOSE
\'
This procedure provides guidance to evaluate plant conditions during an actual or potential emergency situation, determine / assess the Emergency Action Level (EAL) exceeded and classify the emergency according to its severity. 2.0 APPLICABILITY This procedure applies to the Shift Supervisor, Duty Emergency Director (DED), and Duty Emergency Manager (DEM). This procedure shall be implemented immediately upon recognition of an emergency or off-normal condition. 3.0 DEFINITIONS 3.1 EMERGENCY CONDITIONS Situations occurring which cause or may threaten to cause radiological hazards affecting the health and safety of employees or the public, or which may result in damage to property. 3.2 EMERGENCY CLASSIFICATION f N A system used to define the severity of emergencies into one of four categories based upon Emergency Action Levels and Fission Product Barrier Integrity Conditions. Classifications listed in order of increasing severity are: Notification of Unusual Event, Alert, Site Area Emergency and General Emergency. 3.3 EMERGENCY ACTION LEVELS (EAL'S) Specific parameters or conditions that may be used as thresholds for declaring a particular emergency classificatien. 3.4 FUEL INTEGRITY BREACH The existence of a radioactive material concentration within the reactor coolant of five (5) times the allowable Specific Activity of Technical Specification 3.4.8 of 100/E uCi/gm. A Specific Activity of 600 uCi/gm indicates loss of fuel cladding as a fission product barrier. EPP 01-2.1 Rev. 3 31 Page 1 of l
3.5 REACTOR COOLANT SYSTEM INTEGRITY BREACH 3.5.1 The inability to maintain normal liquid inventory ; within the Reactor Coolant System (RCS) by operation of l_ the Chemical and Volume Control System. 3.5.2 A loss of RCS pressure concurrent with high steam line flow from a steam generator or increasing narrow range level (i.e., steam generator tube rupture). 3.6 CONTAINMENT INTEGRITY BREACH A loss of the containment's ability to retain radioactive materials within its pressure boundary as specified in 10 CFR 50, Appendix J. Containment includes: Containment Building, Main Steam Lines to the MSIV's, steam line safety valves and power operated relief valves; or other systems with RCS leakage paths outside containment. NOTE: A Containment Breach, by itself, is classified as a Notification of Unusual Event. However, a Containment Breach, when coupled with other
- fission product barrier breaches, shall dictate escalation to a more severe emergency
/'~'j classification.
b 3.7 CRITICAL SAFETY FUNCTION STATUS TREES (CSFST) i ! For purposes of emergency classification, the following conditions are conservatively defined: 3.7.1 Red Path Barriers will be considered breached when the CSFST associated with the barrier is proceeding along a red path. 3.7.2 Orange Path Barriers will be considered to be subject to a severe challenge and have the potential for being breached when the CSFST associated with the barriers is proceeding along an orange path. EPP 01-2.1 Rev. 3 Page 2 of 31
7 4.0 INSTRUCTIONS l 4.1 PRECAUTIONS -l 4.1.1 Plant-specific operator actions required to mitigate j the emergency condition are prescribed in the appropriate Emergency Procedures (EMG) or Off-Normal Procedures (OFN) and are independent of any actions required by this procedure. 4.1.2 The DED/DEM should consider the effect that combinations of events have upon the Emergency Classification. That is, events if taken individually I would constitute a lower Emergency Classification, but collectively may constitute a higher Emergency l Classification. i 4.1.3 Only the DED/DEM can escalate to a more severe Emergency Classification or de-escalate to a less severe Emergency Classification. 4.1.4 Plant conditions shall be continually assessed to ensure conditions are not degrading such that a loss of j any of the three (3) fission product barriers is postulated. Should any condition degrade further, event reclassification shall be considered. 4.1.5 Some Emergency Action Levels are not, by their very nature, intended to be used during startup, shutdown, j maintenance or testing situations where abnormal i temperatures, pressures, equipment status, etc. are ! expected. The Shift Supervisor shall declare an appropriate Emergency Classification when, in his judgement, the station status warrants such a
- declaration.
4.2 INITIAL ACTIONS l 4.2.1 Upon recognition that an abnormal or emergency i condition exists, the Shift Supervisor shall be immediately notified. Recognition of the event can occur as a result of any plant personnel observing an abnormal or amargency condition. 4.2.2 Control Room personnel shall continue to monitor the appropriate plant parameters, instrument readings and j any other symptoms which would indicate further system / plant degradation. EPP 01-2.1 Rev. 3 Page 3 of 31
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Simultaneously, the Shift Supervisor shall evaluate the 4 .% . 3
- - event using the EAL's (Attachments 1.0 thru 4.0) to determine the need for classifying the emergency condition into one of the four emergency l j c{ . classifications.
4.2.4 If no classification is warranted, no further-' action is E
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required Except to continue monitoring the event. 4.2.5 If the Shift Superviscr be.'. laves that the event does fit one of~the descriptions for an emergency . classification, he shall declare the appropriate-emergency classification within 15 minutes of the initiating event or, where warranted, verification of the initia?.ing event. NOTE: When deemed appropriate, the Shift Supervisor, DED or DEM may classify'an event based on O' opinion and professional jadgament. This may be done when parameters and indications are not y conclusive as to which emergency' classification l is to be declared. Y
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4.2.6 CSFST's ortcnge paths which nay go to red paths in less time than it would take To do-an evacuation of the e, affected arhan, as presented'in EPP 01-10.1,
" Protective Action Recommendations", shall bet S ' considered as red paths and the appropriate emergency classification declared in accordance with Step 4 2.5 4
above. NOTE: For the purposes of combining a loss of RCS pressure boundary by means of a steam generator tube rupture, with a loss of containment i integrity by means of a secondary system fault, s the two failures must be affecting the same steam generator to be considered as two (2) fission. product barrier breaches. l l 4.2.7 . Simultaneous with the declaration of an emergency i classification, the Shift Supervisor shall assume the isole of DED and implement EPP 01-2.2, "Activiation of E63rgancy Pitn/ Organization" and EPP 01-3.1, "Immediate Notification".
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4 k. I. 3 l EPP 01-2.1 Rev. 3 Page 4- of
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\ 4.3 SUBSEQUENT ACTIONS V 4.3.1 After the TSC or the EOF is activated, Attachments 1.0 through 4.0 should be used by the DED and/or the DEM to verify, escalate, or de-escalate the emergency classification.
4.3.2 The Operations Emergency Coordinator (OEC) , Technical Support Coordinator and Technical Resources Manager (TRM) should use Attachments 1.0 through 4.0 to assess changes in plant conditions affecting the emergency classification. 4.3.3 For further assistance in accident assessment / mitigation, refer to EPP 01-2.3, " Accident Assessment i and Mitigation". 4.3.4 When declared, recovery operations shall be conducted in accordance with EPP 01-12.1, " Reentry and Recovery l Operations".
5.0 REFERENCES
5.1 Wolf Creek Generating Station Radiological Emergency , Response Plan. O 5.2 5.3
" Technical Specifications for Wolf Creek Unit 1",
Docket No. 50-482, NUREG 1136 Code of Federal Regulations (10CFR) Part 50, Appendix J l 5.4 EPP 01-2.2, " Activation of Emergency Plan / Organization" 5.5 EPP 01-2.3, " Accident Assessment and Mitigation" 5.6 EPP 01-3.1, "Immediate Notification" 5.7 EPP 01-10.1, " Protective Action Recommendations" 5.8 EPP 01-12.1, " Reentry and Recovery Operations 6.0 RECORDS NONE [N EPP 01-2.1 l Rev. 3 Page 5 of 31
= l 7.0 ATTACHMENTS ,
i 7.1 Attachment 1.0, " Emergency Actions Levels For Notification of Unusual Event" 7.2 Attachment 2.0, " Emergency Action Levels For Alert" 7.3 Attachment 3.0, " Emergency Action Levels For Site Area Emergency" 7.4 Attachment 4.0, " Emergency Action Levels For General Emergency" i r i i I t i l l i EPP 01-2.1 Rev. 3 Page 6 of 31 l l
ATTACEMENT 1.0 (Page 1 of 15) ! EMERGENCY ACTION LEVELS FOR NOTIFICATION OF UNUSUAL EVENT Condition Indication (s) i RCS Leak Rate > RCS Leakage Evaluation or Allowed by Water Inventory Balance Technical indicating: Specifications
- 1. a. Total primary to secondary leakapc from all Steam Generators is > 1 gpm.
OR
- b. Total primary to secondary leakage from one Steam Generator is > 500 gallons per day.
OR
- 2. a. Unidentified leakage is > 1 gpm for more than 4 hours.
AND (T b. The Action Statement of Technical Specifications ( d 3.4.6.2 cannot be met. OR
- 3. a. Identified RCS leakage is > 10 gpm for more than 4 hours. ,
AND
- b. The Action Statement of Technical Specifications 3.4.6.2 cannot be met.
OR
- 4. a. Centrolled leakage at 2235 1 20 psig RCS pressure is > 8 gpm per RC pump for more than 4 hours.
AND
- b. The Action Statement of Technical Specifications 3.4.6.2 cannot be met.
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EPP 01-2.1 Rev. 3 Page 7 of 31
ATTACHMENT 1.0 g (Page 2 of 15) l EMERGENCY ACTION LEVELS FOR NOTIFICATION OF UNUSUAL EVENT Condition Indication (s) Abnormal Coolant 1. a. Any combination of Temperature and/or Thermal Power, Pressure, or Pressurizer Press, and Abnormal Fuel RCS. Average Temp. Temperature exceeding the limits of Tech. Spec. Figure 2.1-1. OR
- 2. a. RCS Press > 2735 psig per Tech. Spec. 2.1.2. ,
OR' '
- 3. a. Core Subcooling <
0 deg. F based on the subcooling meter (s) or derived value from the core exit thermo-couples OR <20 deg. F (bcsed on derived value from Th or Tc) RCS Degrees Subcooling flg Instrument (s) RP081A or RP081B.
\V>] OR
- b. Derived by taking difference between saturation temperature inferred from wide range RCS pressure from PT403 or PT405 and the highest of either Th, Tc or core exit thermocouples.
O k,j EPP 01-2.1 Rev. 3 ' Page 8 of 31 l l l
I ATTACHMENT 1.0 (Page 3 of 15) l EMERGENCY ACTION LEVELS FOR , NOTIFICATION OF UNUSUAL EVENT ' Condition Indication (s) High CJolant 1. a. Confirmed reator Coolant Activity Sample analysis indicates or Failed Fuel > 1.0 but < 15 uCi/ gram Monitor Alarms Dose Equivalent I-131. AND
- b. Plant Shutdown is required and cannot be achieved as required by applicable Technical Specification Action Statement.
OR
- 2. a. Confirmed reactor coolant analysis indicates Dose Equivalent I-131 activity exceeding the limits of Tech. Spec.
Figure 3.4.1. AND /N b. Confirmed analysis ( _, ) indicates an increase of > 0.1% but < 1.0% equivalent fuel failures within 30 minutes. OR
- 3. a. Confirmed reactor cool-ant analysis indicates >
100/E bar uci/ gram. AND
- b. Confirmed analysis indicates an increase of > 0.1% but < 1.0%
equivalent fuel failures within 30 minutes. OR
- 4. a. Chemical and Volume Control System Letdown Monitor Alert alarm.
AND
- b. Confirmed analysis indicates an increase of > 0.1% but < l.0%
equivalent fuel failures within 30 minutes. Os EPP 01-2.1 Rev. 3 Page 9 of 31
ATTACHMENT 1.0 . (Page 4 of 15) l EMERGENCY ACTION LEVELS FOR NOTIFICATION OF UNUSUAL EVENT Condition Indication (s) Unplanned 1. a. Centrifugal Charging Initiation of Pump A or B running. ECCS with Discharge AND to Core in mode 1 or 2 b. Centrifugal Charging Pumps to Boron Injec-tion Tank flow elements indicate flow in the lines. OR
- 2. a. Safety Injection Pump A or B running.
AND
- b. Safety Injection Pump Discharge flow elements indicate flow in the lines.
i OR l 3. a. RHR Pump A or B running. AND
, j b. RHR/ Accumulator injec-l 'd tion flow element (s) indicating flow in the lines.
Failure of Reactor 1. a. Manual or automatic Protection System reactor trip initiated. to Initiate and/or AND Complete a Trip 2. a. Intermediate range Which Brings the monitor indicating Reactor Subcritical positive startup rate. l EPP 01-2.1 Rev. 3 Page 10 of 31
ATTACHMENT 1.0 (Page 5 of 15) 7-~s l
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EMERGENCY ACTION LEVELS FOR NOTIFICATION OF UNUSUAL EVENT Condition Indication (s) Loss of Engineered 1. a. Any Engineered Safety Safety Feature or Feature is found to be Fire Protection Inoperable per the System Requiring Technical Specifications Plant Shutdown by Limiting Condition for Tech. Specs. Operations for the Engineered Safety Feature Actuation System Instrumentation. OR
- b. The Fire Suppression Water System is found to be Inoperable per the Technical Specifications, limiting condition for Operations for the Fire Suppression Water System.
AND (} 2. a. Plant shutdown is required and cannot be achieved as required by applicable action state-ment. _, EPP 01-2.1 Rev. 3 Page 11 of 31 .
ATTACHMENT 1.0 g (Page 6 of 15) . 1 EMERGENCY ACTION LEVELS FOR NOTIFICATION OF UNUSUAL EVENT Condition Indication (s) j complete Loss of Either of the following sets Any Function Needed of conditions exist: For Cold Shutdown l FIRST SET - NORMAL COOLDOWNl
- 1. a. Steam Generator levels
<28%.
AND
- b. Total available feedwater flow to Steam Generator <300,000 lb/hr.
OR
- 2. a. Steam Dump Valves to Condenser AB-UV-34, 35 or 36 are not responding to Steam Header Pressure Controller.
AND
- b. Steam Generator steam dump valvos to O atmosphere are not operating properly.
lSECOND SET - RHR COOLDOWNl
- 1. a. RHR Pumps A and B not running.
OR'
- 2. a. RHR/ Accumulator injec-tion flow <2500 gpm.
OR
- 3. a. Component Cooling Water to RHR Heat Exchanger A and B Hi/Ic Alarm and Computer Points EGF63 l and EGF64 indicates l <7350 gpm.
OR
- 4. a. Complete loss of Service and Essential Service Water EPP 01-2.1 Rev. 3 Page 12 of 31 l
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ATTACHMENT 1.O (Page 7 of 15) l O- EMERGENCY ACTION LEVELS FOR NOTIFICATION OF UNUSUAL EVENT Condition Indication (s) Complete Loss of Any 1. a. Centrifugal Charging Function Needed for Pump A and B and Hot Shutdown Positive Displacement Charging Pump not running and unable to start the charging pumps. OR
- b. Centrifugal Charging Pump A or B, or Positive Displacement Charging Pump running.
WITH
- a. Inadequate charging pump ,
flow. OR
- b. Inadequate charging pump flow to Boron Injection Tank (BIT).
O EPP 01-2.1 Rev. 3 Page 13 of 31 o
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ATTACHMENT 1.0 ( (Page 8 of 15) l EMERGENCY ACTION LEVELS FOR NOTIFICATION OF UNUSUAL EVENT Condition Indication (s) Loss of Contain- 1. a. All Penetrations are ment Integrity not capable of being Requiring Plant closed by an Operable Shutdown by Tech. Automatic Isolation , Specs. Valve System or by manual valves, blind flanges, or automatic valves in the shut position except as indicated in Technical Specifications, Limiting Condition for Operations for Containment isolation valves. OR
- b. Equipment Hatch is not closed and sealed.
OR ( c. Air Lo'ck(s) are not l operable per Technical specifications limiting
- Conditions for Operations, for Contain-ment air locks.
OR
- d. Containment leakage rates exceed the Technical Specifications, Limiting l Condition for Operations for Containment leakage.
l OR t
- e. A sealing mechanism (associated wi h each penetration) is not operable.
AND
- 2. a. The action statement of Tech Spec 3.6.1.1 cannot be met.
EPP 01-2.1 Rev. 3 l Page 14 of 31 i
I ATTACHMENT 1.0 !
N (Page 9 of 15) l I EMERGENCY ACTION LEVELS FOR NOTIFICATION OF UNUSUAL EVENT I
Condition Indication (s) l Rapid Depressur- 1. a. Low steam pressure ization of Second- < 615 psig with RCS ary Side pressure > 1970 psig. AND
- b. Coincidence of 2 of 3 steam pressure instru-ments reading < 615 psig in one or more steam generator (s).
OR
- 2. a. High negative steam pressure rate (-100 psig in < 50 seconds) and steam line isolation with steam line pressure SI blocked (A and B trains).
OR
- 3. a. Containment pressure i
([',)) 17.0 psig (High II) with no significant increase in containment radiation j levels. EPP 01-2.1 Rev. 3 Page 15 of 31
1 l l ATTACHMENT 1.0 (Page 10 of 15) l EMERGENCY ACTION LEVELS FOR NOTIFICATION OF UNUSUAL EVENT Condition Indication (s) Failure of Press- 1. a. 1. Pressurizer pressure urizer or Steam < 2315 psig and i Generator Safety decreasing in an l or Relief Valve uncontrolled manner. AND
- b. 1. Pressurizer safety valve (s) discharge temperature increasing.
OR
- 2. Pressurizer power operated relief dis-charge temperature increasing and the asscciated Block Valve cannot be closed.
OR
- 2. a. 1. Steam Generator A, B, C, or D Steam Dump to
('N Atmosphere Valve Posi-( tion indicates valve (s) open. OR
- 2. Visual and/or audible indication of an open Steam Generator safety or steam dump valve.
AND
- b. 1. Main Steam pressure is
< 100 psi below set point of affected valve and decreasing in an uncontrolled manner.
EPP 01-2.1 Rev. 3 Page 16 of 31
ATTACHMENT 1.0
-s (Page 11 of 15) l EMERGENCY ACTION LEVELS FOR I NOTIFICATION OF UNUSUAL EVENT l l
Condition Indication (s) i i Indications or 1. a. Radiation monitoring Alarms not Func- instrumentation less tional in Control than minimum channels Room Requiring operable per Technical Plant Shutdown or Specifications Limiting Significant Loss Condition for Operations of Assessment or for Radiation Communications Monitoring and the capability action statements of Tech Spec 3.3.3.1 cannot be met. OR
- 2. a. Accident monitoring i instrumentation less than minimum channels
, operable per Technical l Specifications Limiting Condition for Operations l O for accident monitoring instrumentation.
( OR 1
- 3. a. The total loss of meteorological monitor-ing required to perform offsite dose calcula-tions.
OR
- 4. a. Complete loss of
, communications. l l l EPP 01-2.1 Rev. 3 Page 17 of 31
ATTACHMENT 1.0 (Page 12 of 15) l (s s ,)
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EMERGENCY ACTION LEVELS FOR NOTIFICATION OF UNUSUAL EVENT Condition Indication (s) Loss of Offsite 1. a. Undervoltage on Buses Power and/or Loss of PA01 and PA02. Onsite AC Power AND/OR Capability 2. a. Undervoltage on Buses NB01 and NB02. Radiological Ef- 1. a. Valid Digital Radia-fluent Technical tien Monitoring Panel Specification high alarm on one of Limits Exceeded the following effluent monitors: Liquid Rad-waste Discharge HB-RE-13, SG Blowdown l BM-RE-52, Secondary
- Liquid Waste Discharge
! x HF-RE-45, Unit Vent Activity GT-RE-21B, Radwaste Bldg. Vent GH-RE-10B. AND
- b. Isolation does not occur.
AND
- c. Confirmed sample analysis for a gaseous or liquid release indicates greater than Limiting Conditions for gaseous or liquid effluents and the action statements of Tech Spec 3.11.1.1 and 3.11.2.1 cannot be met.
(Continued) ! s EPP 01-2.1 Rev. 3 Page 18 of 31
ATTACHMENT 1.0
. (Page 13 of 15) l j l
EMERGENCY ACTION LEVELS FOR NOTIFICATION OF UNUSUAL EVENT Condition Indication (s) - Radiological Ef- OR fluent Technical 2. a. Confirmed sample Specification analysis for a gaseous Limits Exceeded or liquid release (continued) indicates greater than Limiting Condition for Operations for Gaseous or Liquid Effluents (see Tech Spec 3.11.1.1 and , 3.11. 2.1) . Transportation of 1. a. Any event which requires Contaminated Injured /Ill the transportation of a Individual from the Site contaminated injured /ill to a Hospital individual to an offsite medical facility. Fire Which has Caused or 1. a. Fire within the plant Threatens to Cause which has the potential Degradation of for causing a safety Safety Systems system not to be operable as defined in Tech. Spec. 1.18. OR ' 2. a. Fire within the plant which causes major degradation of safety system function required for protection of the public. AND
- b. Affected systems are not operable per definition of operable-operability in the Technical Specifications.
O EPP 01-2.1 Rev. 3 Page 19 of 31
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ATTACHMENT 1.0 g (Page 14 of 15) l EMERGENCY ACTION LEVELS FOR NOTIFICATION OF UNUSUAL EVENT Condition Indication (s) Security compromise 1. a. Confirmed report by a senior member of the Security Force that security of the plant has been degraded through an occupation of plant areas, but loss of vital areas and control I of shutdown capability , is not imminent. Natural Phenomenons 1. a. Operating Basis Earthquake (OBE) l Annunciator 98D Alarms in the Control Room.
\w- 2. a. Earthquake greater than OBE levels (0.12g) in the horizontal and vertical direction.
OR
- 3. a. Tornado damage reported in the Protected Area.
OR
- 4. a. Flooding resulting in the loss of operability i of any safety system.
( ,) EPP 01-2.1 Rev. 3 Page 20 of 31
ATTACHMENT 1.0 (Page 15 of 15) l EMERGENCY ACTION LEVELS FOR NOTIFICATION OF UNUSUAL EVENT Condition Indication (s) Other Hazards Existing 1. a. Aircraft crash within or Being Projected the Protected Area. OR
- 2. a. Onsite explosion resulting in structural or equipment damage to the Power Block.
OR
- 3. a. Any release of toxic or flammable gases which, in the judgement of the Shift Supervisor, presents a hazard to WCGS facilities or
, personnel. OR
- 4. a. Turbine trip and observation of a failure causing casing penetration.
EPP 01-2.1 Rev. 3 Page 21 of 31
ATTACHMENT 2.0 s (Page 1 of 4) I k,, EMERGENCY ACTION LEVELS FOR ALERT Barrier Status Indication (s) Fuel Breached Process Indication No indication of increased leakage of reactor coolant (e.g., significant loss of RCS pressure, significant reduction in VCT level, or increasing Containment sump level). Radiation Monitoring Indication The CVCS letdown radiation monitor is off-scale, high (>1.0 uCi/cc). The Containment air particulate, iodine, and radio-gas monitors may increase significantly due O' to reactor coolant which normally leaks to containment. Area radiation monitors about the letdown line, charging line, VCT demineralizers in service, filters in service for letdown filtration, and the gas header from the VCT may indicate a major increase in radiation intensity. Loss of cladding as a fission product barrier results in a pervasive condition of high radiation intensity at all locations where reactor coolant is processed or leaks. (Continued) l n
, EPP 01-2.1 Rev. 3 Page 22 of 31
ATTACHMENT 2.0 I (Page 2 of 4) l (m
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EMERGENCY ACTION LEVELS FOR ALERT l l Barrier Status Indication (s) Fuel Breached Sampling verifies the existence (continued) of failed fuel (any Specific Activity >600 uCi/gm or >5 times Technical Specification limits ) and provides an indication of the extent of fuel failure. l Reactor Coolant Process Indication System Breached Loss of RCS pressure boundary as a fission product barrier is evident by the loss of mass from the RCS, resulting in either a major difference in charging to letdown flow or else loss of system pressure. The Containment sump level indicators respond at a rate consistent with the leak rate from the RCS. For Loss to Containment: Process indication as above. (Continued) l O f EPP 01-2.1 Rev. 3 Page 23 of 31 l
ATTACEMENT 2.0 (Page 3 of 4) l EMERGENCY ACTION LEVELS FOR ALERT Barrier Status Indication (s) Reactor Coolant For Loss to a Steam Generator: Sygtem Breached co:itinued) Dependent upon the size of the steam generator tube rupture, the steam generator Narrow Range Level will provide means to identify the defective generator immediately or in minutes following unit shutdown. Radiation Monitoring Indication Any of the above indications must be combined with a significant radiation increase in thy volume which receives the reacter coolant; either the l steam ?!enerator or the ! , Containment.
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For Loss to Containment: Containment air particulate, iodine, and racio-gas monitors increase very rapidly to the off-scale, high conditions. The Containment high range area monitor indicates downscale or is near the lowest indication l onseale. The Containment area radiation monitors, when in service, increase significantly above normal reactor shutdown conditions and approach the maximum of their indicating range. i EPP 01-2.1 l Rev. 3 l Page 24 of 31
4 ATTACHMENT'2.0 s (Page 4 of 4) [ EMERGENCY ACTION LEVELS FOR ALERT Barrier Status Indication (s) Reactor Coolant For Loss to a Steam Generator: System Breached (continued) The condenser air-removal radiation monitor increases very rapidly to indicate off-scale, high (1 x 10E-2 uCi/cc). The steam generator blowdown monitor increases rapidly to off-scale, high (1 x 10E-2 , uCi/cc). Plant vent monitor increases significantly due to the radioactive material vented from the condenser air-removal system. A steam generator PORV monitor indicates greater than normal background radiation intensity. EPP 01-2.1 Rev. 3 Page 25 of 31
ATTACHMENT 3.0 (Page 1 of 5) ! i
\ EMERGENCY ACTION LEVELS FOR SITE AREA EMERGENCY Barrier Status Indication (s)
Fuel and Reactor Coolant Process Indication System Breached A breach of cladding with a breach of RCS pressure boundary is indicated by extremely high radiation levels in the Containment or the steam generator. The dominant mechanism to result in clad damage is inadequate heat removal capability due to loss of coolant from the RCS. For Loss to a Steam Generator: Process indication as above For Loss to Containment: () Process indication as above Radiation Monitoring Indication A fuel breach event becomes a fuel and reactor coolant system breach event with a resulting major increase in radiation levels throughout the facility, including area monitors near i piping systems containing fluid i associated with core cooling. (Continued) I i EPP 01-2.1 Rev. 3 :, Page 26 of 31
ATTACHMENT 3.0 (Page 2 of 5) l EMERGENCY ACTION LEVELS FOR SITE AREA EMERGENCY l Barrier Status Indication (s) Fuel and Reactor Coolant For Loss to a Steam Generator: System Breached (continued) The steam generator blowdown monitor, when aligned to the defective steam generator, indicates extremely high radiation intensity, or a sample from the defective generator i indicates >100 uCi/ml.; however, the steam generator pressure corresponds to reactor coolant saturation pressure or the reactor coolant system pressure, whichever is higher. Contact reading for the defective generator steam line indicates greater than 2 R/hr contact. O All area monitors within the Auxiliary Building near the header indicate very high radiation intensity if letdown is continued following clad failure. For Loss to Containment: The containment high-range radiation monitor enters the range of 1000 R/hr or higher. I All area radiation monitors located near the ESF piping system recirculating containment-sump liquid are off-I scale, high. (Continued) l l l l EPP 01-2.1 Rev. 3 Page 27 of- 31 l
l ATTACHMENT 3.0 ' (Page 3 of 5) l O EMERGENCY ACTION LEVELS FOR SITE AREA EMERGENCY l Barrier Status Indication (s) Fuel and Reactor Coolant Auxiliary Building air System Breached particulate monitors are (continued abnormally high due to the concentration of fission products in water being processed within the building which is subject to low leakage from systems. Plant unit vent monitors for air 1 particulates, iodine, and radio-gas are abnormally high from minor leakage within the Auxiliary Building of extremely high concentrations of radioactive materials in fluids being processed. s Reactor Coolant System . Process Indication and Containment Breached All indications of an RCS breach plus Containment breach exist. Loss to a Steam Generator: Process indication as above. Loss to Containment: Process indication as above. (Continued) l EPP 01-2.1 Rev. 3 4 Page 28 of 31 I w,, *~ --a.--,. y .- f - - - .. -._ 9 _.
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ATTACEMENT 3.0 ' s (Page 4 of 5) l EMERGENCY ACTION LEVELS FOR SITE AREA EMERGENCY Barrier Status Indication (s) Reactor Coolant System Radiation Monitoring Indication and Containment Breached (continued) The breach of both containment and the RCS results in above-normal radioactive releases from the facility. Radiation levels throughout the facility are higher than normal, but do not exceed a few Rems /hr on contact with coolant system piping. Extremely high radiation levels do not exist. Loss to a Steam Generator: The steam dump to atmosphere valve monitor of the affected steam generator which has a tube failure plus an open path to the environment by a relief valve, safety valve, isolation valve, or pipe failure indicates an (-~]x g
'- abnormally high radiation level. Indication below 2 R/hr contact on a steamline indicates clad integrity in this event.
Loss to Containment: If the Containment Purge System is in operation, Containment purge exhaust monitors for air particulate, iodine, and radio- I gas are offscale, high. The plant vent monitor for air particulates is high on-scale, as are the associated iodine and radio-gas monitors. If the l containment breach is through a penetration, the plant radio-gas I mongtorindicatesmorethan4x 10 uCi/cc at design ventilation flow rate. EPP 01-2.1 Rev. 3 Page 29 of 31
ATTACHMENT 3.0 x (Page 5 of 5) ! EMERGENCY ACTION LEVELS FOR SITE AREA EMERGENCY Barrier Status Indication (s) , i Fuel and Containment Process and Radiation Monitoring Breached Indications The combination of indications of fuel breach and Containment breach exist. NOTE: Other than operator observation of conditions such as open valves or defective seals on containment components, there is no sure means to distinguish between fuel breach plus containment breach and a fuel breach only event. O EPP 01-2.1 Rev. 3 Page 30 of 31
W ATTACHMENT 4.0 (Page 1 of 1) l
- EMERGENCY ACTION LEVELS FOR GENERAL EMERGENCY Barrier Status Indication (s)
All Barriers Breached Process Indication As before for Fuel, Reactor Coolant System and Containment Breaches. 1 Radiation Monitoring Indication The indications of fuel breach plus reactor coolant system breach are combined with extremely high radiation in the pathway to the environment. Loss of Containment to the Auxiliary Building results in release rates from the plant vent at cogcentrations in excess of 1 x 10 uCi/cc. Site boundary monitoring with portable radiation monitoring equipment indicates high concentrations of radio-gas near l or above 10 CFR 20 limits. Loss of all fission product barriers results in extremely high radiation within the plant, indication of very high l radioactive material release rates from the plant, and indication of high concentrations at the Exclusion Area Boundary. Other Indication Loss of physical control of the facility. EPP 01-2.1 Rev. 3 Page 31 of 31 2
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WCLF CREEK GENERA'IING STATION. s ff ' a RADIOLOGICAL EMERGENCY RESPONSE PLAN IMPLEM2irITNG PROCEDURE
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IMMEDIATENO'NFICATIONS'j p s EPP 01-3.1 Revision 5 ! e
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4-1.0 PURPOSE . This procedure provides guidance to notify Fedsr,al, i State and County authorities in the event of an emergency classification. 4 2.0 APPLICABILITY This procedure applies to immediate notification methods from the Control Room, Technical Support Center (TSC), and Emergency Operations Facility (EOF) . This procedure is applicable to Shift Supervisors, Control Room Communicators, Duty Emergency Director (DED), Duty Emergency Manager (DEM), Administrative Emergency Coordinator (AEC), TSC Communicators, Administrative Resources Manager (ARM), EOF Communicator, and other KGEE personnel who are responsible for making immediate notifications to offsite authorities. 3.0 DEFINITIONS 3.1 EMERGENCY CLASSIFICATION A system us'ed to define t,he severity of emergencies into one of four categories based upon Emergency Action Levels and Fission Produce Barrier Integrity Conditions. Classifications listed in order of O increasing severity are: Notification of Unusual Eve -! b , Alert, Site Area Emergency and General Emergency. 4.0 INSTRUCTIONS 4.1 PRECAUTIONS 4.1.1 State and County authorities and the KG&E System Operations Dispatcher shall be notified within fifteen (15) minutes following an emergency. classification, or changing an Emergency Classification or Protective Action Recommendation (P'afer to Attachment 3.0
" Initial Notification Call List" Form EP 3.1-3).
4.1.2 The Nuclear Regulatory Commission (NRC) Resident Inspector should be notified within fifteen (15) minutes, or as soon as possible depending upon his availability. EPP 01-3.1 Rev. 5 j Page 1 of 16 i
4.1.3 The NRC Operations Center notification shall be made /} ( immediately after notification of the State and County and no later than one (1) hour following an emergency classification - via the Emergency Notification System (ENS). If the ENS is inoperative, the notification shall be via commercial telephone or any other method to assure that a report is made as soon as practical to the NRC Operations Center. 4.1.4 Attachment 1.0, " Wolf Creek Generating Station Immediate Notification Form", Form EP 3.1-1, shall be used when contacting State and County authorities for both initial notification of an emergency classification - with appropriate recommended protective action recommendations, and subsequent changes in emergency classification and/or protective action recommendations. 4.1.4.1 Attachment 1.0 shall also be used to contact the KG&E System Operations Dispatcher. 4.1.4.2 Attachment 1.0 shall be approved by the DED, or the DEM, prior to contacting State and County authorities. 4.1.5 Attachment 2.0, "NRC Notification / Report Form", Form EP 3.1-2 shall be used to initially contact the NRC and for subsequent changes in emergency
-s classification, unless continuous communications with A ) the NRC have been established.
k_ / . 4.1.5.1 Maintaining continuous NRC communications regarding technical information at the Alert, Site Area Emergency and General Emergency classifications shall be performed by a designated TSC NRC Communicator. (Attachment 2.0 should be used to document time.) 4.1.5.2 Maintaining NRC communications regarding protective action recommemdations and public information shall be performed by a designated EOF Communicator. 4.1.6 In the event that the emergency condition requires offsite assistance (e.g., ambulance, hospital, fire department), such assistance should be requested coincidentally with the immediate notification process. Refer to EPP 01-3.3, "Offsite Support Notifications". 4.1.7 Follow-up notification and communications to State and County authorities shall be approved by the DED or DEM - refer to EPP 01-3.2, " Followup Notifications." (- ) EPP 01-3.1 Rev. 5 Page 2 of 16
4.1.8 Two attempts shall be made to use commercial telephone [\ . lines to notify the State and County authorities. In the event that commercial telephone communications are unsuccessful, use the Motorola Series 90 radio with Modem 36 Paging Encoder (refer to Attachment 4.0,
" Radio Console Operation - State Notification") to notify State authorities, and use Motorola radio Model TIG17CM to notify County authorities (refer to Attachment 5.0, " Radio Console Operation - County Notification").
4.2 INITIAL ACTIONS 4.2.1 Control Room 4.2.1.1 The Shift Supervisor shall assign a control Room Communicator who will relay plant parameters to the Operations Assessment Coordinator and to the TSC/ EOF Operations Status Recorder (s). 4.2.1.1.1 A Nuclear Station Operator will be assigned as the Control Room NRC Communicator and will contact the NRC via the Emergency Notification System (ENS) phone using Attachment 2.0. 4.2.1.1.2 The Shift Clerk will be assigned as the Control Room Offsite Communicator and will perform immediate noti-ff ations using Attachments 1.0 and 3.0. Os 4.2.1.2 Immediate notification verification shall be accomplished using the verification phone (Brown) in the Control Room or by including predesignated code word (located under the phone) during message transmission to Coffey County, Attachment 6.0, " Code Word Instructions." 4.2.2 TSC 4.2.2.1 The AEC shall verify the status of immediate notifications from the Control Room Communicators by completing Attachments 1.0 and 2.0 and obtaining verification code word, Attachment 6.0, " Code Word Instructions." 4.2.2.1.1 The forms should be completed using information from the current Attachments 1.0 and 2.0 completed by the Control Room Communicators. 4.2.2.1.2 The AEC shall inform the DED of the status of immediate notifications and NRC notification. EPP 01-3.1 Rev. 5 Page 3 of 16 f
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I 4.2.2.1.3 The DED shall verify that the immediate notifications ! Cg appropriate for the emergency classification have been made to State, County, NRC, and KG&E System l Operations. 4.2.2.2 The DED shall inform the Shift Supervisor that he is assuming notification responsibilities concurrently with activating the TSC and assuming the DED position. 4.2.2.3 The AEC shall assign a TSC Communicator to make notifications to State, County and KG&E Systems Operations; and a TSC NRC Communicator for NRC notifications and ccmmunications via the ENS phone. 4.2.2.4 The TSC Communicator shall assure that the verification phone (Brown) is connected and operable. 4.2.3 EOF 4.2.3.1 The ARM shall verify the status of immediate notifications from the TSC by reviewing the "hardcopy" of the current Attachments 1.0 and 2.0, and obtaining the verification code word from the TSC Communicator, Attachment 6.0. 4.2.3.1.1 If the "hardcopy" is not available, the ARM shall complete Attachments 1.0 and 2.0 using information (g obtained from the current Attachments 1.0 and 2.0 t, f completed by the TSC Communicator. N/ 4.2.3.1.2 The DEM shall verify that the immediate notifications appropriate for the emergency classification have been made to State, County, NRC, and KG&E System Operations. 4.2.3.2 The DEM shall inform the DED that he is assuming notification responsibilities concurrently with activating the EOF and assuming the DEM position. 4.2.3.3 The ARM shall assign an EOF Communicator to make notifications to the State, County, KG&E System Operations and the TSC Communicator. 4.2.3.4 The EOF Communicator shall assure that the verification phone (Brown) is connected and operable. 4.2.3.5 The ARM shall also designate an EOF Communicator to maintain NRC Communications for protective action recommendations and public information. x . EPP 01-3.1 Rev. 5 Page 4 of 16
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-w 4.3 SUBSEQUENT ACTIONS N_ / 4.3.1 Control Room 4.3.1.1 Immediate notification responsibilities shall be transferred to the DED and AEC immediately following TSC activation.
4.3.1.1.1 Upon activation of the TSC, the Control Room Offsite
; Communicator shall transfer immediate and followup notification responsibilities to the TSC Communicator.
4.3.1.1.2 The verification phone (Brown) shall be disconnected after the TSC has assumed notification responsibilities. 4.3.1.1.3 Upon activation of the TSC and the addition of the TSC NRC Communicator to the ENS, the Control Room NRC i Communicator may request the NRC for permission to terminate the control room contact.
- a. If permission is granted, the Control Room NRC Communicator can " hang up" the phone, terminating the control room direct contact with the NRC and completing the transfer of NRC communications responsibilities to the TSC NRC Communicator.
, b. If permission is denied, the Control Room NRC communicator shall remain on the ENS phone with the TSC NRC Communicator until further notice. 4.3.2 TSC 4.3.2.1 Immediate notifications for changes in emergency classification or protective action recommendations shall be approved by the DED and made using Attachments 1.0, 2.0 and 3.0. 4.3.2.2 The AEC shall complete Attachments 1.0 and 2.0, and the DED shall approve for transmittal. 4.3.2.2.1 The TSC Communicator shall verify that a hard copy of completed Attachments 1.0 and 2.0 are transmitted
- (telecopy) to the EOF. i 4.3.2.3 Immediate notification responsibilities shall be transferred to the DEM and ARM immediately following EOF activation.
i i EPP 01-3.1 Rev. 5 i Page 5 of 16 l
4.3.2.3.1 The verification phone (Brown) shall be disconnected A after the EOF has assumed notification responsibilities. 4.3.2.3.2 Upon activation of the EOF, the TSC Communicator shall transfer immediate notification responsibilities to an EOF Communicator. 4.3.2.4 Upon notification of a change in emergency classifi-cation from the EOF, the AEC shall complete Attachment 2.0, and obtain DED approval prior to transmitting to the TSC NRC Communicator. 4.3.3 EOF 4.3.3.1 Immediate notifications for changes in emergency classification or protective action recommendations shall be made using Attachment 1.0 and 3.0. 4.3.3.1.1 The ARM, or his designee, shall complete Attachment 1.0, and the DEM shall approve for transmittal. 4.3.3.1.2 The form shall be routed to the ARM and the EOF Communicator. The EOF Communicator will contact the State, County, KG&E System Operations Dispatcher and TSC Communicator and provide the information' indicated on the form. O- 4.3.3.1.3 The EOF Communicator should transmit "hard copies" of Attachment 1.0 to the State, County and TSC Comunicators, as requested.
5.0 REFERENCES
5.1 WCGS Radiological Emergency Response Plan 5.2 WCGS Radiological Emergency Telephone Directory. l 5.3 EPP 01-3.2, " Followup Notifications" f 5.4 EPP 01-3.3, "Offsite Support Notifications" l 6.0 RECORDS 6.1 Form EP 3.1-1, " Wolf Creek Generating Station Immediate Notification Form" 6.2 Form EP 3.1-2, "NRC Notification / Report Form" 1
\ EPP 01-3.1 Rev. 5 Page 6 of 16 0
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6.3 Form EP 3.1-3, " Initial Notification Call List" 6.4 The records generated by this procedure during an actual emergency shall be forwarded to the Emergency Planning Coordinator (EPC) at the termination of the emergency. The EPC forwards the records to Records Management for storage. These records will be retained for the life of the plant. These records shall be considered QA records. 6.5 The records generated by this procedure during drills and exercises shall be forwarded to the EPC upon i termination of the drill or exercise. The EPC shall maintain these records for at least one year. These records shall be considered non-QA records. 7.0 ATTACHMENTS 7.1 Attachment 1.0, " Wolf Creek Generating Station Immediate Notification Form" 7.2 Attachment 2.0, "NRC Notification / Report Form" 7.3 Attachment 3.0, " Initial Notification Call List" 7.4 Attachment 4.0, " Radio Console Operation - State Notification" l 7.5 Attachment 5.0, " Radio Console Operation - County Notification" i 7.6 Attachment 6.0, " Code Word Instructions" l EPP 01-3.1 Rev. 5 Page 7 of 16 l
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ATTACHMENT 1.0 l (Page 1 of 2) + e WOLF CREEK GENERATING STATION IMMEDIATE NOTIFICATION FORM [m]
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ss FORM EP3.1-1 Rev. 1 WOLF CREEK GENERATING STATION IMMEDIATE NOTIFICATION FORM MDmGE e
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@ NOT APPLICABLE (INITIAL NOTIFICATION FOR INFORMATION ONLY)
@ EXDCISE/tRIIL/ TEST B PREPARE FOR POSSIBLE ACTIONS INVOLVING DE PUBLIC
- 2. resr% 2 ItE 2IVID FWDt:
NOTIFY PUBLIC M TAKE WE FOUDWING PROTICTIVE ACTIONS NAt%DATE APPETE) Erg srutarmsE CIE12 ACTION M TAKE Wolf Creek Time Is 0 - 2 MILES CTR SHELTER / EVAC" ATE panemane pK2IVE BT: 2 - 5 MILES JRR SHELTER / EVACUATE E-1 SHELTER / EVACUATE N-1 SHELTER / EVACUATE Tour Name NE-1 SHILTER/ EVACUATE NW-1 SHELTER / EVACUATE
- 3. p CIABIFIOTIN S-1 SHELTER / EVACUATE SE-1 SHELTER / EVAC 2JATE SW-1 SHELTER /EVACDATE
@ NOTIFIOTION OF UNUSA EVENT wl SHELTER /EVACDATE b ALERT 5 - 10 MILES E-2 SHELTER / EVACUATE SITE ARFA DERCDCT N-2 SHILTER/ EVACUATE NE-2 SHELTER / EVACUATE D GDERAL DERCDCT NE-3 SHILTER/IMO. ATE tw-2 SHELTER /EVM:UATE l
- ; [D)
@ RII%NERT/PEDrTRY S-2 SE-2 SHILTER/TVACUATE SMILTER/ EVACUATE \ TERMINATION SE-3 SHELTER / EVACUATE \ SE-4 SHELTER / EVACUATE
- 4. TDE W CIAmiIFICkTICRI SW-2 SHELTER / EVACUATE W2 SHELTER / EVACUATE TIME @ PEACE MII2 PRGICING ANIMAIS ON STORID FEID OUT M _ MILES IN DOWNWI!O SICTORS A, B, C, D, E, F, G, H, J, R, L, M, N, P,
- 5. TYPE W ACCIDENT C, R (CIRCLE AFFICTID SIEMRS).
@ PERSONNEL INJURY 9. VMIFIOTICRI
@ NAWRE PHDOENON VERIFIED (IDEt exwTT ON:.7)
C SIEURITT WREAT VERIFIID WInt NAME
@ FIRE /TXPEDSION
@ FUIL CIR DING DAMAGE VERIFICATION PHONE tOBERS (CAIL ONE):
tt)sS Or (D0thrT NDEE CREEK VERIFICATION - (316) 364-8840
- 6. RADICIDGICAL REIAhSE STATUS STATE OF RANSAS (913) 296-3176 A NONE (DFTET CoUtrTY (316) 364-2123
@ POTDFTIAL 10. THE PutJANING HAVE BEEN MDFIFIEt C IN PROGRESS A C0f7ET CDUNTT D TERMINATID @ STATT DIVISION OF DERGENCY PREPARIDNESS
- 7. WDC DhTh 11. IDFIFICATItal APPROVAL DEDB GIE OK.7)
WI!O CIRICTION: hee / Title / Time /Date 17 09 M WIND SPEID: t t l Ns) EPP 01-3.1 Rev. 5 Page 8 of 16
l [T ATTACHMENT 1.0 l ( ) (Page 2 of 2) 1 FORM EP 3.1-1 NUMBERING INSTRUCTIONS Form EP 3.1-1 is used by the Control Room, TSC and EOF for immediate notifications. To assist in keeping records, each location will assign a unique two-part alpha numeric number to each message use of the form. For example, the first message use of Form EP 3.1-1 from the Control Room will have three copies (i.e.: one copy for contact with Coffey County, one copy for contact with the State of Kansas, and one copy for contact with KG&E System Operations) but only one message number.
- The first part of the number will be comprised of two or three letters indicating the originating location as shown below:
CR - Control Room TSC - Technical Support Center, or EOF - Emergency Operations Facility. The second part of the number is comprised of sequential numbers of three digits starting with 001.
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EXAMPLE: The first message use of Form EP 3.1-1 by the TSC would be: TSC-001. r l EPP 01-3.1 Rev. 5 i Page 9 of 16 l
. FORM EP 3.1-2 REV. 1~
ATDO9ENT 2.0 g (Page 1 of 2)
\ L;.5. Ni;CLEAk REGULAIORY COf9tI55 ION OPEAATIONS CLN!Ea ETEET E071F1C&T10s WORESBEET NOTIFICATION TIME FACILITY OR ORGANILATION UNIT CALLfi"5 NAME TELEPHONE NU SER (For CaII laca)
EVEirt CLA$$tFICATION T N EVElrf CATECORY INITIATION $1CNAL CAUSE OF FAILURE CENERAL EMERCENCY REACTOR TRIP / SCRAM MECHANICAL
$1TE ARE A EMERGENCY E$F ACTUATION ELECTRICAL ALERT ECCS ACTUATION PER$0NNEL ERROR UNU$UAL EVENT SAFETY INJECTION FLOW PROCEDURE INADEQUACT
& l4 LCO ACTION STATEMENT OTHER hr I hr 50.72 NON-EMERCENCY l A 2 he hr $ECUR1TT/$AFECUAjlD$ OTHER TRANSPORTATION EVEN1 $YSTEMt EVENT TIE ZONE EVE.E MONTH DAY DATE OTHERt CO WONENT:
ETEET DESCR1PTION l
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POWER PRiot TO ETENT (E): Did all systems funetton as required' fee If No. Esplain above. CI'RRENT POWER OR MODEt Anything " unusual" or not und e rs t ood ? No If fee, Esplain above. DUTSIDE ACEBCT 08 Pee - CotaECTITE ACTION (S) upTIFTED ST LICENSEE STATE ($): toCAL RESIDENT TES NO WILL BE - OTu!R, M0et Or OrtuTiON Ttt.t CORueTroNi lESTruTETruTORESTuti l l rREss REtta$E ll l ADD: Trout tNr0RMATtON ON RACR i N- EPP 01-3.1 Rev. 5 Page 10 of 16
IDRM EP 3.1-2 REV. 1 j ATDGMENT 2.0 ('q) J (Page 2 of 2) ADDITICEAL INF0WETICE FOR RADIOWICICAL REIAASSS LIQUID RELEASE PLANNED SOURCE ($): CASEOUS RELEASE UNFLANNED RELEASE RAM (Ct /see)? EST TOTAL ACTIVITY (C1)r RELEASE DURATION EST TOTAL IODINE (Cl) T.S. LIMITS: CRAS SAMPLE MONITOR READfMC Arese Evacuated? Y N List Below Personnel exposed /contasiaated Y N Describe below Flant Nealth Phystes backup requested? Y N Notet Only if T.S. exceeded or actual contamination ADDITIONAL INFORMATION ( ADDITIONAL INFORMATION FOR REACTOR COOLANT OR STEAM GENERATOR TUBE LEAES
$UDDEN OR LONC TERM DEVELOF* TENT? START DATEt START TIMEt PRIMARY COOLANT LEAK RATE: ACTIVITY IGNITOR READIECS SECONDART C00LANI LEAX VOLLME: ACTITITTt CONDEN$tti T.S. LIMITS MAIN STM LINE SC SLOWDOWNt LIST OF $AFETT RELATED EQU1FMENT g OPERATIONAL
$PECIAL ACTIONS TAKEN ST LICEN$1E (if any):
v - EPP 01-3.1 Rev. 5 Page 11 of 16
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FORM EP 3.1-3 REV. O ATTACHMENT 3.0 (PAGE 1 of 1) INITIAL NOTIFICATION CALL LIST ORGANIZATIONS METHODS OF NOTIFICATION CLASSIFICATION TIME NOTIFIED PERSON CONTACTED KG4E System Operations 1) Dedicated Phone Line NOTIFICATION OF UNUSUAL EVENT
- 2) Dispatch Line ALERT SITE AREA EMERGENC1
- 3) Cosssercial Phone GENERAL EMERGENCY 261-6303 or 261-6304 REENTRY / RECOVERY Kansas Division of !) Commercial Phone NOTIFICATION OF Energency Preparedness (913)296-3176 x301, 303 UNUSUAL EVENT (Division Duty Officer) 2) Microwave Radio to ALERT Topeka by paging 12 on SITE AREA EMERGENC1 the Pager System GENERAL EMERGENCY REENTRY / RECOVERY Coffey County Sheriff !) Commercial Phone Office 364-2123
- 2) Station Radio Frequency O't NOTIFICATION OF UNUSUAL EVENT Kansas Highway Patrol 1) Commercial Phone ALERT Division 4. Chanute, KS (316)431-2100 SITE AREA EMERGENC1 GENERAL EMERGENCY REENTRY / RECOVERY WCGS NRC Resident 1) Co m rcial Phone NOTIFICATION OF IrSpector Home (316)364-5820 UNUSUAL EVElff Office Z111 ALERT SITE AREA EMERGENC1
\ GENERAL EMERGENCY REENTRY / RECOVERY US Nuclear Regulatory 1) Dedicated Phone Line NOTIFICATION OF Commission Incident 2) Coassercial Phone UNUSUAL EVENT Response Centar - (301)-951-0550 ALERT Bethesda (301)-427-4056 SITE AREA EMERGENC1 (301)-427-4259 GENERAL EMERGENCY (301)-492-8893 REENTRY / RECOVERY American Nuclear 1) 24 Nr. Number Insurers 2) As soon as practical after Alert or greater ALERT classification SITE AREA EMERGENC1
- 3) (203) 677-7305 GENERAL EMERGENCY EPP 01-3.1 Rev. 5 Page 12.of 16
ATTACHMENT 4.0 (Page 1 of 2) RADIO CONSOLE OPERATION - STATE NOTIFICATION Moden 36 Paging Encoder Operation
- 1. Position the AC-OFF-DC power switch to the power source being used (AC or DC), located on the back panel of the Encoder.
- 2. Turn ON/OFF switch for the Motorola horizontal console to the "ON" position.
- 3. Adjust the volume on the Motorola horizontal console to approximately the mid position.
- 4. Paging 4.1 Number Entry - Enter the pagar code number using the numbered pushbuttons on the keyboard. As a number is entered, it assumes the rightmost position and shifts to the left when another digit is entered (entry is from right to left).
NOTE: If a mistake is made in entering the pagar code number, re-enter the correct code number. , 4.2 Monitoring - The channel must be monitored to prevent l g co-user interference, prior to depressing the P (page) l j or T (talk) pushbutton. This is accomplished by setting i the receiver audio volume control on the base station in j local control systems to a comfortable listening level. . The transmitted message will be garbled if the channel is not clear. When clear, proceed to page or transmit. NOTE For carrier squelch systems - channel monitoring is automatic; i.e., the channel activity is heard when the base station is not transmitting. For PL squelch systems - channel monitoring is accomplished by depressing the MONITOR switch on the microphone. ! 4.3 Tone-only Paging - When the P (page) keyboard pushbutton I is momentarily depressed, an automatic paging cycle is initiated. 4.3.1 The PAGE lamp glows, indicating that the transmitter is - keyed and paging tones are being generated.
- 4.3.2 While the PAGE lamp is on, the keyboard is locked out and no other function can be performed. At the end of the paging tone interval, the PAGE lamp goes out.
EPP 01-3.1 l Rev. 5 l Page 13 of 16 i \
ATTACHMENT 4.0 (Page 2 of 2) RADIO CONSOLE OPERATION J 4.4 Tone-and-Voice Paging - This operation is similar to a tone-only page with the following exceptions: BEFORE the PAGE lamp goes out, depress the T (Talk) pushbutton on the keyboard or the TRANSMIT paddle on the microphone in carrier squelch systems. While holding the T (talk) pushbutton down, and after the PAGE lamp goes out, the voice message portion of the page should be given. In a PL squelch system, this is accomplished by depressing the T (talk) pushbutton on the keyboard. 5.0 Voice Transmission To transmit a voice message without paging in a mixed mobile / paging system, use the following procedures: 5.1 Carrier Squelch System - Monitor the channel as previously described. Depress and hold the TRANSMIT paddle on the microphone or the T (talk) pushbutton on the keyboard for the duration of the voice message. 5.2 PL Squelch System - Monitor the channel as previously described. Simultaneously depress and hold the TRANSMIT and MONITOR paddles on the microphone for the duration of the voice message. O ( ,/ 6.0 For deactivation of the Encoder, perform the following: 6.1 Turn the ON/OFF switch for the horizontal Motorola console to the OFF position. . 6.2 Turn the volume control for the horizontal Motorola console fully counter clockwise. 6.3 Push the number zero "0" twice on the Moden 36. ) I \ EPP 01-3.1 Rev. 5 Page 14 of 16
. ATTACHMENT 5.0 RADIO CONSOLE OPERATION - COUNTY NOTIFICATION
- 1. Turn the On/Off dial, located on the horizontal section, to the "ON" position.
- 2. Adjust the " Volume" dial, located on the horizontal section, by turning the dial clockwise to approximately the mid position. Adjust volume as desired.
- 3. Assure the "Unselected Volume" dial, located on vertical section, is fully clockwise.
- 4. Assure that the vertical section " Mute" buttons are lined-up in their desired positions.
NOTE: The speaker located on the upper right hand corner of vertical section monitors all the unselected channels. By depressing the mute buttons in, the incoming chanel is muted.to predetermined level up to twenty (20) dB.
- 5. Depress the desired " Channel" button located on the horizontal section. This disconnects the previously selected channel and connects the desired channel from the horizontally located speaker. In addition this enables the transmit keying circuits for the desired channel.
With the desired channel selected, the operator can 6. monitor incoming messages on the select audio speaker (horizontal section) and transmit messages over the t selected channel by depressing the " TRANSMIT paddle on the desk microphone. NOTE: Before transmitting, the operator shall Assure , that the applicable radio channel is not already in use by depressing the " MONITOR" paddle on the microphone. This disables the coded squelch system and permits all calls to be heard. y EPP 01-3.1 Rev. 5 Page 15 of 16
, ATTACHMENT 6.0
(N CODE WORD INSTRUCTIONS
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1.0 GENERAL The code word is to be used for telephone communications between the WCGS Emergency Response Organization and Coffey County (Sheriff's Office Dispatcher) only. The code word is placed in an envelope and taped to the bottom of the phone in the Control Room and to the bottom of the Coffey County Sheriff Office Dispatcher's phone. The same code word will be used throughout the , emergency and will be replaced during recovery operations. 2.0 INSTRUCTIONS 2.1 Initial Use The Control Room Communicator contacting the Coffey County Sheriff's Office Dispatcher by telephone shall provide the Dispatcher the code word contained in the Control Room Envelope to the Dispatchar at the beginning of the notification. The Dispatcher will verify that the Control Room code word corresponds to the County l code word. The notification process will proceed as l ) specified after this confirmation. 2.2 Subsequent Use All subsequent telephone contacts with Coffey County will use the code word at the beginning of the contact. The code word will be passed on to the.TSC and I:OF Communicators for their use in telephone conversations with Coffey County. The code word will still be passed on to the TSC and EOF Communictors even if initial County contact was made via radio and code word was not needed, i EPP 01-3.1 Rev. 5 Page 16 of 16 y,, , ,- - .m---, ----,,w- ,,-,----,-- --,,-.,-va.1-,---, -- . -- -- , , , - - - _ , - - , , - - - - - - - - - , - - - - - - - --
4 n N.s l WOLF CREEK GENERATING STATION RADIOLOGICAL EMERGENCY PESPONSE PLAN IMPLEMENTING PROCEDURE FOLLOWUP NOTIFICATIONS EPP 01-3.2 Revision 4 l O
),A l du a le/n EMERGINCf PLANNI COORDI ATOR' REVIEW DATE / /-'
- f. -vt < CL-M u% /6 $lh@ '
EMERGENCY PLANNING ADMINIS'IRATOR REVIEW DATE' '
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/Ene Nh DATE
//-3-K PSRC APPROVAL RECOMME~N3 TION kb0&N V.P. NUCLEAR PPROVAL n/7/Ps DATE '
RELEASED DC29 Il- 7'8h DATE O
1.O PURPOSE k- 1.1 This procedure provides instructions for conducting followup notifications to State and County authorities in the event of a declared emergency condition at Wolf Creek Generating Station (WCGS). 2.0 APPLICABILITY This procedure applies to followup notification methods from the Control Room, Technical Support Center (TSC), and Emergency Operations Facility (EOF). This procedure is applicable to Shift Super-visors, Duty Emergency Director (DED), Duty Emergency Manager (DEM), Administrative Emergency Coordinator (AEC) , Radiological Emergency Coordinator (REC) , Oper-ations Emergency Coordinator (OEC), TSC Communicator, Administrative Resources Manager (ARM), Radiological Assessment Manager (RAM), Technical Resources Manager (TRM), EOF Communicator, and other KG&E personnel who are involved in making followup notifications to offsite authorities. 3.0 DEFINITIONS 3.1 EMERGENCY CLASSIFICATION A system used to define the severity of emergencies into one of four categories based upon Emergency Action Levels and Fission Product Barrier Integrity Conditions. Classifications listed in order of increasing severity are: Notification of Unusual Event, Alert, Site Area Emergency and General Emergency. 4.0 INSTRUCTIONS 4.1 PRECAUTIONS 4.1.1 Followup communications with State and County author-ities shall be approved by the DED or, if the EOF is activated, the DEM. 4.1.2 In the event that the emergency condition requires immediate offsite assistance (e.g., ambulance or firefighting), such assistance shall be summoned prior to proceeding with the followup Notification processes. Refer to EPP 01-3.3, "Offsite Support l Notification". O EPP 01-3.2 Rev. 4 Page 1 of 7 .
i l 4.1.3 Notification message forms provided in this procedure [ 'N are to be used for communications with the State and ( ) County emergency response organizations. These message forms are not intended to be used for public ' ' i information purposes. l 4.1.4 Prior to arrival of the DEM at the EOF, the DED is responsible for communications with offsite organi-zations. 4.1.5 In the event that an Alert or higher emergency classi-fication is declared at WCGS, State and County authorities shall be provided with periodic radio-logical status updates until such time that the plant has been placed in a safe, stable condition. 4.1.6 Periodic updates to the State and County should be made at approximately 30 minute intervals or as soon as more definitive information becomes available. 4.1.7 Followup Notifications shall be accomplished using commercial telephones. If after two attempts commer-cial telephone lines are unavailable, radio communi-cations shall serve as the backup means of notifi-cations (refer to EPP 01-3.1, Attachments 4.0 and 5.0). l (S 4.1.8 Followup Notifications shall be accomplished using ( Attachment 1.0, " Wolf Creek Generating Station
\w_/) Followup Notification Message Form", Form EP 3.2-1.
Copies of Attachment 1.0 shall be filed as appropriate. 4.1.9 Verification of followup Notifications is not required. 4.2 INITIAL ACTIONS l 4.2.1 Control Room l 4.2.1.1 The Shift Supervisor shall assure followup Notific-ation is performed by completing Attachment 1.0. 4.2.1.2 The Shift Supervisor will then route Attachment 1.0 to the Control Room Offsite Communicator. The Control Room Offsite Communicator will contact the appropriate offsite authorities indicated on Attachment 2.0,
" Followup Notification Call List", Form EP 3.2-2, and provide the information indicated on Attachment 1.0.
EPP 01-3.2 Rev. 4 Page 2 of 7 l 1 . . _ __ _ - - - . - _ . - __ - - . -. _ _ _ - . - _ . - - - _ - _. -__
._. - . =- . __ __.
4.2.2 TSC ()
's ,/ 4.2.2.1 The AEC shall complete Attachment 1.0.
4.2.2.2 Attachment 1.0 should be completed using information available from the TSC status boards; or the REC and the OEC. 4.2.2.3 Attachment 1.0 shall then be routed to the DED for his review and approval. 4.2.2.4 Attachment 1.0 shall then be routed to the TSC Communicator. The TSC Communicator will contact the appropriate offsite authorities indicated on Attachment 2.0, and provide the information indicated on Attachment 1.0. 4.2.3 EOF 4.2.3.1 The AR 1 shall complete Attachment 1.0. 4.2.3.2 Attachment 1.0 should be completed using information available from the EOF status boards, or the RAM and the TRM.
- 4.2.3.3 Attachment 1.0 shall then be routed to the DEM for his review and approvr.l.
l ! 4.2.3.4 Attachment 1.0 shall then be routed to the EOF ' \ Communicator. The EOF Communicator will contact the appropriate offsite agencies indicated on Attachment 2.0 and provide the information indicated on AttachLant 1.0. 4.3 SUBSEQUENT ACTIONS 4.3.1 Control Room 4.3.1.1 The Shift Supervisor transfers followup notification l l responsibility to the DED upon activation of the TSC. 4.3.1.2 Upon activation of the TSC, the Control Room Offsite Communicator will contact the TSC Communicator with information on any followup communications made. l [ 4.3.2 TSC l 4.3.2.1 The AEC shall assure that followup notifications are transmitted to appropriate State and County author-ities on a periodic basis. EPP 01-3.2 Rev. 4 Page 3 of 7
l 4.3.2.2 Upon activation of the EOF, the TSC Communicator shall transfer followup notification responsibilities to the i ( EOF Communicator. A hard copy of the most recent Attachment 1.0 shall be transmitted (telecopy) to the EOF. 4.3.3 EOF 4 4.3.3.1 The ARM shall assure that followup notifications are l transmitted to appropriate State and County authorities on a periodic basis.
5.0 REFERENCES
5.1 Wolf Creek Generating Station Radiological Emergency
. Response Plan I
5.2 EPP 01-3.1, "Immediate Notification" i 5.3 EPP 01-3.3, "Offsite Support Notification" 6.0 RECORDS 6.1 Form EP 3.2-1, " Wolf Creek Generating Station Followup Notification Massage Form" j 6.2 Form EP 3.2-2, " Followup Notification Call List" [ 6.3 The records generated by this procedure during an
, actual emergency shall be forwarded to the Emergency Planning Coordinator (EPC) at the termination of the emergency. The EPC forwards the records to Records Management for storage. These records will be retained for the life of the plant. These records shall be considered QA records. 1 6.4 The records generated by this procedure during drills and exercises shall be forwarded to the EPC upon i termination of the drill or exercise. The EPC shall maintai'n these records for at least one year. These records shall be considered non-QA records.
7.0 ATTACHMENTS 7.1 Attachment 1.0, " Wolf Creek Generating Station Followup Notification Message Form" 7.2 Attachment 2.0, " Followup Notification Call List"
\ ,
f EPP 01-3.2 , Rev. 4 i Page 4 of 7
e ATTACHMENT 1.0 (Page 1 of 2) l v FClee EP3.21 aav. 1 WOLF CREEK GENERATING STATION FOLLOWUP NOTIFI;:ATION FORM .esucs e
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\ EPP 01-3.2 Rev. 4 Page 5 of 7
ATTACHMENT 1.0 (Page 2 of 2) FORM EP 3.2-1 NUMBERING INSTRUCTIONS Form EP 3.2-1 is used by the Control Room, TSC and EOF for follow-up notifications. To assist in keeping records, each location will assign a unique two-part alpha numeric number to each use of the form. The first part of the number will be comprised of two or three letters indicating originating locations, i.e.: CR - Control Room TSC - Technical Support Center, or EOF - Emergency Operations Facility. The second part of the number is comprised of sequential numbers of three digits starting with 001. EXAMPLE: The first use of Form EP 3.2-1 by the TSC would be: TSC 001. There will be two copies of each form used: one for contacting the County and one for contacting the State. f i i V i i l EPP 01-3.2 l Rev. 4 i Page 6 of 7 i
l i e Form EP 3.2-2 REV. 2 i ATTACHMENT 2.O ("' I (Page 1 of 1) ' NJ FOLLOWUP NOTIFICATION CALL LIST l PROVIDED WITH INFORMATION THAT WAS ORGANIZATION PHONE CURRENT AS OF: (From bottom of Form EP 3.2-1) l Received by Time /Date Your Name (Name) Coffey County 364-2123 Sheriff Backup is Dedicated ' Radio Kansas Divi- (913) 296-3176 sion of Ext 301,303 ( Emergency l s - Preparedness Backup is Dedicated Radio Link l EPP 01-3.2 Rev. 4
- Page 7 of 7 (s_'
i
O i WOLF CREEK GENERATING STATION RADIOLOGICAL EMERGENCY RESPONSE PLAN IMPLEMENTING PROCEDURE ONSITE EMERGENCY RESPONSE ORGANIZATION MANUAL CALL-OUT EPP 01-3.4 Revision 3 l O TA W COORDIN f REVIE P DATE
/$
f Yn T EMERG'EQCY PLANN /'
- ' YA ! $- + &L6 /8 /.2/' / S $
EMERGENCY PLANNING ADMINISTRATOR REVIEW DATE/ d/A_ _ r$ ll-3k& DATE PSRCAPPROVALRECOMMENDAT}ON WOb 67,dak n/7//s h V.P. NUCLEAR APPROVAL DATB ' RELEASED DC29 [ /- 7-flo DATE O
I s c 1.O PURPOSE This procedure provides guidance for manually calling out members of the Onsite Emergency Response Organization (ERO). 2.0 APPLICABILITY 2.1 This procedure shall be implemented to ensure suffi-cient personnel are available~to staff onsite Emergency Response Facilities. 2.2 This procedure is applicable to the Shift Supervisor / Duty Emergency Director (DED), Administrative Emergency Coordinator (AEC), Control Room Communicator (CR Communicator), and the Non-Responding Emergency Communicators A-D (NRECs A-D). 3.0 DEFINITIONS 3.1 CALL-OUT Call-out is the methodology that is implemented to ensure proper staffing of the Emergency Response Facilities. 3.2 RADIOLOGICAL EMERGENCY TELEPHONE DIRECTORY (RETD) , WCGS Radiological Emergency Telephone Directory (RETD)
- contains the phone numbers for members of the ERO in five (5) divided sections.
l 3.3 PRIMARY EMERGENCY RESPONSE PERSONNEL i Primary emergency response personnel are those person- , nel that will be called upon first to staff Emergency
- Response Facilities. Primaries are designated with a
{ "P" in the RETD. 3.4 ALTERNATE EMERGENCY RESPONSE PERSONNEL Alternative emergency response personnel are those , personnel that will be called upon to staff Emergency i Response Facilities in the event Primaries are unavailable. Alternates are designated with an "A" in the RETD. l l EPP 01-3.4 Rev. 3 Page 1 of 8 i
7-3.5 POSITION PAGER ( ,j A position pagar is an emergency pager assigned to an emergency response position and which may be carried by any individual assigned to that position in the ERO. Position pagers are identified by listing the paging code next to the emergency response title in Section IV of the RETD. 3.6 PERSONAL PAGER 1 A personal pager is an emergency pagar assigned to an individual within the ERO. Personal pagers are identified by listing the paging code next to the individual's name in Section IV of the RETD. ', 4.0 INSTRUCTIONS 4.1 PRECAUTIONS 4.1.1 Notification by commercial telephone is not success-ful unless contact is actually made with the appro-priate emergency response personnel. 4.1.2 Verify that contact is made with the correct ERO personnel before an emergency message is stated. gs 4.1.3 Individuals with an asterisk adjacent to their name in g Section IV of the RETD shall be called first or as noted in the procedure. 4.1.4 Alternates listed in Section IV of the RETD, are in
- order of call-out preference.
4.1.5 Extension numbers listed in Section IV of the RETD, use the General Office in Wichita as a reference and include one digit access codes. These codes need only be used if applicable. 4.2 INITIAL ACTIONS . 4.2.1 Shift Supervisor /Dutv Emergency Director (DED) 4.2.1.1 Upon the necessity of staffing Emergency Response i Facilities, the Shift Supervisor /DED shall perform the 4 following actions:
/ EPP 01-3.4 Rev. 3 I Page 2 of 8 1
< w i 6,
, \
\'i '
5" 3 l s , 4.2.1.1.1 Assign a CR Communicator the responsibility of call- ({ l out initiatio'n. s pQ ( 4.2.1.E.2 Direct the CR Communicator to initiate the call-out r of s
. personnel in accordance with Step 4.2.2. <
e \ 4.2.2 control RooE (CR) Communicator l k . : . l 4.2.2.1 Complete Attachment 1.0, " Emergency Call-Out Message", = with the required information. NOTE: The applicable parts of the message are to be read when contact is made with ERO personnel i via commercial telephone or the personn,el
=- paging system. J 4.2.2.2 Notify KG&E System Operations'and request that they initiate the applicible call-out process per EPP.01- 'l 3.5, " EOF, HOEC and,Public Information Emergency' i Response Organization Call-Out", for the emergency a classification declared.
4.2.2.3 Notify the Plant Manager via commercial telephone utilizing Section IV of the RETD. l 4.2.2.4 Notify the Call Superintendent via commercial tela-
- phone if unable to contact the Plant-Manager.
l 4.2.2.5 Upon an-Alert or higher emergency classification j notify both NRECA and NRECC via commercial telephone utilizing Section IV of the RETD. 4.2.2.5.1 Notify alternate' individuals if unable to contact the primaries. j 4.2.3 Non-Responding Emergency Communicator (NREC) A and C i 4.2.3.1 Upon notification of ERO Call-Out NRECs A and C shall perform the following actions: , 4.2.3.1.1 Complete Attachment 1.0, " Emergency Call-Out Message," ! with the required information. 4 4.2.3.1.2 Contact NRECs B and D, as applicable, utilizing ) Section IV of the RETD as indicated by your NREC number. ! 4.2.3.1.3 Read the applicable message as determined by Attachment 1.0, " Emergency Call-Out Message." EPP 01-3.4 Rev. 3 Page 3 of 8 { 4 i 4
1 4.2.3.1.4 Contact individuals with an asterisk adjacent to their ! { name listed in Section IV of the RETD. 4.2.3.1.5 Complete notification of primary individuals listed in Section IV of the RETD as indicated by your NREC number. i 4.2.3.1.6 Contact alternates to staff emergency response posi-tions if unable to notify primary individuals. 4.2.3.1.7 Document successful notifications by recording the names of the individuals contacted, emergency response
- positions and contact time on Form EP 3.5-3, "WCGS Emergency Response Personnel Call-Out Log Sheet."
4.2.4 Non-Responding Emergency Communicator (NREC) B and D 4.2.4.1 Upon notification of ERO personnel, Call-Out NRECs B and D shall perform the following actions: : I 4.2.4.1.1 Complete Attachment 1.0, " Emergency Call-Out Message," i with the required information. 4.2.4.1.2 Contact in61viduals with an asterisk adjacent to their name listed in Section IV of the RETD. 4.2.4.1.3 Read the applicable message over the paging system as determined by Attachment 1.0, " Emergency Call-Out Message." 4.2.4.1.4 Complete notification of primary individuals listed in Section IV of the RETD as indicated by your NREC number. 4.2.4.1.5 Contact alternates to staff emergency response posi-tions if unable to notify primary individuals. i
- 4.2.4.1.6 Document successful notifications by recording the J
names of the individuals contacted, emergency response ! positions and contact time on Form EP 3.5-3, "WCGS , Emergency Response Personnel Call-Out Log Sheet." 4.3 SUBSEQUENT ACTIONS 4.3.1 Control Room Communicator (CR Communicator) 4.3.1.1 Submit all completed Attachment 1.0, " Emergency Call-Out Message" and Form EP 3.5-3, "WCGS Emergency Response Personnel Call-Out Log Sheet," to the WCGS Site Emergency Planning Administrator, and report call-out results to the Administrative Emergency l Coordinator. { l i ! l EPP 01-3.4 i l Rev. 3 l l Page 4 of 8 l l l
l l 4.3.2 Non-Responding Emergency Communicator (NREC) A-D f O 4.3.2.1 Report the results of the manual call-out of the ERO to the AEC at the TSC. 4.3.2.2 Submit all completed Attachment 1.0, " Emergency Call-Out Message" and Form EP 3.5-3, "WCGS Emergency Response Personnel Call-Out Log Sheet," to the WCGS Site Emergency Planning Administrator. 4.3.3 Administrative Emergency Coordinator (AEC) 4.3.3.1 Compile the call-out results from the following per-sonnel as they call in their results: Non-Responding Emergency Communicators (NREC) A-D 4.3.3.2 Report the results of the manual call-out of the ERO to the DED.
5.0 REFERENCES
5.1 WCGS Radiological Emergency Response Plan 5.2 WCGS Radiological Emergency Telephona Directory 5.3 EPP 01-3.1, "Immediate Notifications" 5.4 EPP 01-3.5, " EOF, HOEC and Public Information Emergency Response Organization Call-Out" 6.0 RECORDS 6.1 Form EP 3.4-1, " Emergency Call-Out Message" 6.2 Form EP 3.5-3, "WCGS Emergency Response Personnel Call-out Log Sheet" 6.3 The records generated by this procedure during an actual emergency shall be forwarded to the Emergency Planning Coordinator (EPC) at the termination of the amargency. The EPC forwards the records to Records Management for storage. These records will be retained for the life of tha plant. These records shall be considered QA records. 6.4 The records generated by this procedura during drills and exercises shall be forwardeC to the EPC upon termination of the drill or exercise. The EPC shall maintain these records for at least one year. These records shall be considered non-QA records. ( EPP 01-3.4 Rev. 3 Page 5 of 8
f 5 i . ! 7.O ATTACHMENTS 7.1 Attachment 1.O, " Emergency Call-Out Message" l 7-2 Attachment 2.0, "Pager Activation" l l } l 1 i i i
! i i
I l i 4 1 ,! l i i i
', t i !
L 1 i 1 i l I l f l 1 l I I i I l l i s i j i EPP 01-3.4 { Rev. 3 i s i Page 6 of 8 i
f FORM EP 3.4-1 REV. O v Attachment 1.0 (Page 1 of 1) Emergency Call-Out Message NOTE: The message to be read is determined by the means of notification, either by paging or commercial telephone. Paging Only "This is a utility notification, I repeat, this is a utility notification." COMMERCIAL TELEPHONE "This (is/is not) a drill. This is of the KG&E (Circle One) (Name) Emergency Response Organization. At on (Time) (Date) a/an (Unusual Event / Alert / Site Area Emergency / General Emergency) (Circle One) was declared at Wolf Creek Generating Station. You are being notified to assume your Emergency Response Organization position of . Are you able to staff this (ERO position from RETD) position (record response on Form EP 3.5-3)? This (is/is not) (Circle One) a drill." T EPP 01-3.4 Rev. 3 Page 7 of 8
f~ ATTACHMENT 2.0 (Page 1 of 1) Pager Activation NOTE: The geographical area of paging transmissions is determined by the footnotes A, B, C, D, or E, as listed by the paging code. A: Wichita (System Operations) B: Wolf Creek (System Operations) C: Wolf Creek (Wolf Creek) D: Emporia (Wolf Creek) E: Ottawa (Wolf Creek) Reception is adequate within a 25 mile radius about the transmitter. To activate a pager or group of pagers proceed as follows:
- 1. Locate pagar sccess telephone numbers, as deter-mined by the footnotes, A, B, C, D, or E, next to the paging codes in Section IV of the RETD.
- 2. Dial a pagar access telephone number, via touch O 3.
tone dialing. Key punch in paging code or group paging code and j listen for a constant tone indicating the trans-1 mission of an alert beeping through the pagers.
- 4. Broadcast your message (approximately 10 seconds) i immediately after the alert tone ceases.
- 5. Repeat the paging process until all indicated pager access telephone numbers have been accessed for paging.
i EPP 01-3.4 Rev. 3 Page 8 of 8
i
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WOLF CREEK GENERATING STATION RADIOLOGICAL EMERGENCY RESPONSE PLAN IMPLEMENTING PROCEDURE PERSONNEL ACCOUNTABILITY EPP 01-6.1 Revision 4 O l SAldA$ ~ E8ERbT$CY P NG COOR INATOR REVIEW DATE/ '/
/m M EMERGENCY PLANNING ADMINISTRATOR REVIEW
/0/1//S b DATE '
leo /' //- S A DATE PSRC APPROVAL RECOMMEN_DATION i ll 7 /b V.P. NUCLEAR APPROVAL DATE ' RELEASED M 29 ll~ 7'[h DATE
/~'s 1.0 PURPOSE This procedure provides guidance for personnel accountability in the event of a Personnel Accountability Assembly or Exclusion Area Evacuation at Wolf Creek Generating Station (WCGS).
2.0 APPLICABILITY This procedure may be implemented at a Notification cf Unusual Event by direction from the Duty Emergency Director (DED). This procedure shall be implemented following the declaration of an Alert, Site Area Emergency or General Emergency at WCGS. This procedure applies to all personnel on site. 3.0 DEFINITIONS 3.1 PROTECTED AREA That area around the plant which is encompassed by physical barriers and to which access is controlled for security purposes. 3.2 PRIMARY ACCESS CONTROL STATION (PACS) Main Security Building where access to the Protected Area is controlled. 3.3 NON-ESSENTIAL PERSONNEL All personnel not having emergency response organization assignments. 3.4 PERSONNEL ACCOUNTABILITY ASSSEMBLY An assembly of all non-essential personnel from the protected area evacuated to the parking lot adjacent , to the PACS. J 3.5 EXCLUSION AREA EVACUATION I l An evacuation of all non-essential personnel within that area surrounding the Containment Building to a distance of 1200 meters. 4.0 INSTRUCTIONS 4.1 PRECAUTIONS 4.1.1 Individuals requiring an escort shall remain with their escort at all times until released by the escort or security personnel upon exiting the PACS. EPP 01-6.1 Rev. 4 Page 1 of 5 I l
g 4.1.2 Personnel exiting the Protected Area through the PACS shall use the key card reader to log out, when operable. 4.1.3 , Personnel accountability, which includes identification of all personnel missing, must be accomplished within thirty (30) minutes from the time the accountability process is initiated. 4.1.4 In the event of an Exclusion Area Evacuation, Security shall dispatch officers to inform personnel and verify evacuation of the exclusion area. Non-essential personnel should be instructed to leave the site via the site access road and designated County evacuation routes. 4.1.5 If an Exclusion Area Evacuation is to take place, assure personnel have been notified of potential plume direction. The Radiciogical Emergency Coordinator (REC) shall inform the Security Emergency Coordinator (SEC) of appropriate radiological plant data for dissemination to evacuating personnel. 4.1.6 All off-duty emergency response organization personnel that are called in response to an emergency at the WCGS shall report to the WCGS Education Center or
. Emergency Operations Facility (EOF), if activated.
4.2 INITIAL ACTIONS 4.2.1 Upon determining the need for initiating the accountability process, the DED shall: 4.2.1.1 Notify the SEC at the Secondary Alarm Station (SAS) of the decision to conduct a Personnel Accountability Assembly. l 4.2.1.2 Instruct the Control Room Operator to sound the plant Emergency Alarm and to make the announcement in accordance with EPP 01-2.2, " Activation of Emergency i Plan / Organization." l 4.2.1.3 Once personnel accountability is completed assure that search and rescue operations are initiated for unaccounted personnel. The Maintenance Emergency Coordinator (MEC) performs search and rescue in areas inside the Radiation Controlled Area Radiation Controlled Area (RCA). The SEC directs search and rescue for all areas within the Exclusion Area Boundary excluding the RCA. (See EPP 01-9.4,
- " Emergency Team Formation").
I I EPP 01-6.1 Rev. 4 Page 2 of 5 i ___ - . _ _ . _ . __ ___ _ _ _ _ __ __
[N 4.2.2 Upon receiving notification to initiate an evacuation Q and to conduct an accountability of all personnel within the Protected Area, the SEC shall: 4.2.2.1 Note the time and message in the Security Log. 4.2.2.2 Initiate automatic personnel accountability method. NOTE: In the event the security card reader computer i is inoperable, proceed to Manual Personnel ' Accountability Method, Step 4.2.2.7. 4.2.2.3 Instruct the SAS Operator to obtain a list of all essential personnel within the Protected Area from the Security Computer for comparison with the reports from each emergency response facility of essential personnel present. NOTE: A list of essential personnel not accounted for at each emergency response facility will be added to the master list of all personnel not accounted for, to be reported to the DED. 4.2.2.4 Instruct Security Officers to assure personnel processing continues in.an orderly manner at the PACS, j and to segregate and retain personnel who alarm portal l monitors.' Notify the Radiological. Emergency Coordinator (REC) of any contaminated individuals. l 4.2.2.5 Upon completion of the out-processing of non-essential personnel through FACS, instruct the SAS Operator to obtain a list from the security computer of all non-essential personnel in the Protected Area and add the names of any visitors not accounted for from the Visitor Log. , 4.2.2.6 Upon receipt of the initial accountability report from l each emergency response facility Operations Support l Center (OSC) , Technical Support Center (TSC) , and i Control Room, shall notify the AEC, if available, or the DED of all unaccounted for personnel and last location known. 4.2.2.7 Manual Personnel Accountability Method NOTE: Accountability results shall be reported to the AEC or DED no later than thirty (30) minutes after activation of the evacuation order. O' EPP 01-6.1 Rev. 4 Page 3 of 5
4.2.2.7.1 Dispatch a sufficient number of Security Officers to y PACS to perform manual badge processing to assure Personnel Accountability is performed in an orderly and timely manner and to separate and isolate any personnel who alarm portal monitors. Notify the REC of any contaminated individuals. 4.2.2.7.2 Obtain the list of individuals identified by badge slot number. 4.2.2.7.3 Rack exiting personnel badges in the badge racks under j their proper slot numbers. . 4.2.2.7.4 Record and identify all unaccounted for individuals by missing badges 4.2.2.7.5 Obtain personnel accountability reports from Control Room, TSC, and OSC. 4.2.2.7.6 Report any unaccounted for individuals to the AEC or the DED. 4.2.3 OSC Personnel Accountability l 4.2.3.1 Upon arrival, the OSC Supervisor shall: 4.2.3.1.1 Assure that all OSC personnel log in on the Personnel Acccuntability Board upon arrival at the facility and the results are reported to the SEC. 4.2.3.1.2 Designate an individual to initiate a security log to l maintain personnel accountability at the entrance to the OSC. 4.2.4 TSC Personnel Accountability 4.2.4.1 Upon arrival, the AEC shall: 4.2.4.1.1 Assure that all TSC personnel sign in on the TSC' Staffing Status Board upon arrival at the facility and the results are reported to the SEC. 4.2.4.1.2 Designate an individual to initiate a security log to maintain personnel accountability at the entrance to the TSC. 4.2.5 Control Room Personnel Accountability 4.2.5.1 Control Room accountability is accomplished through the Security Card Reader system, when operable. I EPP 01-6.1 Rev. 4 Page 4 of 5
'T 4.2.5.2 In the event the Security Computer System is inoperable, the Shift Supervisor shall:
4.2.5.2.1 Report essential Control Room personnel not accounted for to the SEC. - 4.2.6 Upon arrival at the designated facility, Emergency Response Organization Personnel shall: 4.2.6.1 Log-in on the status board for accountability. OSC - Personnel Accountability Status Board TSC - Emergency Assignment Board Ocntrol Room - Card Reader System 4.3 SUBSEQUENT ACTION 4.3.1 Upon completion of the initial accountability, the SEC shall assure that personnel accountability is maintained throughout the duration of the emergency condition. 4.3.2 Accountability shall be maintained throughout the duration of the emergency by establishing access control and logging entrance and exit via the emergency response facility accountability board. 5.O REFERENCES 5.1 Wolf Creek Generating Station Radiological Emergency Response Plan 5.2 EPP 01-2.2, " Activation of Emergency Plan / Organization 5.3 EPP 01-5.1, " Exclusion Area Evacuation" 5.4 EPP 01-9.4, " Emergency Team Formation" 6.0 RECORDS 6.1 NONE 7.0 ATTACEMENTS 7.1 NONE EPP 01-6.1 Rev. 4 Page 5 of 5
l l , WOLF CREEK GENERATING STATION ! RADIOLOGICAL EMERGENCY RESPONSE PLAN IMPLEMENTING PROCEDURE MANUAL DETERMINATION OF RELEASE RATE EPP 01-7.2 Revision 6 O ( ~
/A EMERBENCY PLANNI COORDINA R REVIEW a x /
DATE / wo AA M /0 ~A W$ b EMERGENCY PLANNING ADMINISTRATOR REVIEW DATE M i'/2 ab ll- S kb PSRC APPROVAL RECOMMENDATION DATE w 'cIm Q A S n/,/'n, V.P. NUCLEAR A ROVAL DAffE ' RELEASED 29 g { - 7_ f(f, DATE O
l c i l 1.0 PURPOSE
, 1.1 This procedure provides guidance and instruction for determining release rates of airborne radioactivity when the Radiological Release Information System (RRIS) is inoperable during emergency conditions at Wolf Creek Generating Station (WCGS).
2.0 APPLICABILITY 2.1 This procedure shall be utilized when the RRIS com-puter is inoperable during emergency conditions. 2.2 The estimated release rate and total releaso values calculated in accordance with this procedure shall be used in conjunction with EPP 01-7.3, " Manual Dose Projection Determination" and EPP 01-10.1, " Protective Action Recommendations", as a basis for determining what offsite protective actions should be recommended to State and County officials. 2.3 This procedure will be implemented by WCGS emergency response personnel in the following manner: 2.3.1 Prior to manning the Technical Support Center (TSC), Control Room personnel who are trained in this pro-l cedure, shall perform these calculations. O) After the TSC is activated, but prior to the ( 2.3.2 activation of the Emergency Operations Facility (EOF), Dose Assessment Coordinator (DAC) shall assure that the RRIS Operator implements this procedure. 2.3.3 Upon activation of the EOF, the Radiological Assess-ment Manager (RAM) shall assure that the RRIS operator implements this procedure. , 3.0 DEFINITIONS 1 3.1 RELEASE RATE The quantity of radioactive material being released to the environment expressed in curies per second (Ci/sec). 3.2 SOURCE TERM The calculated quantity of radioactive material avail-able for release or being released to the environment. EPP 01-7.2 Rev. 6 Page 1 of 21 i i
l l I 1 4.0 INSTRUCTIONS 0 4.1 4.1.1 PRECAUTIONS Calculations contained in this procedure should be reviewed by the DED or REC at the TSC, or the DEM or RAM at the EOF, prior to changing the Radiological l Status Board or dissemination of results to other emergency response personnel. 4.1.2 Upon activation of the EOF, the RRIS Operator and/or Dose Assessment Supervisor (DAS) shall have the RAM or ' DEM review intermediate calculations, when appropriate. 4.1.3 Review of offsite determination of release rates will be performed by the DAC/DAS. 4.2 INITIAL ACTIONS 4.2.1 The DAC or DAS, as appropriate, shall: 4.2.1.1 If RRIS is inoperable, assure the completion of Attachment 1.0, "Onsite Determination of Vent Release Rate," Form EP 7.2-1 4.2.1.2 If vent monitor (s) are inoperable, consider the dis-patch of Onsite Survey Team (s) to collect appropriate Q(h grab samples from the unmonitored locations in accordance with CHM 01-007, " Sampling of Unit and i Radwaste Vents for Radioactive Gases and Tritium" or CHM 01-005, " Exchange of Unit and Radwaste Vent Parti-culate and Iodine Filter Cartridges." 4.2.1.2.1 Recommend that Offsite Monitoring Teams be dispatched to determine offsite dose rates in accordance with EPP 01-8.2, "Offsite Radiological Monitoring." 4.2.1.2.2 Record results on Attachment 1.0. 4.2.1.3 If a steam generator tube rupture is suspected or verified, assure the completion of Attachment 4.0,
" Steam Generator Tube Rupture Release Rate Determina-tion," Form EP 7.2-4.
EPP 01-7.2 Rev. 6 Page 2 of 21 l L
4.2.1.4 As required to calculate the release rate using off-O site data (backcalculations), assure the completion of Attachment 5.0, " Release Rate Calculation Using Offsite Field Team Data (Backcalculations)", Form EP 7.2-5. 4.2.1.5 To determine the containment leak rate contribution to the containment release rate, assure the completion of Attachment 6.0, " Containment Release Rate Calculation," Form EP 7.2-6. 4.2.1.6 Review completed Attachments. 4.2.1.7 Inform REC / RAM or DED/DEM of results. l 4.3 SUBSEQUENT ACTIONS 4.3.1 The DAC/DAS shall: 4.3.1.1 Continue to evaluate the results supplied by the attachments. 4.3.1.2 As new results are received, assure they are posted on the appropriate Radiological Status Boards. l
~
5.0 REFERENCES
~h 5.1 WCGS Radiological Emergency Response Plan \_- 5.2 EPP 01-7.3, " Manual Dose Projection Determination" 5.3 EPP 01-10.1, " Protective Action Recommendations" 5.4 WCGS Final Safety Analysis Report, Chapter 15.0 5.5 CHM 01-005, " Exchange of Unit and Radwaste Vent Particulate and Iodine Filter Cartridges" 5.6 CHM 01-007, " Sampling of Unit and Radwaste Vents for Radioactive Gas and Tritium" 6.0 RECORDS 6.1 Form EP 7.2-1 "Onsite Determination of Vent Release Rate" 6.2 Form EP 7.2-2 " Exhaust Fan Status" 6.3 Form EP 7.2-4 " Steam Generator Tube Rupture Release Rate Determination" b
EPP 01-7.2 Rev. 6 Page 3 of 21
i ( 's) 6.4 Form EP 7.2-5 " Release Rate Calculation Using Offsite ( Field Team Data (Backcalculations)" ' N_ / ' 6.5 Form EP 7.2-6 " Containment Release Rate Calculation" 6.6 The records generated by this procedure during an actual emergency shall be forwarded to the Emergency Planning Coordinator (EPC) at the termination of the emergency. The EPC forwards the records to the WCGS vault for storage. These records will be retained for the life of the plant. These records shall be considered QA records. 6.7 The records generated by this procedure during drills and exercise shall be forwarded to the EPC upon termi-nation of the drill or exercise. The EPC shall main-tain these records for at least one year. These records shall be considered non-QA records. 7.O ATTACHMENTS 7.1 Attachment 1.0, "Onsite Determination of Vent Release Rate"
! 7.2 Attachment 2.0, " Exhaust Fan Status" 7.3 Attachment 3.0, " Design Basis Accident Release Rates" 4
7.4 Attachment 4.0, " Steam Generator Tube Rupture Release Rate Determination" 7.5 Attachment 5.0, " Release Rate Calculation Using Offsite Field Team Data (Backcalculations)" 7.6 Attachment- 6. 0, " Containment Release Rate Calculation" EPP 01-7.2 Rev. 6 Page 4 of 21
EDRM EP 7.2-1 REV. 2 ATTACHMEffr 1.0 l !
- (Page 1 of 2) l ONSITE DETERMINATION OF VENT RELEASE RATE i , (See Back for Instructions) / ) \ ,,
DATE: TIME:
#1 UNIT VEffr FLOR RATE = CEM C Calculated (from Attachtsnt 2.0) Measured
#2 UNIT VEffr CONCElfTRATION = uCi/cc Noble Gas Monitor Plant Sample Default Value
#3 UNIT VEffT CONCENTRATION = uCi/cc Iodine Monitor O elant sample Default value UNIT VENT RELEASE RATE =
#4 ( uCi/ce)( CEM) (4.72E-4) = Ci/sec Noble Gas
#5 ( uCi/cc){ CEM) (4.72E-4) = Ci/sec Iodine
#6 RADRASTE VENT FIDW RATE = CEM C Calculated (from Attachment' 2.0) Measured I
#7 RADRASTE VENT CONCENTRATION = uCi/cc Noble Gas Monitor Plant Sample Default Value
#8 RADNASTE VE!ff CONCENTRATION = uCi/cc Iodine O Monitor Plant Sarnple Default Value RADWASTE VENT RELEASE RATE =
Concentration X Flow Rate X Conversion Factor = Release Pate
#9 ( uCi/cc)( CEM)(4.72E-4) = Ci/sec Noble Gas
#10 ( uCi/ce) ( CEM)(4.72E-4) = Ci/sec Iodine TOTAL RELEASE RATE =
#11 Unit Vent Release , Radwaste Vent Release ,
Total Noble Gas Rate (Noble Gas) Rate (Noble Gas) Release Rate
+ = Ci/sec l Noble Gas
#12 Unit Vent Release , Radwaste Vent Release , Total Iodine Rate (Iodine) Rate (Iodine) Release Rate n
[d \ + = Ci/sec Iodine l Prepared By: EPP 01-7.2 Reviewed By: Rev. 6 Page 5 of 21
EORM EP 7.'2-1 REV. 2 ATTACHMENT 1.0 l
. (Page 2 of 2)
INSTRUCTIONS
#1 Obtain Radiation Monitoring Syste (RMS) readings from the Control Room for the Unit Vent and/or Radwaste Vent flow rate (s) in cubic feet per minute (CEM) and insert at Iten #1 and #6, respectively.
If vent flow rate is unavailable, determine flow rate by using EPP 01-7.2, Attachment 2.0, " Exhaust Fan Status," Form EP 7.2-2.
#2 Obtain the noble gas activity concentration (uCi/cc) of the unit vent from the RMS display. If vent monitor is out of service, refer to Onsite Survey Team data or Attachment 3.0, " Design Basis Accident Release Rates."
#3 Obtain iodine activity concentration (uCi/cc) of the unit vent from the RMS display. If vent monitor is offscale or out of service, refer to Onsite Survey Team data or Attachment 3.0, " Design Basis Accident Release Rates."
#4 Multiply concentration in Item #2 by flow rate in Item #1 and the conversion factor to obtain release rate of noble gas through the unit vent.
#5 Multiply concentration in Item #3 by flow rate in Iten #1 and the conversion factor to obtain release rate of iodine through the unit vent. .
#6 See Item #1, then proceed to Item #7.
i O #7 Obtain the noble gas activity concentration (uCi/cx:) of the radwaste , vent from the RMS display. If vent monitor is out of service, refer to Onsite Survey Team data or Attachment 3.0, " Design Basis Accident Release Rates."
#8 'Obtain iodine activity concentration (uci/cc) of the radwaste vent from the RMS display. If vent monitor is offscale or out of service, refer to Onsite Survey Team data or Attachment 3.0, " Design Basis Accident Release Rates."
#9 Multiply concentration in Item #7 by flow rate in Item #6 and the conversion factor to obtain release rate of noble gas through the radwaste vent.
#10 Maltiply concentration in Item #8 by flow rate in Item #6 and the conversion factor to obtain release rate of iodine through the radwaste vent.
#11 Add the release rate in Item 44 and the release rate in Iten #9 to obtain the total release rate of noble gas.
#12 Add the release rate in Item #5 and the release rate in Iten #10 to obtain the total release rate of iodine.
#13 Report results to either the DAC (TSC) or DAS (EOF) .
! EPP 01-7.2 Rev. 6 Page 6 of 21
.EURM EP 7.2-2 REV. O O
ATTACHMEffr 2.0 EXHAUST FAN STATUS tKYTE: Contact Control Room for fan status Exhaust Fan Design Enter Design System ID Flow Flow on Unit Vent Flow CGLO3A 12,000 (slow) Aux Bldg HVAC 32,000 fast CEM CGLO3B 12,000 (slow) 32,000 fast CEM Control Bldg CGK02A 6,000 CEM HVAC CGK02B 6,000 CEM Fuel Bldg CGG02A 9,000 CEM HVAC CGG02B 9,000 CEM g Condenser Air CGE01B 1,000 CEM j Removal HVAC CGE01A 1,000 CEM Contairrnent CGr01 20,000 CEM Purge Exhaust CGr02 4,000 CEM Main Steam CT03A 17,000 CEM Enclosure Building Exhaust Fans CT 03B 17,000 CEM Unit Vent Total Flow CEM Radwaste Vent Flow Radwaste CGH01A 12,000 CEM Building Exhaust CGH01B 12,000 CEM Radwaste Vent Total Flow CEM EPP 01-7.2
\ Rev. 6 Page 7 of 21 l
ATDGMDir 3.0 (Page 1 of 1) DESIGN BASIS ACrm1FNr REIEASE RATES FSAR Section Type of Accident Release Rate (Ci/sec) Iodine Ratio
- Noble Gas )
15.6-6 I.DCA l Noble Gas 8.27 0.088 ) Iodine 0.73 , 15.1-3 Main Steam Line Break (Most limiting) Noble Gas 0.0031 4.71 Iodine 0.0146 15.2-3 Ioss of Non-emergency AC Noble Gas 0.0031 0.29 Iodine 0.000092 15.3-3 Iccked Rotor Noble Gas 0.83 0.006 Iodine 0.0054 15.4-4 RCEA Ejection Noble Gas 0.146 0.760 Iodine 0.111 15.6-2 CVCS Istdown Line Break Outside Containment p Noble Gas Iodine 0.08 0.00046 0.006 15.6-4 Steam Generator Tube Rupture Case 1 (0-8 Hr.) Nile Gas 0.282 0.51 Iodine 0.145 j 15.7-7 Fuel Handling Accident j Noble Gas 14.31 0.0006 ! Iodine 0.008 , 15.7-3 Waste Gas Decay Tank Rupture Noble Gas 2.99 0.000047 Iodine 0.00014 Steam 'Iurbine Driven Auxilliary Feed Pump PAL 02 Noble Gas 1.40 0.014 Iodine 0.02
- Precaution: If given the Noble Gas whiuation cmly, multiply by ratio to obtain the i Iodine u m iuation. If given the Iodine w-iuation only, divide by l ratio to obtain the Noble Gas wmiuation.
EPP 01-7.2 Rev. 6 i Page 8 of 21
,,----r- -w, ,-naw---,-. - . _ . . - -- , , , . m., . - _ _ - - -
7 m FDIE EP 7.2-4 REV. 1 ATDOMENT 4.0 (Page 1 of 2) STEAM GE2EM1VR TUBE RUPIURE REIEASE RATE IEIERMINATIN (See Back for Instructions) DATE: TIME: Steam Flcar Rate Determination
#1 Release Rate Determination A. Affected Steam Flow (11mVhr) x Release Valve (mr/hr) = lhan.mr Monitor Reading hr E S/G-A x =
S/G-B x = S/G-C x = S/G-D x = m =
#2 Noble Gas Release Rate IUIAL x conversion factor = Noble Gas Release Rate x 1.44E-5 Ci/sw =
Ci/sec mr/hr . lkm/hr
#3 Iodine Release Rate Noble Gas Release Rate x conversion factor = Iodine Release Rate Ci/sec x .51 =
Ci/sec l l Performed By: Re/iewed By: O EPP 01-7.2 Rev. 6 Page 9 of 21
FORM EP 7.2-4 REV. 1 ATDGMENT 4.0 (Page 2 of 2) INmUCTIWS
#1 Obtain the steam flow rate (s) (ll:mVhr) fran the affected steam generator (s) steam line and insert into the first half of the equation.
Obtain the release valve monitor reading (mr/hr) fran the Corfml Room or RMS and insert into the second half of the equation. If the release valve monitors are out of service, insert the appropriate noble gas / iodine ratio frcan EPP 01-7.2, Attachment 3.0, " Design Basis Accident Release Rates." Hultiply the two halves to obtain a release rate determination for each affected steam generator. Add all the release rata datambaticns to obtain a 'IUIAL. 42 Nultiply the 'IDIAL (fran #1) by the conversion factor to obtain the noble gas release rate (Ci/sec).
#3 Multiply the noble gas release rate by the conversion factor to obtain the iodine release rate (Ci/sec).
#4 Report results to DAC (TSC) or EAS (EOF) .
2 I J l l EPP 01-7.2 Rev. 6 Page 10 of 21
l-EORM EP 7.2-5 REV. 2 l ATDOIMDTI 5.0
]' (Page 1 of 8)
REIEASE RATE CAlmIATIN USDC OMSITE FIEID TEAM DATA (Backral mlations) DATE: TIME: IDCATIN
#1 Nhole Body Dose Rate to 'Ibtal Concentration l 3
ReWHr = Ci/m Noble Gas
- Obtain this value frcan the appropriate Whole Body Dose Conversion Factors Graphs
#2 Offsite Carhakation(s) to Plant Release Rate (s)
Coraidation (uCi/oc or Ci/m3) = CVsec X/Q value (sec/m') Cv=3 . Cysec weal I sec/m' Release Rate i #3 uCi/oc . Ci/sec Iodine (NOIE: Use this if d sec/m 3 Release data is Rate available; I Otherwise, pwCaisiil to . Step 4).
#4 Iodine Release Rate Estimate (Offsite Icdine Ccrs.Laticri Unknown) l Note: Skip this step if step 3 is ocupleted.
Noble Gas Release Rate x Attachment 3.0 Iodine / Noble Gas Ratio = Iodine Release Rate l l Ci/sec x = Ci/sec Icxiine Release Rate l l Performed by l Reviewed by: Assumptions:
- 1) Offsite dose rate measured while suinersed in semi-infinite cloud.
- 2) Noble Gas Release Rate = ('1btal Release Rate)-(Iodine Release Rate) 3 IUfE: 1 Ci/m = 1 uCi/oc EPP 01-7.2 Rev. 6 Page 11 of 21
FORM EP 7.2-5 REV. 2 I ' ATIX2] MENT 5.0 (Page 2 of 3) l INSIRDCTIWS
#1 Obtain ganana (closed window) idole body dose rate readings at a location en er near a known X/Q value and record. 'Ihis location is determined by using the maps and s w stability class isopleths available in the sie.upq lockers.
Insert this reading into the left side of the equation. Divide the reading by the ocrwursion factor (see graphs) to obtain the total isotopic concentration at that 1ccation. 'Iha time scale at the botte of the graphs is time since plant shutdown. 'Iha appropriate graphs should be selected haw on whether the closed window dose rate reading is measuring noble gas only, iodine only or a mixture of noble gas and iodine.
#2 Divide the total isotcpic concentration by the known X/Q value to obtain the total release rate. .
l
#3 Obtain the iodine concentration at the location fr a the DAC or DAS.
If reading is unavailable, refer to step #4. - 1 Divide this concentration by the known X/Q value to obtain the iodine release rate.
#4* Refer to EPP 01-7.2, AMar+= ant 3.0 to obtain the appwgiate iodine / noble gas ratio.
Multiply this ratio by the m w h ation in step #1 to obtain the iodine release rate.
#5 Report results to DAC (TSC) or DAS (EOF) .
- Note: Skip this step if step 3 is ocapleted.
f EPP 01-7.2 Rev. 6 Page 12 of 21 i
i 1 1 1 1 m ATIAQ EENI'5.0 (Page 3 of 8) NHOIE IDD'l EOSE CENVERSICH FACIURS (INCT.UDES IODINES) 0-24 Hours 4 10 ~ u y W4 w.g , . ;+., .,. y Jih ,t'=. 6* *L _7Mi&' -
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HOURS EPP 01-7.2 Rev. 6 Page 13 of 21 1
ATIAGMENT 5.0 N-) (Page 4 of 8) l (WHOIE Bt>DY DOSE CWVERSIN FACIORS (INCIIJDE:S IODINES) l i 0-30 Days I A, e. .. , :- 4e- n- 't 3_ way - .
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2 10 . . N 5 10 15 20 25 DAYS EPP 01-7.2 Rev. 6 Page 14 of 21
( ATIACHET 5.0 (Page 5 of 8) NHOIE BODY GAS DOSE FACIURS (IODINES NCTT DiCLUDED)
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1 -___ . e-- - 10 4 8 16 20 M 12 \ HOUHS EPP 01-7.2 Rev. 6 Page 15 of 21
ATIAGMENT 5.0 (Page 6 of 8) MDIE IDDY GAS DOSE FA"IURS (IODINES NOT INCIDDED) l 1 3 0-30 Days _ [ lN& & w.,, .p.j . a; y . . 4-7 d
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10 5 10 15 20 . 25 30 i DAYS EPP 01-7.2 Rev. 6 Page 16 of 21 . , I l l
O/ ATIAGME27I 5.0 (Page 7 of 8) NHOIE BCDY DOSE FACICR (IODINES CNLY) 0-24 Hours 4 b.
. . - _a m .
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10 1 1 16 20 24 p 4 8 12 HOURS (N EPP 01-7.2 Rev. 6 Page 17 of 21 l l
i ATDOM2Tf 5.0
' (Page 8 of 8)
MOIE BODY DOSE FACItR (IODINES OILY) 0-30 Days , 10 4- ggg b , s '--9-"W
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t __. l 2 __= _ to 5 10 15 20 25 30 s DAYS EPP 01-7.2 Pet. 6 Page 18 of 21
1 0 FORM EP 7.2-6 REV. 1 ATDGMENT 6.0 (Page 1 of 3) (INDJNMENT REI. EASE RATE CAIDJIATION DATE: TIME:
- 1. In-Containment Hi-Range Monitor Reading R/hr
- 2. Time Post Accident in Hours hour (s)
- 3. From Table below select the Ci/R/hr fra the block beneath the hour block that cotir.spcsis to hour (s) in 2 above.
Post Reactor Trip Hours 0 1 3 10 24 Ci/R/hr 86 160 270 500 1200 and rcoord (Ci/R/hr)
- 4. Calculation for DBA Isak Rate.
- a. In-centainment Manitors:
I _ _. _ _ _ _ Hi-Range Monitor x R per hour x Factor IEA % = Ci/sec _Randing _ _fr m step 3_ _of free volume _
-1 R/hr x Ci/R/hr x 2.32E-8 sec =
Ci/sec
. b. Containment Air Sanple DBA Isak Rate x Containment Concentration 3 3 1.64 E-3 m /sec x Ci/m = Ci/ w
, 5. Calculation for known or estimated leak rate if otM r tJ a LDA leak rate,
- a. In-Containment Monitors:
-Containment " Curies per - ted-Hi Range Monitor x R per hour x ~Known Flow Rate or $m /sec =
Ci/sec _Raading _ _fr m step 3_ V Volume m' _ of tainment _ R/hr x Ci/R/hr x 3 m /sec/ M= Ci/sec
- b. Containment Air Sample
Isak Rate Containment CLic= itation 3 , m /sec x Ci/m = Ci/sec I ! 'N EPP 01-7.2 l Rev. 6 Page 19 of 21 (
I EOM4 EP 7.2-6 REN. 1 ATIACH4ENT 6.0 (Page 2 of 3) Containment Pressure at ty Containment Pressure at t 2 Flow Rate (m /sec) = 1) - 2I t (sec) = (t 2 -t y in cec.) 3 m /sec = ( ) - ( ) i ( } Performed By: REC Review 3 Available Carc h Volume (m ) l 'g 10 \ 20 \ 30 F \ g 40 - t 50 60 \ 1 70 go" 3 10 10' ! EPP 01-7.2 l Rev. 6 Page 20 of 21 1
1
+
FOIE EP 7.2-6 REV. 1 ATDOBENT 6.0 (Page 3 of 3) I!camx;nCNS FOR CCHPIETING FORM EP 7.2-6
#1 The containment release rate may be estimated ha d on High Range In-Containment Monitor readings and ocupletion of this form.
#2 q/
ft minor 1.64x10 design basismay oc/sec) leagberate of 0.2% m2ltiplied byfree volume known or per 24 hcuts (3.47 estimated containment ocncentrations to quantify this release source if requested by the REC or DED. (RAM or MM at the EDF) . Use Step 4.
#3 If contairment integrity is lost perform the follwing:
#4 Obtain fr m the Operations Status Board the high range monitor reading in ocntainment and record.
#5 Record the initial ocntainment pressure and time (ty) .
#G Record the initial available ocntainment volume y (V ) h h g@.
#7 Obtain an additional containment pressure value at time (t2)* i Record the value. Record the available cor**4% volume (V 2 ) frm the graph.
Flw Rate (m /sec) = W1) - W)2 t
#7a Calculate time difference ( t) in seccn3s.
3
#8 Calculate the flw rate in m /sec and record the flw rate in Step 5.
#9 Calculate the number of Ci/R/hr using Steps 2 and 3. Record in Step 5.
i
#10 Calculate the release rate by performing Step 5. Report data to REC or DED (RAM or DEM at the EOF) . As app vg. late, use the results of this step as input for manual dose calculations as called out in EPP 01-7.3, Attachment 1.0.
EPP 01-7.2 Rev. 6 Page 21 of 21 i
1 WOLF CREEK GENERATING STATION I RADIOLOGICAL EMERGENCY RESPONSE PLAN IMPLEMENTING PROCEDURE MANUAL DOSE PROJECTION DETERMINATION EPP 01-7.3 Revision 6 l
/
EMERGQCTP'
> ING'COOR L
ATOR TtEVMW
-e DAT{
/
c xw_ EMERGENCY PLANNING ADMINISTRATOR REVIEW
-an DATE f A j'/i .c / $ ll-3d6 DATE PSRC APPROVAL RECOMMENDATION b67 $E%
hV.P. NUCLEAR 'qPPROVAL u/7lVs DA'I$ / RELEASED OC29 ll ~ 7"hh DATE
)
v
..-..._. . _. .._.-_.._,,_...m,-__ _ _ . _ , , _ . _ _ , , _ _ . . - - , . - . ,
l l i
- I i
1 1.0 PURPOSE 1 Os 1.1 This procedure provides guidance for estimating I
]
offsite dose rates and integrated doses to the whole , body and thyroid in the event of a release of airborne radioactive material from Wolf Creek Generating Station (WCGS) and the Radioactive Release Information i System (RRIS) becomes inoperable. 2.0 APPLICABILITY 2.1 This procedure shall be implemented by WCGS emergency response personnel in the following manner: 2.1.1 Prior to the activation of the Technical Support Center (TSC), the on-duty Shift Supervisor shall be responsible for implementation of this procedure. 2.1.2 Following the activation of the TSC, but prior to the activation of the Emergency Operations Facility (EOF), the Radiclogical Emergency Coordinator (REC) or the Dose Assessment Coordinator (DAC) shall assure that the RRIS Operator implements this procedure.
. 2.1.3 Upon activation of the EOF, the Radiological Assessment Manager (RAM) or the Dose Assessment
, Supervisor (DAS) shall assure that the RRIS Operator implements this procedure. 3.0 DEFINITIONS 3.1 EXCLUSION AREA BOUNDARY (EAB) That area surrounding the station, in which Kansas Gas and Electric Company (KG&E) has the authority to determine all activities including exclusion or removal of personnel and property from the area. l l 3.2 EMERGENCY PLANNING ZONE (EPZ) i That area surrounding the station in which emergency l preparedness planning is conducted for the protection ! of the public. With respect to protecting the public I from the plume exposure resulting from an incident, the EPZ encompasses an area with a radius of approximately 10 miles surrounding the facility. With , respect to the ingestion exposure pathway, the EPZ l encompasses an area with a radius of about 50' miles. i l EPP 01-7.3 l 1 g'- Rev. 6 l Page 1 of 25
4 3.3 INTEGRATED DOSE That dose of ionizing radiation that has been received during a given period of time by a population or group. , 3.4 PASQUILL ATMOSPHERIC STABILITY CLASSIFICATIONS The Pasquill atmospheric stability classifications are a measure of the stability or instability of an air mass based upon the vertical temperature differential between two points. 3.5 PROJECTED DOSE That dose of ionizing radiation that is likely to be received by a population or group if no protective action measures are implemented. 3.6 PROJECTED INTEGRATED DOSE The summation of the Integrated Dose (previous) and the Projected Dose (future). 3.7 PROTECTIVE ACTIONS l Those emergency measures taken to prevent or minimize I radiological exposures to affected population groups. 3.8 SOURCE TERM The calculated quantity of radioactive material avail-able for release or being released to the environment. i 3.9 X/Q A factor based on meteorological dispersion character-istics which. relates atmospheric radionuclide release rates to offsite air concentrations. 4.0 INSTRUCTIONS 4.1 PRECAUTIONS 4.1.1 The dose projection capabilities of the manual calcu-lation method depend solely upon meteorological data, which become less exact at greater distances from the release point and/or at longer time intervals after the release. EPP 01-7.3
- Rev. 6 Page 2 of 25 l
l l
. . _ _ _ _ _ _ . . . _ , , . . _ _ _ _ _ _ _ _ . . . ~ . . - _ . . _ _ . . , _ - .__ . . _ _ . - - _ . . _ . . _ . . - _ . . _ _ ,
4.1.2 The projected offsite doses calculated in accordance l with this procedure may be used in conjunction with EPP 01-10.1, " Protective Action Recommendations", as a basis for determining any offsite protective actions to be recommended to State and County officials. l 4.1.3 This procedure shall be used in conjunction with EPP 01-7.2, " Manual Determination of Release Rate." l 4.1.4 Wind direction is given as the direction from which the wind is blowing. 4.2 INITIAL ACTIONS 4.2.1 Obtain the dose assessment material from Control Room, TSC or EOF storage lockers. This material consists of the following equipment: 4.2.1.1 A base map covering a 10-mile radius out from WCGS (Plume Exposure Pathway EPZ). 4.2.1.2. A set of six plume overlays, one for each of the six Pasquill atmospheric stability classes. These over-lays are used to estimate the location of the affected downwind areas as a result of the plume expansion. l 4.2.2 Perform offsite dose cal'culations by using Attachment l 1.0, " Manual Calculation Worksheet. l 4.2.3 Upon completion of an offsite dose calculation, compare the whole body and thyroid dose estimates with the values specified in EPP 01-10.1, " Protective Action Recommendations." l 4.2.4 Assure that the Duty Emergency Director (DED) or Duty l Emergency Manager (DEM) is informed of the dose rate and projected integrated whole-body and thyroid doses. 4.3 SUBSEQUENT ACTIONS I 4.3.1 Offsite dose projection calculations should be l performed at least once per hour during the first eight hours after the accident unless it is determined that releases of airborne radioactivity from the plant have been terminated. 4.3.2 Offsite dose projection calculations should be updated if any of the following conditions occur: l i EPP 01-7.3 Rev. 6 Page 3 of 25 l 1
s 4.3.2.1 Release rates increase by more than 25 percent, o 4.3.2.2 Wind direction changes by more than 22.5 , 4.3.2.3 Atmospheric stability classification changes, 4.3.2.4 Wind speed changes by more than 50 percent; or 1 4.3.2.5 Prior to any planned releases. 4.3.3 All personnel performing the offsite dose calculations at the TSC should keep the REC informed as to the status of all offsite dose projection calculation results. As appropriate, the REC shall advise the DED regarding the status of offsite dose calculations and provide recommendations if dose projections warrant implementation of protective actions. 4.3.4 All personnel performing offsite dose calculations at the EOF should keep the RAM informed as to the status of all offsite dose projection calculation results. The RAM shall advise the Duty Emergency Manager (DEM) regarding the status of offsite dose calculations and provide recommendations if dose projections warrant implementation of protective actions. 4.3.5 Attachment 4.0, " Thyroid Dose Equivalent Worksheet," I Form EP 7.3-6, is used to project adult thyroid dose equivalent for individuals making reentries into.known or suspected iodine airborne areas.
5.0 REFERENCES
5.1 WCGS Radiological Emergency Response Plan 5.2 EPP 01-3.2, " Followup Notifications" 5.3 EPP 01-7.1, " Radiological Release Information System" 5.4 EPP 01-7.2, " Manual Determination of Release Rate" 5.5 EPP 01-10.1, " Protective Action Recommendations" 5.6 USNRC Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I", (Rev. 1, October 1977) 5.7 USNRC Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light Water Cooled Reactors", (Rev. 1, July 1977) EPP 01-7.3
% Rev. 6 Page 4 of 25
5.8 USNRC Regulatory Guide 1.145, " Atmospheric Dispersion
$ Models for Potential Accident Consequence Assessments at Nuclear Power Plants", (August 1979) 5.9 USNRC Regulatory Guide 1.23, " Meteorological Programs in Support of Nuclear Power Plants", (September 1980) 5.10 USNRC Regulatory Guide 1.4, " Assumptions Used for '
Evaluating the Potential Radiological Consequences of 1 a Loss of Coolant Accident for Pressurized Water Reactors", (Rev. 2, June 1974) 6.0 RECORDS 6.1 Form EP 7.3-2, " Manual Calculation Worksheet" 6.2 Form EP 7.3-6, " Thyroid Dose Equivalent Worksheet"
< 6.3 Form EP 7.3-7, " Integrated Dose By Sectors" 6.4 The records generated by this procedure during an actual emergency shall be forwarded to the Emergency Planning Coordinator (EPC) at the termination of the emergency. The EPC forwards the records to the WCGS vault for storage. These records will be retained for
- the life of the plant. These records shall be con-sidered QA records.
6.5 The records generated by this procedure during drills and exercise shall be forwarded to the EPC upon termination of the drill or exercise. The EPC shall maintain these records for at least one year. These records shall be considered non-QA records. 7.0 ATTACHMENTS 7.1 Attachment 1.0, " Manual Calculation Worksheet" 7.2 Attachment 2.0, " Atmospheric Stability Classifications" 7.3 Attachment 3.0, "Z Table" 7.4 Attachment 4.0, " Thyroid Dose Equivalent Worksheet" 7.5 Attachment 5.0, " Integrated Dose By Sectors" l EPP 01-7.3 Rev. 6 Page 5 of 25 l _ - _ - - -_ - -____. .. ._. -__ . . - _ _ - . _ _ - - - . , _ _ - . _ _ . . _ _ _ _ _ _ . - - , _ _
FORM EP 7.3-2 REV. 2 ATTACHMENT 1.0 fx MANUAL CALCULATION WORKSHEEf [ (Page 1 of 13)
\ ,
}
x .. - Calculation Performed By: Date/ Time Calculation Reviewed By: I.) INFORMATION REQUIRED Wind Stability Classification Release Rate (Noble Gas) Release Rate (Iodine) II.) A. RR NG sec) + RR IOD sec) = X
+ =
B. (X) X CF WB R**. *Ci* ( hr ) O X = (Insert Product in Column 4) III.) WHOLZ BODY DOSE RATE CALCULATIONS 1 2 3 4 5 M STANCE Z No. . WIND SPEED X/Q Whole Body (Table A or B) 7 (mph or kph) = (sec/M ) x Q = Dose Rate (Rem /Hr) l EAB = x = 2 mile i = x = 5 mile h = x = 10 mile f = x = 5 6 7 8 ; I DISTANCE Whole Body 4 Br. 24 Hr. Dose Rate (Rem /Hr) x4= Int. Dose (Rem) x6= Int. Dose (Rem) Int. Dose (State Time) EAB x4= x6= l 2 mile x4= x6= 1 ! 5 mile x4= x6= l 10 -ile x4= x6= EPP 01-7.3 Rev. 6 (p) v Page 6 of 25
_1 s "% - . (% ( t FORM EP 7.)-2 REV. 2 ATTACHMENT 4.0 (Page 2 of 13) i. I IT.) Gita TRYLOID DOSE RATE CA!IDIATIOIIS 1 9 to , il 12 11 le DISTANCE CF Ree I RR100 (C1/sec) , M g, Rem a e' hr C1 a I/Q (sec/m ) = Dg Y x 4 hr Inc. Dose (Rem) x 24 hr int. Dose (Rem) EAR a x = a4= x6= 2 mile a a = a4= x6-1 5 mile a a = . a4= x6-i j 10 mile u x = =4= x6= i i T.) 3085 RATE PA8m AT1085 BASEB OE FIRIA TEast RATA i 15 16 IF 18 DR I/QA sec/m 3 I/q 3 De ! A Rem /hr u 8 sec/m . = 3 Rem /hr a i = , = i = I .
= 7 =
. = i = l 1. . . . = 1; . + = 4
'U to b M .f.8o M < 'U to .
s O N&~ l o y
% e PJ Ln %
i i
' FORM EP 7.3-2 REV. 2 ATDGMENT 1.0
' (Page 3 of 13)
INSTRUCTICNS FUR USING MANUAL CAI4UIATICH NORMEET I. INFORMATICN REQUIRED KR CAI4UIATICNS A. Date/ Time calculation initiated. B. Wind Stability Maamification is obtained fra the radiological status board or use AthM 2.0 to calculate if unavailable. C. Wind Speed is obtained frm the status board or Control Rom. Enter the value in l Column 2. Circle the ywper units, i.e. 2@h (miles per hour) or kph (kilaneters per hour). D. Radiological Release Rate for Noble Gas ( ) is obtained fr a the Radiological l Status Board or may be de M mined by EPP 01 .2, " Manual Release Rate Determination". E. Radiological Release Rate for Iodine ( y is obtained fr a the Radiological Status Board or may be deMmined by E-7.2, " Manual Release Rate Determination". F. Name of person peufm ming calculation. l G. Name of person ruviewing calculation. l l NII. A. se Add the noble gas release rate (RRg) to the iodine release rate (RRIOD) .
- these results in the next step.
i B. Obtain the t ole body dose conversion factor (CFWB) fra the appropriate dose conversion factor graph and enter value in w e iate blank. Multiply the total release rate by the dose conversion factor. Insert the product in column 4. l l III. INSTRUCTIONS FOR NECIE BOD'l DOSE RATE CAI4UIATICHS , A. Obtain the Z rannbar, refer to Attachment 3.0. Use the table en Attachment 3.0 l t for wir-M-=d entered in Column 2. Circle Wich table the Z value is frm. B. Take the wind = pani runnhar (Column 2) and divide it into the Z runnbar in Column 1 and record in Column 3. 'Ihis is the X/Q number. C. Record the sum obtained in Step II. C. above and record in Column 4. l l EPP 01-7.3 Rev. 6 Page 8 of 25
' FORM EP 7.3-2 REV. 2 l ATDCDENT 1.0 /G (Page 4 of 13) !
t b) INSTRUCTINS FOR USDC MANUAI, CAlmIATIN NtMSHEET
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I l D. Multiply the sum fmn the above step by the X/Q (3) and record in Column 5. Thisl is the Dose Rate for the Nhole Body (WWB)* E. Multiply 4 (5) by four to determine the projected four hour Whole Body dose and record In Column 6. I F. Multiply the four hour projected dose (6) by six to obtain the projected 24 hour Whole Body dose and record in Column 7. NOTE: Column 8 is provided as a spare. It may be user 2 to record other time interval data or running total values, etc. If the column is used, note what time frame at the bott m of the page. G. Perform the above calculaticms for each distance listed. H. Results should be given to the Dcee A=-== ant Supervisor for review prior to beirrJ given to the Radiological Emmu.pcf Coordinator or Radiological Assessment Manager arri posting of status board. IV. INSTRUCTIONS FOR CEIID THYROID DOSE RATE CAIGIATICNS A. Record the Radiological Release Rate for Iodine (RRIOD) tep I. he
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and record in Column 9. B. Record the X/Q values obtained in Step III. B. in Column 11 C. Obtain the child thyroid (CF Dose Conversion Factor (IodiE) ) graph doseand conversionrecord thefactor value frm the Child in Column 10. Thyroid D. Multiply RRm under Column 10 anak(9) by the Dose Conversion Factor for Child 7hyroid (CFthe X/Q (11 ( g ) under Column 12. E. To obtain the four hour Projected Integrated 0111d Thyroid Dose, multiply g (12) by four and record in Column 13 (4 hr Int. Dose) . l EPP 01-7.3 Rev. 6 Page 9 of 25
- FOPM EP 7.3-2 REV. 2 !
ATDOMENT 1.0 (Page 5 of 13) INSUUCTIONS PUR USDG MANUAL CETIATIN WOM3HEET F. 'Ib obtain the 24 hour Projected 0111d 'D1yroid Dose, ultiply the rumbar in Column 13 (4 hr Int. Dose) by six and record in Column 14. G. Results should be given to the Dose amannenant Cbordinator (DAC) or the Dose ! Assessment Supervisor (DAS) for review prior to being given to the Radiological Emergency Coordinator (REC) or Radiological Assessment Manager (PAM) and posting of status board. V. INSTRUCIIONS FOR DOSE RATE CAIGIATIONS BASED N FIELD TEAM DATA l NOTE: Whole Body, 'Ihyroid Dose and Dose Rate mim1ations are based using a direct relationship between dose and X/Q values. 'Iherefore, once reliable field data has been obtained for one known X/Q location all others may be calculated by the calculation worksheet. A. Obtain the Dose Rate ( ) frcan the Radiological Monitoring 'IWun(s) for a known X/Q point and record in lumn 15 (IRg) . B. ReccId the X/Q value for the survey point in Step IV. A. above in Column 17 l (X/QA) *
\ C. Record the X/Q value for the new location for whict1 dose rate is to be determined in Column 16 (X/QB I*
D. Multiply the (15) by X/Q (16) and divide the product by X/QA (17). Record the quotient in lumn 18 ( ). E. DRB (18) is the dose rate at the new point. l F. Repeat Steps A through E for each new point where dose rates are required. t l EPP 01-7.3 Rev. 6 Page 10 of 25 l
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(Page 13 of 13) i l GIID 'IHYROID DOSE CIINERSIN FACIURS (IODINE) 0-30 Days 7 to enrwrr we _:.ga sa wp m a l g,'
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[ Page 18 of 25 l
O ATDGMENT 2.0 (Page 1 of 2) A'DOSIHERIC STABILITY CIASSIFICATIONS O 1.0 For += pmature differential in C. ']he t , r-Las differential is obtained fram the base of the met tower. NOIE: The 60-10m Delta T is the preferred height for determining stability class if it is available. STABILITY ) ) ) CIASS (85-10m) (60-10m) (35-10m) A <-1.42 <-0.95 <-0.47 B -1.42 to -1.27 -0.95 to -0.85 -0.47 to -0.42 C -1.27 to -1.12 -0.85 to -0.75 -0.42 to -0.37 D -1.12 to -0.37 -0.75 to -0.25 -0.37 to -0.12 E -0.37 to 1.12 -0.25 to 0.75 -0.12 to 0.37 F 1.12 to 3.00 .75 to 2.00 0.37 to 1.00 { G > 3.00 > 2.00 > 1.00 f Example: 1. If the T is available for the 85-10 differential and the T is -1.5, the stability class is A. i I
) 2. If the T is available for the 85-10 differential and the
,._./ T is -1.32, the stability class is B.
l 2.0 For +==nture differential in k STABILITY ) ) ) l CIASS (85-10m) (60-10m) (35-10m) l A <-2.56 -1.71 <-0.85 B -2.56 to -2.29 -1.71 to -1.53 -0.85 to -0.76 C ~2.29 to -2.02 -1.53 to -1.35 -0.76 to -0.67 D -2.02 to -0.67 -1.35 to -0.45 -0.67 to -0.22 E -0.67 to 2.02 -0.45 to 1.35 -0.22 to 0.67 F 2.02 to 5.40 1.35 to 3.60 0.67 to 1.80 G > 5.40 > 3.60 > 1.80 t 3.0 If delta T ses1 sors are ii%. Live for the time frame or the arv irL=1t sequence doesn't allow for g-_----iivig to the met tower, use an anemauster fremt the energency kits and the table cm the following page to der areirne the stability class. 4.0 Additional weather informaticn may be obtained fran the National Weather Service in Topeka at (913) 295-2631. EPP 01-7.3 Bev. 6 Page 19 of 25 l
ATI3OIMEKr 2.0 (Page 2 of 2) O S'3RTTTTY CEASS BY OBSERVATION SURFACE WIND DAY NIGHT Light Clear Overcast Broken Clear IGH nVsec Scat. Broken Overcast Clouds Scat. Clouds Clouds Overcast Clouds
<4.5 <2 A A-B B E F 4.5-7.8 2-3.5 A-B B C E F 7.8-10 2-3.5 B B-C C D E 10-13 4.5-6 C C-D D D D
>13 >6 C D D D D O
i i 1 I v l i EPP 01-7.3 f PeV. 6 l - Page 20 of 25 I \
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ATIAGMENT 3.0
} (Page 1 of 3) y Z TABLE For wind speed'in mph use Table A. For wird speed in kn/hr use Table B to determine Z value.
Table A (units are sec. mph) m# Stab. Class A B C D E F G Distance EAB (3/4 mile) 4.79E-6 3.12E-5 7.45E-f 1.32E-4 1.93E-4 3.30E-4 5.03E-4 2 mile 1.33E-6 4.49E-6 1.30E-5 3.77E-5 6.58E-5 1.27E-4 2.22E-4 5 mile 5.81E-7 7.73E-7 2.49E-6 1.09E-5 2.31E-5 5.05E-5 1.03E-4 10 mile 3.11E-7 4.13E-7 7.09E-7 4.18E-6 1.01E-5 2.41E-5 5.47E-5 Table B (units are sec. km/hr) m# Stab. Class 3 B C D E F G Distance EAB (3/4 mile) 7.66E-6 4.99E-5 1.19E-4 2.11E-4 3.08E-4 5.28E-4 8.05E-4 2 mile 2.13E-6 7.19E-6 2.09E-5 6.03E-5 1.05E-4 2.03E-4 3.54E-4 5 mile 9.30E-7 1.24E-6 3.98E-6 1.75E-5 3.70E-5 8.08E-5 1.65E-4 10 mile 4.98E-7 6.62E-7 1.13E-6 6.68E-6 1.61E-5 3.85E-5 8.75E-5
*NOII: For distances other than those listed, refer to the following two pages and indicate, in the " Distance" column of the Manual calculation Worksheet, the actual distance. 'y EPP 01-7.3 Rev. 6 Page 21 of 25
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v) EPP 01-7.3 Pev. 6 Page 23 of 25
r-FORM EP 7.3-6 REV. 1 j O (Page 1 of 1)
'HlYROID DOSE EQUIVAIENT NORIGHEET IOCATIai - Actual DaTE TIME [ Planned on Site Off Site Adult 'Ihyroid Emergency Worker Projection RADIOIODEE DOSE l RADIOIODDE l ISOIOPE FACIOR X CJNCEtERATION = RDycc (REM /uCi) (uCi/cc) inhaled inhaled 131 1.5E+0 132 1.4E-2 133 2.7E-1 134 3.7E-3 135 5.6E-2 SUM 9.13E+5 =
BREATHING EXBDSURE THYROID
-^ RATE X IIJRATION X 'IDIAL = DOSE
[' _/
] (cc/hr) l (heurs) I (RD4/cc) EQUIVALDTI (RDf) 0111d 'Ihyroid Off Site Projection RADIOIODHE DOSE l RADIOIODEE l ISOIOPE FACIOR X CONCENIRATIGT =
RDf/cc (RDf/uCi) (uCi/cc) inhaled inhaled 131 4.4E+0 132 5.2E-2 133 1.0E+0 134 1.4E-2 135 2.lE-1 SUM 4.22E+5 = BREAIHDIG EXEOSURE THYROID RATE X IIJRATIOT X 'IOIAL = DOSE (cc/hr) l (hours) I (REM /cc) DRUIVAIDq (RD4) l Rerarks:
^
/ N EPP 01-7.3
! ! DDSE ASSESSMDC OJORDDGIOR Rev. 6 SIG WIURE Page 24 of 25
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n* V . WOLF CREEK GENERATING STATION RADIOLOGICAL EMERGENCY RESPONSE PLAN IMPLEMENTING PROCEDURE 4 PROTECTIVE ACTION RECOMMENDATIONS EPP 01-10.1 Revision 3 l s i j e.
$ k?/ h
, EMERGENQY PLANN COORDI ATOR REVIEW DATE/ Mh / 8 ' c3 8 ~~8 6 EMERGENCY PLANNING ADMINISTRATOR REVIEW DATE Afri n ll .3N PSRC APPROVAL RZCOMMENDATION DATE JLaAuL h V.P. NUCLEAR [ APPROVAL DAT2 nh/n ' O RELEASE, oc , DATE
1.0 PURPOSE
'-- This procedure provides guidelines for formulating and recommending protective action measures to the appropriate State and County authorities.
2.0 APPLICABILITY 2.1 This procedure is applicable to the Duty Emergency Director (DED), the Duty Emergency Manager (DEM), the radiological assessment personnel who are responsible for evaluating the potential for exceeding protective action guides, and operational / technical personnel who are responsible for accident assessment as well as the potential for containment failure. 2.2 This procedure may be implemented to evaluate the need for recommending protective actions at the Alert or Site Area Emergency classification. This procedure shall be implemented to determine recommendations for protective action (s) at any emergency classification. 3.0 DEFINITIONS
~
3.1 PROJECTED DOSE The dose from ionizing radiation which is likely to be O received by a population group if no protective actions were implemented. 3.2 PROTECTIVE ACTIONS i Those emergency measures taken for the purpose of preventing or minimizing radiological exposures to affected population groups. 3.3 PROTECTIVE ACTION GUIDES (PAG) The projected radiological dose values to individuals in the general population that warrant the implementation of protective actions. Protective actions would be warranted if the expected reduction in individual dose is not offset by the risks to individual safety caused by carrying out that protective action. 3.4 PROTECTIVE ACTION RECOMMENDATION (PAR) The PAR is a recommendation from WCGS based on an l analysis of plant and/or radiological parameters to
- the State of Kansas and Coffey County, to implement protective measures for the public.
[ EPP 01-10.1 Rev. 3 Page 1 of 16 i
. - _ - - - - . ,n - _, , - - . _ . - , _ , -,-.-,-..___.-...-.._,--c,--_..n -.-
[} 3.5 EMERGENCY PLANNING ZONE (EPZ)
The area for which planning is needed to assure that prompt and effective actions can be taken to protect the public in the event of an accidental release of radioactivity from WCGS.
4.0 INSTRUCTIONS e 4.1 PRECAUTIONS 4.1.1 Prior to EOF activation, the DED is responsible for acquiring plant operational assessments and plant radiological assessments to evaluate and recommend protective action (s) to the State of Kansas and Coffey County. 4.1.2 After EOF activation, the DEM is responsible for j acquiring plant operational assessments from the
, Technical Resources Manager (TRM) and plant radiological assessments from the Radiological Assessment Manager (RAM) to evaluate >and recommend protective action (s) to the State of Kansas and Coffey County.
4.1.3 The DED, or the DEM, shall not delegate the authority to transmit protective action recommendations to the O 4.1.4 State of Kansas and Coffey County. Protective actions outlined in this procedure shall be presented to offsite authorities as recommendations , i only. 4.1.4.1 The final decision-making authority regarding protective action (s) shall be Coffey County for State of Local Disaster Emergencies, and the State of Kansas for State of Disaster Emergencies. 4.1.5 Recommendations shall be timely in order to achieve i the desired degree of protection for the public. , 4.2 INITIAL ACTIONS ! 4.2.1 No protective actions to the public are to be expected , for a Notification of Unusue.1 Event classification. 4.2.2 Upon declaration of an Alc)t, Site Area Emergency or General Emergency: 4.2.2.1 The REC / RAM shall: 4.2.2.1.1 Evaluate actual or potential radiological releases. ! EPP 01-10.1 l Rev. 3 Page 2 of 16
r 4.2.2.1.2 Utilize Attachment 1.0, " Radiological Protective Action Recommendation Chart", to prepare a protective action recommendation for submittal to the DED/DEM. 4.2.2.1.3 Inform the DED/DEM of the radiological recommendation. 4.2.2.2 The OEC/TRM shall: 4.2.2.2.1 Evaluate actual or potential radiological releases. 4.2.2.2.2 Utilize Attachment 2.0, " Operational Protective Action Recommendation Chart", to prepara a protective action recommendation for submittal to the DED/DEM. 4.2.2.3 The DED/DEM shall: 4.2.2.3.1 Evaluate the protective action recommendation (s) received from the REC / RAM and the OEC/TRM utilizing
. Attachment 1.0 through 10.0.
l 4.2.2.3.2 Determine the protective action recommendation (s). 4.2.2.3.3 Directs the AEC/ ARM to complete the Immediate Notification Form per the protective action recommendation and assure its transmittal to State and Coffey County officials. 4.3 SUBSEQUENT ACTIONS 4.3.1 The DED/DEM, REC / RAM and OEC/TRM shall continue to monitor plant and radiological conditions. 4.3.2 If changes occur in the plant and radiological conditions, a reevaluation of the protective action recommendations shs11 occur following steps 4.2.1 through 4.2.2.3.3.
5.0 REFERENCES
5.1 Wolf Creek Generating Station Radiological Emergency Response Plan. 5.2 EPP 01-3.1, "Immediate Notifications" 5.3 WCGS Plant Recovery Core Damage Assessment Methodology
- 6.0 RECORDS j NONE EPP 01-10.1 Rev. 3 Page 3 of 16
F 7.0 ATTACHMENTS 7.1 Attachment 1.0, " Radiological Protective Action Recommendation Chart" 7.2 Attachment 2.0, " Operational Protective Action Recommendation Chart" 7.3 Attachment 3.0, " Protective Action Guides - Plume Exposure Pathway" 7.4 Attachment 4.0, " Protective Actions to be Considered for Controlling Consumption of Water from Supplies contaminated with I Radioactivo Materials" l 7.5 Attachment 5.0, " Recommended Protective Actions for Different Accident Phases" , 7.6 Attachment 6.0, " Protective Action Guides - Ingestion J Exposure Pathway" 7.7 Attachment 7.0, " Effective 10-Mile Emergency Planning l Zone" 4 7.8 Attachment 8.0, "10 Mile Populations by l . N 22 1/2 Sectors" s- m 7.9 Attachment 9.0, "10 Mile Populations by Subzones" l l 7.10 Attachment 10.0, "10 Mile Evacuation Times" l i I i l l t i j EPP 01-10.1 Rev. 3 J Page 4 of 16
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ATTACHMENT 1.0 RADIOLOGICAL PROTECTIVE ACTION RECOMMENDATION CHART START W . I ASSESS T R ADIOLOGIC A L PAa& METERS i i i ASSESS no IS TWRE A PLAarf RELSAM us PROGASSS PAmaas7WIS OA PROACfD ftG 1r 4 0ATA ASSSSSENO.N AVAILasta POII 0008 P AA AMSTERS AN0/0A PROACM USE 80P AULT V ALUES TES s PG.A.P.O.RM PmOACTIOes ir EP A P AO'S mo SEPTCTED TO M SICE0000 ftS twACUAft CTa Aase SHELita tuott w .g g, agg Vit APPSCTED Sue 20NES ""I AmeAS THAT CA8sIOT W TMYDOM 888 HEM M EVACUATSO 70 to MILS $ i ,
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ACito - 1 ne ou.m.e o EPP 01-10.1 Rev. 3 l l ( Page 5 of 16 1
I 1 I 1 i R ATTACHMENT 2.0 [V '3 OPERATIONAL PROTECTIVE ACTION RECOMMENDATION CHART I START l OF
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c O ATDOiMENT 3.0 kh (Page 1 of 1) PRorECTIVE ACTICH GUIIES - PIDME EXPOSURE PATHNAY Projected Dose (Rem) PM Actions (Note 1) n=nants General Population: No specific action requi M Monitoring will be Whole Body less than 1 (Note 2). Considerations may continued until the Thyroid less than 5 be given to: extent of the inci-
- 1. An advisory to seek dent can be deter-shelter and await mined and the further instructions, situation fully
- 2. Voluntary evacuation. evaluated.
- 3. Monitor environmental radiation levels.
General Population: 1. An advisory to seek Monitoring will be khole Body 1 to 5 shelter and await initiated so the Thyroid 5 to 25 further instructions. projected dose can
- 2. Evacuation of children be more accurately and p . pant wt:nen. determined and
- 3. Caltrol access. initial action re-
- 4. Monitor envircreantal evaluated for pos-O' radiation levels. sible adjustments.
The situation will be re-evaluated continually ac more data bactnes avail-able. General Population: 1. Mandatory evacuation Monitoring will be hhole Body greater than 5 of populations in a used to confirm the Thyroid greater than 25 predetermined area. evacuation area or.
- 2. Seeking sheltar if as a basis for evacuation is not m aary adjust-innartiately possible. ments in the
- 3. Control access. evacuation area.
Note 1: These actions are reocamended for planning purposes only. Practical action decisions at the time of the incident nust taka the existing conditions into consideration (e.g., weather and plume arrival tima). i Note 2: At the time of the incident, officials may inplement low-impact protective action measures in keeping with the principle of maintaining radiation exposure as low as reasonably achievable (AIARA) . EPP 01-10.1 Rev. 3 Page 7 of 16 . I i l
V e ATDGMENT 4.0 (Page 1 of 1) j PIUTECTIVE ACTICNS 70 BE CCHSIIERED KR CINIROILING
'v CCt!SUMPIICH OF NATER FRCH SUPPIRS CINEAMINAIED WrIH RADIQACTIVE MATERIAIS Projected Dose (Rem) Actions Considered N General Population:
thole Body 1 No action required. Monitoring will be per-i Public annourv'amants of formed to determine that Ihyroid 5 monitoring results and projected concentrations time required for pass- do not result in t h a age of peak ocncentration h _ing PAGs. may be made. General population: Whole Body 1-5 1. Prohibit use of the Initial actions (if time water for human con- permits) and/or re-Thyroid 5-25 sumption. avaluaticr1 of initial
- 2. Manitor ocncentration actions will be based
- levels. upon monitorinJ of water directly fran the supply and after treatment.
\
4 i
References:
EPA-520/1-75-001 Fansas Protective Action Guides l ( EPP 01-10.1 Rev. 3 Page 8 of 16 i
ATDalMDir 5.0 (Page 1 of 1) f i REC 29 ENDED PMIECTIVE ACTIONS s FOR DI.TERDir ACCIMNT PHASES ACCIDDTI PHASE . EXIOSURE PADJ4Y EXAMPLES OF ACTIONS 70 BE RE039EMED Emerg y Inhalation or Evacuation, shelter, ama== ocntrol, PHASE gases, radio- respiration m i ;fcian, prophylaxis iodine, or (thyroid protection) (0.5 to 24 hours), particulate Direct whole body Evacuation, shaltar, ama== control a vev w n yg Ingestion or milk Taka cows off pasture, prevent cows fra drinking surface water, dis-card contaminated milk, or divert to INTERyEDIATE stored Dreducts sucts as cheese PHASE ~ Ingestion of Wash all produce, or inpound pro-fruits duos, delay harvest until approved uneentaminated produce can be _ substituted Ingestion of watec Cut off contaminated supplies, substitute frtaa other sources, f (24 hour filtar, domineralize ( 30 days)g to
\ Whole body exposure l'alocation, hihtien, and inhalation acoess control Ingestion of food Dxsontaminaticn, ocndemnation, or and water centami- d struction of food; deep plowing, nated from the soil cundemnation, or alternate use of IDNG either by resus- land PHAS pension of uptake throudi roots Whole body exposure Relocation, access control, decon-frcan deposition ta aination, fixing of contamina-(over 30 days)* material or inhal- tien, deep plowing, ation of resuspended material.
1 Emergency Phase - Time period of major release and subsequent plume exposure.
' Intermediate Ihase - Time period of moderata continuous release with plume exposure and contamination of envirtalment.
3 long Term Ihase - Recovery period.
* "Iypical" Post-Accident time periods.
References:
Kansas Protective Action Guides EPP 01-10.1 Rev. 3 Page 9 of 16
f ( NITAQ dtr 6.0 l (Page 1 of 2) HUIIrrIVE ACTION GJIDES - DK;ESTION EXPOSURE PA'IHWAY I. Ground Contamination A. Action Ievels
- l. Projected Wiole body dose above the Q - 1 Reut.
- 2. Ground contamination levels = 200 u0i/m at t = 1 hr post-accident.
- 3. Fvpr==nw rate = 12 mRemVhr at 1 meter above ground at t = 1 hr post-accident.
B. W Protective Actions
- 1. Evacmaation of affected areas.
- 2. Restriction of entry to contautinated offsite areas until radiation level has decr==asd to State approved levels.
II. Food art! Water Contamination A. Action Imvels concentration in Milk i or Water (0.5 Rent M (5 Rent W or bone: or bone: 1.5 Remi 15 Ren Total Intaka Via ,
'Ihyroid) 'Ihyroid) all Food and Noter Pasture Grass Pathways (Fresh Welctit)
Preventive Du!trgency Nuclide* Preventive Lpy Preventive Deergency (uci/1) (uci/1) (uci) (uci) (uci/kg) (uci/kg). l I-131 0.012 0.12 0.09 0.9 0.27 2.7 y CIhYroid) CS-137 0.34 3.4 7 70 3.5 35 (itiole Body) Sr-90 0.007 0.08 0.02 0.2 0.7 7 ! (Bone) Sr-89 0.13 1.3 2.6 26 13 130 (Bone) EPP 01-10.1 Rev. 3 Page 10 of 16 , l l
ATTAQs.i2TT 6.0 l (Page 2 of 2) inim;nVE ACTIQi GJIDES - DEESTIOi EXPOSURE PAT 11 HAY B. Recomended Protective Actions Preventive Emergency
- 1. Removal of lactating Isolate food and water from its dairy cows fram contam- introduction into ocueneroe after inated pasture and sub- considering:
stitution of uncontam- 1. Availability of other inated stored feed. possible actions.
- 2. Substitute source of 2. Ies. Lum of particular uim.mLuminated water. food in m trition.
- 3. Withhold contaminated 3. Time and effort to take action.
milk fram market to 4. Availability of other foods. allow radioactive decay.
- 4. Divert fluid milk to producticn of dry Wole 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 W of the population. +
References:
U.S. Food and Drug Jdninistration, Baderal Register, Vol. 43, No. 242, hr 15,1978. EPP 01-10.1 Rev. 3 Page 11 of 16
f ( l p ATTACHMENT 7.0 l EFFECTIVE 10-MILE EMERGENCY PLANNING ZONE
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1 i PLUME EXPOSURE EMERGENCY PLANNING ZONE WOLF CREEK GENER ATING ST ATION F##A EFFECTIVE 2-MILE EPZ I I EFFECTIVE 5-MILE EPZ % I I EFFECTIVE 10-MILE EPZ EPP 01-10.1 Rev. 3 Page 12 of 16
)
i
-l ATTACHMENT 8.0
- 10 MILE POPULATIONS BY 22 1/2 0 SECTORS i
i I
)
A
! E A I 98 i R g i C 84 73 31 3 Q C i 10 ins
] 71 90 i
' D
} I 0 i 11s 9 14 25 6 60 22 25 857 I 16 N 44 17
- 9 63 E I ei i 2 i ?? I 127 1 14 i 4s5 27 76 133 M 11 25 ,
le Q 377 199 W i 87 57 144 ] L G i I :a6:1 l 2361 1 , j K M , 7
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; POPULATION TOTALS
! maa.m6ss Q",b,, I tora mtse %ggjljj ] i1 12 03 3-1 8 37 3 0's 1?14 l 4 l'54 09 84ss i j EPP 01-10.1 Rev. 3 ) Page 13 of 16 I l
O ATTACHMENT 9.0 10 MILE POPULATIONS BY SUBZONES l l l l Evacuation Subzona Evacuation Zone Population l l CTR 0-2 85 N-1 2-5 73 NE-1 2-5 60 E-1 2-5 60 SE-1 2-5 45 S-1 2-5 45 ; SW-1 2-5 3,070 i W-1 2-5 519 ] NW-1 2-5 85 N-2 5 - 10 135 4 NE-2 5 - 10 773 NE-3 5 - 10 150 E-2 5 - 10 80 SE-2 5 - 10 140 SE-3 5 - 10 781 SE-4 5 - 10 60 S-2 5 - 10 100 SW-2 5 - 10 100 l W-2 5 - 10 115 l NW-2 5 - 10 130 !'i Effective 10-Mile Emergency Planning Zone Subtotals: l 0 - 2 mils zone = 85 persons 1 2 - 5 mile zone = 3,957 persons J 5 - 10 mile zone = 2,564 persons i 0 - 10 mile zone - 6,606 persons .I . Total Coffey County population = 9,600 persons 4 i 4 EPP 01-10.1 i Rev. 3 i Page 14 of 16
, ATTACHMENT 10.0 l 10 MILE EVACUATION TIMES (Hours)
AVERAGE WEATHER CONDITIONS (O) v (Page 1 of 2) Effective Effective Effective Subzone 2-mile 5-mile 10-mile CTR 1.2 1.2 1.2 N-1 - 1.2 1.2 NE-1 - 1.2 1.2 E-1 - 1.2 1.2 SE-1 - 1.2 1.2 i S-1 - 1.2 1.2 SW-1 - 1.2 1.2
; W-1 -
1.2 1.2
! NW-1 -
1.2 1.2 JRR - 1.5 1.5
! N-2 - -
1.2 NE-2 - - 1.2 NE-3 - - 1.2 E-2 - - 1.2 SE-2 - - 1.2 SE-3 - - 1.2 SE-4 - - 1.2 S-2 - - 1.2 SW-2 - - 1.2 W-2 - - 1.2 NW-2 - - 1.2 ADVERSE WEATHER CONDITIO*TS v Effective Effective Effective Subzone 2-mile 5-mile 10-mile
. CTR 1.5 1.5 1.5 N-1 -
1.5 1.5 NE-1 - 1.5 1.5 E-1 - 1.5 1.5 SE-1 - 1.5 1.5 S-1 - 1.5 1.5 SW-1 - 1.5 1.5 i W-1 - 1.5 1.5 NW-1 - 1.5 1.5 N-2 - - 1.5 I NE-2 - - 1.5 NE-3 - - 1.5 E-2 - - 1.5 SE-2 - - 1.5 SE-3 - - 1.5 SE-4 - - 1.5 S-2 - - 1.5 SW-2 - - 1.5 W-2 - - 1.5 NW-2 - - 1.5 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 i hours is the estimated using area resources..
) EPP 01-10.1 i U
- See Note Page 2 Rev. 3 I Page 15 of 16
_ . . _ _ _ - - - =. . . . . . . .-. .. - - - .
! ATTACHMENT 10.0 (Page 2 OF 2)
NOTE: A new subzone configuration has been developed for the effective 10 mile EPZ surrounding the WCGS. The number of l subzones has increased from 16 subzones to 21 subzones i 1 I with only a slight change in the boundaries of the ! effective 10-mile EPZ. ; 4, 1 A population study was conducted to determine the ! ! population distribution within the new subzones. The ;
~
1 study indicated the EPZ population had decreased slightly , with minor population shifts within the EPZ. Details are provided in Attachment 9.0 of this procedure. l.
! The longest evacuation time estimates from the previous ,
- subzone configuration will be utilized as conservative j i evacuation time estimates for the new subzones until new [
calculations are performed. New evacuation time estimates will be calculated and incorporated by the end af the second quarter of 1987. The existing evacuation time estimates are considered 4 conservative for the new subzones because: j 1. Populations have decreased for the effective 10-mile ! EPZ i
- 2. Subzone sizes have decreased.
i \ l I i 1 i i i i l l. EPP 01-10.1 i Rev. 3 j Page 16 of 16 l l i i i I , , - . - - ,,,-~,n,n-- .-,__-.n- , _ - , , . . ~ , , - - - . , . - , - _ . - - , -
T l l 1 WOLF CREEK GENERATING STATION RADIOLOGICAL EMERGENCY RESPONSE PLAN IMPLEMENTING PROCEDURE STATUS BOARDS EPP 01-11.2 Revision 3 l l O 3 EMERGENCY P NG COO TRATUR REVIEW DA% / m /s PC l EMERGENCY PLANNING ADMINISTRATOR REVIEW DATE M//E ^) ll-3 kh PSRC APPROVAL RECOMMEN TION DATE d$dddL V.P.'NUCLEA / APPROVAL , nh/r6 DATE/ RELEASED DC29 l l- 7463 DATE 1 l \ i i
1.0 PURPOSE h i The purpose of this procedure is to provide instruc-
'- ,/ tions for entering, keeping current and finally disposing of the information on Status Boards during an emergency.
2.0 APPLICABILITY This procedure applies to Operations Assessment Coordinator (OAC), Radiological Assessment Coordinator (RAC), and the Status Board Recorders responsible for the Operations Status Boards, Radiological Status Boards, 10-mile EPZ Maps and 50- mile EPZ Maps in the Technical Support Center (TSC) and Emergency Operations Facility (EOF) . It also provides information for persons making entries on any status board in any of the emergency response facilities. 3.0 DEFINITIONS 3.1 STATUS BOARD 3.1.1 A status board is intended to provide readily visible, easily updated, summary information on some aspect of emergency conditions at Wolf Creek Generating Station (WCGS). It may be a map, a preformatted chart, a f-~g blank board, or other suitable format. Attachment 1.0 ( j lists all status boards in the emergency response
\s facilities.
4.0 INSTRUCTIONS 4.1 PRECAUTIONS 1 NONE 4.2 GENERAL 4.2.1 The Operations Assessment Coordinator (OAC) shall provide current information for the Operations Status Board by completing the Operations Status Board Sheet (Attachment 2.0). The sheets should be numbered in sequence. The TSC Operations Status Board Recorder shall update the board immediately and then file the
- sheets in order in the " Emergency Response and Recovery Activity Record" binder.
1 EPP 01-11.2
Rev. 3 Page 1 of 19
4.2.2 When the EOF is activated, the Control Room Communicator shall provide update information to the
' [-~ EOF Operations Status Board Recorder as well as the i
TSC Operations Status Board Recorder via a three-way l phone line. He shall provide update information at intervals of no more than 15 minutes. The EOF Operations Status Board Recorder shall update his board immediately; then he shall transmit the update to the HOEC.
!' 4.2.3 The Radiological Status Boards shall be updated in the same manner as the Operations Status Boards with the Radiological Assessment Coordinator (RAC), providing , update information using the Radiological Status Board Sheet (Attachment 3.0).. The TSC Radiological Status Board Recorder shall also update the 10- and 50-Mile EPZ Maps (Attachment 5.0) using information provided by the RAC. The TSC Radiological Status Board Recorder shall use the Health Physics Line (ash phone) to transmit information to the EOF Radiological Status Board Recorder.
4.2.4 Personnel entering the TSC or EOF shall sign in on the Staffing Status Board (Attachments 6.0 and 7.0) located near the entrance to each facility. Personnel
. . entering the OSC shall sign in on the Personnel l Accountability Board (Attachment 9.0).
4.2.5 The Sequence of Events Board (Attachment 10.0), and the Operations and Radiological Trending Boards (Attachment 11.0) may be used in the TSC and EOF to
- track events as required.
4.2.6 Floor plans of the major buildings in the power block
- are provided in the Operations Support Center (OSC),
TSC, and EOF. These may be used to track radiological conditions and other situations as needed, i i 4.2.7 The HP Activation Task Status Board in the OSC shall ! be used as described in EPP 01-4.2, " Operations Support Center Activation / Operation".
! 4.2.8 In the OSC, the Staffing Status Board (Attachment 8.0) shall be used to record team assignments.
l
5.0 REFERENCES
- 5.1 Wolf Creek Generating Station Radiological Emergency Response Plan 5.2 EPP 01-4.2, " Operations Support Center Activation /
; Operation" EPP 01-11.2 l Rev. 3 Page 2 of 19 i
I i
I 6.0 RECORDS 6.1 Form EP 11.2-2, " Operations Status Board Sheet" 6.2 Form EP 11.2-3, "TSC Radiological Status Board Sheet" 6.3 Form EP 11.2-4, " EOF Radiological Status Board Sheet" 6.4 The records generated by this procedure during an actual emergency shall be forwarded to the Emergency Planning Coordinator (EPC) at the termination of the emergency. The EPC forwards the records to Records Management for storage. These records will be retained for the life of the plant. These records shall be considered QA records. 6.5 The records generated by this procedure during drills and exercises shall be forwarded to the EPC upon termination of the drill or exercise. The EPC shall maintain these records for at least one year. These records shall be considered non-QA records. 7.0 ATTACHMENTS 7.1 Attachment 1.0, " Status Board Summary" 7.2 Attachment 2.0, " Operations Status Board / Sheet" 7.3 Attachment 3.0, "TSC Radiological Status Board / Sheet" 7.4 Attachment 4.0, " EOF Radiolog'ical Status Board / Sheet" 7.6 Attachment 5.0, "EPZ Maps" 7.6 Attachment 6.0, "TSC Staffing Status Board" 7.7 Attachment 7.0, " EOF Staffing Status Board" 7.8 Attachment 8.0, "OSC Staffing Status Board" 7.9 Attachment 9.0, "OSC Personnel Accountability Board" 7.10 Attachment 10.0, " Sequence of Events Board" 7.11 Attachment 11.0, " Operations and Radiological Trending Boards" l I EPP 01-11.2 Rev. 3 Page 3 of 19 i l
_ . .-. .- _ _ - ._. - - . _. .-~ ATTACHMENT 1.0 (Page 1 of 1) 1 STATUS BOARD
SUMMARY
I - Technical Support Cente. l Radiological Status Boards l l Operations Status Board l Floor plans of power block buildings EPZ Maps 10-Mile + 4 overlays 50-Mile Staffing Status Board Significant Events Board Trending Boards: Operations, Radiological Emergency Operations Facility O As TSC Operations Support Center Floor plans of power block buildings Personnel Accountability Board (for sign-ins) Staffing Status Board (for team assignments) HP Activation Task Status Board , 1 EPP 01-11.2 Rev. 3 l Page 4 of 19
FORM EP 11.2-2 REV. 1 / ) \ / ATTACHMENT 2.0 (Page 1 of 1) OPERATIONS STATUS BOARD / SHEET ST ATUS SO ARDS (EOF) PAGE 6 of S wE$T WALL ...............<.. L ATEST POSTING: DATE ACTIV ATED : DATE OPERATIONS STATUS TIM E RCS STEAM GENER ATORS ECCS CONT AINMENT CONDITIONS CSF PRESSURE PetG STM GEN. A 8 C, D PUMPS PRESSURE PSIG Sa ggy T AVG 'F TEMP 'F RvLIS LVL g HUMIOITY % SG CCP PRZR LVL g PRES (pSig) ____ RADLVL RINR p EST RCS LE AK GPM MStV E ____ PHASE A ISO CONT T/C (Hl/ AVG) i % AFwFLOW SPR AY PHASE B ISO CORON CON PPM RwST LEVEL _t VENT ISO LOOP STATUS 08ILSISL I sue CRrT MMH % VOL
$ E O "
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~ ACCUM LEVEL % IN WOTOR 1_ MOTOR 2 TURS- CORE A - 8C g
- COOLING T
u SUPPORT SYSTEMS - COMMENTS: 1 e ESw PUMP STATUS: HE AT SINK ECp 8 IUI ACCUM PRE 84PSIG) (OMIOFF) EMERGENCY SUS ENERG12ED A 8 C RCS Rs TRIP S HRS ~O TRAIN A TRAIN 8 ~ ~ ~ INTE GRfTY
% ~~--
% POWER @ TRIP YES NO CONT OFFSITE POWER DIESEL GEN INVENTORY AV AIL ASLE COMMENTS:
Note: This Attachment shows the EOF Ops. Status Board format. The TSC Opu. Status Board contains the same information in a slightly different format. m EPP 01-11.2 Rev. 3 Page 5 of 19
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HAUlOLOGICAL STATUS 80AHD m O ~ RELEASE STATUS PROTECTIVE ACTIONS O NONE ANTICIPATED D POTENTIAL O IN PROGRESS O TERMINATED ( ) = TIME h RECOMMENDE D P SHE LT E R EVACUATE P SOURCE TERM DATA N l u O RADIATION MONITORING SYSTEM O SAMPLE ANALYSIS O OFFSITE FIELD DATA O FSAR SOURCE TERM ESilMATING w g g O
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PLUME EXPOSURE EMERGENCY PLANNING ZONE WOLF CREEK GENER ATING ST ATION E EFFECTIVE 2-MILE EPZ I I EFFECTIVE 5-MILE EPZ % F 1 EFFECTIVE 10-MILE EPZ , v) EPP 01-11.2 Rev. 3 Page 11 of 19
ATTACHMENT 5.0 (Page 2 of 2) EPZ MAPS
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50-MILE EPZ MAP EPP 01-11.2 Rev. 3 Page 12 of 19
arta es-ese-e, new stee TSC STAFFING STATUS BOARD DUTY EMERGENCY NRC ---- DIRECTOR (DED) TSC CLERK /LOGKEECER i l I l I I I I PUBLIC INFORMATION RADIOLOGICAL ADMINISTRATIVE OPERATIONS MAINTENANCE ' COORDINATOR EMERGENCY EMERGENCY EMERGENCY EMERGENCY COORDINATOR COORDINATOR COOROINATOR COORDINATOR (REC) (AEC) (OEC) (MEC) Q i 01
^
SECURITY EMERGENCY 3 Yh M tQ O
; TSC COORDIN ATOR CHEMISTRY OPERATIONS SUPPORT Zeg U
gm COMMUNICATORS COORDINATOR CENTER to 2: EOF COORDINATOR hk m me . N RADIOLOGICAL DOSE OPERATIONS TECNNICAL ASSESSMENT ASSESSMENT ASSESSMENT SUPPORT U COORDINATOR CO OR DINATOR CO OR DINATOR COORDINATOR MWM Nem j[T TSC FIELD RADIOLOGICAL RRIS OPERATION ENelNEERING o TEAM STATUS OPERATORS STATUS TEAM PwP COMMUNICATORS RECORDER RECORDER w I O P to O
v ' STATUS SOARDS (EOF) PAGE S of 8 WEST W ALL EPLn so-see-3, arv s/as STAFFING STATUS NRC DUTV EMER4ENCY EOF MANAGER (DEM) CL ER K tLO SM E E PER p---------------_ l l I I I I PUStsC RADIOLOelCAL ADMBNGSTR A TIVE I TE CHNIC AL INFORMATeoM AseEsseleser RESOURCES RRSOvects l COORDIIIATOR MADIAGER MARAGER MANAGER M b o I m i u) l H >
>^H I EOF OPER ATIONAL mmh I Mpp SECURITY ,, EOF STATUS SOARD l-t c O STATE OF KANS AS SUPERT960R _ COMMU804CATORS RECORDER Z (D M O ;E PM 03 Z HOH
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(/3 w O U$ O R ADIOLOelC AL POSE U ASSESSMERT 4SSESSMENT EOF ERFIS SUPERVISOR SUPERVISOR COORDNIATOR OPERATOR m :tf M D (D m A<m (D
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~~
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ATTACHMENT 9.0 (Page 1 of 1) OSC PERSONNEL ACCOUNTABILITY BOARD l S
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ATTACHMENT 10.0 (Page 1 of 2) l SEQUENCE OF EVENTS BOARD A E o E E l A
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,O EPP 01-11.2 Rev. 3 Page 17 of 19 ., - _ _ , __. . . . _ , . _ _ _ _ . . _ _ . - . _ _ _ - . . _ _ _ _ . . _ _ . . _ _ ___ _ _ _ _ _ . . _ . -.__ _ __ __ .___ ~. _ ___ _
ATTACHMENT 10.0 (Page 2 of 2) O EXAMPLES OF INFORMATION TO BE PIACED ON SEQUENCE OF EVENTS BOARD (To be used as Guidelines - Not Requirements)
- 1. Injuries
- Who was injured, how were they injured; were they l contaminated; when were they injured; did they have to be decontaminated; were they sent to a hospital; what hospital, when did they leave the site, when was their arrival at the hospital confirmed; what is their status?
- 2. Emergency Classification When did it change, what caused the classification to change; when were other facilities activated?
- 3. Evacuation / Protection Action What zones were recommended evacuated by KG&E, what zones were actually evacuated by the State and County; when were roadblocks put up; when did the EBS notification go off; when did people start arriving at evacuation centers; when was evacuation of an area completed; was airspace closed off; were protection action recommendations made; when were they 4 accepted; when were major notifications made; when were field teams sent out?
I
- 4. Plant Status What major component damage has occurred which could degrade the plant further; when were repair attempts made; when was it repaired? Did any explosions, releases, etc. occur?
When? When was the release terminated?
- 5. Miscellaneous Are any people missing; did any security problems occur, is the Governor flying in, etc? Did a shift change occur?
EPP 01-11.2 Rev. 3 Page 18 of 19
1 s ATTACHMENT 11.0
- (Page 1 of 1)
- OPERATIONS AND RADIOLOGICAL TRENDING BOARDS t
} 1 , 1 i 1 l 4 l 4 i t i i l } 1 1 i i i i 4 4 i. 4 I I ; i i (These boards use a variety of transparent overlay graphs. The boards themselves are blank.) EPP 01-11.2 Rev. 3 Page 19 of 19 i
. I i
WOLF CREEK GENERATING STATION RADIOLOGICAL EMERGENCY RESPONSE PLAN IMPLEMENTING PROCEDURE REENTRY AND RECOVERY OPERATIONS EPP 01-12.1 Revision 4 l O 9 A AJM EMERG1@CY 7
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NG' COOR I1TATOR RTVIEW A ff / DKTE //
/W kvem EMERGENCY PLANNING ADMINISTRATOR REVIEW
/0 /2 / /%
DATE ' ' s ML b /l-Skh PSRC APPROVAL PICOMMENDATION DATE r
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DATE / RELEASED DC29 l1- 7-8h DATE
I l
. )
1.0 PURPOSE This procedure identifies the required actions, responsibilities and interfaces for Wolf Creek i Generating Station (WCGS) personnel reentering ' evacuated onsite areas. It also provides guidance for I
- l. the subsequent recovery phase of emergency response activities, including the transition from the WCGS Emergency Organization to the WCGS Recovery Organization.
2.0 APPLICABILITY 4 This procedure applies to the WCGS Emergency Organization and the WCGS Recovery Organization for those reentry and recovery activities required to restore the plant to normal operating conditions. 3.0 DEFINITIONS 3.1 REENTRY The initial reentry into evacuated onsite areas for l the purpose of information gathering and l
- surveillance. For guidance regarding emergency repair activities, refer to EPP 01-9.4.
3.2 RECOVERY I Post-emergency efforts initiated to restore WCGS to full operation or place the plant in a safe shutdown condition until full operation can be resumed. 4.0 INSTRUCTIONS 4.1 PRECAUTIONS , 4.1.1 The Duty Emergency Manager (DEM) and the Duty Emergency Director (DED) have the responsibility for ' authorizing reentry and/or recovery operations. The conditions listed in Attachment 2.0 shall serve as guidelines for when to initiate recovery efforts. l l EPP 01-12.1 f. i Rev. 4 Page 1 of 19 l 4
k 4.1.2 If an Alert or Site Area Emergency has been declared, the DED or the DEM, as appropriate, shall discuss i either downgrading the emergency classification or establishing the WCGS Recovery Organization with the State Division of Emergency Preparedness, the Chairman of the Coffey County Commissioners, and the NRC prior to either action. Concurrence is not required. l 4.1.2.1 If a General Emergency has been reached, NRC and State of Kansas, Division of Emergency Preparedness concurrence shall be obtained prior to downgrading the event or establishing the WCGS Recovery Organization. 4.1.3 Checklists shall be reviewed periodically to ensure that appropriate updates and calculations are performed. 4.2 REENTRY OPERATIONS 4.2.1 Reentry team personnel exposures in excess of 10CFR, Part 20 limits may be authorized by the Duty Emergency Manager or Duty Emergency Director after discussions with the Radiological Assessment Manager or Radiological Emergency Coordinator. 4.2.2 The Radiological Emergency Coordinator (REC) or his designee has the following responsibilities: 4.2.2.1 Implement the Attachment 3.0, " Radiological Emergency Coordinator Checklist", Form EP 12.1-3. 4.2.2.2 Evaluate the emergency conditions to determine the approximate dose rates and permissible stay times in the affected onsite areas. 4.2.2.3 Brief the Reentry Team members concerning the nature of the emergency conditions and the possibility of hazards which may be encountered during reentry operations. 4.2.2.4 Instruct the Reentry Team regarding reentry operations in the affected area. 4.2.2.5 Supervise the initial entry of the Reentry Teams into any affected area and any subsequent entries until all radiation areas have been properly marked. 4.2.2.6 Select routes for entry into any affected area based upon radiological information available. 4.2.2.7 Assure that all Reentry Team personnel are properly equipped with protective clothing, high-range dosimeters, low-range dosimeters, TLD's, respiratory devices, and other protective equipment as required. EPP 01-12.1 Rev. 4 i Page 2 of 19
~
4.2.2.8 Specify self-monitoring and decontamination procedures [~s (,,)
\ for the Reentry Teams if conditions dictate that such techniques and procedures should be used.
4.2.2.9 Maintain a written log of all reentries into affected onsite areas. 4.2.3 The Reentry Team Leader has the following responsibilities: 4.2.3.1 Receive a briefing on plant conditions and radiological conditions and take assignments from the REC or his designee. 4.2.3.2 Obtain the necessary survey equipment as directed by the Radiological Emergency Coordinator or his designee. 4.2.4 Upon entry into the plant, the Reentry Team shall: 4.2.4.1 Consist of a minimum of two persons, at least one of whom shall be a Health Physics Technician. 4.2.4.2 Be within the sight of at least one other team member. 4.2.4.3 Conduct a visual survey for hazards or potential , hazards associated with the recovery operation. ('] 4.2.4.4 Conduct a radiation survey of specified plant areas and l define radiological problem areas. 4.2.4.5 Isolate areas of the plant by using appropriate warning signs and rope barriers. 4.2.4.6 Maintain a log of all events during the reentry operations. 4.2.5 If the monitored dose rates encountered during the reentry exceed the limits established by the DED, the reentry team shall return to the point from which it was dispatched. 4.2.6 The DED and REC shall review the reentry activity and results. 4.3 TRANSITION TO RECOVERY 4.3.1 The transition from the WCGS Emergency Organization to the WCGS Recovery Organization is dictated by existing plant operational and radiological conditions as specified in Attachment 2.0, " Guidelines Initiating Recovery Operations". The DEM and the DED shall initiate transition to the recovery phase based on : these conditions. ! 1 EPP 01-12.1 Rev. 4 Page 3 of 19
4.3.2 The DEM shall assume the role of Recovery Manager and O 4.3.3 direct the transition from the WCGS Emergency Organization to the WCGS Recovery Organization. The WCGS Emergency Organization personnel shall continue their previous functional assignments until ! they are formally relieved and records are transferred. 4.3.4 Recovery operations shall be conducted in compliance with normal operational exposure levels or as specified in 10 CFR Part 20. 4.3.5 .The WCGS Recovery Organization is shown as Attachment 1.0, "WCGS Recovery Organization". The following + transitions in duties shall be made. 1 Emergency Response Title Recoverv Organization Title 1 Duty Emergency Manager Recovery Manager Duty Emergency Director Plant Manager Technical Resources Manager Technical Manager Radiological Assessment Radiation Protection /Radwaste Manager Manager Wolf Creek Public Information Public Information Officer , Officer Administrative Resources Manager' Administration and Logistics Manager ( WCGS Emergency Organization WCGS Normal Organization 4.4 RECOVERY ORGANIZATION
~
4 4.4.1 The Recovery Manager has the following responsibilities: 4.4.1.1 Implement Attachment 4.0, " Recovery Manager Checklist", Form EP 12.1-4. 4.4.1.2 Provide overall direction and control of the WCGS Recovery Organization. 4.4.1.3 Authorize funds and the utilization of manpower and equipment necessary to accomplish the recovery operation. 4.4.1.4 Notify offsite authorities that a recovery operation will be initiated and indicate any potential impact offsite. ! 4.4.1.5 Provide additional offsite notification whenever recovery operations have potential offsite effects. EPP 01-12.1 Rev. 4 Page 4 of 19
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4.4.2 Technical Manager 4.4.2.1 The Technical Manager provides technical personnel in the support of plant recovery and establishment of normal operation. The Technical Manager has the following responsibilities: 4.4.2.2 Implement the Attachment 5.0, " Technical Manager Checklist", Form EP 12.1-5. 4.4.2.3 Provide engineering and technical specialists to perform support activities. ] 4.4.2.4 Assist the Radiation Protection /Radwaste Manager with i engineering support for required modifications of
; radwaste systems.
4.4.2.5 Provide expertise for repair and modification activities. i 4.4.2.6 Provida qualified personnel to augment repair teams. 4.4.3 Plant Manager i 4.4.3.1 The Plant Manager is responsible for directing the normal WCGS Organization in activities necessary to , restore the plant to an operational status. O , 4.4.3.2 The Plant Manager and or his organization has the following responsibilities: , -4.4.3.2.1 Implement the Attachment 6.0, " Plant Manager Checklist", Form EP 12.1-6. 4.4.3.2.2 Implement the Attachment 4.0, " Recovery Manager Checklist," Form EP 12.1-4, if acting as the DEM. i 4.4.3.2.3 Direct onsite recovery activities. i 4.4.3.2.4 Provide personnel in support of shift operations. 4 4.4.3.2.5 Analyze plant systems, instruments and control problems i resulting from the accident, and develop modification ( and repair plans for their restoration / resolution. 4.4.3.2.6 Analyze conditions and develop guidance for operations personnel regarding core protection. 4.4.3.2.7 Develop recovery procedures for special operations. 4.4.3.3 Assist with an analysis of circumstances leading up to, and resulting from, the emergency.
) EPP 01-12.1 Rev. 4 Page 5 of 19 l
4.4.4 Radiation Protection /Radwaste Manager ( )i 4.4.4.1 The Radiation Protection /Radwaste Manager (RP/RM) is responsible for managing radwasta and radiological controls. The RP/RM has the following responsibilities: 4.4.4.2 Implement Attachment 7.0, " Radiation Protection /Radwaste Manager Checklist", Form EP 12.1-7. 4.4.4.3 Develop plans and procedures for processing, sampling or controlling liquid, gaseous, and solid wastes. 4.4.4.4 Develop design modifications for waste processing. , 4.4.4.5 Direct radiological exposure control for recovery activities. 4.4.4.6 Support offsite sampling programs, dose assessments, dose management, and radiation protection programs. 4.4.4.7 Calculate the total cumulative population exposure. 4.4.5 Public Information Officer The Public Information Officer is responsible for coordinating the flow of media information. As appropriate, the Public Information Officer will O coordinate public information efforts with Coffey County and the State of Kansas. 4.4.6 Administration and Logistics Manager The Administration and Logistics Manager has the following responsibilities. ! 4.4.6.1 Implement Attachment 8.0, " Administrative and Logistics Manager Checklist", Form EP 12.1-8. 4.4.6.2 Establish a shift schedule and identify alternates to the recovery organization. 4.4.6.3 Provide administrative support, equipment and communications support. ! EPP 01-12.1 Rev. 4 Page 6 of 19
4.4.7 Consultant / Vendor Managers The Nuclear Steam Supply System supplier (Westinghouse) , and the Architect / Engineer (Bechtel) have prepared i plans for supplying personnel to assist in recovery. ) The consultants and vendors will initially report to the Administration and Logistics Manager. l 4.4.8 Regional Utility Support The Recovery Manager has the responsibility for l requesting support from Union Electric Company, I signatory companies of the INPO Voluntary Assistance Agreement, and other organizations. This regional utility support will initially be communicated through the Administration and Logistics Manager. ! 4.5 SUBSEQUENT ACTIONS 4.5.3 Each member of the WCGS Recovery Organization shall maintain a record of pertinent recovery activities. Information such as the date, time, and a brief summary of the activity performed shall be noted using Attachment 9.0, " Emergency Response and Recovery Activities Record Sheet," Form EP 12.1-9. Completed sheets shall be placed in an Emergency Response and Recovery Activities Record Binder, which shall be maintained at the work station so as to ensure the continuity of operation during the turnover of personnel. 4.5.4 Each member of the WCGS Recovery Organization shall log all incoming and outgoing communications with individuals, officials, and agencies which are related to recovery efforts. Information such as the date, time of communication, name(s) and affiliation (s) of person (s) called or calling, and any pertinent remarks should be noted using Attachment 10.0, " Emergency Recovery Communications Log Sheet," Form EP 12.1-10. Completed sheets shall be placed in an Emergency Response and Recovery Activities Record Binder, which shall be maintained at the work station so as to ensure the continuity of operations during the turnover of personnel-
5.0 REFERENCES
5.1 Wolf Creek Generating Station Radiological Emergency Response Plan i EPP 01-12.1 Rev. 4 Page 7 of 19 l 1
1 6.0 RECORDS. 6.1 Form EP 12.1-3, " Radiological Emergency Coordinator Checklist" 6.2 Form EP 12.1-4, " Recovery Manager Checklist" i 6.3 Form EP 12.1-5, " Technical Manager Checklist" 6.4 Form EP 12.1-6, " Plant Manager Checklist" i l 6.5 Form EP 12.1-7, " Radiation Protection /Radwaste Manager" l l 6.6 Form EP 12.1-8, " Administrative And Logistics Manager" 6.7 Form EP 12.1-9, " Emergency Response and Recovery Activities Record Sheet" 6.8 Form EP 12.1-10, " Emergency Recovery Communications Log ' Sheet" 6.9 The records generated by this procedure during an actual emergency shall be forwarded to the Emergency Planning Coordinator (EPC) at the termination of the emergency. The EPC forwards the records to Records Management. These records will be retained for the life of the plant. These records shall be considered ' l g-~s QA records, i 6.10 The records generated by this procedure during drills ! and exercises shall be forwarded to the EPC upon termination of the drill or exercise. The EPC shall maintain these records for at least one year. These records shall be considered non-QA records. 7.0 ATTACHMENTS i 7.1 Attachment 1.0, "WCGS Recovery Organization" 7.2 Attachment 2.0, " Guidelines for Initiating Recovery Operations" 7.3 Attachment 3.0, " Radiological Emergency Coordinator Checklist" ! 7.4 Attachment 4.0, " Recovery Manager Checklist" 7.5 Attachment 5.0, " Technical Manager Checklist" l EPP 01-12.1 Rev. 4 ) Page 8 of 19 ' i \ I l
I-7.6 Attachment 6.0, " Plant Manager Checklist" 7.7 Attachment 7.0, " Radiation Protection /Radwaste Manager Checklist" 7.8 Attachment 8.0, " Administrative s and Logistics Manager" 7.9 Attachment 9.0, " Emergency Response and Recovery 4 Activities Record Sheet" 7.10 Attachment 10.0, " Emergency Recovery Communications Log Sheet" i 1 I I l l i EPP 01-12.1 Rev. 4 Page 9 of 19 l 1 l 1
I V ATIE29ENT 1.0 (Page 1 of 1) PdOIGIDGICAL DEIG2iC"i REO7vm CRGANIZATIGi Reowezy Manager i l l I I I Technical Plant Rt.diation Administrative Public Manager Manager Protecticrl/ and Irgistics Information Radwaste Manager Officer Manager Recmery ErgineerincJ m 1 I Recovely Consultant Regional WCre Radiation Protection Vendor Utility Organization Organization Managers Support i Public Information organization i (
\
t EPP 01-12.1 Rev. 4 Page 10 of 19
4
,-s ATTACHMENT 2.0 Guidelines for Initiating Recovery Operations
- 1. Fission product barriers have been restored by mitigating actions, or status of the barriers is sufficiently well defined to allow informed decisions regarding possible hazards to personnel upon entry.
l 2. In-plant radiation levels are stable and are decreasing with time. i 3. Releases of radioactive materials to the environment have ceased or have been controlled within permissible limits.
- 4. Fire, flooding, or other similar emergency conditions no longer constitute a hazard to the plant or to plant personnel.
- 5. Reactor heat removal means are functional.
- 6. Any final conditions of EPP's are close or are being closed out as conditions allow. 7 ';
r E . . 1 l l l f4 e /- F f 4 EPP 01-12.1
- - Rev. 4
. Page 11 of 19
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, FORM EP 12.1-3 REV. O q ATTACHMENT 3.0 Radiological Emergency Coordinator Checklist Reentry Operations Time / Initials Remarks
- 1. Evaluate approximate dose 4 rates and permissible stay s times in the affected onsite area. /
- 2. Specify the type of equipment /
(i.e., protective clothing, TLD's, respirators etc.) re-quired for reentry operations. /
- 3. Specify self-monitoring and decontamination procedures for Reentry Tsams. /
- 4. Brief the Reentry Team g i members on the reentry operation including the a routes for entry into any affected areas. /
- 5. Maintain a tiritten log of all reentries into affected s areas. / A T
i 1 EPP 01-12.1 ' Rev. 4 - Page 12 of 19 +
FORM EP 12.1-4 REV. O ATTACHMENT 4.0 Recovery Manager Checklist Recovery Time / Initials Remarks , 1
- 1. Determine whether to initiate l recovery / reentry operations based guideline conditions in Attachment 2.0. /
- 2. Obtain concurrence of the NRC and State of Kansas, Division of Emergency' Preparedness prior to downgrading-the event from a General Emergency. /
- 3. Notify the State Division of Emergency Preparedness, the Chairman of the Coffey County Commissioners and the NRC when downgrading the event from Alert, Site Area Emergency
., s or General Emergency. /
I \ (/ 4. Assume the role of Recovery Manager. /
- 5. Provide direction and control of the WCGS Recovery organization. /
- 6. Authorize reentry team personnel exposures in excess of 10CFR20 limits. /
- 7. Authorize funds and the utilization of manpower and equipment for recovery 0 operation. /
B). Provide periodic updates I to the offsite authorities concerning the recovery operations especially if there is any potential for offsite effects. / ( EPP 01-12.1 Rev. 4 Page 13 of 19 i i
.n. , - . , - -
FORM EP 12.1-5 REV. O Technical Manager Checklist Recovery / Reentry Time / Initials Remarks
- 1. Assume the role of Technical Manager. /
- 2. Provide engineering and technical specialists for support activities. /
- 3. Assist Radiation Protection /
Radwaste Manager with modifi-cations to radwaste systems. /
- 4. Assist the Plant Manager in developing recovery procedures for special
-~ operations. /
s/ m 5. Provide expertise for repair and modification activities. /
- 6. Provide qualified personnel to augment repair teams. /
/
i 4 ( EPP 01-12.1 Rev. 4 Page 14 of 19
FORM EP 12.1-6 REV. O ATTACHMENT 6.0 Plant Manager Checklist Recovery / Reentry e Time / Initials Remarks
- 1. Assume the role of Plant Manager. /
- 2. Direct onsite recovery I activities. /
- 3. Develop modification and repair plans for plant systems, instruments and control problems resulting from the accident. /
- 4. Analyze conditions and develop guidance for operations personnel re-garding core protection. /
- 5. Develop recovery procedures for special operations. /
- 6. Authorize personnel exposures in excess of 10CFR 20 limits. /
EPP 01-12.1 Rev. 4 Page 15 of 19
FORM EP 12.1-7 REV. 1 l ATTACHMENT 7.0 t Radiation Protection /Radwaste Manager Checklist Recovery / Reentry Time / Initials Remarks
- 1. Assume the role of Radiation Protection /Radwaste Manager. /
4 2. Develop plans and procedures for processing, sampling or controlling liquid, gaseous and solid wastes. /
- 3. Develop design modifications for waste processing. /
- 4. Direct radiological exposure control for recovery activities. /
- 5. Obtain authorizati a of personnel exposures in excess of 10CFR 20 limits from the DEM or DED. /
- 6. Support offsite sampling programs, dose assessments, dose management, and radiation programs. /
- 7. Notify the offsite authorities concerning offsite sampling programs and dose assessments. /
- 8. Calculate the total cumulative population exposure, periodically /
l i EPP 01-12.1 Rev. 4 Page 16 of 19
FORM EP 12.1-8 REV. O y ATTACHMENT 8.0 Administrative and Logistics Manager Recovery / Reentry Time / Initials Remarks
- 1. Assume the role of Administrative i and Logistics Manager. /
- 2. Identify alternates to the Recovery Organization and establish a shift schedule. /
- 3. Provide administrative support equipment and communications i support. /
- 4. Develop.a list of consultants, vendors, utilities, etc. who may provide equipment, personnel, and engineering support during recovery. /
s
- 5. Develop procedures for
, expeditiously procure equipment, personnel and engineering support. / ,
- 6. Coordinate the initial activities of the consultants and vendors brought in for recovery 1 operations. /
EPP 01-12.1 Rev. 4 Page 17 of 19 i
FORM EP 12.1-9 REV. 0
'\_) ATTACHMENT 9.0 (Page 1 of 1)
EMERGENCY RESPONSE AND RECOVERY ACTIVITIES RECORD SHEET KANSAS GAS AND ELECTRIC WOLF CREEK GENERATING STATION EMERGENCY RESPONSE AND RECOVERY ACTIVITIES RECORD SHEET Date: Page: Entered Time Summary of Activity Performed by (Initials) O L) i EPP 01-12.1 Rev. 4 Page 18 of 19 l
FORM EP 12.1-10 REV. O V ATTACHMENT 10.0 (Page 1 of 1)
, EMERGENCY RECOVERY COMMUNICATIONS LOG SHEET NOTE: This log sheet shall be used by members of the WCGS Recovery Organization to make a record of all communications related to recovery efforts. A separate sheet is required for each communication.
DATE TIME Names of persons called or calling Affiliation Pertinent Remarks O Recovery Organization Individual Title EPP 01-12.1 Rev. 4 Page 19 of 19
1 ' O KANSAS GAS AND ELECTRIC COMPANY WOLF CREEK GENERATING STATION RADIOLOGICAL EMERGENCY RESPONSE PLAN IMPLEMENTING PROCEDURE TRAINING PROGRAMS EPP 02-1.2 Revision 5 i
%J i
5%wn _ l r ~ 1 /0 88 b EMERGNICY P ING COOR ITATOR REVIEW DATE / / Nn EMERGENCY PLANNING ADMINISTRATOR REVIEW m /0/22/M DATE fa b //-_54$ PSRC APPROVAL RECOMMENDATION DATE N //!7!Pd, V.P. NUCLEAR / APPROVAL DATE / RELEASED DC29 11 8 6-DATE
. , _ , _ - - - . - - - - - - - - - . - , - - - - - - - - - - - - - - - - ~ - ~ ' ^ ' ~ ^ ~ ^ ' ' ' ' ~ ^ ' ' ' ' ' ' ' ' ' ' ' ' '
I N 1.0 PURPOSE This procedure provides guidelines for developing and implementing the Wolf Creek Generating Station (WCGS) Radiological Emergency Response Plan Training Program. 2.0 APPLICABILITY I This procedure is implemented by the Nuclear Training
- Division in conjunction with the Emergency Planning Coordinator (EPC) and Emergency Planning Admin-
, istrator (EPA). Personnel assigned emergency ! organization positions or response functions shall 2
have appropriate training as described herein. 3.0 DEFINITIONS NONE 4.0 INSTRUCTIONS 4.1 RESPONSIBILITIES i 4.1.1 The EPC shall be responsible for the following:
! 4.1.1.1 Assuring training is provided for the Emergency I
Response organization staff assigned to the Emergency l
! / Operations Facility (EOF), Home Office Emergency
\ Center (HOEC), Information Clearinghouse (IC), Media Release Center (MRC), General Office (GO) and System Operations (SO). Also assuring training is provided for Non-Responding Emergency Communicators and System
- Operators' responsible for calling-out personnel assigned to the above facilities.
4.1.1.2 Assuring the availability of radiological orientation training that supports the training schedules and
- annual exercise.
~ 4.1.1.3 Developing and implementing an Emergency Preparedness Drill and Exercise Program in accordance with EPP 02-1.3, " Drills and Exercises." l 4.1.1.4 Providing the Manager Nuclear Training with a current l list of the Emergency Responsa Organization (ERO). 4.1.1.5 Coordinating with the EPA to provide the Manager l Nuclear Training with a list of candidates for the ERO requiring training. i l EPP 02-1.2 l Rev. 5 Page 1 of 11 i
l l t ! 4.1.1.6 Assuring that personnel designated as controllers O receive the necessary training to qualify them for that pcsition in accordance with EPP 02-1.3, " Drills and Exercises." 4.1.1,7 Reviewing lesson plans that affect the EOF, HOEC, GO, MRC, IC and personnel responsible for callout for the above facilities for technical content. 4.1.2 The Emergency Plan Administrator (EPA) shall be responsible for the following: 4.1.2.1 Assuring that training is provided for the WCGS ERO staff assigned to the Control Room, Technical Support Center (TSC) and Operations Support Center (OSC) , and for Non-Responding Emergency Communicators responsible for calling out personnel assigned to these facilities. 4.1.2.2 Providing the Manager Nuclear Training with a list of candidates for the site portion of the ERO. 4.1.2.3 Reviewing lesson plans that affect the Control Room, TSC, OSC and Security for technical content. 4.1.2.4 Developing and implementing an Emergency Preparedness Drill and Exercise Program in accordance with EPP 02-1.3, " Drills and Exercises." 4.1.3 The Manager. Nuclear Training shall be responsible for: l 4.1.3.1 Scheduling and conducting classroom training for the l ERO. 4.1.3.2 Informing the EPC when ERO candidates have successfully completed training. 4.1.3.3 Informing the EPA when site ERO candidates have l successfully completed training. 4.1.3.4 Assuring that lesson plans are developed in accordance with KP-862, " Training Materials Development." 4.1.3.5 Assuring that a mechanism is available for the student critique of classroom training. 4.1.3.6 Coordinating Emergency Plan training for Security Personnel with the Chief of Security. EPP 02-1.2 Rev. 5 Page 2 of 11
i 4.2 TYPES OF TRAINING i 4.2.1 Initial Training i 1 4.2.1.1 The Content of Initial training is identified in the course content of Attachment 1.0, "WCGS Radiological i Emergency Response Plan Initial Training Course Content." l 4.2.1.2 Personnel identified to be added to the ERO shall l receive Initial Training consistent with the matrix shown in Attachment 2.0, "WCGS Radiological Emergency l Response Plan Initial Training Module Matrix," prior to being added to the ERO Duty Roster. 4.2.1.3 Personnel participating in the Hot License and Reactor Operator Requalification Training Program shall i receive instruction in emergency planning which satisfies the requirements of the initial training program. 4.2.2 Retraining l 4.2.2.1 Required Reading l 4.2.2.1.1 Management Systems shall initiate transmittal forms to l selected members of the ERO upon the issuance of~a new EPP or a revised EPP. 4.2.2.1.2 Notified personnel shall obtain and read a controlled l copy of the procedure (s) itemized on the transmittal form, i 4.2.2.1.3 Notified personnel shall sign the transmittal form, l attesting that they understand the new or revised EPP. 4.2.2.1.4 Notified personnel shall return the signed transmittal l form within 30 celandar days of the date distributed. 4.2.2.1.5 A subsequent notification shall be sent to any indi- l vidual who does not sign and return the initial noti-fication form. 4.2.2.1.6 If personnel do not return the signed transmittal form ' within 45 days of original issue, the Manager Nuclear Training shall determine subsequent action. 4.2.2.2 Annual Classroom Requalification Training l 1 4 i EPP 02-1.2 ; Rev. 5 Page.3 of 11 l i
i l i l
; *O 1 4.2.2.2.1 Personnel assigned to the TSC, OSC, EOF, HOEC and the Public Information Organization shall receive facility specific instructions incorporating the following !
elements: i j - Facility Activation Procedure Identification Chain of Command , Communication Methods Logkeeping Practices ) 4.2.2.2.2 Licensed Control Room personnel shall receiva class-i room instruction on the initial actions required of the Control Room during the first hour after declara-tion of the emergency and the functions of the Control Room after the TSC and OSC are fully operational. 4.2.2.2.3 The annual Control Roon retraining course satisfies l the requirements for licensed personnel assigned to - i the TSC in the positions of Operations Status Board l Recorder and NRC Communicator. 4.2.2.2.4 Nuclear Station Operators (NSOs) and Shift Clerks shall receive instruction consistent with the initial i' training requirements indicated in Attachment 2.0, .
"WCGS Radiological Emergency Response Plan Initial !
Training Module Matrix," annually. This training sat- ! isfies the annual requalification training i , requirements. i I 4.2.2.2.5 Retraining shall be completed every 12 months as l established by the 1986 Retraining Schedule. The
! Manager Nuclear Training may authorize an extension of l no more than three months.
4.2.3 Other Training l 8 4.2.3.1 All personnel with unescorted access to the Protected l ; Area shall receive general Emergency Response Plan j training as part of the General Employee Training ;
; program. ! 4.2.3.2 A radiological orientation training program shall be l
. made available to officials of the State of Kansas, Coffey County, and other offsite agencies. 4.2.3.3 Training on the Post Accident Sampling System (PASS) l 1 is conducted by the Chemistry Group for all Shift , Chemistry Technicians. i l j 4.2.3.4 The Security Training Group provides instruction on l l accountability and evacuation in the Squad Training i Program.
! EPP 02-1.2 Rev. 5 Page 4 of 11 i
_ . _ . _ _ _ . . . _ _ _ . ~ . - , _ _
- i. .
1,
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4.2.3.5 System Operations personnel and those assigned to l nonresponding Emergency Communicator positions shall receive training on the callout procedures only. 4.2.3.6 Personnel from the maintenance and I&C work groups who would be assigned to emergency repair and damage control teams shall receive annual instruction on the emergency plan and on emergency team formation and operation. 4.2.4 Drills (Including Tabletops) l 4.2.4.1 Selected personnel in the ERO shall demonstrate their i ability to perform assigned tasks in accordance with EPP 02-1.3, " Drills and Exercises." 4.2.4.2 Drills shall be considered part of the ERO training l program. Participation in a drill, however, is not a ,
~
substitute for required reading or the annual classroom instruction.
5.0 REFERENCES
5.1 Wolf Creek Generating Station Radiological Emergency Response Plan. 5.2 EPP 01-5.1, " Exclusion Area Evacuation" 5.3 EPP 01-6.1, " Personnel Accountability" 5.4 EPP 02-1.3, " Drills and Exercises" 5.5 KGP-1800, " Training and Qualification Records" 5.6 KP-862, " Training Materials Development" 6.0 RECORDS 6.1 The Nuclear Training Division shall maintain records of all classroom training in accordance with KGP-1800,
" Training and Qualification Records."
7.O ATTACHMENTS 7.1 Attachment 1.0, "WCGS Radiological Emergency Response Plan Initial Training Course Content." 7.2 Attachment 2.0, "WCGS Radiological Emergency Response Plan Initial Training Module Matrix." EPP 02-1.2 Rev. 5 Page 5 of 11
.i 1 l ATTACHMENT 1.0 (Page 1 of 4) WCGS RADIOLOGICAL EMERGENCY RESPONSE PLAN l INITIAL TRAINING COURSE CONTENT Module 1 E Plan Overview Description This session provides an overview of j WCGS Emergency Response Plan. Among the topics discussed are the Plan, the implementing procedures and the sequence of response, i.e., facility } ' function, organization and activation. Additional topics include the utility's a
' role in protecting the health and ,
safety of the general public, response l to callout notification and the l recovery phase. 1 Module 1A TSC Activation and Operation
Description:
This session describes the activation l and operation of the Technical Support l Center (TSC) including initial actions, j individual responsibilities, chain of ! command, communications and record i keeping. ! Module 1B OSC Activation and Operation
Description:
This session describes the activation i and operation of the Operations Support Center (OSC) including initial actions, chain of command, requirements for team i formation and deployment, individual responsibilities and communications. j Module 1C EOF Activation and Operation i
Description:
This session describes the activation i and operation of the EOF including the { j chain of command, organization, communication and record keeping
- functionu.
i
- EPP 02-1.2 l Rev. 5 Page 6 of 11 l
1 .
)
x_ ,/ ATTACHMENT 1.0 l l (Page 2 of 4) 3 l l WCGS RADIOLOGICAL EMERGENCY RESPONSE PLAN INITIAL TRAINING COURSE CONTENT l Module 1D HOEC Activation and Operation
~
Description:
This session describes the activation, and operation of the HOEC including the chain of command, organization, communication and record keeping functions. Module lE GO/MRC/IC Activation and Operation
Description:
This session describes the activation, and operation of the GO/MRC/IC l including the chain of command, organization, communication and record keeping functions.
- j Module 2A Manual Deterr.ination of Release Rate and Dose Projection
Description:
This session explains the techniques for the determination of release rates - and dose projections using manual methods. A hands-on practice is included. 4 Module 2B Radioactive Release Information System (RRIS)
Description:
The classroom portion of this course discusses the principles of operation I for the RRIS and covers the methods nad modes of operation. The hands-on portion allows students direct interface with the equipment (both hardware and software). Module 3A Emergency Classification
Description:
This session describes the methods for determining an emergency classification at WCGS. In addition, this session discusses the activation of the WCGS Emergency Response Plan. EPP 02-1.2 Rev. 5 Page 7 if 11 _. _ - _ , _ _ _ _ . _ _ . _ _ _ _ . _ _ _ _ . . _ _ - _ . _ _ _ . ~ - _ . _ _ _ _
-- - -~ .. . _ -. . . . . . . -_
l t . I ATTACHMENT 1.0 (Page 3 of 4) WCGS RADIOLOGICAL EMERGENCY RESPONSE PLAN INITIAL TRAINING COURSE CONTENT Module 3B Radiological Assessment
Description:
This session supplies the student with guidance on how to use the results of various analyses to identify the ' severity of radiological problems associated with a plant emergency. A
- discussion is also included on the use of the plant Emergency Plan Implementing Procedures to determine the need to make a Protective Action Recommendation (PAR).
Module 4 Communications
Description:
This classroom session provides , training on types and uses of j l communication equipment specific to Emergency Planning and covers the l principles of communications, logging and recording and use of status boards. Also included in this session is a discussion on the immediate and followup notification methodologies l and associated record keeping. Module 5A On-site Radiological Monitoring
Description:
This classroom and hands-on-trai-ing j session describes job functions for those personnel assigned to on-site radiological monitoring teams. Also included is a discussion of the proper a technique to be used while conducting surveys. Module SB Off-Site Radiological Monitoring 1
Description:
This classroom and hands-on-training session describes job functions for
!~ those personnel assigned to off-site 1 radiological monitoring teams. Also l included is a discussion of the proper i technique for conducting surveys.
EPP 02-1.2 ! Rev. 5 l Page 8 of 11
ATTACHMENT 1.0 l , (Page 4 of 4) WCGS RADIOLOGICAL EMERGENCY RESPONSE PLAN INITIAL TRAINING COURSE CONTENT Callout Module
Description:
This classroom session provides training for the functions of the Non-Responding Emergency Communicators (NRECs) during callout of the Emergency Responsa Organization. i l I i l l l 1
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l 1 1 1 I. l l I l i EPP 02-1.2 Rev. 5 l Page 9 of 11 l l l 1
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WCCS RADIOfAGICAL EMERGENCY RESPONSE PLAN INITIAL TRAINING MODULE MATRIX TITLE I IA IB IC ID lE 2A 2B 3A 3B 4 5A 58 Callout Shift Clerk X X X l Nuclear Station Operators X X X X X Duty Emergency Director X X X X { Operations Emergency Loord. X X X X Radiological Emergency Coord. X X X X l z Administrative Emergency Coord. X X Chemistry Coordinator X X Radiological Assessment Coord. X X X X Dose Assessment Coordinator X X X X X X Maintenance Emergeacy Coord. X X X Security Emergency Coordinator X X Operations Assessment Coord. X X X TSC Public information Coord. X X Technical Support Coordinator X X EOF Coordinator X X TSC Engineering Team X X TSC NRC Communicator X X TSC Communicator X X X TSC Field Team Communicator X X X TSC Clerk /Logkeeper X X X TSC Radiological Status Recorder X X X l TSC Operations Status Recorder X X X TSC RRIS Operators X X X X l Operations Support Center Supv. X X
,g Chemistry Director X X
! mom On-Site Survey Team Director X X X l
$ .4 " Dosimetry Coordinator X X g,y Chemistry Technician X X o 8 Survey Teams X X X X l
o . Duty Emergency Panager X X X X
* " Technical Resources Manager X X X X w
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l v i WOLF CREEK GENERATING STATION RADIOLOGICAL EMERGENCY RESPONSE PLAN IMPLEMENTING PROCEDURE PUBLIC EDUCATION EPP 02-1.4 Revision 2 l ra EFIERGEblQY P NG COORDI Ja R M VIEW DATE / a/=/u / l 2 - EMERGENCY PLANNING ADMINISTRATOR REVIEW n -x +u DATE
/) fd~ ll~3 hh
- PSRC APPROVAL RECOMMENDATION DATE ll l V. P. DATE '
NUCLEAR [PPROVAL RELEASED D 1 l '/- $ h DATE
- - - - , - . - - , . . _ . . - _ , -,_-e..--,-..__._,-_,,__v.,
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, 1.0 PURPOSE
\ The purpose of this procedure is to delineate the authorities, responsibilities, and actions required for annual review of Wolf Creek Generating Stations (WCGS) Emergency Public Information Booklet. This
, procedure includes emergency materials, booklet distribution, and annual news media information 4 briefing. j 2.0 APPLICABILITY This procedure applies to personnel responsible for maintaining the facilities, supplies, and staff in a ready state in the event of a declared emergency at WCGS. It includes the annual review and distribution
- of emergency related materials to the public. This
; procedure includes the annual news media information briefing in coordination with the State of Kansas and Coffey County.
3.0 DEFINITIONS 3.1 WCGS Public Information Emergency Program Materials l
. The materials distributed and available to the public i on emergency plans relating to WCGS include but are j not limited to:
i i o public information booklet o telephone book cover o telephone book page statements o John Redmond Reservoir signs 3.2 KG&E General Office (GO) l The facility in Wichita, Kansas, where WCGS public l 1 information activities take place prior to Information ] Clearinghouse (IC) and Media Release Center (MRC) activation. It is the location for the joint Rumor control operations during all emergency
; classifications. This facility is located at 120 E.
j 1st Street in Wichita, Kansas. I i 5 l \ EPP 02-1.4 Rev. 2
. Page 1 of 3 1
e 3.3 Information Clearinghouse (IC) l The facility at 2800 Topeka Ave, Topeka, Kansas, used jointly by WCGS, State of Kansas, and Coffey County for development of news releases and coordination of , information during an emergency at WCGS. This facility is activated upon notification of EOF activation or when sufficient interest by news media warrants it. 3.4 Media Release Center (MRC) l The facility, at 2722 Topeka Avenue, Topeka, Kansas used jointly by WCGS, State of Kansas, and Coffey County to disseminate emergency related information to the public and news media. It is activated coincidentally with the Information Clearinghouse and has facilities for news conferences and a news media work area. 4.0 INSTRUCTIONS 4.1 Precautions 4.1.1 Routine utility public information programs, which do not involve emergency preparedness activities for
- WCGS, are not covered by this procedure.
l 4.1.2 WCGS employees and/or agents who distribute l t information regarding off-normal events at the WCGS to the general public or the news media through casual conversation or unauthorized interviews will be subject to disciplinary action. All inquiries for information should be directed to the WC PIO or upon full activation of the GO to the appropriate phone-team. ! 4.1.3 In the event any of the emergency facilities or function location change, the Emergency Planning Coordinator assures that telecommunications equipment and notification call lists reflect current and accurate information. I 4 l i , i l O V EPP 02-1.4 Rev. 2 Page 2 of 3
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l 4.2 INITIAL / SUBSEQUENT ACTIONS 4.2.1 The Emergency Planning Coordinator should on a semi-
, annual basis, verify the availability of adequate l emergency supplies and materials at all three facilities (GO, IC, MRC). This shall include testing phones twice yearly.
4.2.2 The Emergency Planning Coordinator (EPC), on an annual basis, shall assure review of, preparation of, and i I distribution of emergency information to the public in cooperation with the State of Kansas and Coffey County. l 4.2.3 The Emergency Planning Coordinator shall assure the j scheduling of an annual news media information briefing i and then, in conjunction with the State of Kansas and Coffey County, coordinate and participate in the briefing. 4.2.3.1 The annual news media information briefing shall l include, but not be limited to: o The emergency response plan
, o Dissemination of information to the news media- -
) j o Information about radiation 1
5.0 REFERENCES
i 1 5.1 Wolf Creek Generating Station Radiological Emergency j Response Plan . 5.2 EPP 01-1.4, Public Information Organization 5.3 EPP 01-4.5, General Office Activation 1 l 5.4 EPP 01-4.6, Information Clearinghouse / Media Release ! Center Activation i 5.5 EPP 01-10.2, Preparation of News Releases I 5.6 EPP 01-10.3, Release of Emergency - Relatnd Information to the Public 6.0 RECORDS . NONE 7.0 ATTACEMENTS l I NONE l EPP 02-1.4 Rev. 2
- Page 3 of 3
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I i WOLF CREEK GENERATING STATION RADIOLOGICAL EMERGENCY RESPONSE PLAN IMPLEMENTING PROCEDURE MAINTENANCE OF EMERGENCY FACILITIES AND EQUIPMENT EPP 02-1.5 Revision 6 l O
/ 0A lb M EMERGEMGY P NG CO INATONVIEW DATF/ /'~
e SJL&& EMERGENCY PLANNING ADMINISTRATOR REVIEW
/ 0lA 2 / 2 $
DATE ftL / D l >m /k_3Yb DATE PSRCAPPROVALRECOMMENDjTION d[4 67db V.P. NUCLEAR APPROVAL
/
/
/[/7/rrs DATE /
( O RELEASED OC24 ) / - 7* 8h DATE
1.0 PURPOSE' t
!Ci This procedure provides guidance for verifying the availability and operability of emergency response facilities and equipment, controlling the radiological emergency response vehicles during routine conditions, and controlling the keys required during a radiologi-cal emergency response at Wolf Creek Generating Station (WCGS).
2.0 APPLICABILITY This procedure applies to the Emergency Planning Coordinator (EPC), Emergency Planning Administrator (EPA), and personnel assigned the responsibility of
, assuring the availability and operability of emergency j response facilities and equipment.
3.0 DEFINITIONS 3.1 EMERGENCY EQUIPMENT Any item which is dedicated for radiological emergency response use. , 3.2 DESIGNATED RADIOLOGICAL EMERGENCY RESPONSE VEHICLES j WCGS vehicles which have been designated for use I daring radiological emergency response conditions and haose routine use is controlled to assure their availability. The list of vehicles is shown in Attachment 1.0, " Designated Radiological Emergency Response Vehicles." I 4.0 INSTRUCTIONS 4.1 RESPONSIBILITIES 4.1.1 The EPA is responsible for assuring that all WCGS emergency response facilities, equipment and supplies 'j are operationally inspected, inventoried, inspected, and maintained per this procedure. I i 4.1.2 The EPC is responsible for assuring that the Home i Office Emergency Center (HOEC), General Office, Media Release Center (MRC) and Information Clearinghouse (IC) are properly maintained. The EPC is also responsible for assuring reasonable support is available to maintain the State and County Emergency Operations Centers (EOCs). i l' EPP 02-1.5 Rev. 6 l Page 1 of 33 1 a
i ~ 4.1.3 The Site Health Physicist is responsible for assuring
\ that quarterly inventories are conducted of emergency kits and lockers as listed in Attachments 4.0, 5.0, l 6.0, 7.0, 8.0, 9.0, 10.0 and 11.0. Additionally, that
, quarterly inventories of portable radiological survey instruments contained in emergency lockers are com-plated, and calibration and testing of radiation l monitoring equipment is conducted in accordance with Health Physics procedures. l 4.1.3.1 All kits and cabinets shall be inventoried on a quarterly basis. Kit and cabinet seals shall be
- inspected on a monthly basis to assure the contents
. have not been tampered with. If a seal is found to be broken, the contents shall be inventoried and the kit or cabinet resealed within 24 hours.
4.1.4 The EPC and/or EPA is responsible for reviewing the results of inspections / inventories (including those i during drills and exercises), correcting deficiencies, and providing additional equipment and supplies, as appropriate, to their respective facilities. 1 4.2 EMERGENCY EQUIPMENT AND SUPPLIES l - NOTE: Whenever equipment or components are found to , te malfunctioning, the responsible organization , will be notified. l s) 4.2.1 Emergency equipment and supplies shall be maintained I at the following locations: 4.2.1.1 Control Room (Attachment 4.0) 4.2.1.2 Technical Support Center (TSC) (Attachment 5.0) 4.2.1.3 Operations Support Center (OSC) (Attachment 6.0) I I 4.2.1.4 Emergency Operations Facility (EOF) (Attachment 7.0) ) l 4.2.1.5 Offsite Monitoring Team Kits (Attachment 8.0) i j 4.2.1.6 Coffey County Ambulance-WCGS Security (Attachment 9.0) 4.2.1.7 Ransom Memorial Hospital (Attachment 10.0) 4.2.1.8 Primary Access Control Station (Attachment 11.0) 4.2.2 Radiological emergency equipment and supplies shall be inventoried quarterly and after each use. i 4.2.3 Where applicable, radiological emergency and communications equipment shall have operability tests j performed quarterly and after each use. EPP 02-1.5 i Rev. 6 Page 2 of 33 . I
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s t 4.2.4 ' Radiation survey instruments.and respiratory protection equipment shall have a current calibration or inspection tag,. - 7'L 4.2.5 Radiological emergency skuipment' removed from its designated storage area-shall be replaced within 24 hours. > 4.2.6 Radiological emergency equipment found to be 3 inoperable or out-of-calibration shall be removed from service and replaced within 24 hours. t 4.2.7 Radiological emergency equipment.shall not be used until the Duty Emergency Director (DED) or Duty Emergency Manag'er' (DEM) has declared an emergency classification er.as deemed necessary by the Duty l Shift Supervisor ^1n other extraordinary occurrences. i Use in these latter situations will be minimized. i 4.2.8 Material having a fixed shelf life shall be dated to j assure appropriat'e cycling prior to its expiration 4 t date. - , 4.2.9 Non-rechargeable batteries installed in instruments
- shall be fanctionally tested when kits.and cabinets
} are inventoried, and shall be replaced if found i discharged. Spare non-rechargeable batteries shall be j( i ' replaced during the first and third quarter inventories and shall be noted as changed in the romarks siction of inventory forms. Rechargeable
-batteries'shall be connected to a recharger when not in use and the batteries shall be rtplaced when i
~
inoperable. Batteries showing signs of leakage,
) corrosion, or similar deterioration shall be replaced. ; 4.2.10 Thermoluminescent Dosimeters (TLDs) shall be cycled
- annually.
4.2.11 Carrest revisions of plans, procedures and forms I ; required:to be'in the emergency response facilities,
- cabinets, and kits are placed by Document Control. 1 i j -
? /
i 4.2.12 Health Physics personnel sha'11 inventory all items using the appropriate inventory list. included in the , attachments. Completed inventory lists shall be j transmitted to the EFA. [ 4.3 RADIOLOGICAL EMERGENCY RESPONSE VEHICLES 4 , o l 4.3.1 Radiological Emergency Response Vehicles may be used
- routinely in accordance with the provisions of this j procedure for both onsite and offsite purposes.
I EPP 02-1.5
. Rev. 6
{ Page 3 of 33 I l
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4.3.2 When not logged out, these vehicles shall remain parked at the locations shown in Attachment 1.0,
" Radiological Emergency Response Vehicles."
4.3.3 Keys shall be obtained from Security Officers at the . Primary Access Control Station or WCGS Education Center. 4.3.4 The date, time, driver's name, estimated time of return, destination and vehicle number shall be recorded in Attachment 2.0, " Radiological Emergency Response Vehicle Control Log". 4.3.5 When the vehicle is in use, the vehicle's radio or the portable radio shall remain on so that the driver can receive instructions to return the vehicle. If the driver will be away from the vehicle, he should take the portable radio with him. Portable radios for these vehicles will be stored in the PACS building and ' may be obtained from Security. 1 Vehicles shall not be taken more than twenty miles 4.3.6 from WCGS without permission from the Security Shift Lieutenant; Chief of Security or Security Emergency Coordinator, or Emergency Education Center Security Officer. i 4.3.7 Prior to returning the vehicle, the driver shall check 4 the fuel level. If the fuel tank is one-half full or less, the driver shall refuel the vehicle prior to returning it. 4.3.8 If the driver receives notification by radio, plant emergency alarm, or an emergency announcement, he/she shall immediately return the vehicle to its designated parking space, unless directed differently, and return the keys to the PACS or WCGS Education Center. 4.3.9 The driver shall record the return time and the fuel level on the designated Radiological Emergency Response Vehicle Control Log. t 4.3.10 As required, the DED or DEM shall designate additional vehicles for use in emergency response. 4.4 KEYS 4.4.1 The primary set of keys for the emergency response facilities, equipment and supply cabinets shall be kept by the Security Officers at the PACS and WCGS Education Center. I EPP 02-1.5 g Rev. 6
\
Page 4 of 33
l l
^ l
( ( s 4.4.2 Keys should be numbered or identified as to their use, and a signout log maintained. The keys are listed in l Attachment 3.0, " Radiological Emergency Response Facility Key List". l
=,
'4. 5 SIRENS 4
4.5.1 Emergency notification sirens will be surveilled and b maintained by WCGS Maintenance Communication Group. l Reference EPP 02-1.8, " Testing and Maintenance of Alert and Notification System Sirens." 4.6 CODE WORD 4.6.1 The verification code word for use in immediate 4 notifications shall be changed at least annually and after each use. 4.6.2 Thescode word shall be changed at the Control Room,
; Coffey County Sheriff's Office and WCGS Simulator.
5.0 REFERENCES
5.1 WCGS Radiological Emergency Response Plan 5.2 EPP 02-1.8, " Testing and Maintenance of Alert and Notification System Sirens" 6.0 RECORDS l 6.1 The emergency equipment and supplies checklists and inventories used during drills, exercises, and radiological svents shall be retained for five (5) years by Records Management. 6.2 The emergency equipment and supplies checklists ( completed on a periodic basis shall be retained for two years by the EPA. 6.3 This EPP does not generate Quality Assurance records. l< 7.O ATTACHMENTS
, 7.1 Attachment 1.0, " Radiological Emergency Response Vehicles" l 7.2 -Attachment 2.0, " Radiological Emergency Response 4 l Vehicle Control Log" 7.3 Attachment 3.0, " Radiological Emergency Response Facility Key List" l 7.4 Attachment 4.0, " Control' Room Radiological Emergency Kit / Cabinet Supplies" l C .
EPP 02-1.5 Rev. 6 Page 5 of 33 (
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s 7.5 Attachment 5.0, " Technical Support Center Radiological
\
Emergency Kit / Cabinet Supplies" l 7.6 Attachment 6.0, " Operations Support Center Radiological Emergency Kit / Cabinet i Supplies" 7.7 Attachment 7.0, " Emergency Operations Facility Radiological Emergency Kit / Cabinet I Supplies" 7.8 Attachment 8.0, "Offsite Monitoring Team Kit" 7.9 Attachment 9.0, " Ambulance Radiological Emergency Kit / Cabinet Supplies" 7.10 Attachment 10.0, " Ransom Memorial Hospital Radiological Emergency Equipment and Supplies" 7.11 Attachment 11.0, " PACS Emergency Cabinet Equipment" 7.12 Attachment 12.0, " Locations and Descriptions of First Aid Supplies" lO I l t' EPP 02-1.5 Rev. 6 Page 6 of 33
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ATTTACHMENT 1.0 O (Page 1 of 1) RADIOLOGICAL EMERGENCY RESPONSE VEHICLES \ KG&E No. Year Make Model Color Kansas License No. 1024 1984 Chev. Suburban White CF-J-984 - 1042 1984 Chev. Suburban White CF-J-985 1043 1984 Chev. Suburban White CF-J-994 NOTE: 1) Two vehicles will be parked at the north end of the parking lot in designated spaces. ,
- 2) One vehicle will be parked at the WCGS Education j Center. '
- 3) Vehicles may be rotated between locations.
- 4) Vehicle keys are kept by security.
4 l l EPP 02-1.'5 Rev. 6 Page 7 of 33
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0.1 E Om l i t 2 S A w rom f d i I e D1SE l M l ieR t i. Cg N f AaY O TPC I e r( T N N b E A G N t R I s E T u n M S r E E e
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i ATTACHMENT 3.0 (Page 1 of 1) RADIOLOGICAL EMERGENCY RESPONSE FACILITY LIST l Keys Location i TSC Security OSC Security i EOF Security ; i l I i l 1 l
,EPP 02-1.5 Rev. 6 Page 9 of 33 i
i
1 V EDIN EP 02-5 REV.1 Al"rACININT 4.0 Page 1 of 3 ( _DNTROL ROOM RADIOUXIICAL FMERGFNCY/CABINF;P SUPPI,IF.] SurveilIanm Frequency: Quarter 1y Surveillance Date: EUJIPMENT SURVEIU,ANCE MINIMUM ITtN RENARKS Slit 2,F REQUIRFNINT QUANTITY VERIFICATION t.I FE (INITIALS) Frisker Inventory and 1 verify operability i B/G Survey Meter Inventory and 2 verify operability Air Sanpler - Lo Vol Inventory 1 Air Sanpler Filters / Cartridges Inventory Filters, Particulate 1 Dox Filters, Zeolite 10 Air Sanple Labels Inventory 25 Dosirneter Charger Inventory and 2 verify operability Duct Tape Inventory 5 Rolls PC Gloves Surgeons Inventory 1 Box Cloth Gloves Inventory 20 Pair Flashlight Inventory and 5 m to tg verify operability
>am
$. Batteries -(D) Inventory 48 Pmu -(9V) 12 o e P Self-Contained Breathing Inventory 6 k* Apparatus d Spare Bottles for SCBA Inventory and 2 pressure check First Aid Kit Inventory by list 1
; inside kit
V ) l f
- I4)ld EP 02-5 REV. 1 ATTACIMIWP 4.0 P.vp 2 of 3
- CotfrIKX. ROOM RADIOLOGICN, IMERGI2CY/CABINLT. SUPPI,lES
~~5urveillance Fregtency: Quarterly Surveill.uce IMte:
EX)UllHENT SURVEILLANCE MINIMUM ITFN RENARKS SIELF t REX)UIREMENr QUANTITY VERIFICATION LIFE j . (INITIALS) Potassiun Iodide Tablets Inventor', 10 Bottles (Individual Doses) l !. Sanple Holder Inventory 1 , Snears Inventory 1 Box i 4 Tweezers Inventory 1 i Check Source Inventory 1 Paper Inventory 5 Pads Pencils Inventory 12 Pens Inventory 12 Planchettes Inventory 50 Plastic Bags 12" x 15" Inventory 25 6" x 8" Inventory 25 Pocket Ion Qiamber (200R) Inventory 5 Pocket Ion Chamber (SR) Inventory 10 mmm to <: M Pocket Ion Onnber (500PR) Inventory 10 e*
,i o
- P as to RAD Monitor Data Sheets Inventory 25 1 H 8 2
O H. Respirators - Full Face Inventory 6
,m ui ! u Spare Cartridges for Inventory 12 W Respirators i
EPZ Mips Inventory 1 Set
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1- . l EUIN EP 02-5 REV. 1 ATTACINFNr 4.0 Page 3 of 3 j CCNTROL HOOM RADIO (DGICAL EME.HGENCY/CABINE?r SCTPLIIS l . Surveillance Frequency: Quarterly a Surveillance Date:
! MJU tin' ENT SURVEILLANCE MINIMLN ITEM RINARKS SIELF REQUIRIMENT QUANrlTY VERIFICATION LIFE i
i t (INITIALS) i l Overlays for EPZ map Inventory 1 Set j Calculator Inventory and verify 1 ! operability l Reviewed By: Date: 1 Dnergency Planning Administrator 1 i 1
- m :o M WeM '
1 tQ < M I t e* O j P 0% M t N I H p O e i O D m W I f i : i i I ! _ _ _ __ _ _____ _____ _ _r
% m i
e tVHM EP 02-6 REV. 2 I ATTACINDir 5.0 Page 1 of 3 ' TECliNICAL SUPPORT CFNTER RADIOUX3tCAL FMERGENCY/CM3INE'.r SUPPLIFE SurvelIIance Frequency: Quarterly Surveillance Inte: EQUIEMErrr SURVEILLANCE MINIltJM ITFM RD%RKS SilF1F REQUIRfMDff QUAPfrITY VERIFICATION LIFE (INITIALS) Air Sanpler - Lo Vol Inventory and 2 verify operability Air Sanpler Filters / Cartridges Inventory Filters, Particulate 1 Box Filters, Zeolite 10 Air Sanple Labels Inventory 25 Frisker Inventory and 2 verify operability PC Coveralls: Inventory Paper 2 Cases i PC Gloves - Surgeons Inventory 1 Box PC Gloves - Cotton Liner Inventory 20 Pairs PC Shoe Covers - Paper Inventory 2 Cases Pocket Ion Chamber (SR) Inventory 10 Pocket Ion Chamber (200R) Inventory - 5 (($ Q<M Pocket Ion Chamber (500 MR) Inventory 10
** Planchettes Inventory 50
{ o i P m PJ W Snears [ Inventory 1 Box o - M M Potasslun Iodide Tablets Inventory 100 Bottles (Individual Doses) w W Dosimeter Charger Inventory and verify 2 operability
) \ b.
U Euel EP 02-6 REV. 2 AfrA0lMfNr 5.0 Page 2 of 3 TEDINICAL SUPPORT CENTER RADIOtMGICAL EMERGENCY /CABINFir SUPPLIES Survelliance Frequency: Quarterly Surveillance Date: EJQU1I? TENT SUHVEILIANCE MINIMUM iTPM REPRRKS SIELF REQUIRENENT QUANTITY VERIFICATION LIFE (INITI AIE) liandie - Talkie Radio Inventory and verify 1
- j. operability 1
Batteries - D Cell Inventory 48
- 9V 12 l Penciis - Mech Inventory 12 l Paper Inventory 12 Pads Pens Inventory 24 Calculator Inventory and verify 3
. operability } Stapler Inventory 5 Staples Inventory 5 Boxes 1 Duct Tape Inventory 5 Rolls Plastic Bags 12" x 15" Inventory 10 1 6" x 8" 25
'Neezers Inventory 2 MWM
$k$
(D - Step Off Pads Inventory 5 J gmO First Aid Kit Inventory to list 1 A inside kit H O -
% ui Flashlights Inventory and 10 g check batteries u
Respirators Inventory 30 ] Filters - Combo 40 I B/G Survey meters Inventory and 2 verify operability
s EUHM EP 02-6 REV. 2 A1TACitMFNT 5.0 Page 3 of 3 TFDINICAL SUPPORT CENTER RADIOLOGICM, ENERGENCY/CAllINhT SUPPLIES Surveillance Frerphmey: Quarterly Surveillance Date: EQUltttENT SURVEILLANCE MINIMLM ITEN REMARKS SHELF REQUIRINEffr QUAKr1TY VERIFICATION LIFE (INITIALS) Check source Inventory 1 WOGS Radiological anergency Inventory 1 l Response Plan EPP(s) Inventory 2 sets EPP Forms 10 sets FSAR Inventory 1 Environmental Report Inventory 1 Operating License Tech. Specs. Inventory 1 State of Kansas Nuclear Inventory 1 Facilities Incidents Response Plan Coffey County Dnergency Inventory 1 Plan EPZ Map Inventory 1 yyg overlays for EPZ Map Inventory 1 Set waM j ,< M Plant drawings (Control Inventory 1 Set o Copy No. ) P os to
" Station Procedures h Inventory 1 Set O *
" " RRIS Film Inventory 5 Packages u u Reviewed By: Date: Dnergency Planning Adninistrator
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i I 1 EDIN EP 02-7 RtN.1
- ATTACIMDrr 6.0 Page 1 of 4 OPERATIONS SUPPORT CDrrER RADIOtMGICAL UtRGDeCY KIT /CAlllNFIP SUPPLIES
! Surveillance Frequency: Quarterly ' Surveillance Date: EQUlINEIG SURVEILLANCE MINIMM ITEM RD%RKS SIFX,P REQUIRD Bir QU,WrITY VERIFICATION LIFE {; (INITIALS) Air Sanpler - to Vol Inventory and 3
. verify operability 1
Air Sappler Filters Inventory ! Filters, Particulate 1 Box ! Filters, Zeolite 10 l j Air Sample Labels Inventory 25
- Frisker Inventory and 3 verify operability l B/G Survey Meters Inventory and 3 verify operability 4 Instr Teletechtors Inventory and 2 t I verify operability PC Coveralls
- Inventory
- 4 Cloth 25 4
PC Hoods - Cloth Inventory 25 I PC Shoe Covers Inventory Plastic 40 Pairs 4 e<o k$ Rubber 25 Pairs
** FC Wet Suits Inventory 5 l o 4
H m to
- PC Gloves
[ Inventory O . Rubber 40 Pairs i W " Surgeons 1 Box w Cotton Liner 20 Pairs u i
! 11andie - Talkie Radios Inventory and verify 5 j operabiiity
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4 RMN EP 02-7 REV.1 ATTAO NENT 6.0 Page 2 of 4 OPERATIONS SUPPORT CENTER RADIOwGICAL EMERGNCY KIT /CAllINI?P SUPPLIES i Surveillance E'requency: Quarterly Surveillance Date: EQUIPMENT SURVE!! LANCE MIN!PUt ITEM REMARKS SHELF REQUIREMENT QUAfRITY VERIFICATION LIFE (INITIALS) , 1 ! Respirators Inventory and 25 verify operability i Respirator Filters - Cambo Inventory 50 Ion Ownber (SR) Inventory 25 Ion Chamber (200R) Inventory 10 Ion Onmber (500re) Inventory 25 I Dosimeter Chargers Inventory and 3 verify operability j Duct Tape Inventory 5 Rolls Trowel Inventory 1 Potassium Iodide Tablets Inventory 100 Bottles (Individual Doses) , Plastic Bags 12" x 15" Inventory 25 6" x 8" 100 i Large Plastic Ihgs Inventory 10 mmm Flashlights Inventory and 10 mWm verify operability d2 < m , O o Calculator Inventory 1 e os u 4 I I e Battera.es (D) Inventory 24 i Q -(C) 12 l -(9V) 24 1 u First Aid Kit Inventory to list in kit 1 l Neezers Inventory 2 l )
,a.C- m - . , - . - - -c- .t.:. A. -= e- .a.- .
4 L .-...b-.*A+4 m.e s. - . 4 N Nt IT)RM EP 02-7 RE. V .1 ATTACIMFNr 6.0 Page 3 of 4 i OPERATIONS SUPPORT CENTER RADIOLOGICM, EMERGENCY KIT /CMilNE.r ' SUPPLIES I Surveillance Frequency: Quarterly l Survel1larw.e Date: EQUIIMENT SURVEILtANCE minim.M iTFM RD%RKS SHEIE l REQUIREMENT QUAMrlTY VERIFICATION LIFE (INITIALS) Check Source Inventory 3 l Herculite Inventory 1 Roll 1 Liter Poly Bottle Inventory 10 i Pencils - Mech Inventory 24 Grease 12 ' Paper Inventory . 5 Pa's i Pens Inventory 24 Perm Markers Inventory 12 4 Stop Watch Inventory and 3 j verify operability
)
Clipboard Inventory 3 Ccuipass Inventory 1 Sala Invetory and 6 ygg Spare Cylinders verify operability 12 l wam i (Q < M e* Planchettes Inventory 25 o ' P 04 h) Rad Mon Data Sheets Inventory 25 o> I i H j o . Sanple Holder Inventory I n tn t.) Snears Inventory 1 Box
] Step-Off Pad Inventory 5 l
2
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1 i EUlM EP 02-7 REv. 1 ATTACINENT 6.0 Page 4 of 4 , OPERATIONS SUPPOffr CENTER RADIOLOGICAL FNERGENCY KIT /CARINLT SUPPLIES Survoillance From: Quarterly Surveillance Date: EUJ1EMENT SURVEILLANCE, MINIMJM ITfM RENARKS SHELF - i REQUIRfMENT QUAMPITY VERIFICATION LIFE (INITIALS) Rope Stanchions Inventory 6 i
- Radiation Signs Inventory 40 Radiation Rope Inventory 1 Roll i Offsite Survey Maps Inventory 2 55 Gallon Drtas Inventory 5 Decon Supply Kit Inventory, to list in kit 1 On Site Survey Map (Out of Plant) Inventory 3 j Bu11 horn Inventory 1 1
! Extension Cords Inventory 3 i
Scissors Inventory 3 Reviewed By: Date: Bnergency Planning Administrator [ M ,tf M W9M d2 < T
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p FURM EP 02-8 REV. 1 l A'I"rAOlMENT 7.0 Page 1 of 4 EMERGENCY OPERATIONS FACILITY RADIOLOGICAL ENERGENCY KIT /CAflINh*T SUPPLIES Surveillarre Frequency: Quarterly Surveillance Date: EQUIPMENT SURVEILLANCE MINIMID1 ITEM REFERKS SilELF REUJIRtNENF . QUANTITY VERIFICATION LIFE (INITIALS) i j Air Sanpler - to Vol Inventory and 3 verify operability Air Sanpler Filters / Cartridges Inventory Filters, Particulate 1 Box Filters, Zeolite 10 l Air Sanple Labels Inventory 25 Frisker Inventory and 3 verify operability B/G Survey Meter Inventory and 3 verify operability i PC Coveralls - Cloth Inventory 30 Papr IQw PC Hoods - Cloth Inventory 30 PC Gloves - Surgeon Inventory 1 Box Rubber 40 Pairs Cotton Liners 20 Palts
'O W M j$@ PC Shoe Covers - Plastic Inventory 40 Palts go . - Rubber 25 Pairs o
o *7e PC Wet Suits Inventory 5 k
; Respirators Inventory and 25 ! Filters - Combo verify operability 50 w
rocket Ion Ownber, (SR) Inventory and 15 verify operability rocket Ion Charnber (200R) Inventory and 10 verify operability l
N 00f04 EP 02-8 REV. 1
; ATTAOPIENT 7.0 Pvje 2 of 4 EMERGENCY OPERATIONS FACILITY RADIOLOGICAL EMEIGNCY KIT /CM11 NET SUPPLIES Surveillance Frequency: Quarterly
] Surveillance Date: EUJ1EHENT SURVEILLANCE MINIMLM ITEM RFNARKS SIELF REQUIREMENT QUAlfrITY VERIFICATION LIFE (INITIALS) Pocket Ion Oiamber (500 tm) Inventory and 15 verify operability Rad Monitor Data Sheets Inventory 25 Duct Tape Inventory 5 Rolls Plastic Bags 12" x 15" Inventory 25 6" x 8" 150 Large Plastic Bags Inventory 10 TIDs Inventory 100 s Flashlights Inventory and 3
; verify operability i Spare Batteries Inventory D Cell 24 9V 24 First Aid Kit Inventory to list in kits 1
! Radiation Rope Inventory 1 Roll I m 21 t1 1
$k m
Rope Stanchions Inveatory 6 wmO H l Radiation Signs Inventory 25 0 f Step Off Pad Inventory 5 et ui i Potassita Iodide Tablets Inventory 100 Bottles (Individual Doses) l l Dosimeter Charger Inventory and 3 verify operability a e - _ - - - -
. _ . _ ._ . -~ _ ._ _ _ .m.. .. .
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O ^ J i . FOIM EP 02-8 RFN.1 i ATTACIIMIWP 7.0 P.vje 3 of 4 FNERGENCY OPERATIONS FACILITY RADIOLOGICAI, FNERGEN.'.Y KIT /CMl!Nt'r SUPPLIES Surveillance Frequency: Otnrterly Surveillance Date: EXNIEMENT SURVEllLANCE MINIMUM ITEM Rf2%RKS SilLP REQU1REMENr QU,WF1TY VEDIFICATION LIFE (INITIALS) SCIR Inventory and 4 verify operability Spare Cylinders Inventory and 8 verify operability Check Source Inventory 3 Offsite Survey Maps Inventory 3 IIPfl Procedure:; Inventory 1 Set Forms 10 ea Calculator Inventory and 1 verify operability-Clip Board Inventory 3 , Pencils - Mech Inventory 24 , Grease 8 Paper Inventory 12 Pads ygg Pens Inventory 24 Dr to m j j ,4 *tf Perm Markers Inventory 12 i o i umu Stop Watch Inventory and 3 ) d verify operability I o . ]
" " Conpass Inventory and 1 l u verify operability u
{ 4
g. i l FOIN CP 02-8 REV. 1 l ATTACINFNr 7.0 Page 4 of 4 FNERGENCY OPERATIONS FACILITY RADIOLOGICAL FNFJGM.'Y KIT /CNilNF?r SUPPLIES Surveillance Frequency: Qturterly Surveillance Date: FJOUIPMINT SURVEILLANCE HINIPRM ITEN RENARKS SHELF REQU1RENENT QUANTITY VERIF1 CATION LIFE (INITIALS) 4 Handie Talkie Radios Inventory and verify 3 operability Herculite Inventory 1 Roll 1 Liter Poly Bottle Inventory 10 Planchettes Inventory 50 anears Inventory 1 Box Sanple Holder Inventory 1 I Trowel Inventory 1 weezer Inventory 2 Maps of Plant Radiation Inventory 1 Set Control Area 4 RRIS Film Inventroy 5 Packages l M Al M
> mm Reviewed By: Date:
j .4 T Fanergency Planning Adninistrator i o N 0% M W I 1 H
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i [ l l l l l FT)NM EP 02-9 REV. O ATTACINENT 8.0 Page 1 of 3 OFFSITE MONl'IORING TEAM K1T Surveillance Frequency: Quarterly Surveillance Date:
, EXJUIPMENT SURVEILLANCE MINIMUM ITtN REMARKS SitLF REQUIREMENT QUAMPITY VERIFICATION LitT (INITIALS) i ,
- 1 Liter Poly Bottle Inventory 1 A/S Filters Part Inventory 1 Box l
1 A/S Filters Zeolite Inventory 20 i Battery 9 Volt Inventory 12 Battery D Cell Inventory 12 Calculator Inventory 1 i Check Source Inventory 1 i
! Clipboard Inventory 1 Conpass Inventory 1 Duct Tape Inventory 1 Roll Flashlights Inventory 3 j B/G Survey Meter Inventory 1 4
yyM Frisker Inventory 1 i or a m l j .4 9 In-Vol Air Sanpler Inventory 1 0 1
%*y Survey Maps Inventory 1 H
O
- PC Gloves Rubber Inventory 3 Pairs y PC Gloves Surgeon Inventory 1 Box PC Set Inventory 3 j Pencils (Mech) Inventory 5
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U i . I PUHM EP 02-9 REV. O ATTACIMFNr 8.0 Page 2 of 3
; OFFSITE MON 11DRING TFAM KIT Surveillance Frequency: Quarterly j Survei1 lance Date:
4 EQUIINENF SURVElILANCE MINIPRM ITEPt RFPRRKS SitLP j REQUIRDtENT QUANTITY VERIFICATION LIFE (INITIALS) Ibns Inventory 5 Perm Markers Inventory 4
- Planchettes Inventory 50
) Plast!O Bags 12" x 15" Inventory 5 1 Plastic Bags 6" x 8" Inventory 25 ! Plastic Bags. - Large Inventory 5 Rad Mon Data Sheets Inventory 10 j Se ple Holder Inventory 1 Snears Inventory 1 i Stopwatch Inventory 1 Tape Measure Inventory 1 i
- Trowel Inventory 1 j ((h to 4 'o Tweezers Inventory 1
- 8* Scissors o Inventory 1 w as u
" Potassitan Iodide Tables
$ Inventory 5 Bottles (Individual Doses)
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- Clipboard Inventory 1 W
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H)HM EP 02-9 REV. 0 ATTACitMFNT 8.0 Page 3 of 3 OFFSITE MONI1DRING TEAM KIT Surveillance Frequency: Quarterly Surveillance IMte: EQUIPMENT SURVE!LIANCE MINIPtM ITEM RENARKS fRIELF ' REQUIRD Mrr QUAffrITY VERIFICATION LIFE (INITIALS) Air Sanple Labels Inventory 50 Keys (lake Gate,1LD Boxes, Air Inventory 4 Sanpler, Met Toner
- Reviewed By: Date:
Bnergency Planning Administrator FDRM EP 02-10 REV. 2 i 4 m :o m aem tQ < M e. o uau m I H O
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A ! ) i 1 mRM EP 02-10 REV. 2 l ATTACINfNT 9.0 Page 1 of I l AP11UIRCE RADIOft)GICAL FNFRGF20Y KIT /CAllINET SUPPhilg ; j Surveillance Ftrvjtq: Quarterly l Surveillance Ibte: 1 EQUIPMENT SURVEILINCE MINIMLN ITFM RfMARKS SifEIE REQUIRFNFNr QUAPfflTY VERIFICATION LIFE (INITIALS) ! Frisker Inventory 1 I . 6
- Duct Tape Inventory 2 Rolls s
j anears Inventory 1 Hox t l 'D' Cell Batteries Inventory 6 l Labels Inventory 1 Roll ] Pens arul Markers Inventory 2 each t 4 Lapel Air Sar@ler Inventory 1 i i 1
- i 0-500 MR Pocket Ion Chamber Inventory 3 l
] 0-SR Pocket Ion Chamber Inventory 3 " i i Assorted Plastic Rags Inventory Badge TLD Inventory 6 j Dosimetry Issue Forms Inventory 2 Form EP 9.1-3 Inventory 5 TWM Form EP 9.1-4 Inventory 5 ' } g,O Form EP 9.2-1 Inventory 5 l t 4 : O Form @ 9.M Iw W ory 5 a ui l J. Dosimeter Charger Inventory 1 u N0frE: 1he kit is stored in PACS. i Reviewer 1 By: Date:
- Hnergency Plan Attninistrator.
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)
l FUIM EP 02-11 REV. 1 l AfrAONENT 10.0 Page 1 of 3 4 RANSOM MFNORII.L Il0 SPITAL RADIO [DGICAL EMERGFNCY EQUIINENT AM) SUPPLIES SurvRilance Frequency: Quarterly Surveillance Date: l EQUIPMENT SURVEILIANCE MINIPUt ITFN RDERKS Sitt2_F l REQUIRENENT QUANTITY VERIFICATION LIFE j (INITIALS) l Mobile Radiation Bnergency Cart Inventory 1 i Frisker with Probe and Cable . Inventory and Verity
; Operability 1 t
0-500 Pet /Hr Self Reading i Dosimeter Inventory 10 l Ibdge TID's Inventory 10 ) Ring T[D's - Inventory 10 j Dosimeter Charger Inventory 1 l , j Decontamination Table Top Inventory 1 Mobile Trash Receptacles Inventory 2 , 15 Gallon Water Re ptacles Inventory 2 j Decontamination Kit Inventory 1 l Sample Taking Kit Inventory 1
! MWM .
- y$$ Protective Clothing Packs Inventory 20 to -
g,O Pusking Tape Inventory 6 rolls
, c) j f Radiation Rope Inventory I roll n t.n Lead Pig Inventory 1 Decontamination Manual Inventory 1
! Radiation Accident Posters Inventory 2 r l i
N l v) l. IN)f44 EP 02-11 REV.1 ATTAONENr 10.0 Page 2 of 3 RANSOM MENORIAL Il0 SPITAL RADIOLDGICAL EMERGENCY EUUllHENT Surveill.ince Frequency: Quarterly
- Surveillance Date
- EQU1PMENT SURVEILEANCE MINIf1JM iTIN RENARKS SHELF j REQUIREMENT QUAffflTY VERIFICATION LIFE j (INITIALS)
Yellow lierculite Inventory 1 Roll 3 Miite Herculite Inventory 1 Roll l Green Herculite (Precut) Inventory 1 Yellow Herculite (Precut) Inventory 3 i
- Step Off Pads Inventory 2 Snears Inventory 1 Box
! Radiation Area Signs Inventory 10 l
R02 Survey Meter Inventory and Verify Operability 1 i Low Voltsune Air Sanpler Inventory and Verify Operability 1
, Duct Tape Inventory 1 Roll l
Air Sanpler Filters Inventory 1 Box l Air Sanple Labels Inventory 15 m !d M y8y Plastic Bag (6" x 8") Inventory 15
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l g,$ Plastic Bags (Large) Inventory 10 m e g 7 Batteries (9 Volt) Inventory 8 n un w Batteries (D Cell) Inventory 6 u Form EP 8.1-3 Inventory 5 l i J
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i EUlM EP 02-11 REV. 1 ! i ATTACINENT 10.0 Page 3 of 3 j RANSOM MINORIAL IIOSPITAL RADIOIDGICAL EMERGENCY EQUIETGNF SuWeTitance Frequency: Quarterly Surveillance Date: R)UIPMENT SURVEIILANCE MINIMLM ITIM RIMARKS SIELF
- REQUIREMEN! QUANTITY VERIFICATION LIFE (INITIALS) ;
e i l Form EP 9.1-3 Inventory 5 Form EP 9.1-4 Inventory 5 Kimwipes Inventory 1 Box Masslin Inventory 1 Package Drain Hose Inventory 1 j Reviewed By: Date: l Bnergency Planning Attninistrator i , i 1, l m%M l' ' Wem 4 m<m m-O W og M O I H O
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] PACE INEICENCY CABINET EQUIPMENT #' F \
j Surveillance Frequency: Quarterly
^
Surveillance Date: ^
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SURVEILLANCE ITEN g " HQUIPMENT MINIPS.N t, f P' MARKS SPfELF l l , REQUIREMElfr QUANTITY VERIFICATION ./ , LitT ;
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l 4 (INITIALS) ! / , s .
, - TID's Inventory , , ,15 ~ ; { , -(
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i 500 mn PIC's Inventory 15 y * ., s
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'0-5 R PIC's
, ;,' i Inventory 15 t y l i y '. O - 6 f Battery Charger Inventory 1 i i ~
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' - 9V Ikth: ries
- Inventory 1 Box >
g., S. + 13 - a i .F D Cell Batterier , y
,f , / Inventory 1 Box ', 't
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N A/S lisbels i Inventory. ~, 1 Role ~ -l ,
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- g. (f 4 Pencils ,- '} } Inveutcry,,' )3 l 6- . g . . . ,
j i Pens
- Inventory 1 %
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- w Cotton Linets Invmitory 2 Burrfles #
. , < , s , Duct Tape ' Inventory ,, 3 2 i
Emwes, Inventory 1 Box ' m A t1 pam 12 x 15 Bags Inventory 25 to 4 'o 1 m+ l o 6 x 8 Bags . Inventory 25 u os u H l p Surgeon Gloves Inventory 3 Box i O * ' Misslin i Inventory 1 Pkg u t l ". Clear Bags Plastic Inventory 12 ! I Paper Bootle:, Inventory 6 Pair s i i , e s
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FOIN EP 02-12 REV. O A1TACIMENr 11.0 Page 2 of 2 PACS EMERGENCY cal 31 NET. EQUIPMENT Sorveillance Frequency: Quarterly Surveillarx:e Date: 1 EUJIEMENT SURVEIILANCE M!NIMM ITEM REMARKS SfELF REQUIREMENT QUANTITY VERIFICATION LIFE , (INITIALS) l Iloods Inventory 6 i j Plastic Shoecovers Inventory 3 Dozen 4 Paper Coveralls Inventory 3 Cases { i Kinwipes Inventory 1 Box
, Precut Ambulance Hurculite Inventory 1 i
Radwaste Bags Inventory 10 Rad Ribbon Inventory 2 Roles Radiation Area Signs Inventory 6 E I Contamination Area Signs Inventory 6 Step Off Pads Inventory 2 i j Respirators Inventory 20
- Anbulance Kit Inventory 1 W ,d M N O *0 u2 4 'If '
e Reviewed By: Date: g,Og Snergency Planning Adninistrator , N I i p r i O
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FORM EP 02-13 REV 0 0 1 ( [ jq ,/ ATTACHMENT 12.0 (Page 1 of 1)
< LOCATIONS AND DESCRIPTIONS OF FIRST AID SUPPLIES Locations: 1) Control Building Health Physics Office 1984' Elevation
- 2) Operational Support Center (OSC)
Emergency Care Kits
- ITEM QUANTITY t Cervical Collar 1 Scissors n, 1 .
2" Roller Gauze , 6 Rolls , 5x9 Surgical Pad 5 Adhesive Tape 1 Roll Paper Tape _1 Roll Bite Stick -t x 1 Tongue Depressor , 5 Air Splints 2 Triangular Bandage 2 Exam gloves 5 Pair Saline 1 Bottle { 4x4 Gauze Pads 5 S. ! f [~'N Eyewash Solution ' l' s Cold Packs 2
\~ Burn Spray 2 Petroleum Gauze Bandage 1 Bandafds > '
1 Box Ace Bandage 3" 3 Snake Bite Kit 1 Rescue Breather 1 Cotton Swabs 15 Iodine Swabs 2 Boxes
.. Methiolads Swabs 1 Box 3" Bandage Compress 1 Ammonia Inhalants 1 Box Pen & Paper
)
- NOTE: Supplies will be replaced as soon as possible after use.
1 y
.i i EPP 02-1.5 t Rev. 6 Page 33 of 33 l
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O KANSAS GAS & ELECTRIC COMPANY WOLF CREEK GENERATING STATION RADIOLOGICAL EMERGENCY RESPONSE PLAN IMPLEMENTING PROCEDURE COMMUNICATIONS TESTS EPP 02-1.6 Revision 3 I O i L1uM EKERGENC7 P 0 NG <:OORD ATDR E VIEW AL /[ N ~ DATE/ [ E, AMw to/s> /e s EMERGENCY PLANNING ADMINISTRATOR REVIEW DATE' ' i // d . / m PSRC'~ APPROVAL RECOMMENDATION DATE ll' N b
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V.P. DATE' NUCLEAR [ APPROVAL RELEASED DC29 ll-7-8h { DATE I
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~~ 1.0 PURPOSE \s / This procedure defines the requirements-for emergency preparedness communications checks to be conducted on a periodic basis to satisfy the requirements of 10 CFR 50, Appendix E. -
2.0 APPLICATIONS This procedure applies to the Emergency Planning Administrator (EPA) who is responsible for assuring that the communication checks defined in this procedure are performed and documented. 3.0 DEFINITIONS NONE 4.0 INSTRUCTIONS 4.1 This procedure shall be implemented:
- At the discretion of the EPA
- Monthly, per Section 4.4
- Quarterly, per Section 4.5
- Annually, per Section 4.6 4.2 The EPA shall:
4.2.1 Assure that monthly, quarterly, and annual communications checks in sections 4.4, 4.5 and 4.6 respectively, are completed at their required intervals. , 4.2.2 Assign individuals to perform the communications
- checks.
i i 4.2.3 Assure that EPP 02-1.1, " Emergency Preparedness j Program Maintenance" is utilized whenever corrective actions are to be taken. 4.2.4 Review all documentation associated with the communication checks. i f 3 r _- / EPP 02-1.6 Rev. 3
. Page 1 of 12
s , 4.2.5 Assure that.the completed attachments are forwarded to Document Control and a copy is kept on file. 4.3 COMMON GUIDELINES I 4.3.1 Complete all the required communications checks listed on Attachments 1.0, 2.0, and 3.0. 4.3.2 Utilize any conventional telephone in the appropriate facility to complete calls other than those requiring dedicated telephones. 4.3.3 Use the message shown on Attachment 4.0, " Message for
; Communications Checks", when making calls for offsite agencies.
4.3.4 Completing calls on the dedicated telephones will require two individuals. 4.3.5 If the call cannot be completed: 4.3.5.1 Contact the agency using the back-up means as identified in EPP 01-11.1, " Communications", to inform them of the problem. 4.3.5.2 Identify the problem and cause if possible and note it i under the Comments Section of the attachment. l 4.3.6 Await verification call-backs as required. I v 4.3.7 Document the completion of the communication checks on the appropriate cttachment. 4.3.7.1 If the back-up means is not used, mark N/A in the i' appropriate block.
- 4.4 MONTHLY COMMUNICATIONS CHECKS 4.4.1 Conduct communication checks each month.
l 4.4.2 Document monthly communication checks on Attachment 1.0. 4.4.3 Instruct the following agencies that a verification l call-back, repeating the message given to them, is needed. 4.4.3.1 Coffey County Sheriff's Office, 4.4.3.2 Kansas Highway Patrol, Division 4, 4.4.3.3 State Division of Emergency Preparedness. y EPP 02-1.6 Rev. 3 Page 2 of 12 l _
4 4.5 QUARTERLY COMMUNICATIONS CHECKS 4.5.1 Conduct a communications check as described in Attachment 2.0 each calendar quarter. 4.5.2 Document quarterly communications checks on Attachment 2.0. 4.5.3 It is only necessary to use one extension to test the communication network in the TSC and EOF. 4.6 ANNUAL COMMUNICATIONS CHECKS 4.6.1 Conduct annual communications checks on the following communication systems. j 4.6.1.1 In the TSC; radio console channel 4 to vehicles 1, 2 and 3, EOF radio consoles 1-4, Coffey County Ambulance phone line, Ransom Memorial phone line and radio channel 2 to hand-held radios. 4.6.1.2 In the EOF; radio console channel 4 to selected monitoring points (Attachment 3.0), TSC radio console channel 1-4 and coffey County Ambulance phone line. l NOTE: The LKR ra'dios (referred to as hand held radios I or Handie-Talkie Radios) are inventoried and operability checked by Reference 5.5.
\- 4.6.2 Document-annual communications checks on Attachment 3.0.
5.0 REFERENCES
5.1 Wolf Creek Generating Station Radiological Emergency Response Plan 5.2 EPP 01-8.2, Attachment 2.0, " Predetermined Emergency ' Sampling Locations" 5.3 EPP 01-11.1, " Communications" i 5.4 EPP 02-1.1, " Emergency Preparedness Program ,
- Maintenance" i 5.5 EPP 02-1.5, " Maintenance of Emergency Facilities and Equipment" l
5.6 10 CFR 50, Appendix E l EPP 02-1,6 i Rev. 3 Page 3 of 12 1 v
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i . 6.0 RECORDS 6.1. The checklists used for this procedure shall be retained for at least two (2) years by the EPA. 6.2 This EPP does not generate Quality Assurance records. 6.3 Form EP 02-19, " Monthly Communications Checks" l 6.4 Form EP 02-14, " Quarterly Communications Checks" 6.5 Form EP 02-15, " Annual Communications Checks" 7.0 ATTACHMENTS 7.1 Attachment 1.0, " Monthly Communications checks" 7 . 2. Attachment 2.0, " Quarterly Communications Checks" 7.3 Attachment 3.0, " Annual Communications Checks" 7.4 Attachment 4.0, " Message for Communications"
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; FOIE EP 02-19 REV. O
- ATTACHMENT 1.0 i (Page 1 of 2) t MONTHLY COPNUNICATIONS CHECKS Initiated by Received by Verification Comalnications Circuits (Name) (Name) Time Date Call-Back j conpleted j Control Hocm
- 1. NRC ENS NA Direct Ringdown Backup (202) 951-0550 NA l 2. NRC HPN NA Comercial Line (817) 860-8100 NA
- 3. Coffey County Sheriff
- 1) phone 364-2123 I
j . 2) Station radio frequency i
- 4. Kansas Highway Patrol i 1) Phone 431-2100 ,
- 5. State Division of l Dnergency Preparedness
- 1) Ph. (913) 233-9253
- Ext. 321 f
j 2) Radio to Topeka t N i 4 I i EPP'02-1.6 Rev. 3
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I FORM EP 02-19 REV. O ATTACHMEMr 1.0 (Page 2 of 2) MORTHLY COPfiUNICATIONS CHECKS Initiated by Received by Verification Communications Circuits (Name) (Name) Time Date Call-Back r conpleted Technical suoport Center (TSC)
- 1. NRC ENS NA Direct Ringdown Backup (202) 951-3550 NA 5
- 2. NRC-HPN NA
! Commercial Line j (817) 860-8100 NA Dnergency Ooerations
- Facility (EOF) ;
- 1. NRC ENS NA
, 5 Direct Ringdown Backuo (202) 951-0550 NA
- 2. NRC HPN NA Conrnercial Line
] (817) 860-8100 NA i i i I Conducted By Reviewed By , EPA EPP 02-1.6 Rev. 3 Page 6 of 12 4 y.. ..r.p-9eg,m..ygm9.-.ww, %--..-,,%%-4 35e,9y-y _..9,es y .,g-. mqmq7c,s w--w----.. +e yw-, , r,w.,,_ __,_w_ ,_g,,, , ,nw ,-.,.,%,%
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FGE EP 02-14 REV.1 I ATDOMENT 2.0 4 (Page 1 of 2) l I atmarEnts CmemICmcmS omsS i j Received l1hene color Initiated nummication Circuit No. By By Time Date i ' CINIROL ROCH PEMES t i 1. Shift Supv. 340 Orange
- 2. Operation Supv.
, Multi-Line Phcme 343 Brown l 3. CR Comunicator 380 Ivory ,
l 4. Notification 364-Verification 8840 Brown
- 5. Op. Status Board Ring-Recorder down SAS PHONE l
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- 1. Security Shift i Supv. 376 Black TSC PENES
- 1. DED 341 Orange
- 2. DED (Multi-Line) 5751 Brown i
- 3. Notification 364-
, Verificaticri 8840 Brown
- 4. AEC 375 Black
' \
\
- 5. Chemistzy Coor. 5713 Blue with I
Brown Hndl. l 6. DAC 353 White i
- 7. MEC 347 Green
- 8. NRC-Cczuman Use 5701 Brown
- 9. NRC-Camen Use 5702 Brown
- 10. NRC-Crnnen Use 5711 Brown
! 11. Field h Com. 359 Ash
- 12. GAC 346 Green
- 13. OEC 345 Green
- 14. Ops. Status Board Ring-
- Reco A down Brown
- 15. PIC 396 Blus
! 16. RAC 389 Ash l 17. REC 352 1811te { ! 18. SEC 365 Rairym with ! Brown Hndl.
- 19. TSC nummicator 382 Ivory i 20. TSC owmmicator 392 Ivory i
- 21. Tech. Support Coor. 366 Beige
- 22. Telecopy Verify 2673 Brown
! 23. Telecopy Verify 2273 Brown EPP 02-1.6 Rev. 3 Page 7 of 12 i i ,i-
.n--, ,-e-,,-v- - - - ,-n.--. - - , . . -,.,v, , , , , , - . ,,,n_,.n. _.n-.__... _,,..nn.~-enna,- ,. . , - , , _ ,y,
FORM EP 02-14 REV. 1 ATIAQ EENT 2.0 (Page 2 of 2) caAmEY 0:MMICATINS GECKS Itcale Color Initiated Received Cctumunication Circuit No. By By Time Date OSC PHONES
- 1. OSCS 348 Green
- 2. OSCS 360 Ash
- 3. OSTD 361 Ash
- 4. 01em. Director 2318 Brown
- 5. Dosimetry Director 2320 Brown EOF PHGIES
- 1. DEM 342 Orange
- 2. DDI (Multi Line) 5750 Beige
- 3. PIC 372 Blue
- 4. Ringdown Verifica- 364-tion Line 8243 Brown
- 5. ARM 378 Black
- 6. Coffey County Line 364-8734 Brown
- 7. IG State Rep. 364-Emer. Preparedness 8859 Brown
- 8. Security Officer 5822 Brown
- 9. Op. Status Ring- Ring-down (387) down Brown
- 10. NRC General Use 77 5705 Brown (v) 11. NRC General Use
- 12. NRC General Use 5706 5707 Brown Brown
- 13. NRC General Use Conf. Room 5709 Brown
- 14. NRC General Use Conf. Rocan 5710 Brown
- 15. EOF Communicators 384 Ivo29/
- 16. EOF Ccanmunicators 393 Ivory
- 17. Verification Line 364-8840 Brown
- 18. IG State Rep. Rad. 364-8282 Brown
- 19. RAM 355 White
- 20. TI@i 368 Beige
- 21. RRIS Ooerator 5825 Brown
- 22. RAS 391 Ash
- 23. DAS 356 White
- 24. Engineerirn Ibam 368 Beige
- 25. Engineering Team 5071 Brown
- 26. Eng. IDF To Wichita Ring-down Brown Conducted by Reviewed by EPA /Date Q EPP C2-1.G Rev. 3 Page 8 of 12
, FOIM EP 02-15 REV. 1 ATDGMENT 3.0 (Page 1 of 3) s ANNUAL C290NICATINS GECES Initiated by Received by Canmunications Circuits (Name) (Name) Time Date Technical Support Center
- 1. Radio Console -
i Q1annel 4 to 1 a) Vehicle 1 radio , b) Vehicle 2 radio c) Vehicle 3 radio d) Vehicle 4 radio
- 2. EOF Radio Console Qiannels 1 - 4
- 3. Coffey Ccunty Ambulance Co.
(316) 364-2998 .
- 4. Ransom Memorial (913) 242-3344
! 5. Radio Qiannel 2 to hand held radios a 6 I i 1
)
i l EPP 02-1.6 Rev. 3 Page 9 of 12
,. FORM EP 02-15 REV. 1 ATDGMENT 3.0 (Page 2 of 3)
O ANNUAL CIMUNICATIONS CHECES Initiated by Received by Ctanmunications Cizulits (Name) (Name) Time Date j i Emergency Operations Facility
, 1. Radio Console
! Channel 4 to selected i Inonitoring points , (Page 3 of 3) i i 2. TSC Radio Console Channel 1 - 4
- 3. Coffey County Ambulance (316) 364-2998 1
j 1 1 1 EPP 02-1.6 Rev. 3 Page 10 of 12 l
- - - - , . . ~ , , - - _ - - - - - - - - - - -
, FOPM EP 02-15 REV. 1 ATDGMENT 3.0 , (Page 3 of 3)
V aman cxmmemmS oans Check 20% of the Field Monitorirq Sample Incations (as specified in Prrvwhire EPP 01-8.2, Attadment 2.0), annually, rotatirq year to year to ensure that all points are checked in 5 years. List the ~ points checked and Wether or not the cruminications link was satisfactory or unsatisfactory. Refer to past connunication check sheets to make sure that different points are used year to year. Point Sat or Unsat Point Sat or Unsat I Conducted By Reviewed By EPA / Data [ EPP 02-1.6 Rev. 3 i Page 11 of 12 I
4 4 . i 6 , l l ATDGMENT 4.0 MESSAGE FOR CDfCNICATIONS GECKS This is (Name) frem the Wolf Creek Generating Station. This check is being performed (Monthly, Quarterly, Annually) to ccuply with NRC regulations. No emergency exists at the Wolf Creek Plant. May I please have your name for @ % tion purposes. Thank you for your csrp=.ation. i a i , i i i i b
- V l
i i i i I i l I l i I I EPP 02-1.6 Rev. 3 Page 12 of 12
5 O l WOLF CREEK GENERATING STATION RADIOLOGICAL EMERGENCY RESPONSE PLAN IMPLEMENTING PROCEDURE TONE ALERT RADIO MAINTENANCE AND COMPENSATING MEASURES EPP 02-1.7 Revision 1 l l O h E4NMINGVCOOADINATOR REVIEW EMERGENCY'P
/s 2D SY-DATE / /
I 44A h M EMERGENCY PLANNING ADMINISTRATOR REVIEW 10 l2 Y $ $ DATE' '
/)/?t_ 3 ll~3kto I
PSRC' APPROVAL RECOMMENDATION DATE db, dl/$dL ill1/Fs . eA E , Av.P. .ecmAR7,ReVAL RELEASED 0C29 l l $Y DATE
- O 1
4-w--_.-.,-4 ,.-,--,-%- - ,,---,-- - -, - - -
1.O PURPOSE
's - This procedure describes the tone alert radio main-tenance program and the compensating measures which are taken when the tone alert radios are unable to operate on an area-wide basis.
2.0 APPLICABILITY This procedure is applicable to the Emergency Planning Coordinator (EPC) and the Emergency Planning Admin-istrator (EPA). l 3.O PROCEDURE The initial county-wide distribution of tone alert radios was performed from July 1984 to November 1984. Approximately 550 tone alert radios were placed into residents' homes which were outside the 70 dB(C) range of the emergency sirens but inside the 10-mile effec-tive Emergency Planning Zone (EPZ). Following is a description of how the distribution of tone alert radios will be monitored and audited. l 3.1 The Coffey County Emergency Preparedness Office is responsible for distributing the tone alert radios to the residents in the above described area, per Contingency Plan Implementing Procedure No. 40.
\
3.2 A copy of the tone alert radio contract completed by each new recipient is forwarded monthly to the EPC. l Also, a copy of any maintenance entries made on old contracts is forwarded to the EPC monthly. l 3.3 In addition, the names and addresses of the residents who refuse a tone alert radio is forwarded to the EPC l monthly. 3.4 The EPC is responsible for directing an audit of the l County tone alert radio contracts quarterly. 3.5 If the coffey County Emergency Preparedness
- Coordinator calls the EPC and requests additional tone l alert radios, the EFC orders the additional radios l
through Purchasing. j 3.6 All defective units are returned to the Coffey County Emergency Preparedness Coordinator, who then gives
- them to the EPC for final disposition (e.g. repair, j replacement).
l l EPP 02-1.7 l Rev. 1 Page 1 of 2
4.0 COMPENSATORY MEASURES
- 4.1 When notified of an Emergency Broadcast System (EBS) malfunction such that an EBS signal is unable to transmit into Coffey County or that a siren (s) is nonfunctional, the EPC is responsible to ensure that l the Coffey County Sheriff's Office is notified of the situation. The Sheriff's Office institutes plans to notify the affected area by use of available Sheriff vehicles equipped with sirens.
4.2 The EPC assures that an NRC Resident Inspector is informed of the occurrence. 4.3 The EPC ensures that compensatory measures are main-tained until the malfunction is corrected. 4.4 The EPC assures Licensing is notified of the occurrence. Licensing will perform a reportability l evaluation in accordance with regulations. I
5.0 REFERENCES
l l 5.1 Contingency Plan Implementing Procedure #40, " Tone Alert Radio Distribution and Maintenance" 6.0 RECORDS ( None 7.0 ATTACHMENTS None i t l i EPP 02-1.7 Rev. 1 Page 2 of 2
KANSAS GAS AND ELECTRIC COMPANY THE ELECTRC COMPANY GLENN L MOESTEa November 14, 1986 v4CE PRE.sDgre? NUCLEam Mr. R. D. Martin, Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Document Control Desk U. S. Nuclear Regulatory Commission Washington, D. C. 20555 KMLNRC 86-215 Re: Docket No. STN 50-482 Subj: Changes to the Wolf Creek Generating Station Radiological Emergency Response Procedures Gentlemen: Transmitted herewith are the latest revisions to the Wolf Creek Generating Station (WCGS) Radiological Emergency Response Plan Implementing Procedures which are listed below. Procedure revision implemented on 10/17/86: TCN No. 01-1,1-2 (Issued against EPP 01-1.1 Revision 5) Procedure revisions implemented on 10/30/86: EPP 02-1.1 Revision 4 EPP 02-1.8 Revision 3 Procedure revisions implemented on 11/07/86: EPP 01-1.1 Revision 6 EPP 01-7.3 Revision 6 EPP 01-2.1 Revision 3 EPP 01-10.1 Revision 3 EPP 01-3.1 Revision 5 EPP 01-11.2 Revision 3 EPP 01-3.2 Revision 4 EPP 01-12.1 Revision 4 EPP 01-3.4 Revision 3 EPP 02-1.2 Revision 5 EPP 01-6.1 Revision 4 EPP 02-1.4 Revision 2 EPP 01-7.2 Revision 6 EPP 02-1.5 Revision 6 EPP 02-1.7 Revision 1 EPP 02-1.6 Revision 3 h0 ; 2-q 201 N. Markd -Wichita, Kansas - Masi Address: PO, Box 208 i Wichota, Kansas 67201 - Telephone: Area Code (316) 2616451
KMLNRC 86-215 Page 2 November 14, 1986 i This submittal is in accordance with 10 CFR 50 Appendix E Section V. If you
' have any questions concerning this subject, please contact me or Mr. O. L.
Maynard of my staff. Very truly yours,
'u/O C a Glenn L. Koester GLK:see e es uent - Nucle r Enclosures cc: P0'Connor (2) 4 JCummins i CHackney 1
1 l i 4 i j ( i i l' 4 I I 1 4 d 4 l 1 i i 4
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