ML031250101: Difference between revisions

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| number = ML031250101
| number = ML031250101
| issue date = 04/14/2003
| issue date = 04/14/2003
| title = Watts Bar - Emergency Plan Implementing Procedure Revision, Table of Contents - Section 4.1
| title = Emergency Plan Implementing Procedure Revision, Table of Contents - Section 4.1
| author name = Hagy J F, Pavlechko F L
| author name = Hagy J, Pavlechko F
| author affiliation = Tennessee Valley Authority
| author affiliation = Tennessee Valley Authority
| addressee name =  
| addressee name =  
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==1.0 INTRODUCTION==
==1.0 INTRODUCTION==


===1.1 Purpose===
1.1 Purpose A. This Procedure provides instructions for accounting for all onsite personnel and visitors prior to an orderly evacuation of a specific area(s) or the site during a radiological or toxic hazard emergency.
A. This Procedure provides instructions for accounting for all onsite personnel and visitors prior to an orderly evacuation of a specific area(s) or the site during a radiological or toxic hazard emergency.
This Procedure describes the method for notifying all site personnel and gives guidance for re-entry initiation.
This Procedure describes the method for notifying all site personnel and gives guidance for re-entry initiation.
This Procedure also describes the method for notifying and conducting an orderly evacuation of the near site facilities within the Owner Controlled Area (OCA).B. The scope of this procedure includes emergency and non-emergency response personnel, visitors, contractor/construction personnel and other persons who may be within the OCA during an emergency situation.
This Procedure also describes the method for notifying and conducting an orderly evacuation of the near site facilities within the Owner Controlled Area (OCA).B. The scope of this procedure includes emergency and non-emergency response personnel, visitors, contractor/construction personnel and other persons who may be within the OCA during an emergency situation.
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==2.0 REFERENCES==
==2.0 REFERENCES==


===2.1 Industry===
2.1 Industry Documents 1. NUREG-0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants 2. CFR 50.47, Code of Federal Regulations
Documents 1. NUREG-0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants 2. CFR 50.47, Code of Federal Regulations
: 3. NRC Information Notice 2002-14, Ensuring a Capability to Evacuate Individuals, Including Members of the Public, from the Owner-Controlled Area 2.2 Plant Instructions
: 3. NRC Information Notice 2002-14, Ensuring a Capability to Evacuate Individuals, Including Members of the Public, from the Owner-Controlled Area 2.2 Plant Instructions
: 1. TVA Radiological Emergency Plan 2. EPIP-2, Notification of Unusual Event 3. EPIP-3, Alert 4. EPIP-4, Site Area Emergency 5. EPIP-5, General Emergency 6. EPIP-6, Activation And Operation Of The Technical Support Center (TSC)7. EPIP-7, Activation And Operation Of The Operations Support Center (OSC)8. EPIP-1 1, Security and Access Control 9. EPIP-14, Radiological Control Response 10. EPIP-16, Termination Of The Emergency And Recovery PAGE 4 OF 34 REVISION 18 I WBN PERSONNEL ACCOUNTABILITY AND EVACUATION
: 1. TVA Radiological Emergency Plan 2. EPIP-2, Notification of Unusual Event 3. EPIP-3, Alert 4. EPIP-4, Site Area Emergency 5. EPIP-5, General Emergency 6. EPIP-6, Activation And Operation Of The Technical Support Center (TSC)7. EPIP-7, Activation And Operation Of The Operations Support Center (OSC)8. EPIP-1 1, Security and Access Control 9. EPIP-14, Radiological Control Response 10. EPIP-16, Termination Of The Emergency And Recovery PAGE 4 OF 34 REVISION 18 I WBN PERSONNEL ACCOUNTABILITY AND EVACUATION
_PIPFra I 3.0 INSTRUCTIONS
_PIPFra I 3.0 INSTRUCTIONS 3.1 General Personnel Information A. Normal Entering and Exiting of the Plant Protected Area (PA).1. Individuals entering the plant PA shall: Swipe their badge into the entry card reader,* Enter the PA in accordance with security procedures.
 
===3.1 General===
Personnel Information A. Normal Entering and Exiting of the Plant Protected Area (PA).1. Individuals entering the plant PA shall: Swipe their badge into the entry card reader,* Enter the PA in accordance with security procedures.
: 2. Individuals exiting the PA shall: Swipe their badge into the exit card reader in the appropriate exit portals.* Exit the PA in accordance with security procedures.
: 2. Individuals exiting the PA shall: Swipe their badge into the exit card reader in the appropriate exit portals.* Exit the PA in accordance with security procedures.
: 3. Exit card readers function as accountability card readers for personnel exiting the PA.4. Protected Area assembly/Accountability card reader locations are identified in Appendix A.3.2 Activating the Assembly and Accountability Process A. Shift Manager/Site Emergency Director 1. The Shift Manager (SM) or Site Emergency Director (SED) shall initiate the activation of the assembly and accountability process.a. The SM\SED can delegate a designee to carry out the actions of this process, but can not delegate the decision to activate the process.2. Refer to Appendix D for activation.
: 3. Exit card readers function as accountability card readers for personnel exiting the PA.4. Protected Area assembly/Accountability card reader locations are identified in Appendix A.3.2 Activating the Assembly and Accountability Process A. Shift Manager/Site Emergency Director 1. The Shift Manager (SM) or Site Emergency Director (SED) shall initiate the activation of the assembly and accountability process.a. The SM\SED can delegate a designee to carry out the actions of this process, but can not delegate the decision to activate the process.2. Refer to Appendix D for activation.
PAGE 5 OF 34 REVISION 18 C WBN PERSONNEL ACCOUNTABILITY AND I EPIP-8 l lEVACUATION
PAGE 5 OF 34 REVISION 18 C WBN PERSONNEL ACCOUNTABILITY AND I EPIP-8 l lEVACUATION 3.0 INSTRUCTIONS (continued) 3.3 Site Assembly and Accountability A three-minute undulating siren (a siren that raises and lowers in volume and pitch) or public address announcements are the general methods for notifying personnel that emergency conditions exists requiring the assembly and accountability of site personnel.
 
===3.0 INSTRUCTIONS===
(continued) 3.3 Site Assembly and Accountability A three-minute undulating siren (a siren that raises and lowers in volume and pitch) or public address announcements are the general methods for notifying personnel that emergency conditions exists requiring the assembly and accountability of site personnel.
Upon recognition that the assembly and accountability process has been activated, all personnel shall begin immediately to take applicable actions.A. Non-Emergency Responders inside the PA 1. Upon recognition of the assembly and accountability process, non-emergency responders, shall proceed immediately to their designated assembly areas as listed on Appendix A.2. Arriving at the assembly area, personnel shall: a. Swipe their badge into the accountability card reader (applies only to those assembly areas within the protected area).b. Remain in the designated assembly prea until released by the (SED) or a plant evacuation is ordered, following the instructions on the plant address system or through Nuclear Security.B. Non-Emergency Responders outside the PA Note: Specific areas outside the PA (See Appendix B) have designated assembly areas posted.1. Non-Emergency Responders outside the PA represent unescorted visitors, contractors/construction personnel, and others persons in public access areas on or passing within the OCA.2. Upon recognition of the assembly and accountability process, non-emergency responders shall proceed immediately to the closest designated assembly area.3. Nuclear Security will attempt to direct observed personnel to an assembly area as conditions permit.4. Nuclear Security will provide further instructions to personnel in the designated assembly areas.PAGE 6 OF 34 REVISION 18 I WBN PERSONNEL ACCOUNTABILITY AND l I EVACUATION E _P P-8 3.0 INSTRUCTIONS (continued)
Upon recognition that the assembly and accountability process has been activated, all personnel shall begin immediately to take applicable actions.A. Non-Emergency Responders inside the PA 1. Upon recognition of the assembly and accountability process, non-emergency responders, shall proceed immediately to their designated assembly areas as listed on Appendix A.2. Arriving at the assembly area, personnel shall: a. Swipe their badge into the accountability card reader (applies only to those assembly areas within the protected area).b. Remain in the designated assembly prea until released by the (SED) or a plant evacuation is ordered, following the instructions on the plant address system or through Nuclear Security.B. Non-Emergency Responders outside the PA Note: Specific areas outside the PA (See Appendix B) have designated assembly areas posted.1. Non-Emergency Responders outside the PA represent unescorted visitors, contractors/construction personnel, and others persons in public access areas on or passing within the OCA.2. Upon recognition of the assembly and accountability process, non-emergency responders shall proceed immediately to the closest designated assembly area.3. Nuclear Security will attempt to direct observed personnel to an assembly area as conditions permit.4. Nuclear Security will provide further instructions to personnel in the designated assembly areas.PAGE 6 OF 34 REVISION 18 I WBN PERSONNEL ACCOUNTABILITY AND l I EVACUATION E _P P-8 3.0 INSTRUCTIONS (continued)
C. Emergency Responders Note: Emergency Responders should already be in (or in route to) their assigned Response Facility as a result of pager notification.
C. Emergency Responders Note: Emergency Responders should already be in (or in route to) their assigned Response Facility as a result of pager notification.
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: 2. REFER TO EPIP-14, Radiological Control Response.3.4 Particular Limited Area Evacuation CAUTION: KNOWN HAZARDOUS CONDITIONS require Operations or TSC to evacuate a particular plant area(s). Follow announced directions PROMPTLY and EXACTLY.A. The SM/SED or designee shall make a public address (PA) announcement and follow the instructions in Appendix G.B. Personnel in the affected area(s), upon hearing the public address announcement or being notified of the particular area evacuation by any means shall do the following:
: 2. REFER TO EPIP-14, Radiological Control Response.3.4 Particular Limited Area Evacuation CAUTION: KNOWN HAZARDOUS CONDITIONS require Operations or TSC to evacuate a particular plant area(s). Follow announced directions PROMPTLY and EXACTLY.A. The SM/SED or designee shall make a public address (PA) announcement and follow the instructions in Appendix G.B. Personnel in the affected area(s), upon hearing the public address announcement or being notified of the particular area evacuation by any means shall do the following:
: 1. If working in a contaminated zone, exit the zone in accordance with Radiological Control (RADCON) procedures, unless instructed otherwise by RADCON.2. Exit the affected area in an orderly manner.C. Personnel not in the affected area(s) should continue assigned tasks if not instructed otherwise and should not enter the affected area(s) until the "All Clear" has been announced or directed through emergency response processes.
: 1. If working in a contaminated zone, exit the zone in accordance with Radiological Control (RADCON) procedures, unless instructed otherwise by RADCON.2. Exit the affected area in an orderly manner.C. Personnel not in the affected area(s) should continue assigned tasks if not instructed otherwise and should not enter the affected area(s) until the "All Clear" has been announced or directed through emergency response processes.
PAGE 8 OF 34 REVISION 18 WBN PERSONNEL ACCOUNTABILITY AND EVACUATION E _P 3.0 INSTRUCTIONS (continued)
PAGE 8 OF 34 REVISION 18 WBN PERSONNEL ACCOUNTABILITY AND EVACUATION E _P 3.0 INSTRUCTIONS (continued) 3.5 Evacuation of Site Non-Emergency Response Personnel 1. A site evacuation will be conducted upon an order issued by the SM/SED.This Order will be issued to the TSC Nuclear Security Manager or the Nuclear Security Shift Supervisor or their designee, following the completion of Assembly and Accountability.
 
===3.5 Evacuation===
 
of Site Non-Emergency Response Personnel 1. A site evacuation will be conducted upon an order issued by the SM/SED.This Order will be issued to the TSC Nuclear Security Manager or the Nuclear Security Shift Supervisor or their designee, following the completion of Assembly and Accountability.
A. Non-Emergency Responders Within the Plant Protected Area.1. All personnel assembled in designated assembly areas within the protected area shall remain in those areas until released for the purpose of evacuation.
A. Non-Emergency Responders Within the Plant Protected Area.1. All personnel assembled in designated assembly areas within the protected area shall remain in those areas until released for the purpose of evacuation.
Visitors shall remain with escorts until they have exited the protected area.2. The TSC or NS will by public address announcement(s) or dispatching Security personnel, brief and release persons in assembly areas.3. Once released, personnel shall go immediately to the protected area exit portal. Personnel shall swipe their badge into the exit card reader or as instructed by NS. The protected area shall be exited in accordance with security procedures unless otherwise instructed.
Visitors shall remain with escorts until they have exited the protected area.2. The TSC or NS will by public address announcement(s) or dispatching Security personnel, brief and release persons in assembly areas.3. Once released, personnel shall go immediately to the protected area exit portal. Personnel shall swipe their badge into the exit card reader or as instructed by NS. The protected area shall be exited in accordance with security procedures unless otherwise instructed.
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E. Nuclear Security (NS) will implement Appendices B. C, & H of this procedure.
E. Nuclear Security (NS) will implement Appendices B. C, & H of this procedure.
F. Radiological Control (RADCON) will implement Appendix I of this procedure.
F. Radiological Control (RADCON) will implement Appendix I of this procedure.
 
4.0 RECORD RETENTION 4.1 Records of Classified Emergencies The materials generated in support of key actions during an actual emergency requiring personnel accountability or evacuation are considered Lifetime retention Non-QA records. Materials shall be forwarded to the EP Manager who shall submit any records deemed necessary to demonstrate-performance to the Corporate EP Manager for storage.4.2 Drill and Exercise Records The materials deemed necessary to demonstrate performance of key actions during drills are considered Non-QA records. These records shall be forwarded to the EP Manager who shall retain records deemed necessary to demonstrate six-year plan performance for six years. The EP Manager shall retain other records in this category for three years.PAGE 10 OF 34 REVISION 18 WBN PERSONNEL ACCOUNTABILITY AND EVACUATION E 1IP APPENDIX A PROTECTED AREA ASSEMBLY AREAS Page 1 of 1 LOCATION REPORTING ORGANIZATION(S)
===4.0 RECORD===
RETENTION 4.1 Records of Classified Emergencies The materials generated in support of key actions during an actual emergency requiring personnel accountability or evacuation are considered Lifetime retention Non-QA records. Materials shall be forwarded to the EP Manager who shall submit any records deemed necessary to demonstrate-performance to the Corporate EP Manager for storage.4.2 Drill and Exercise Records The materials deemed necessary to demonstrate performance of key actions during drills are considered Non-QA records. These records shall be forwarded to the EP Manager who shall retain records deemed necessary to demonstrate six-year plan performance for six years. The EP Manager shall retain other records in this category for three years.PAGE 10 OF 34 REVISION 18 WBN PERSONNEL ACCOUNTABILITY AND EVACUATION E 1IP APPENDIX A PROTECTED AREA ASSEMBLY AREAS Page 1 of 1 LOCATION REPORTING ORGANIZATION(S)
El. 713' Mechanical Maintenance Shop Mechanical Maintenance personnel El. 713' Chem Lab Chemistry Laboratory personnel El. 713' RADCON Lab RADCON personnel, AUOs, OSC responders, Fire Operators/others El. 729' Electrical Maintenance Shop Electrical Maintenance personnel El. 729' Instrument Maintenance Shop Instrument Maintenance personnel El. 729' MOB Maintenance Engineering Maintenance Planning/Engineering/others Support Office El. 741' Ops. Procedures Office Procedure Writers/NRC Office/others El. 755' Technical Support Center TSC emergency responders (TSC)El. 755' Main Control Room Control Room and Operations personnel Plant Assembly Room Main Office Building occupants/others EQB, Vending Area EQB and MDB Occupants, MODS personnel/others PAGE 11 OF 34 REVISION 18 WBN PERSONNEL ACCOUNTABILITY AND EVACUATION I EPIP APPENDIX B ASSEMBLY AREA(S) (OUTSIDE THE PROTECTED AREA) NOTIFICATIONS (Page 1 of 3)Nuclear Security (NS) will provide the information from this appendix to all assembly areas outside the protected area (listed below) as it becomes available or as directed by the SMISED or TSC Security Manager.* Initial contact should be by phone with Fax message used for follow-up.
El. 713' Mechanical Maintenance Shop Mechanical Maintenance personnel El. 713' Chem Lab Chemistry Laboratory personnel El. 713' RADCON Lab RADCON personnel, AUOs, OSC responders, Fire Operators/others El. 729' Electrical Maintenance Shop Electrical Maintenance personnel El. 729' Instrument Maintenance Shop Instrument Maintenance personnel El. 729' MOB Maintenance Engineering Maintenance Planning/Engineering/others Support Office El. 741' Ops. Procedures Office Procedure Writers/NRC Office/others El. 755' Technical Support Center TSC emergency responders (TSC)El. 755' Main Control Room Control Room and Operations personnel Plant Assembly Room Main Office Building occupants/others EQB, Vending Area EQB and MDB Occupants, MODS personnel/others PAGE 11 OF 34 REVISION 18 WBN PERSONNEL ACCOUNTABILITY AND EVACUATION I EPIP APPENDIX B ASSEMBLY AREA(S) (OUTSIDE THE PROTECTED AREA) NOTIFICATIONS (Page 1 of 3)Nuclear Security (NS) will provide the information from this appendix to all assembly areas outside the protected area (listed below) as it becomes available or as directed by the SMISED or TSC Security Manager.* Initial contact should be by phone with Fax message used for follow-up.
* Should phone contact not be made, (i.e. off-hours  
* Should phone contact not be made, (i.e. off-hours  
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: 1. RECORD notification that conditions have been met that require an Initials Time order to evacuate site non-emergency response personnel.
: 1. RECORD notification that conditions have been met that require an Initials Time order to evacuate site non-emergency response personnel.
: 2. VERIFY Assembly and accountability have been completed.
: 2. VERIFY Assembly and accountability have been completed.
E 3. NOTIFY the Central Emergency Control Center (CECC) Director of the impending evacuation.  
E 3. NOTIFY the Central Emergency Control Center (CECC) Director of the impending evacuation.
(5-751-1614) (IF not staffed, NOTIFY the Operations Duty Specialist, 5-751-1700).
(5-751-1614) (IF not staffed, NOTIFY the Operations Duty Specialist, 5-751-1700).
: 4. CONSIDER first the precautionary evacuation of all non-essential personnel (outside the Protected Area) from the site. These personnel will be assembled in their designated assembly areas. (Appendices B and C)Once completed, non-essential personnel within the Protected Area can be evacuated (Appendix A).5. PROVIDE any special instructions to assembly area(s) through PA announcements, Emergency Dispatches or NS communications.
: 4. CONSIDER first the precautionary evacuation of all non-essential personnel (outside the Protected Area) from the site. These personnel will be assembled in their designated assembly areas. (Appendices B and C)Once completed, non-essential personnel within the Protected Area can be evacuated (Appendix A).5. PROVIDE any special instructions to assembly area(s) through PA announcements, Emergency Dispatches or NS communications.
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==2.0 REFERENCES==
==2.0 REFERENCES==


===2.1 Source===
2.1 Source Documents 1. NUREG 0654, FEMA-REP-1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in support of Nuclear Power Plants 2. NUREG 0696, Functional Criteria for Emergency Response Facilities, Final Report 2.2 Interfacing Documents 1. NP Radiological Emergency Plan (REP)2. WBN-EPIP-2 Notification of Unusual Event 3. WBN-EPIP-3 Alert 4. WBN-EPIP-4 Site Area Emergency 5. WBN-EPIP-5 General Emergency 6. WBN-EPIP-12, Emergency Equipment and Supplies 7. SPP-3.1 Corrective Action Program 8. SPP-3.5 Regulatory Reporting Requirements
Documents 1. NUREG 0654, FEMA-REP-1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in support of Nuclear Power Plants 2. NUREG 0696, Functional Criteria for Emergency Response Facilities, Final Report 2.2 Interfacing Documents 1. NP Radiological Emergency Plan (REP)2. WBN-EPIP-2 Notification of Unusual Event 3. WBN-EPIP-3 Alert 4. WBN-EPIP-4 Site Area Emergency 5. WBN-EPIP-5 General Emergency 6. WBN-EPIP-12, Emergency Equipment and Supplies 7. SPP-3.1 Corrective Action Program 8. SPP-3.5 Regulatory Reporting Requirements
: 9. ANSI Standard N.18.7-19762.0 PAGE 4 of 24 REVISION 16 WBN MEDICAL EMERGENCY RESPONSE EPIP-1 0 3.0 INSTRUCTIONS 3.1 Initial Response Upon discovering an ill or injured person, ALL WBN personnel shall A. ADMINISTER immediate aid for any life threatening situation (IF TRAINED).B. SUMMON assistance from available personnel in the immediate area.C. NOTIFY the Control Room Ext. 3911 and state that a medical emergency has occurred and RESPOND to ALL Questions.
: 9. ANSI Standard N.18.7-19762.0 PAGE 4 of 24 REVISION 16 WBN MEDICAL EMERGENCY RESPONSE EPIP-1 0 3.0 INSTRUCTIONS
 
===3.1 Initial===
Response Upon discovering an ill or injured person, ALL WBN personnel shall A. ADMINISTER immediate aid for any life threatening situation (IF TRAINED).B. SUMMON assistance from available personnel in the immediate area.C. NOTIFY the Control Room Ext. 3911 and state that a medical emergency has occurred and RESPOND to ALL Questions.
NOTE Individuals not involved in the emergency are to remain at their work stations, refrain from using the phone, portable radio, and elevators, and continue working unless called upon for assistance or told to move to another location.CAUTION Patients known or suspected of being in medical distress shall not be allowed to walk, especially when the cause of distress may be aggravated by exertion.3.2 Control Room Response Upon receipt of medical emergency notification, Control Room personnel shall perform APPENDIX A, Control Room Operator Medical Response Checklist.
NOTE Individuals not involved in the emergency are to remain at their work stations, refrain from using the phone, portable radio, and elevators, and continue working unless called upon for assistance or told to move to another location.CAUTION Patients known or suspected of being in medical distress shall not be allowed to walk, especially when the cause of distress may be aggravated by exertion.3.2 Control Room Response Upon receipt of medical emergency notification, Control Room personnel shall perform APPENDIX A, Control Room Operator Medical Response Checklist.
 
3.3 Shift Manager Response Upon receipt of medical emergency notification, the Shift Manager shall perform APPENDIX B, Shift Manager (SM) Medical Response Checklist.
===3.3 Shift===
IF Offsite Hospital assistance is required, THEN the Shift Manager shall perform APPENDIX D, Hospital Notification Report.PAGE 5 of 24 REVISION 16 I WBN I MEDICAL EMERGENCY RESPONSE I EPIP 0 3.0 Instructions (continued) 3.4 Incident Commander Response Upon receipt of medical emergency notification, the Incident Commander (US) shall perform APPENDIX E, Incident Commander (US) Medical Response Guidelines.
Manager Response Upon receipt of medical emergency notification, the Shift Manager shall perform APPENDIX B, Shift Manager (SM) Medical Response Checklist.
IF Offsite Hospital assistance is required, THEN the Shift Manager shall perform APPENDIX D, Hospital Notification Report.PAGE 5 of 24 REVISION 16 I WBN I MEDICAL EMERGENCY RESPONSE I EPIP 0 3.0 Instructions (continued)
 
===3.4 Incident===
Commander Response Upon receipt of medical emergency notification, the Incident Commander (US) shall perform APPENDIX E, Incident Commander (US) Medical Response Guidelines.
3.5 MERT Response Upon receipt of medical emergency notification, the MERT shall perform APPENDIX F, EMS Leader/EMT Medical Response Guidelines.
3.5 MERT Response Upon receipt of medical emergency notification, the MERT shall perform APPENDIX F, EMS Leader/EMT Medical Response Guidelines.
 
3.6 Medical Services Nurse Response Upon receipt of medical emergency notification, the Medical Services Nurse shall perform APPENDIX H, Medical Services Nurse Medical Response Guidelines.
===3.6 Medical===
3.7 RADCON Response Upon receipt of medical emergency notification, RADCON shall perform APPENDIX G, Radiological Control (RADCON) Medical Response Guidelines.
Services Nurse Response Upon receipt of medical emergency notification, the Medical Services Nurse shall perform APPENDIX H, Medical Services Nurse Medical Response Guidelines.
3.8 Nuclear Security and Standby AUO Response Upon receipt of medical emergency notification, Nuclear Security and Standby AUO(s) shall perform APPENDIX I, Nuclear Security/AUOs (on Standby) Medical Response Guidelines.
 
3.9 Supplies Radiological Emergency Supply Cabinets are located at the agreement hospitals and are stocked in accordance with EPIP-12, Emergency Equipment And Supplies.
===3.7 RADCON===
Response Upon receipt of medical emergency notification, RADCON shall perform APPENDIX G, Radiological Control (RADCON) Medical Response Guidelines.
 
===3.8 Nuclear===
Security and Standby AUO Response Upon receipt of medical emergency notification, Nuclear Security and Standby AUO(s) shall perform APPENDIX I, Nuclear Security/AUOs (on Standby) Medical Response Guidelines.
 
===3.9 Supplies===
Radiological Emergency Supply Cabinets are located at the agreement hospitals and are stocked in accordance with EPIP-12, Emergency Equipment And Supplies.
Specialized replacement items can be obtained in coordination with the WBN EP Manager as required.PAGE 6 of 24 REVISION 16 I WBN I MEDICAL EMERGENCY RESPONSE EPIP-10 4.0 RECORDS 4.1 Records of Classified Emergencies The materials generated in support of key actions during an actual Medical Emergency are considered Lifetime retention Non-QA records. Materials shall be forwarded to the EP Manager who shall submit any records deemed necessary to demonstrate performance to the Corporate EP Manager for storage.4.2 Drill and Exercise Records The materials deemed necessary to demonstrate performance of key actions during drills are considered Non-QA records. These records shall be forwarded to the EP Manager who shall retain records deemed necessary to demonstrate six-year plan performance for six years. The EP Manager shall retain other records in this category for three years.PAGE 7 of 24 REVISION 16 I WBN MEDICAL EMERGENCY RESPONSE I EPIP 0 APPENDIX A CONTROL ROOM OPERATOR MEDICAL RESPONSE CHECKLIST (Page 1 of 1)Control room personnel will USE the following checklist in their RESPONSE to an onsite medical emergency.
Specialized replacement items can be obtained in coordination with the WBN EP Manager as required.PAGE 6 of 24 REVISION 16 I WBN I MEDICAL EMERGENCY RESPONSE EPIP-10 4.0 RECORDS 4.1 Records of Classified Emergencies The materials generated in support of key actions during an actual Medical Emergency are considered Lifetime retention Non-QA records. Materials shall be forwarded to the EP Manager who shall submit any records deemed necessary to demonstrate performance to the Corporate EP Manager for storage.4.2 Drill and Exercise Records The materials deemed necessary to demonstrate performance of key actions during drills are considered Non-QA records. These records shall be forwarded to the EP Manager who shall retain records deemed necessary to demonstrate six-year plan performance for six years. The EP Manager shall retain other records in this category for three years.PAGE 7 of 24 REVISION 16 I WBN MEDICAL EMERGENCY RESPONSE I EPIP 0 APPENDIX A CONTROL ROOM OPERATOR MEDICAL RESPONSE CHECKLIST (Page 1 of 1)Control room personnel will USE the following checklist in their RESPONSE to an onsite medical emergency.
A. Obtain NAME of caller_B. LOCATION (Bldg., Elev., Column) _C. Type of Medical Emergency_
A. Obtain NAME of caller_B. LOCATION (Bldg., Elev., Column) _C. Type of Medical Emergency_
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IF in shock or the condition is life threatening, he or she should be taken to the nearest facility, (Rhea Medical Center)NOTE 2 IF the patient is suspected or known to have been over exposed or contaminated with radioactive material, use an agreement hospital and ambulance IF use of the WBN ambulance is not preferred.
IF in shock or the condition is life threatening, he or she should be taken to the nearest facility, (Rhea Medical Center)NOTE 2 IF the patient is suspected or known to have been over exposed or contaminated with radioactive material, use an agreement hospital and ambulance IF use of the WBN ambulance is not preferred.
D NOTIFY Nuclear Security to escort the ambulance onsite or prepare the landing C zone and advise of its Estimated Time of Arrival (ETA)FOLLOW-UP ACTIONS A. PERFORM reporting functions required by SPP-3 01 and SPP-3.5.B IF it is determined that the patient's "Emergency Contact" (located on the a employee's Form TVA 9880, Employee Status and Information Record) needs to be notified, ENSURE that Employee Relations  
D NOTIFY Nuclear Security to escort the ambulance onsite or prepare the landing C zone and advise of its Estimated Time of Arrival (ETA)FOLLOW-UP ACTIONS A. PERFORM reporting functions required by SPP-3 01 and SPP-3.5.B IF it is determined that the patient's "Emergency Contact" (located on the a employee's Form TVA 9880, Employee Status and Information Record) needs to be notified, ENSURE that Employee Relations  
& Development is contacted during regular hours and the employee's Supervisor is contacted during off-hours C. IF the victim was determined to be a non-TVA employee, ensure that their supervision has been notified D. NOTIFY the site Physician (or designee) any time TVA personnel receive radiation E doses in excess of the TVA occupational dose limits at the first opportunity and as information becomes available  
& Development is contacted during regular hours and the employee's Supervisor is contacted during off-hours C. IF the victim was determined to be a non-TVA employee, ensure that their supervision has been notified D. NOTIFY the site Physician (or designee) any time TVA personnel receive radiation E doses in excess of the TVA occupational dose limits at the first opportunity and as information becomes available
(#3254)E NOTIFY Industrial Safety (if on duty) (#3418) or at home if the medical emergency 0 has resulted in a fatality or catastrophic injury (i e three (3) or more hospitalized.
(#3254)E NOTIFY Industrial Safety (if on duty) (#3418) or at home if the medical emergency 0 has resulted in a fatality or catastrophic injury (i e three (3) or more hospitalized.
OSHA notification needs to be made within eight (8) hours after these types of accidents by the site Industrial Safety Manager or duty Plant Manager.PAGE 10 of 24 REVISION 16 I WBN I MEDICAL EMERGENCY RESPONSE I EPIP 0 APPENDIX C NOTIFICATION LIST (Page 1 of 1)WATTS BAR ONSITE EMERGENCY CONTACTS Medical Emergency/TVA Ambulance  
OSHA notification needs to be made within eight (8) hours after these types of accidents by the site Industrial Safety Manager or duty Plant Manager.PAGE 10 of 24 REVISION 16 I WBN I MEDICAL EMERGENCY RESPONSE I EPIP 0 APPENDIX C NOTIFICATION LIST (Page 1 of 1)WATTS BAR ONSITE EMERGENCY CONTACTS Medical Emergency/TVA Ambulance  
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El El El El an 0 m/hour 1I ss.El El El El PAGE 17 of 24 REVISION 16 I WBN IMEDICAL EMERGENCY RESPONSE I EPIP-10 APPENDIX G RADIOLOGICAL CONTROL (RADCON)MEDICAL RESPONSE GUIDELINES (Page 2 of 2)FOLLOW-UP on TLD process and isotopic analysis data to the hospital.
El El El El an 0 m/hour 1I ss.El El El El PAGE 17 of 24 REVISION 16 I WBN IMEDICAL EMERGENCY RESPONSE I EPIP-10 APPENDIX G RADIOLOGICAL CONTROL (RADCON)MEDICAL RESPONSE GUIDELINES (Page 2 of 2)FOLLOW-UP on TLD process and isotopic analysis data to the hospital.
D J. COLLECT contaminated material from the hospital and take necessary D actions for disposal.
D J. COLLECT contaminated material from the hospital and take necessary D actions for disposal.
Transport of material shall be in accordance with the TVA Radiological Material Shipping Manual.K. Any personnel known or suspected of receiving radiation exposure in 0 excess of the TVA occupational dose limits should be reported by RADCON to the Site Physician (or designee) at the first opportunity and as information becomes available.  
Transport of material shall be in accordance with the TVA Radiological Material Shipping Manual.K. Any personnel known or suspected of receiving radiation exposure in 0 excess of the TVA occupational dose limits should be reported by RADCON to the Site Physician (or designee) at the first opportunity and as information becomes available.
(#3254) a PAGE 18 of 24 REVISION 16 WBN MEDICAL EMERGENCY RESPONSE EPIP-1 0 APPENDIX H MEDICAL SERVICES (NURSE)MEDICAL RESPONSE GUIDELINES (Page 1 of 1)A. PREPARE to assist with patient care if the patient is brought to the site medical facility or onsite decontamination facility.B. RESPOND to the accident scene when requested, (Nuclear Security will provide an escort).C. COORDINATE radiological decontamination efforts with RADCON while onsite as the medical status permits.D. ACCOMPANY the EMT in the ambulance if needed.NOTE 1 If an ambulance is to be used, an EMT shall ride with the injured F A nurse may accompany the EMT.NOTE 2 One TVA EMT from the Fire Protection Section or a nurse shall re onsite at all times, except in life-threatening situations as determin the site physician or EMS Leader, in consultation with the SM.NOTE 3 Individuals who have received an acute whole body radiation exp(greater than 5 rem should have hematological studies performed I chromosomal aberrations or other changes in blood constituents.
(#3254) a PAGE 18 of 24 REVISION 16 WBN MEDICAL EMERGENCY RESPONSE EPIP-1 0 APPENDIX H MEDICAL SERVICES (NURSE)MEDICAL RESPONSE GUIDELINES (Page 1 of 1)A. PREPARE to assist with patient care if the patient is brought to the site medical facility or onsite decontamination facility.B. RESPOND to the accident scene when requested, (Nuclear Security will provide an escort).C. COORDINATE radiological decontamination efforts with RADCON while onsite as the medical status permits.D. ACCOMPANY the EMT in the ambulance if needed.NOTE 1 If an ambulance is to be used, an EMT shall ride with the injured F A nurse may accompany the EMT.NOTE 2 One TVA EMT from the Fire Protection Section or a nurse shall re onsite at all times, except in life-threatening situations as determin the site physician or EMS Leader, in consultation with the SM.NOTE 3 Individuals who have received an acute whole body radiation exp(greater than 5 rem should have hematological studies performed I chromosomal aberrations or other changes in blood constituents.
REACTS can provide this service and can be contacted at 9-1-865-576-3131 or 9-1-865-576-1005, by the attending physiciar E. IF an emergency medical situation occurs at the Medical Station which requires EMT or ambulance assistance, REQUEST assistance using extension 3911. IF the situation is not of an emergency nature, the SM may be notified directly using a non-emergency phone number.El El El El person.zmain ed by)sure to detect-I.El PAGE 19 of 24 REVISION 16 I WBN I MEDICAL EMERGENCY RESPONSE I EPIP-10 0 APPENDIX I NUCLEAR SECURITYIAUOs (on Standby)MEDICAL RESPONSE GUIDELINES (Page 1 of 1)NUCLEAR SECURITY A. FACILITATE emergency personnel and equipment movement through El site areas, including control of the plant elevator as necessary.
REACTS can provide this service and can be contacted at 9-1-865-576-3131 or 9-1-865-576-1005, by the attending physiciar E. IF an emergency medical situation occurs at the Medical Station which requires EMT or ambulance assistance, REQUEST assistance using extension 3911. IF the situation is not of an emergency nature, the SM may be notified directly using a non-emergency phone number.El El El El person.zmain ed by)sure to detect-I.El PAGE 19 of 24 REVISION 16 I WBN I MEDICAL EMERGENCY RESPONSE I EPIP-10 0 APPENDIX I NUCLEAR SECURITYIAUOs (on Standby)MEDICAL RESPONSE GUIDELINES (Page 1 of 1)NUCLEAR SECURITY A. FACILITATE emergency personnel and equipment movement through El site areas, including control of the plant elevator as necessary.
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4 3.0 INSTRUCTIONS  
4 3.0 INSTRUCTIONS  
...........................................................
...........................................................
5 3.1 General..........................................................................5...................................................5
5 3.1 General..........................................................................5...................................................5 3.2 Access Control to the Protected Area during Emergencies  
 
===3.2 Access===
Control to the Protected Area during Emergencies  
...............................................
...............................................
5 3.3 Access to the Owner Controlled/Site Perimeter Area ........................................................
5 3.3 Access to the Owner Controlled/Site Perimeter Area ........................................................
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: 1. Site Physical Security Plan 2. Site Security Instruction (SSI) 2.3, Security Radiological Emergency Plan Implementation
: 1. Site Physical Security Plan 2. Site Security Instruction (SSI) 2.3, Security Radiological Emergency Plan Implementation
: 3. EPIP-8, Personnel Accountability and Evacuation
: 3. EPIP-8, Personnel Accountability and Evacuation
: 4. NP Radiological Emergency Plan (REP)5. NUREG 0654 6. Title 10 Code of Federal Regulations Part 20 and 50 7. ANSI N18.7-1976 PAGE 4 OF 12 REVISION 11 I WBN I SECURITY AND ACCESS CONTROL I EPIP-1 1 l-'3.0 INSTRUCTIONS
: 4. NP Radiological Emergency Plan (REP)5. NUREG 0654 6. Title 10 Code of Federal Regulations Part 20 and 50 7. ANSI N18.7-1976 PAGE 4 OF 12 REVISION 11 I WBN I SECURITY AND ACCESS CONTROL I EPIP-1 1 l-'3.0 INSTRUCTIONS 3.1 General NOTE: Terms denoting areas or locations are defined and depicted in Appendix A, Owner Controlled/Site Perimeter and Protected Area.A. Nuclear Security will implement these Instructions in conjunction with EPIP-8,"Personnel Accountability and Evacuation," or as directed by the Site Emergency Director (SED).B. The WBN Emergency Preparedness Manager will establish and maintain an"Emergency Response Organization Call List" comprised of current qualified responders.
 
===3.1 General===
NOTE: Terms denoting areas or locations are defined and depicted in Appendix A, Owner Controlled/Site Perimeter and Protected Area.A. Nuclear Security will implement these Instructions in conjunction with EPIP-8,"Personnel Accountability and Evacuation," or as directed by the Site Emergency Director (SED).B. The WBN Emergency Preparedness Manager will establish and maintain an"Emergency Response Organization Call List" comprised of current qualified responders.
This list will be provided to Nuclear Security and updated quarterly.
This list will be provided to Nuclear Security and updated quarterly.
C. The Site Security Manager shall establish an instruction which delineates specific requirements to be performed by NS during a radiological emergency.
C. The Site Security Manager shall establish an instruction which delineates specific requirements to be performed by NS during a radiological emergency.
This instruction shall address directed requirements for the security force contained in this Procedure.
This instruction shall address directed requirements for the security force contained in this Procedure.
 
3.2 Access Control to the Protected Area during Emergencies A. If directed by the SM/SED, NS will restrict access to the Protected Area during any emergency situation at Watts Bar that has resulted in conditions within the Protected Area which warrant accountability and or evacuation (i.e., Alert, Site Area Emergency, or General Emergency.)
===3.2 Access===
Control to the Protected Area during Emergencies A. If directed by the SM/SED, NS will restrict access to the Protected Area during any emergency situation at Watts Bar that has resulted in conditions within the Protected Area which warrant accountability and or evacuation (i.e., Alert, Site Area Emergency, or General Emergency.)
B. As directed by the SM/SED or TSC Security Manager, onsite hazards should be identified to the emergency responder prior to entering the Protected Area using the hazards awareness board in the Access Portal.C. Emergency responders whose names appear on the Emergency Response Organization Call List or as authorized by the SED or NS representative in the TSC or OSC Manager will be authorized access.D. NRC Personnel have authorized access.E. Personnel allowed entry will be responsible for entering into the accountability card readers as soon as possible after entering the protected area.F. Fire protection vehicles, radiological control (RADCON) monitoring vans, and other emergency vehicles and personnel will be permitted immediate access upon confirmation with the SED that an onsite emergency does exist and their service has been requested.
B. As directed by the SM/SED or TSC Security Manager, onsite hazards should be identified to the emergency responder prior to entering the Protected Area using the hazards awareness board in the Access Portal.C. Emergency responders whose names appear on the Emergency Response Organization Call List or as authorized by the SED or NS representative in the TSC or OSC Manager will be authorized access.D. NRC Personnel have authorized access.E. Personnel allowed entry will be responsible for entering into the accountability card readers as soon as possible after entering the protected area.F. Fire protection vehicles, radiological control (RADCON) monitoring vans, and other emergency vehicles and personnel will be permitted immediate access upon confirmation with the SED that an onsite emergency does exist and their service has been requested.
PAGE 5 OF 12 REVISION 11 I WBN I SECURITY AND ACCESS CONTROL IEPIP-1 1 3.3 Access to the Owner Controlled/Site Perimeter Area A. NS will control access at the OCA Traffic Control Point (Appendix A -map).Access control will be as follows: B. NS will GRANT access to those individuals who display a site or other TVA photo ID badge C. NS will GRANT access to those individuals whose names are indicated on the Emergency Response Organization Call List and/or other approved list as provided by the SED, TSC Security Manager, or OSC Manager.D. NS will GRANT access to others as verbally approved by the SED or NS representative in the TSC.E. As DIRECTED by the TSC Security Manager/Security Shift Supervisor, onsite hazards should be identified to the emergency responder prior to entering the site.NOTE 1: Personnel identification cards, uniforms, vehicle markings or letter of access may be used for identification.
PAGE 5 OF 12 REVISION 11 I WBN I SECURITY AND ACCESS CONTROL IEPIP-1 1 3.3 Access to the Owner Controlled/Site Perimeter Area A. NS will control access at the OCA Traffic Control Point (Appendix A -map).Access control will be as follows: B. NS will GRANT access to those individuals who display a site or other TVA photo ID badge C. NS will GRANT access to those individuals whose names are indicated on the Emergency Response Organization Call List and/or other approved list as provided by the SED, TSC Security Manager, or OSC Manager.D. NS will GRANT access to others as verbally approved by the SED or NS representative in the TSC.E. As DIRECTED by the TSC Security Manager/Security Shift Supervisor, onsite hazards should be identified to the emergency responder prior to entering the site.NOTE 1: Personnel identification cards, uniforms, vehicle markings or letter of access may be used for identification.
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C. In the event of a Protected Area evacuation, site personnel will receive instructions from the SM or the TSC/SED concerning what actions to take prior to exiting the Protected Area. Security personnel will follow the instructions provided in EPIP-8 "Personnel Accountability and Evacuation and/or the Physical Security Plan.3.5 Egress Control from the Site Area and Owner Controlled Area NOTE: Unauthorized personnel found in the owner controlled area will be reported to the TSC Security Manager for egress instructions.
C. In the event of a Protected Area evacuation, site personnel will receive instructions from the SM or the TSC/SED concerning what actions to take prior to exiting the Protected Area. Security personnel will follow the instructions provided in EPIP-8 "Personnel Accountability and Evacuation and/or the Physical Security Plan.3.5 Egress Control from the Site Area and Owner Controlled Area NOTE: Unauthorized personnel found in the owner controlled area will be reported to the TSC Security Manager for egress instructions.
A. Egress from the owner controlled area will be authorized only after RADCON completes a survey (if radiological release has occurred) or as granted by the SED through the TSC, NS Manager.B. NS will provide traffic control (if security staff are available).
A. Egress from the owner controlled area will be authorized only after RADCON completes a survey (if radiological release has occurred) or as granted by the SED through the TSC, NS Manager.B. NS will provide traffic control (if security staff are available).
 
3.6 Security and Media Contingencies A. Press personnel who respond to WBN during an emergency will be directed to the Joint Information Center (JIC) in Chattanooga. (Appendix C)B. If the emergency situation has been terminated or the JIC has not been activated and Press personnel respond to the site, the Owner Controlled Area Security Traffic Control Point will notify the SM or SED. Once approval has been granted by the Plant Duty Manager and escorts are provided, the Press will be directed to the WBN Local News Center (LNC) which is classroom 19 in the Training Center to await a briefing or additional instructions.
===3.6 Security===
and Media Contingencies A. Press personnel who respond to WBN during an emergency will be directed to the Joint Information Center (JIC) in Chattanooga. (Appendix C)B. If the emergency situation has been terminated or the JIC has not been activated and Press personnel respond to the site, the Owner Controlled Area Security Traffic Control Point will notify the SM or SED. Once approval has been granted by the Plant Duty Manager and escorts are provided, the Press will be directed to the WBN Local News Center (LNC) which is classroom 19 in the Training Center to await a briefing or additional instructions.
C. The WBN Communications Specialist should be notified as soon as possible of the situation (i.e., numbers of people, from: TV, radio, etc.). The contact is listed in the Plan of the Day (POD). IF the contact is unavailable, THEN request the ODS to notify the Information Duty Officer of the situation.
C. The WBN Communications Specialist should be notified as soon as possible of the situation (i.e., numbers of people, from: TV, radio, etc.). The contact is listed in the Plan of the Day (POD). IF the contact is unavailable, THEN request the ODS to notify the Information Duty Officer of the situation.
PAGE 7 OF 12 REVISION 11 I WBN I SECURITY AND ACCESS CONTROL I EPIP-1 I 4.0 RECORD RETENTION 4.1 Records of Classified Emergencies The materials generated in support of key actions during an actual emergency are considered Lifetime retention Non-QA records. Materials shall be forwarded to the EP Manager who shall submit any records deemed necessary to demonstrate performance to the Corporate EP Manager for storage.4.2 Drill and Exercise Records The materials deemed necessary to demonstrate performance of key actions during drills are considered Non-QA records. These records shall be forwarded to the EP Manager who shall retain records deemed necessary to demonstrate six-year plan performance for six years. The EP Manager shall retain other records in this category for three years.PAGE 8 OF 12 REVISION 11 I WBN I SECURITYAND ACCESS CONTROL l EPIP-1 1 APPENDIX A Owner Controlled/Site Perimeter and Protected Area (Page 1 of 2)DEFINITIONS:
PAGE 7 OF 12 REVISION 11 I WBN I SECURITY AND ACCESS CONTROL I EPIP-1 I 4.0 RECORD RETENTION 4.1 Records of Classified Emergencies The materials generated in support of key actions during an actual emergency are considered Lifetime retention Non-QA records. Materials shall be forwarded to the EP Manager who shall submit any records deemed necessary to demonstrate performance to the Corporate EP Manager for storage.4.2 Drill and Exercise Records The materials deemed necessary to demonstrate performance of key actions during drills are considered Non-QA records. These records shall be forwarded to the EP Manager who shall retain records deemed necessary to demonstrate six-year plan performance for six years. The EP Manager shall retain other records in this category for three years.PAGE 8 OF 12 REVISION 11 I WBN I SECURITYAND ACCESS CONTROL l EPIP-1 1 APPENDIX A Owner Controlled/Site Perimeter and Protected Area (Page 1 of 2)DEFINITIONS:
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==2.0 REFERENCES==
==2.0 REFERENCES==


===2.1 Interfacing===
2.1 Interfacing Documents 1. RCDP-8, Radiological Control Departmental Procedure: "Radiological Instrumentation and Equipment Controls" 2. NP Radiological Emergency Plan (REP)3. ANSI Standard N18.7-1976
 
: 4. WBN FSAR Chapter Six 2.2 Other Documents 1. NUREG 0654, Revision 1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants Page 4 of 41 Revision 19 WBN EMERGENCY EQUIPMENT AND SUPPLIES I EPIP-12 l3.0 INSTRUCTIONS 3.1 General Instructions
Documents 1. RCDP-8, Radiological Control Departmental Procedure: "Radiological Instrumentation and Equipment Controls" 2. NP Radiological Emergency Plan (REP)3. ANSI Standard N18.7-1976
: 4. WBN FSAR Chapter Six 2.2 Other Documents 1. NUREG 0654, Revision 1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants Page 4 of 41 Revision 19 WBN EMERGENCY EQUIPMENT AND SUPPLIES I EPIP-12 l3.0 INSTRUCTIONS
 
===3.1 General===
Instructions
: 1. Responsible Organizations (as designated below) shall conduct inventory at the specified frequencies For the purposes of these inventories, monthly is defined as once per calendar month, quarterly is defined as once per calendar quarter, and annual is defined as once per calendar year. Similar frequency definitions as customarily used by performing organizations are acceptable.
: 1. Responsible Organizations (as designated below) shall conduct inventory at the specified frequencies For the purposes of these inventories, monthly is defined as once per calendar month, quarterly is defined as once per calendar quarter, and annual is defined as once per calendar year. Similar frequency definitions as customarily used by performing organizations are acceptable.
RESPONSIBILITIES FOR EMERGENCY EQUIPMENT AND SUPPLIES INVENTORY AND MAINTENANCE  
RESPONSIBILITIES FOR EMERGENCY EQUIPMENT AND SUPPLIES INVENTORY AND MAINTENANCE  
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B. TSC and OSC position activity books are maintained/verified by EP.C. SCBA units and spare bottles shall be verified ready for use.D. Protective clothing and heat or moisture-sensitive items shall be checked for deterioration.
B. TSC and OSC position activity books are maintained/verified by EP.C. SCBA units and spare bottles shall be verified ready for use.D. Protective clothing and heat or moisture-sensitive items shall be checked for deterioration.
E. Flashlights shall be checked for power/operability, and batteries verified within expiration date.F. As necessary, replace batteries with fresh batteries from Power Stores.(Flashlight batteries may be discarded with ordinary refuse. Return calculator or other batteries to the Toolroom for disposal.)
E. Flashlights shall be checked for power/operability, and batteries verified within expiration date.F. As necessary, replace batteries with fresh batteries from Power Stores.(Flashlight batteries may be discarded with ordinary refuse. Return calculator or other batteries to the Toolroom for disposal.)
G. Potassium Iodide (KI) in the OSC medical supply cabinet shall be checked for expiration date as indicated on Appendix H. Stock should be replaced if it expires prior to next projected inventory  
G. Potassium Iodide (KI) in the OSC medical supply cabinet shall be checked for expiration date as indicated on Appendix H. Stock should be replaced if it expires prior to next projected inventory
(#Pkgs * #Tablets/pkg  
(#Pkgs * #Tablets/pkg  
= #doses).H. Seals or break-away locking devices are in place on cabinets which are not routinely used to provide a means of determining if a cabinet has been opened.Page 6 of 41 Revision 19 WBN EMERGENCY EQUIPMENT AND SUPPLIES I EPIP-12 3.1 General Instructions (cont.)9. Emergency Preparedness shall ensure that the contents of emergency equipment and supply cabinets in the emergency facilities are inventoried, inspected, and checked for operability and/or material condition each calendar quarter unless otherwise specified.
= #doses).H. Seals or break-away locking devices are in place on cabinets which are not routinely used to provide a means of determining if a cabinet has been opened.Page 6 of 41 Revision 19 WBN EMERGENCY EQUIPMENT AND SUPPLIES I EPIP-12 3.1 General Instructions (cont.)9. Emergency Preparedness shall ensure that the contents of emergency equipment and supply cabinets in the emergency facilities are inventoried, inspected, and checked for operability and/or material condition each calendar quarter unless otherwise specified.
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& LIMITATIONS A. This Appendix involves contact with NRC's Incident Response Center through the Emergency Notification System (red phone). The SM should be notified prior to testing the red phone to inform him that it is in use and to ensure proper response if NRC calls back for acknowledgment.
& LIMITATIONS A. This Appendix involves contact with NRC's Incident Response Center through the Emergency Notification System (red phone). The SM should be notified prior to testing the red phone to inform him that it is in use and to ensure proper response if NRC calls back for acknowledgment.
B. This Appendix may be performed during any Operational Mode.C. Test steps can be ran out of sequence on this Appendix.2.0 PREREQUISITE ACTIONS[1] OBTAIN permission from the SM prior to testing NRC, ENS phone, communications diesel, and Information Services (I S) diesel.[2] ARRANGE (as needed) for an individual to assist in communication test between facilities.
B. This Appendix may be performed during any Operational Mode.C. Test steps can be ran out of sequence on this Appendix.2.0 PREREQUISITE ACTIONS[1] OBTAIN permission from the SM prior to testing NRC, ENS phone, communications diesel, and Information Services (I S) diesel.[2] ARRANGE (as needed) for an individual to assist in communication test between facilities.
 
3.0 PERFORMANCE 3.1 TSC EMERGENCY NOTIFICATION SYSTEM (ENS) -RED PHONE NOTE 1 The TSC ENS has two connections in the TSC #337-1422.
==3.0 PERFORMANCE==
3.1 TSC EMERGENCY NOTIFICATION SYSTEM (ENS) -RED PHONE NOTE 1 The TSC ENS has two connections in the TSC #337-1422.
NOTE 2 Report failures of ENS to the SM immediately.
NOTE 2 Report failures of ENS to the SM immediately.
If the ENS is out of order from the TSC and the MCR, call the NRC Operations Center immediately on the commercial telephone.
If the ENS is out of order from the TSC and the MCR, call the NRC Operations Center immediately on the commercial telephone.
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& LIMITATIONS A. This Appendix involves testing of emergency facility communications and data equipment.
& LIMITATIONS A. This Appendix involves testing of emergency facility communications and data equipment.
The SM should be notified prior to testing.B. This Appendix may be performed during any Operational Mode.C. Test steps may be performed out of sequence on this Appendix.D. Other precautions are noted within the Appendix.2.0 PREREQUISITE ACTIONS[1] OBTAIN permission from the SM prior to testing.[2] ARRANGE (as needed) for an individual to assist in communication test between facilities.
The SM should be notified prior to testing.B. This Appendix may be performed during any Operational Mode.C. Test steps may be performed out of sequence on this Appendix.D. Other precautions are noted within the Appendix.2.0 PREREQUISITE ACTIONS[1] OBTAIN permission from the SM prior to testing.[2] ARRANGE (as needed) for an individual to assist in communication test between facilities.
 
3.0 PERFORMANCE 3.1 TSC TELEPHONE TESTS[1] VERIFY Key Phones for TSC are functional by calling each number listed in the REND and checking on a copy of the REND page.TSC PHONES SAT UNSAT REMARKS 3.2 TSC FAX MACHINES[1] SEND and RECEIVE faxes using each machine.[2] IDENTIFY the received copies and ATTACH them to data package.[3] CHECK for sufficient supplies of fax/copy paper TSC supply cabinet/copy machine.3865 SAT UNSAT REMARKS 3866 SAT UNSAT REMARKS Page 28 of 41 Revision 19 WBN EMERGENCY EQUIPMENT AND SUPPLIES I EPIP-12 Appendix J QUARTERLY COMMUNICATIONS/EQUIPMENT TEST (Page 2 of 14)3.3 TSC COPIER[1 ] RUN a copy of Attachment 1 to check for proper operation.
==3.0 PERFORMANCE==
3.1 TSC TELEPHONE TESTS[1] VERIFY Key Phones for TSC are functional by calling each number listed in the REND and checking on a copy of the REND page.TSC PHONES SAT UNSAT REMARKS 3.2 TSC FAX MACHINES[1] SEND and RECEIVE faxes using each machine.[2] IDENTIFY the received copies and ATTACH them to data package.[3] CHECK for sufficient supplies of fax/copy paper TSC supply cabinet/copy machine.3865 SAT UNSAT REMARKS 3866 SAT UNSAT REMARKS Page 28 of 41 Revision 19 WBN EMERGENCY EQUIPMENT AND SUPPLIES I EPIP-12 Appendix J QUARTERLY COMMUNICATIONS/EQUIPMENT TEST (Page 2 of 14)3.3 TSC COPIER[1 ] RUN a copy of Attachment 1 to check for proper operation.
TSC COPIER SAT UNSAT REMARKS[2] IDENTIFY and ATTACH copy to data package.[3] CHECK for sufficient supplies of copy paper and toner in copier cabinet.COPIER SAT _ UNSAT REMARKS 3.4 TSC/DRILL ICS TERMINALS[1] PRINT sample ICS data group or screen.[2] IDENTIFY the printout and ATTACH it to data package.TSC ICS Terminals (3) SAT UNSAT REMARKS Page 29 of 41 Revision 19 I WBN I EMERGENCY EQUIPMENT AND SUPPLIES I EPIP-12 l Appendix J QUARTERLY COMMUNICATIONSIEQUIPMENT TEST (Page 3 of 14)3.5 TSC CLASSIFICATION CLOCK[1] VERIFY the time is correct on each clock.[2] VERIFY that a battery UPS is installed at the clock and clock display continues after clock is unplugged from AC power.[3] IF needed, THEN CALL Naval Observatory for correct time.(202-762-1401).
TSC COPIER SAT UNSAT REMARKS[2] IDENTIFY and ATTACH copy to data package.[3] CHECK for sufficient supplies of copy paper and toner in copier cabinet.COPIER SAT _ UNSAT REMARKS 3.4 TSC/DRILL ICS TERMINALS[1] PRINT sample ICS data group or screen.[2] IDENTIFY the printout and ATTACH it to data package.TSC ICS Terminals (3) SAT UNSAT REMARKS Page 29 of 41 Revision 19 I WBN I EMERGENCY EQUIPMENT AND SUPPLIES I EPIP-12 l Appendix J QUARTERLY COMMUNICATIONSIEQUIPMENT TEST (Page 3 of 14)3.5 TSC CLASSIFICATION CLOCK[1] VERIFY the time is correct on each clock.[2] VERIFY that a battery UPS is installed at the clock and clock display continues after clock is unplugged from AC power.[3] IF needed, THEN CALL Naval Observatory for correct time.(202-762-1401).
TSC Clock SAT UNSAT REMARKS 3.6 TSC CECC TERMINAL AND PRINTER[1] PRINT met data from CECC terminal.[2] ATTACH met data printout to Data Sheet for documentation.
TSC Clock SAT UNSAT REMARKS 3.6 TSC CECC TERMINAL AND PRINTER[1] PRINT met data from CECC terminal.[2] ATTACH met data printout to Data Sheet for documentation.
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==2.0 REFERENCES==
==2.0 REFERENCES==


===2.1 Interfacing===
2.1 Interfacing Documents 1. CECC-EPIP-9, "Emergency Radiological Monitoring Procedures" 2. EPIP-6, "Activation and Operation of the Technical Support Center (TSC)" 3. EPIP-7, "Activation and Operation of the Operations Support Center (OSC)" 4. EPIP-8, " Personnel Accountability and Evacuation" 5. EPIP-10, "Medical Emergency Response" 6. EPIP-1 1 "Security and Access Control" 7. EPIP-12, "Emergency Equipment and Supplies" 8. EPIP-13, " Initial Dose Assessment for Radiological Emergencies" 9. EPIP-15, "Emergency Exposure Guidelines" 10. EPIP-16, 'Termination of the Emergency and Recovery" 11. NRC Information Notice 90-08, Kr-85 Hazards from Decayed Fuel 2.2 Developmental Documents 1. CFR 50.72 Immediate Notification Requirements for Operating Nuclear Power Reactors 2. NUREG 0654, FEMA-REP-1, Rev. 1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants 3. RCI-101, Radiation Contamination, and Airborne Surveys 4. RCI-120, Respirator Minimization Process 5. RCI-130, Personnel Decontamination
 
Documents 1. CECC-EPIP-9, "Emergency Radiological Monitoring Procedures" 2. EPIP-6, "Activation and Operation of the Technical Support Center (TSC)" 3. EPIP-7, "Activation and Operation of the Operations Support Center (OSC)" 4. EPIP-8, " Personnel Accountability and Evacuation" 5. EPIP-10, "Medical Emergency Response" 6. EPIP-1 1 "Security and Access Control" 7. EPIP-12, "Emergency Equipment and Supplies" 8. EPIP-13, " Initial Dose Assessment for Radiological Emergencies" 9. EPIP-15, "Emergency Exposure Guidelines" 10. EPIP-16, 'Termination of the Emergency and Recovery" 11. NRC Information Notice 90-08, Kr-85 Hazards from Decayed Fuel 2.2 Developmental Documents 1. CFR 50.72 Immediate Notification Requirements for Operating Nuclear Power Reactors 2. NUREG 0654, FEMA-REP-1, Rev. 1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants 3. RCI-101, Radiation Contamination, and Airborne Surveys 4. RCI-120, Respirator Minimization Process 5. RCI-130, Personnel Decontamination
: 6. ANSI N18.7-1976
: 6. ANSI N18.7-1976
: 7. CFR 20 Standards for Protection Against Radiation 8. EPA 400-R-92-001, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents 9. ICS System User's Guide PAGE 4 OF 26 REVISION 16 I WBN I RADIOLOGICAL CONTROL RESPONSE I EPIP-141 y> 3.0 INSTRUCTIONS
: 7. CFR 20 Standards for Protection Against Radiation 8. EPA 400-R-92-001, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents 9. ICS System User's Guide PAGE 4 OF 26 REVISION 16 I WBN I RADIOLOGICAL CONTROL RESPONSE I EPIP-141 y> 3.0 INSTRUCTIONS 3.1 General Instructions 3.1.1 The response to radiological emergencies by RADCON personnel will depend upon the type and magnitude of the existing emergency condition.
 
===3.1 General===
Instructions 3.1.1 The response to radiological emergencies by RADCON personnel will depend upon the type and magnitude of the existing emergency condition.
This can range from a minimal response requiring one or two people to a total manpower mobilization.
This can range from a minimal response requiring one or two people to a total manpower mobilization.
In addition, it should be noted radiological problems may not be associated with a given emergency  
In addition, it should be noted radiological problems may not be associated with a given emergency
[as defined in the Radiological Emergency Plan (REP)]. Natural phenomena, security threats, or other events not involving radiological problems could be the cause for the emergency status.3.1.2 IF an ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY is classified, RADCON is required to assemble a specific number of personnel as described below.A. During normal and off-shifts, an ALERT will be announced over the public address system and the emergency pagers will be activated. (In the event of a SITE AREA EMERGENCY or GENERAL EMERGENCY, the offsite sirens will be activated by the state.)B. The RADCON Lab will be contacted by the SM/SED, or designee.
[as defined in the Radiological Emergency Plan (REP)]. Natural phenomena, security threats, or other events not involving radiological problems could be the cause for the emergency status.3.1.2 IF an ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY is classified, RADCON is required to assemble a specific number of personnel as described below.A. During normal and off-shifts, an ALERT will be announced over the public address system and the emergency pagers will be activated. (In the event of a SITE AREA EMERGENCY or GENERAL EMERGENCY, the offsite sirens will be activated by the state.)B. The RADCON Lab will be contacted by the SM/SED, or designee.
The Radiological Control Shift Supervisor (RCSS) will determine the number of RADCON personnel currently onsite and will ensure at least a total of seven (7) additional are available onsite within approximately 60 minutes.PAGE 5 OF 26 REVISION 16 I WBN I RADIOLOGICAL CONTROL RESPONSE EPIP-14 3.0 INSTRUCTIONS (continued)
The Radiological Control Shift Supervisor (RCSS) will determine the number of RADCON personnel currently onsite and will ensure at least a total of seven (7) additional are available onsite within approximately 60 minutes.PAGE 5 OF 26 REVISION 16 I WBN I RADIOLOGICAL CONTROL RESPONSE EPIP-14 3.0 INSTRUCTIONS (continued) 3.2 Precautions and Limitations During a radiological emergency, established radiological control procedures will normally be utilized to cover most situations.
 
===3.2 Precautions===
 
and Limitations During a radiological emergency, established radiological control procedures will normally be utilized to cover most situations.
Since the magnitude of the problem(s) may be more severe, it is imperative that all requirements for entry into affected plant areas be met. This section summarizes items that will need to be addressed prior to entry into the affected areas and during recovery operations.
Since the magnitude of the problem(s) may be more severe, it is imperative that all requirements for entry into affected plant areas be met. This section summarizes items that will need to be addressed prior to entry into the affected areas and during recovery operations.
 
3.2.1 Plant accidents involving core damage may produce excessive dose rates and airborne activity concentrations within plant areas.Radiological precautions must be followed under these conditions until available data indicates otherwise.
====3.2.1 Plant====
3.2.2 These precautions could include the following:
accidents involving core damage may produce excessive dose rates and airborne activity concentrations within plant areas.Radiological precautions must be followed under these conditions until available data indicates otherwise.
 
====3.2.2 These====
precautions could include the following:
* The use of respiratory equipment.
* The use of respiratory equipment.
* Issuance of KI.* Multiple layers of protective clothing.* The use of electronic dosimeters, multiple TLDs and extremity TLDs as appropriate.
* Issuance of KI.* Multiple layers of protective clothing.* The use of electronic dosimeters, multiple TLDs and extremity TLDs as appropriate.
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Initial entry will probably require the use of respiratory equipment, since iodines may be present in significant quantities.
Initial entry will probably require the use of respiratory equipment, since iodines may be present in significant quantities.
CAUTION IF spent fuel damage is involved, be aware of the potential for significant skin doses from Kr-85. After spent fuel has decayed greater than 190 days, Kr-85 is the predominant gaseous nuclide.Consequently, the dose to the skin could be approximately 150 times the whole body dose.PAGE 6OF 26 REVISION 16 I WBN I RADIOLOGICAL CONTROL RESPONSE I EPIP-14 4 3.0 INSTRUCTIONS (continued) 3.2.4 The respiratory guidelines in Appendix H will be considered during emergency incidents.
CAUTION IF spent fuel damage is involved, be aware of the potential for significant skin doses from Kr-85. After spent fuel has decayed greater than 190 days, Kr-85 is the predominant gaseous nuclide.Consequently, the dose to the skin could be approximately 150 times the whole body dose.PAGE 6OF 26 REVISION 16 I WBN I RADIOLOGICAL CONTROL RESPONSE I EPIP-14 4 3.0 INSTRUCTIONS (continued) 3.2.4 The respiratory guidelines in Appendix H will be considered during emergency incidents.
 
3.2.5 Special precautions must be taken when obtaining samples. Smears may have significant dose rates (in the REM/hr range). High airborne activity could result in significant activity concentrations being collected onto the filter media. FOLLOW standard RADCON procedures, should samples be considered radiological hazards.3.2.6 ENSURE all electronic dosimeters are properly processed for each worker. MAKE arrangements to have TLDs read, as soon as possible.IF possible, RESTRICT repetitive entries of workers. SUBSTITUTE other qualified personnel for team members, on reentry's, to distribute exposures.
====3.2.5 Special====
precautions must be taken when obtaining samples. Smears may have significant dose rates (in the REM/hr range). High airborne activity could result in significant activity concentrations being collected onto the filter media. FOLLOW standard RADCON procedures, should samples be considered radiological hazards.3.2.6 ENSURE all electronic dosimeters are properly processed for each worker. MAKE arrangements to have TLDs read, as soon as possible.IF possible, RESTRICT repetitive entries of workers. SUBSTITUTE other qualified personnel for team members, on reentry's, to distribute exposures.
Employee's remaining allowable dose shall be verified by RADCON prior to entry into plant areas.3.2.7 IF plant conditions are such that radiological conditions are changing rapidly, it may not be possible to use previous data in order to determine protective requirements.
Employee's remaining allowable dose shall be verified by RADCON prior to entry into plant areas.3.2.7 IF plant conditions are such that radiological conditions are changing rapidly, it may not be possible to use previous data in order to determine protective requirements.
This factor must be considered prior to allowing survey teams into affected plant areas.3.2.8 The "Buddy System" shall be utilized for initial entries into any area where radiological conditions are not known or any area where radiological conditions could be changing due to plant conditions.
This factor must be considered prior to allowing survey teams into affected plant areas.3.2.8 The "Buddy System" shall be utilized for initial entries into any area where radiological conditions are not known or any area where radiological conditions could be changing due to plant conditions.
At least one person of the buddy system must be qualified in radiological controls procedures.
At least one person of the buddy system must be qualified in radiological controls procedures.
Monitoring teams should maintain communication capabilities with the RADCON Lab.3.2.9 Habitability surveys of OSC, TSC, and assembly areas shall be performed as necessary.
Monitoring teams should maintain communication capabilities with the RADCON Lab.3.2.9 Habitability surveys of OSC, TSC, and assembly areas shall be performed as necessary.
3.2.10 Advanced Radiation Worker (ARW) trained REP responders will respond (upon request) to the Radiological Control Shift Supervisor during a radiological emergency and provide support and surveillance as needed during the initial phase.PAGE 7 OF 26 REVISION 16 WBN RADIOLOGICAL CONTROL RESPONSE EPIP-1 4 3.0 INSTRUCTIONS (continued)
3.2.10 Advanced Radiation Worker (ARW) trained REP responders will respond (upon request) to the Radiological Control Shift Supervisor during a radiological emergency and provide support and surveillance as needed during the initial phase.PAGE 7 OF 26 REVISION 16 WBN RADIOLOGICAL CONTROL RESPONSE EPIP-1 4 3.0 INSTRUCTIONS (continued) 3.3 Response Classification Guidelines 3.3.1 NOTIFICATION OF UNUSUAL EVENT A. No offsite radiological problems are postulated during a NOTIFICATION OF UNUSUAL EVENT.B. These events require a certain notification to be made to offsite agencies.
 
===3.3 Response===
Classification Guidelines
 
====3.3.1 NOTIFICATION====
 
OF UNUSUAL EVENT A. No offsite radiological problems are postulated during a NOTIFICATION OF UNUSUAL EVENT.B. These events require a certain notification to be made to offsite agencies.
These events will not have any major impact on RADCON.C. RADCON will follow standard practices and procedures during response work.3.3.2 ALERT A. A limited radiological release is possible during an ALERT situation.
These events will not have any major impact on RADCON.C. RADCON will follow standard practices and procedures during response work.3.3.2 ALERT A. A limited radiological release is possible during an ALERT situation.
Onsite emergency teams will be activated and offsite agencies contacted.
Onsite emergency teams will be activated and offsite agencies contacted.
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OBTAIN further instructions and PERFORM required surveillance(s).
OBTAIN further instructions and PERFORM required surveillance(s).
K. Additional manpower support and equipment may be obtained from other TVA nuclear facilities.
K. Additional manpower support and equipment may be obtained from other TVA nuclear facilities.
 
3.3.4 GENERAL EMERGENCY A. During a GENERAL EMERGENCY, there may be radiation releases to the environment requiring RADCON response.
====3.3.4 GENERAL====
EMERGENCY A. During a GENERAL EMERGENCY, there may be radiation releases to the environment requiring RADCON response.
These releases may require the implementation of evacuation procedures.
These releases may require the implementation of evacuation procedures.
B. An extensive RADCON response will be required during a GENERAL EMERGENCY.
B. An extensive RADCON response will be required during a GENERAL EMERGENCY.
C. The actions described under SITE AREA EMERGENCY will be applicable to a GENERAL EMERGENCY condition as well.D. During a GENERAL EMERGENCY, conditions in the RADCON Lab may be such that evacuation is warranted.
C. The actions described under SITE AREA EMERGENCY will be applicable to a GENERAL EMERGENCY condition as well.D. During a GENERAL EMERGENCY, conditions in the RADCON Lab may be such that evacuation is warranted.
If this situation develops, REFER TO Appendix B.E. All subsequent offsite activities will be coordinated with offsite support agency survey teams to make the best use of available manpower.REPORT all survey results as soon as possible to the TSC or CECC (if activated) so recommendations to the proper agencies can be made to initiate any required protective actions.PAGE 10 OF 26 REVISION 16 WBN RADIOLOGICAL CONTROL RESPONSE EPIP-14 3.0 INSTRUCTIONS (continued)
If this situation develops, REFER TO Appendix B.E. All subsequent offsite activities will be coordinated with offsite support agency survey teams to make the best use of available manpower.REPORT all survey results as soon as possible to the TSC or CECC (if activated) so recommendations to the proper agencies can be made to initiate any required protective actions.PAGE 10 OF 26 REVISION 16 WBN RADIOLOGICAL CONTROL RESPONSE EPIP-14 3.0 INSTRUCTIONS (continued) 3.4 Duties of RADCON Personnel Assigned to the TSC 3.4.1 The TSC is activated during an ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY, and may be activated during a NOTIFICATION OF UNUSUAL EVENT.3.4.2 The RADCON Manager is the designated RADCON TSC Manager.Approved alternates rotate this Emergency Responder Organization (ERO) duty. Additional, suitably trained and qualified personnel are listed on the ERO call list. It should be noted that the duty RCSS may serve as the TSC representative during the initial stages of an emergency until relieved by a duly qualified individual 3.4.3 The responsibilities and duties of the TSC RADCON Manager are summarized in EPIP-6.PAGE 11 OF 26 REVISION 16 I WBN I RADIOLOGICAL CONTROL RESPONSE I EPIP-1 4 3.0 INSTRUCTIONS (continued) 3.5 Duties of RADCON Personnel Assigned to the RADCON Lab.3.5.1 The RADCON Shift Supervisor (RCSS) or qualified designee is responsible for managing the activities of the 713' Lab. Appendix A of this procedure can be used as a guide by the RCSS during REP activities.
 
3.5.2 Survey teams are dispatched from the OSC staging areas. The RCSS is responsible for ensuring survey teams are properly equipped and protected and are aware of any special precautions, plant conditions, or requirements, (e.g., RWP).3.5.3 The RCSS will ensure all entries are properly coordinated and approved by the OSC.3.5.4 The RCSS is responsible for ensuring adequate numbers of RADCON personnel are available to support emergency activities.
===3.4 Duties===
of RADCON Personnel Assigned to the TSC 3.4.1 The TSC is activated during an ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY, and may be activated during a NOTIFICATION OF UNUSUAL EVENT.3.4.2 The RADCON Manager is the designated RADCON TSC Manager.Approved alternates rotate this Emergency Responder Organization (ERO) duty. Additional, suitably trained and qualified personnel are listed on the ERO call list. It should be noted that the duty RCSS may serve as the TSC representative during the initial stages of an emergency until relieved by a duly qualified individual 3.4.3 The responsibilities and duties of the TSC RADCON Manager are summarized in EPIP-6.PAGE 11 OF 26 REVISION 16 I WBN I RADIOLOGICAL CONTROL RESPONSE I EPIP-1 4 3.0 INSTRUCTIONS (continued)
 
===3.5 Duties===
of RADCON Personnel Assigned to the RADCON Lab.3.5.1 The RADCON Shift Supervisor (RCSS) or qualified designee is responsible for managing the activities of the 713' Lab. Appendix A of this procedure can be used as a guide by the RCSS during REP activities.
 
====3.5.2 Survey====
teams are dispatched from the OSC staging areas. The RCSS is responsible for ensuring survey teams are properly equipped and protected and are aware of any special precautions, plant conditions, or requirements, (e.g., RWP).3.5.3 The RCSS will ensure all entries are properly coordinated and approved by the OSC.3.5.4 The RCSS is responsible for ensuring adequate numbers of RADCON personnel are available to support emergency activities.
When an Alert or higher emergency has been classified, ensure seven (7) additional RADCON personnel have responded to the emergency page (printout in OSC/TSC).
When an Alert or higher emergency has been classified, ensure seven (7) additional RADCON personnel have responded to the emergency page (printout in OSC/TSC).
For a summary of minimal assignments during emergency see Appendix G of this Procedure.
For a summary of minimal assignments during emergency see Appendix G of this Procedure.
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For immediate offsite monitoring, the RCSS should request assistance from SQN.3.5.6 The RCSS will dispatch survey teams to assembly areas, the OSC, and TSC to evaluate radiological conditions and monitor radiation levels as conditions dictate. These survey teams will be responsible for monitoring contamination levels (both on personnel and floor/equipment areas) and implementing corrective actions (e.g., decontamination or zoning) as necessary.
For immediate offsite monitoring, the RCSS should request assistance from SQN.3.5.6 The RCSS will dispatch survey teams to assembly areas, the OSC, and TSC to evaluate radiological conditions and monitor radiation levels as conditions dictate. These survey teams will be responsible for monitoring contamination levels (both on personnel and floor/equipment areas) and implementing corrective actions (e.g., decontamination or zoning) as necessary.
3.5.7 The RCSS will monitor the 713' Lab for habitability and will coordinate evacuation activities to the alternate lab location (Appendix B) if warranted.
3.5.7 The RCSS will monitor the 713' Lab for habitability and will coordinate evacuation activities to the alternate lab location (Appendix B) if warranted.
3.5.8 The RCSS may use ICS or Appendix C to track radiological conditions in the plant.PAGE 12 OF 26 REVISION 16 WBN RADIOLOGICAL CONTROL RESPONSE I EPIP- 4 3.0 INSTRUCTIONS (continued)
3.5.8 The RCSS may use ICS or Appendix C to track radiological conditions in the plant.PAGE 12 OF 26 REVISION 16 WBN RADIOLOGICAL CONTROL RESPONSE I EPIP- 4 3.0 INSTRUCTIONS (continued) 3.6 Issuance of Potassium Iodide (KI)3.6.1 IF the TSC RADCON Manager or designee has reason to believe a person's projected cumulative dose to the thyroid from inhalation of radioactive iodine might exceed 10 rem, the exposed person should be started immediately on a dose regimen of potassium iodide (KI). Anyone authorized to administer KI shall be familiar with the Food and Drug Administration's approved package insert and be sure each proposed recipient is similarly informed.
 
KI recipients will acknowledge their understanding of the consequences of taking or refusing KI by signing-in on Appendix F, Potassium Iodide (KI) Issue Report. The initial dose of KI should not be delayed and those who begin therapy should continue the 1 0-day course of KI unless their thyroid dose is determined not to have exceeded 10 rem. An adequate supply of KI for the site is stored at the OSC staging area. FOLLOW dosage schedules as outlined on the package insert.3.6.2 Projected cumulative doses to the thyroid from inhalation of radioactive iodine can be determined using Appendix D, "Occupational Dose from Inhalation of Iodine-131." 3.6.3 KI is stored in the Emergency Medical Supply cabinet (OSC staging area). KI has an approved shelf-life with the expiration date listed on each tablet package. Expiration date verification and necessary replacement are performed in EPIP-12.3.6.4 A copy of the Food and Drug Administration approved package insert shall accompany the issuance of K1. Dosage schedules and other pertinent information are outlined on the package insert and should be followed closely (Appendix E).3.6.5 The issuing agent shall complete Appendix F, Potassium Iodide (KI)Issue Report, when KI is issued. A copy of this report will be routed to the TSC RADCON Manager in a timely manner.PAGE 13 OF 26 REVISION 16 I WBN I RADIOLOGICAL CONTROL RESPONSE I EPIP-14 3.0 INSTRUCTIONS (continued) 3.7 Radioiodine Sample Acquisition CAUTION 1 RCI-101 should be referenced for hazards associated with Silver Zeolite cartridge use.CAUTION 2 Sample cartridges may exhibit high dose rates after sampling during accident conditions.
===3.6 Issuance===
of Potassium Iodide (KI)3.6.1 IF the TSC RADCON Manager or designee has reason to believe a person's projected cumulative dose to the thyroid from inhalation of radioactive iodine might exceed 10 rem, the exposed person should be started immediately on a dose regimen of potassium iodide (KI). Anyone authorized to administer KI shall be familiar with the Food and Drug Administration's approved package insert and be sure each proposed recipient is similarly informed.
KI recipients will acknowledge their understanding of the consequences of taking or refusing KI by signing-in on Appendix F, Potassium Iodide (KI) Issue Report. The initial dose of KI should not be delayed and those who begin therapy should continue the 1 0-day course of KI unless their thyroid dose is determined not to have exceeded 10 rem. An adequate supply of KI for the site is stored at the OSC staging area. FOLLOW dosage schedules as outlined on the package insert.3.6.2 Projected cumulative doses to the thyroid from inhalation of radioactive iodine can be determined using Appendix D, "Occupational Dose from Inhalation of Iodine-131." 3.6.3 KI is stored in the Emergency Medical Supply cabinet (OSC staging area). KI has an approved shelf-life with the expiration date listed on each tablet package. Expiration date verification and necessary replacement are performed in EPIP-12.3.6.4 A copy of the Food and Drug Administration approved package insert shall accompany the issuance of K1. Dosage schedules and other pertinent information are outlined on the package insert and should be followed closely (Appendix E).3.6.5 The issuing agent shall complete Appendix F, Potassium Iodide (KI)Issue Report, when KI is issued. A copy of this report will be routed to the TSC RADCON Manager in a timely manner.PAGE 13 OF 26 REVISION 16 I WBN I RADIOLOGICAL CONTROL RESPONSE I EPIP-14 3.0 INSTRUCTIONS (continued)
 
===3.7 Radioiodine===
 
Sample Acquisition CAUTION 1 RCI-101 should be referenced for hazards associated with Silver Zeolite cartridge use.CAUTION 2 Sample cartridges may exhibit high dose rates after sampling during accident conditions.
Exercise good ALARA practices when handling, storing, and disposing of these cartridges.
Exercise good ALARA practices when handling, storing, and disposing of these cartridges.
 
3.7.1 During accident conditions, noble gas concentrations may be present in significant quantities.
====3.7.1 During====
accident conditions, noble gas concentrations may be present in significant quantities.
The collection of these noble gases on charcoal cartridges during iodine sampling will interfere with subsequent iodine analysis.
The collection of these noble gases on charcoal cartridges during iodine sampling will interfere with subsequent iodine analysis.
Silver zeolite (AgZ) cartridges are provided for use during periods of high noble gas concentrations.
Silver zeolite (AgZ) cartridges are provided for use during periods of high noble gas concentrations.
 
3.7.2 Radioiodine samples should be collected at 30 liters per minute (LPM)for daily or weekly samples. Grab samples may be collected at 30 or 60 LPM based upon the type of air sampler used and the conditions in the sample location.3.7.3 Radioiodine sample volumes of less than 900 liters may be performed if it is known or suspected that dose rates on the AgZ cartridges will exceed 10 mrem/hr. During these instances, sample duration's may be reduced to 5 minutes. Sample duration's less than 5 minutes may be used for ALARA purposes but shall be pre-approved by the RCSS.3.7.4 Upon completion of sampling activities, the air sample should be returned to the RADCON Lab for analysis as soon as possible.
====3.7.2 Radioiodine====
A radiation survey of the sample head shall be performed to determine the contact dose rate. The results of this survey shall determine any special handling or packaging requirements during analysis.PAGE 14 OF 26 REVISION 16 I WBN I RADIOLOGICAL CONTROL RESPONSE I EPIP-1 4 3.0 INSTRUCTIONS (continued) 3.7 Radioiodine Sample Acquisition (continued) 3.7.5 IF the iodine sample activity is  1 mrem/hr., a contact dose rate should be taken by using a Ludlum 14-C or equivalent GM survey instrument with the beta window CLOSED. The radioiodine air activity can be approximated by using the following formula:[Average of the Front and Back Contact laCi/ml = Dose Rate (mrem/hr)
 
samples should be collected at 30 liters per minute (LPM)for daily or weekly samples. Grab samples may be collected at 30 or 60 LPM based upon the type of air sampler used and the conditions in the sample location.3.7.3 Radioiodine sample volumes of less than 900 liters may be performed if it is known or suspected that dose rates on the AgZ cartridges will exceed 10 mrem/hr. During these instances, sample duration's may be reduced to 5 minutes. Sample duration's less than 5 minutes may be used for ALARA purposes but shall be pre-approved by the RCSS.3.7.4 Upon completion of sampling activities, the air sample should be returned to the RADCON Lab for analysis as soon as possible.
A radiation survey of the sample head shall be performed to determine the contact dose rate. The results of this survey shall determine any special handling or packaging requirements during analysis.PAGE 14 OF 26 REVISION 16 I WBN I RADIOLOGICAL CONTROL RESPONSE I EPIP-1 4 3.0 INSTRUCTIONS (continued)
 
===3.7 Radioiodine===
 
Sample Acquisition (continued) 3.7.5 IF the iodine sample activity is  1 mrem/hr., a contact dose rate should be taken by using a Ludlum 14-C or equivalent GM survey instrument with the beta window CLOSED. The radioiodine air activity can be approximated by using the following formula:[Average of the Front and Back Contact laCi/ml = Dose Rate (mrem/hr)
X 5.1 E-3]Volume (liters)3.7.6 Radioiodine cartridges with contact gamma dose rates greater than or equal to 100 mrem/hr shall not be delivered to the Chemistry Lab without prior approval of the Chemistry Count Room Supervisor and the RCSS.3.7.7 RADCON personnel shall inform Chemistry personnel of the contact dose rates of the samples. RADCON personnel should provide radiological coverage during handling, analysis and disposal if samples read greater than 100 mrem/hr. The RCSS will approve disposal methods and location for all samples reading greater than 100 mrem/hr.3.7.8 Gamma analysis results shall be reported to the RCSS as soon as possible.3.7.9 Accident related radioiodine samples should be documented and analyzed in accordance with RCI-101 or CECC-EPIP-9 as appropriate.
X 5.1 E-3]Volume (liters)3.7.6 Radioiodine cartridges with contact gamma dose rates greater than or equal to 100 mrem/hr shall not be delivered to the Chemistry Lab without prior approval of the Chemistry Count Room Supervisor and the RCSS.3.7.7 RADCON personnel shall inform Chemistry personnel of the contact dose rates of the samples. RADCON personnel should provide radiological coverage during handling, analysis and disposal if samples read greater than 100 mrem/hr. The RCSS will approve disposal methods and location for all samples reading greater than 100 mrem/hr.3.7.8 Gamma analysis results shall be reported to the RCSS as soon as possible.3.7.9 Accident related radioiodine samples should be documented and analyzed in accordance with RCI-101 or CECC-EPIP-9 as appropriate.
PAGE 15 OF 26 REVISION 16 I WBN I RADIOLOGICAL CONTROL RESPONSE I EPIP 4 3.0 INSTRUCTIONS (continued)
PAGE 15 OF 26 REVISION 16 I WBN I RADIOLOGICAL CONTROL RESPONSE I EPIP 4 3.0 INSTRUCTIONS (continued) 3.8 Personnel Decontamination and Facilities 3.8.1 RCI-130 describes the procedures to be used for personnel decontamination.
 
3.8.2 Contaminated personnel are normally decontaminated at the 713'elevation decon facility.
===3.8 Personnel===
 
Decontamination and Facilities 3.8.1 RCI-130 describes the procedures to be used for personnel decontamination.
 
====3.8.2 Contaminated====
 
personnel are normally decontaminated at the 713'elevation decon facility.
This facility is equipped with a wash sink, shower, and all necessary supplies.
This facility is equipped with a wash sink, shower, and all necessary supplies.
These supplies normally include various decontamination agents and soaps, towels, clean clothing, and other miscellaneous supplies.3.8.3 Concerning radiation injuries, grossly contaminated personnel with injuries are normally treated at the 713' elevation prior to transfer to an offsite medical facility unless the injury requires immediate transportation (REFER TO EPIP-10).3.8.4 Contaminated personnel requiring offsite medical attention are treated at either of the agreement hospitals (Rhea County Medical Center [Dayton]or Athens Regional Medical Center [Athens]).
These supplies normally include various decontamination agents and soaps, towels, clean clothing, and other miscellaneous supplies.3.8.3 Concerning radiation injuries, grossly contaminated personnel with injuries are normally treated at the 713' elevation prior to transfer to an offsite medical facility unless the injury requires immediate transportation (REFER TO EPIP-10).3.8.4 Contaminated personnel requiring offsite medical attention are treated at either of the agreement hospitals (Rhea County Medical Center [Dayton]or Athens Regional Medical Center [Athens]).
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==2.0 REFERENCES==
==2.0 REFERENCES==


===2.1 Performance===
2.1 Performance References
 
References
: 1. SPP-5.1, Radiological Controls 2. WBN EPIP-10, Medical Emergency Response 3. WBN-RCI-120 Respirator Minimization Process" 2.2 Developmental References
: 1. SPP-5.1, Radiological Controls 2. WBN EPIP-10, Medical Emergency Response 3. WBN-RCI-120 Respirator Minimization Process" 2.2 Developmental References
: 1. ICRP Publication 26, "Recommendation of the International Commission on Radiological Protection" 2. ICRP Publication 28, "The Principles and General Procedures for Handling Emergency and Accidental Exposures of Workers" 3. TVA NP Radiological Emergency Plan 4. EPA 400-R-92/001, and subsequent revisions, "Manual of Protective Action Guides and Protective Actions for Nuclear Incidents" 5. NUREG-0654/FEMA-REP-1, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" 6. Title 10, Code of Federal Regulations, Parts 20 and 50 7. ANSI Standard N.18.7-1976
: 1. ICRP Publication 26, "Recommendation of the International Commission on Radiological Protection" 2. ICRP Publication 28, "The Principles and General Procedures for Handling Emergency and Accidental Exposures of Workers" 3. TVA NP Radiological Emergency Plan 4. EPA 400-R-92/001, and subsequent revisions, "Manual of Protective Action Guides and Protective Actions for Nuclear Incidents" 5. NUREG-0654/FEMA-REP-1, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" 6. Title 10, Code of Federal Regulations, Parts 20 and 50 7. ANSI Standard N.18.7-1976
: 8. ANSI Standard N.13.11 PAGE 4 OF 16 REVISION 11 I WBN I EMERGENCY EXPOSURE GUIDELINES I EPIP-1 56 3.0 INSTRUCTIONS NOTE: Specific definitions as used in this procedure are contained in Appendix D.A. The Site Emergency Director (SED) is the only individual responsible for authorizing Emergency dose limits in excess of TVA Administrative dose limits and 10 CFR 20.1201. Appendix A and B shall be used to provide written authorization.
: 8. ANSI Standard N.13.11 PAGE 4 OF 16 REVISION 11 I WBN I EMERGENCY EXPOSURE GUIDELINES I EPIP-1 56 3.0 INSTRUCTIONS NOTE: Specific definitions as used in this procedure are contained in Appendix D.A. The Site Emergency Director (SED) is the only individual responsible for authorizing Emergency dose limits in excess of TVA Administrative dose limits and 10 CFR 20.1201. Appendix A and B shall be used to provide written authorization.
NOTE: As defined by the emergency situation, this approval may be relayed verbally and documented later.B. The Radiological Control (RADCON) Group is responsible for completing Appendix B-1, "Authorization to Exceed Occupational Dose Limits," obtaining the Site Emergency Director's approval and will perform radiological surveys or other assessments to estimate the radiation doses.C. In all cases, the site RADCON Manager shall be informed of any emergency exposure immediately so that a determination of the total quarterly exposure can be made. Based on the results of the determination, the worker may be restricted from further dose.3.1 EXPOSURE LIMITATIONS
NOTE: As defined by the emergency situation, this approval may be relayed verbally and documented later.B. The Radiological Control (RADCON) Group is responsible for completing Appendix B-1, "Authorization to Exceed Occupational Dose Limits," obtaining the Site Emergency Director's approval and will perform radiological surveys or other assessments to estimate the radiation doses.C. In all cases, the site RADCON Manager shall be informed of any emergency exposure immediately so that a determination of the total quarterly exposure can be made. Based on the results of the determination, the worker may be restricted from further dose.3.1 EXPOSURE LIMITATIONS 3.1.1 ACTIONS FOR LIFE SAVING OR PROTECTION OF THE PUBLIC A. For immediate activities up to 25 rad which are necessary to: (1) Save Human Life.For lifesaving operations situations may occur in which a dose in excess of 25 rad would be required.
 
====3.1.1 ACTIONS====
FOR LIFE SAVING OR PROTECTION OF THE PUBLIC A. For immediate activities up to 25 rad which are necessary to: (1) Save Human Life.For lifesaving operations situations may occur in which a dose in excess of 25 rad would be required.
It is not possible to prejudge the risk that one person should be allowed to take to save the life of another. However, persons undertaking an emergency mission in which the dose would exceed 25 rad to the whole body should do so only on a voluntary basis and with full awareness of the risks involved.(2) Restore equipment necessary to maintain critical safety functions or to establish and maintain a safe shutdown, (3) Prevent or Mitigate a release of radioactivity to the environment for which off-site protective measures may be required.
It is not possible to prejudge the risk that one person should be allowed to take to save the life of another. However, persons undertaking an emergency mission in which the dose would exceed 25 rad to the whole body should do so only on a voluntary basis and with full awareness of the risks involved.(2) Restore equipment necessary to maintain critical safety functions or to establish and maintain a safe shutdown, (3) Prevent or Mitigate a release of radioactivity to the environment for which off-site protective measures may be required.
For these activities, the TEDE of personnel directly involved shall not exceed 25 rad. This limit is applicable only if actions establishing adequate or equivalent protection, with less dose, are not readily available.
For these activities, the TEDE of personnel directly involved shall not exceed 25 rad. This limit is applicable only if actions establishing adequate or equivalent protection, with less dose, are not readily available.
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* RespiratorlSCBA not required to enter airborne (priority I or 2) areas if the the following are true: NOTE: IF INDIVIDUAL'S TOTAL .Individual's internal dose plus external dose will INTAKE FOR THE YEAR not result in TEDE exceeding NRC annual dose TO DATE EXCEEDS 200 limit; and DAC-HRS., DOSE .Delays or hindrances caused by issuing or wearing RESULTING FROM ALL respirators/SCBAs will jeopardize the success or INTAKES FOR THE YEAR timeliness of the task; or ASSESSED IN .Use of a respirator/SCBA will result in a higher DETERMINING THE TEDE. TEDE to the responding individuals.
* RespiratorlSCBA not required to enter airborne (priority I or 2) areas if the the following are true: NOTE: IF INDIVIDUAL'S TOTAL .Individual's internal dose plus external dose will INTAKE FOR THE YEAR not result in TEDE exceeding NRC annual dose TO DATE EXCEEDS 200 limit; and DAC-HRS., DOSE .Delays or hindrances caused by issuing or wearing RESULTING FROM ALL respirators/SCBAs will jeopardize the success or INTAKES FOR THE YEAR timeliness of the task; or ASSESSED IN .Use of a respirator/SCBA will result in a higher DETERMINING THE TEDE. TEDE to the responding individuals.
LOW or MID PRIORITY TASKS Use RCI-120 for respirator issue guidance.NOTE: Protective requirements may be revised at the discretion of the TSC RADCON Manager as sample data becomes available.
LOW or MID PRIORITY TASKS Use RCI-120 for respirator issue guidance.NOTE: Protective requirements may be revised at the discretion of the TSC RADCON Manager as sample data becomes available.
PAGE 14 OF 16 REVISION 11  
PAGE 14 OF 16 REVISION 11
((E RESPIRATOR EVALUATION CHIART (7 RE: RCI-120 OJ z Documented TEDE ALARA evaluation required above 40 DAC-Ilrsicntry ASSUMPTIONS:  
((E RESPIRATOR EVALUATION CHIART (7 RE: RCI-120 OJ z Documented TEDE ALARA evaluation required above 40 DAC-Ilrsicntry ASSUMPTIONS:
: 1. Inefficiency factor = 1.25 2. Respirator P.F. > 100 3. Use of respirator eliminates internal dose component.
: 1. Inefficiency factor = 1.25 2. Respirator P.F. > 100 3. Use of respirator eliminates internal dose component.
10,000 1,000-o G)m 0 In 100 V Ai- 1+F T-T-F H.USE SPHADM PRO'n:CT ou 7- FI-I L F-ATOR.PROTEC N III PMENT--H t M (0 (D 0-4, m m G)m z m cn 0 cn X Cn m I-z m C,-r m cn:D m z x m G)m x-u 0 C,)C G)C m 1-1 C,)10 1 01 I 10 100 1,000 10,000 100,000 DOSE RATE (mrem/hour)
10,000 1,000-o G)m 0 In 100 V Ai- 1+F T-T-F H.USE SPHADM PRO'n:CT ou 7- FI-I L F-ATOR.PROTEC N III PMENT--H t M (0 (D 0-4, m m G)m z m cn 0 cn X Cn m I-z m C,-r m cn:D m z x m G)m x-u 0 C,)C G)C m 1-1 C,)10 1 01 I 10 100 1,000 10,000 100,000 DOSE RATE (mrem/hour)
Line 911: Line 801:
==2.0 REFERENCES==
==2.0 REFERENCES==


===2.1 Interfacing===
2.1 Interfacing Documents 1. EPIP-2, Notification of Unusual Event 2. EPIP-3, Alert 3. EPIP-4, Site Area Emergency 4. EPIP-5, General Emergency 5. EPIP-6, Activation and Operation of the Technical Support Center 6. EPIP-7, Activation and Operation of the Operations Support Center 7. EPIP-15, Emergency Exposure Guidelines
 
: 8. CECC-EPIP-6, CECC Plant Assessment Staff Procedure for Alert, Site Area Emergency, and General Emergency 9. NP Radiological Emergency Plan (REP)10. SPP-4.1, Procurement of Materials, Labor, and Services 2.2 Other Documents 1. NUREG 0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants.2. NRC Administrative Letter 97-03, Plant Restart Discussions Following Natural Disasters 3. CFR 50.47 Emergency Plans and Part 50 Appendix E 4. CFR 20 Standards for Protection Against Radiation 5. ANSI N.18.7-1976 PAGE 4 OF 15 REVISION 16 WBN TERMINATION OF THE EMERGENCY EPIP-16 AND RECOVERY 3.0 INSTRUCTIONS 3.1 TERMINATION 3.1.1 In extended emergency events the Site Emergency Director (SED) in conjunction with the Central Emergency Control Center (CECC) Director and State Emergency Operations Center (when activated) will make the determination of when an emergency condition is resolved in accordance with the following criteria and may declare the onsite termination of the emergency.
Documents 1. EPIP-2, Notification of Unusual Event 2. EPIP-3, Alert 3. EPIP-4, Site Area Emergency 4. EPIP-5, General Emergency 5. EPIP-6, Activation and Operation of the Technical Support Center 6. EPIP-7, Activation and Operation of the Operations Support Center 7. EPIP-15, Emergency Exposure Guidelines
: 8. CECC-EPIP-6, CECC Plant Assessment Staff Procedure for Alert, Site Area Emergency, and General Emergency 9. NP Radiological Emergency Plan (REP)10. SPP-4.1, Procurement of Materials, Labor, and Services 2.2 Other Documents 1. NUREG 0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants.2. NRC Administrative Letter 97-03, Plant Restart Discussions Following Natural Disasters 3. CFR 50.47 Emergency Plans and Part 50 Appendix E 4. CFR 20 Standards for Protection Against Radiation 5. ANSI N.18.7-1976 PAGE 4 OF 15 REVISION 16 WBN TERMINATION OF THE EMERGENCY EPIP-16 AND RECOVERY 3.0 INSTRUCTIONS
 
===3.1 TERMINATION===
3.1.1 In extended emergency events the Site Emergency Director (SED) in conjunction with the Central Emergency Control Center (CECC) Director and State Emergency Operations Center (when activated) will make the determination of when an emergency condition is resolved in accordance with the following criteria and may declare the onsite termination of the emergency.
The recovery organization duties are the responsibility of the Plant Manager and the WBN Vice President.
The recovery organization duties are the responsibility of the Plant Manager and the WBN Vice President.
3.1.2 The termination of an emergency will be dependent on the nature of the emergency and the status of the plant systems following corrective measures.The provisions within this procedure are expected to be applicable to all long term emergencies (i.e., Alert, Site Area Emergency, General Emergency) where the TSC and CECC have activated.
3.1.2 The termination of an emergency will be dependent on the nature of the emergency and the status of the plant systems following corrective measures.The provisions within this procedure are expected to be applicable to all long term emergencies (i.e., Alert, Site Area Emergency, General Emergency) where the TSC and CECC have activated.
It may be necessary to supplement this guidance with provisions specific to the emergency at hand.3.1.3 The decision to terminate the emergency will be based upon a comprehensive review of plant parameters and completion of Appendix A of this procedure.
It may be necessary to supplement this guidance with provisions specific to the emergency at hand.3.1.3 The decision to terminate the emergency will be based upon a comprehensive review of plant parameters and completion of Appendix A of this procedure.
 
3.1.4 Should an emergency situation recur following a termination, the SED will reactivate the emergency response organization.
====3.1.4 Should====
3.2 RECOVERY 3.2.1 The overall goals of the recovery effort are to assess the in plant consequences of the emergency, perform clean up and repair operations, and restore the plant to a pre-determined status.3.2.2. The decision to enter the recovery phase will be made by the SED with concurrence from the CECC Director and the Senior Vice President, Nuclear Operations.
an emergency situation recur following a termination, the SED will reactivate the emergency response organization.
 
===3.2 RECOVERY===
3.2.1 The overall goals of the recovery effort are to assess the in plant consequences of the emergency, perform clean up and repair operations, and restore the plant to a pre-determined status.3.2.2. The decision to enter the recovery phase will be made by the SED with concurrence from the CECC Director and the Senior Vice President, Nuclear Operations.
Following the decision to enter into the recovery phase, the Senior Vice President, Nuclear Operations or his designee will direct the overall recovery effort.PAGE 5 OF 15 REVISION 16 WBN TERMINATION OF THE EMERGENCY EPIP-1 6 AND RECOVERY 3.2 RECOVERY (cont.)3.2.3 If the recovery phase is expected to be a long-term process, the Site Vice President may form a team to be responsible for continuous control of the recovery operation.
Following the decision to enter into the recovery phase, the Senior Vice President, Nuclear Operations or his designee will direct the overall recovery effort.PAGE 5 OF 15 REVISION 16 WBN TERMINATION OF THE EMERGENCY EPIP-1 6 AND RECOVERY 3.2 RECOVERY (cont.)3.2.3 If the recovery phase is expected to be a long-term process, the Site Vice President may form a team to be responsible for continuous control of the recovery operation.
The organizational structure of such a team would be contingent upon the emergency situation and procedures required for recovery.The Local Recovery Center (LRC) or other appropriate facilities will be made available to provide additional office space near (or on) the site for the recovery team.3.2.4 All major post accident onsite recovery measures shall be performed in accordance with written procedures.
The organizational structure of such a team would be contingent upon the emergency situation and procedures required for recovery.The Local Recovery Center (LRC) or other appropriate facilities will be made available to provide additional office space near (or on) the site for the recovery team.3.2.4 All major post accident onsite recovery measures shall be performed in accordance with written procedures.
 
3.2.5 Personnel protective measures shall be taken on initial entries and throughout the assessment and recovery operation to limit exposures As Low As Reasonable Achievable (ALARA) in accordance with EPIP-15, Emergency Exposure Guidelines.
====3.2.5 Personnel====
 
protective measures shall be taken on initial entries and throughout the assessment and recovery operation to limit exposures As Low As Reasonable Achievable (ALARA) in accordance with EPIP-15, Emergency Exposure Guidelines.
3.2.6 The State of Tennessee has the authority for actions taken offsite however, TVA will serve as an important source of technical and analytical assistance for the State in offsite monitoring and sampling.
3.2.6 The State of Tennessee has the authority for actions taken offsite however, TVA will serve as an important source of technical and analytical assistance for the State in offsite monitoring and sampling.
The Senior Vice President, Nuclear Operations, or his designee will serve as the State's contact for coordination of TVA's efforts in offsite monitoring, sampling and recovery.3.2.7 Should an emergency situation recur in the recovery phase, the SED will reactivate the emergency response organization and any recovery efforts will be suspended until the SED and CECC Director allow them to resume.3.2.8 Recovery operations will continue until the plant is returned to its pre-emergency status or as determined by the WBN Vice President or his designee.PAGE 6 OF 15 REVISION 16 WBN TERMINATION OF THE EMERGENCY EPIP-1 6 AND RECOVERY 4.0 RECORDS 4.1 Records of Classified Emergencies The materials generated in support of key actions during an actual emergency termination or recovery are considered Lifetime retention Non-QA records. Materials shall be forwarded to the EP Manager who shall submit any records deemed necessary to demonstrate performance to the Corporate EP Manager for storage.4.2 Drill and Exercise Records The materials deemed necessary to demonstrate performance of key actions during drills are considered Non-QA records. These records shall be forwarded to the EP Manager who shall retain records deemed necessary to demonstrate six-year plan performance for six years. The EP Manager shall retain other records in this category for three years.PAGE 7 OF 15 REVISION 16 WBN TERMINATION OF THE EMERGENCY EPIP-1 6 AND RECOVERY -APPENDIX A TERMINATION GUIDELINES (Page 1 of 2)1. The Site Technical Staff has evaluated the plant status and recommends that O YES termination guidelines be initiated.
The Senior Vice President, Nuclear Operations, or his designee will serve as the State's contact for coordination of TVA's efforts in offsite monitoring, sampling and recovery.3.2.7 Should an emergency situation recur in the recovery phase, the SED will reactivate the emergency response organization and any recovery efforts will be suspended until the SED and CECC Director allow them to resume.3.2.8 Recovery operations will continue until the plant is returned to its pre-emergency status or as determined by the WBN Vice President or his designee.PAGE 6 OF 15 REVISION 16 WBN TERMINATION OF THE EMERGENCY EPIP-1 6 AND RECOVERY 4.0 RECORDS 4.1 Records of Classified Emergencies The materials generated in support of key actions during an actual emergency termination or recovery are considered Lifetime retention Non-QA records. Materials shall be forwarded to the EP Manager who shall submit any records deemed necessary to demonstrate performance to the Corporate EP Manager for storage.4.2 Drill and Exercise Records The materials deemed necessary to demonstrate performance of key actions during drills are considered Non-QA records. These records shall be forwarded to the EP Manager who shall retain records deemed necessary to demonstrate six-year plan performance for six years. The EP Manager shall retain other records in this category for three years.PAGE 7 OF 15 REVISION 16 WBN TERMINATION OF THE EMERGENCY EPIP-1 6 AND RECOVERY -APPENDIX A TERMINATION GUIDELINES (Page 1 of 2)1. The Site Technical Staff has evaluated the plant status and recommends that O YES termination guidelines be initiated.
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==2.0 REFERENCES==
==2.0 REFERENCES==


===2.1 Interface===
2.1 Interface Documents[1][2][3]AO1-30.1, "Plant Fires," EPIP-1, "Emergency Plan Classification Flowchart" EPIP-10, "Medical Emergency Response" 3.0 INSTRUCTIONS
 
Documents[1][2][3]AO1-30.1, "Plant Fires," EPIP-1, "Emergency Plan Classification Flowchart" EPIP-10, "Medical Emergency Response" 3.0 INSTRUCTIONS
: 1. ENSURE AO1-30.1, "Plant Fires," IMPLEMENTED.
: 1. ENSURE AO1-30.1, "Plant Fires," IMPLEMENTED.
: 2. IF there are personnel injuries, THEN IMPLEMENT EPIP-1 0, "Medical Emergency Response.  
: 2. IF there are personnel injuries, THEN IMPLEMENT EPIP-1 0, "Medical Emergency Response.  
" 3. REFER TO EPIP-1, "Emergency Plan Classification Flowchart."[I[I LI1 4.0 RECORD RETENTION 4.1 No records are contained in this procedure.
" 3. REFER TO EPIP-1, "Emergency Plan Classification Flowchart."[I[I LI1 4.0 RECORD RETENTION 4.1 No records are contained in this procedure.
PAGE 4 of 4 REVISION 0}}
PAGE 4 of 4 REVISION 0}}

Revision as of 04:36, 14 July 2019

Emergency Plan Implementing Procedure Revision, Table of Contents - Section 4.1
ML031250101
Person / Time
Site: Watts Bar Tennessee Valley Authority icon.png
Issue date: 04/14/2003
From: Hagy J, Pavlechko F
Tennessee Valley Authority
To:
Office of Nuclear Reactor Regulation
References
-RFPFR
Download: ML031250101 (172)
v • d • e


Text

TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT EMERGENGY PLAN IMPLEMENTING PROCEDURE EPIP-8 PERSONNEL ACCOUNTABILITY AND EVACUATION Revision 18 Unit 0 PREPARED BY: James F. Hagy SPONSORING ORGANIZATION:

Emergency Planning APPROVED BY: Frank L. Pavlechko Effective Date: 04/14/2003 LEVEL OF USE: REFERENCE NON-QUALITY RELATED 1Z WBN PERSONNEL ACCOUNTABILITY AND EPI P-8 EVACUATION I E I -8 HISTORY OF REVISION/REVIEW Revision Number Implementation Date Pages Affected Description of Revision 13 06/14/00 All Non Intent change. Revised phone numbers to the MET station and McMinn Co. Revised description location of security portal to include (West) portal. Added TVA Police numberto near site organizations.

This revision resolves problems identified in WBN PER, 006394.14 12/11/00 All Non Intent changes. Corrected the fax number for the Main Warehouse to use the fax closest to the assembly area. Revised requirements for visitor(s) and MODS personnel to remain in the Protected area during assembly and accountability operations per directions of the EP PEER Team and TVAN requirements for standardization.

Removed reference to the all clear alarm which is being eliminated for standardization purposes.15 09/25/01 All Plan effectiveness determinations revisions indicate the following revisions do not reduce the level of effectiveness of the procedure pg. 6 or REP: Intent change. Procedure revised to Non-Quality related per requirements of NQAP & pending revision to SPP-2.2. The coversheet and records section of the procedure was revised to reflect this change.16 01/24/02 All pg. 3, 9, 10, 15,20 Plan effectiveness determinations revisions indicate the following revisions do not reduce the level of effectiveness of the procedure or REP: Intent revision.

Per guidance provided in the NRC Safeguards advisory revised App. B, C & D to direct SM and Security to hold limited area evacuations or assembly and accountability activities during a Security Event ( adversary attack) or take cover in specific area until the concern is resolved.Non-intent chanae. Revised ohone number on APP F.17 07/30/02 All Plan effectiveness determinations revisions indicate the following revisions do not reduce the level of effectiveness of the procedure or REP: Intent revision.

Per guidance provided by the TVAN EP PEER Team this procedure was re-written in the new standardized methods of operation and format. Enhancements made to instructions for notifications to outside protected area assembly areas and near site facilities per IN 2002-14. This reference was added to the procedure.

18 04/14/2003 2,15 28, Plan effectiveness determinations on these changes indicate the Ail following revisions do not reduce the level of effectiveness of the procedure or REP.Non-intent change(s):

Updated format for intersite consistency.

Deleted Source Notes. Updated phone numbers. Editorial corrections.

Deleted Appendix J (roster) which is maintained in EPIP-6 or EPIP-7. Enhanced SED instructions adding information from SQN assembly and accountability lessons learned.PAGE 2 OF 34 REVISION 18 WBN l PERSONNEL ACCOUNTABILITY AND EPI P-8 EVACUATION I EPIP TABLE OF CONTENTS

1.0 INTRODUCTION

.........................................................................

4 1.1 Purpose .........................................................................

4

2.0 REFERENCES

.........................................................................

4 2.1 Industry Documents

.........................................................................

4 2.2 Plant Instructions

.........................................................................

4 3.0 INSTRUCTIONS

.........................................................................

5 3.1 General Personnel Information

.........................................................................

5 3.2 Activating the Assembly and Accountability Process ..........................................................

5 3.3 Site Assembly and Accountability

.........................................................................

6 3.4 Particular Limited Area Evacuation

...........................................

..............................

8 3.5 Evacuation of Site Non-Emergency Response Personnel

..................................................

9 4.0 RECORD RETENTION

........................................................................

10 4.1 Records of Classified Emergencies

........................................................................

10 4.2 Drill and Exercise Records ........................................................................

10 APPENDIX A Protected Area Assembly Areas ........................................................................

11 APPENDIX B Assembly Area(s) (Outside The Protected Area) Notifications

..........................

12 APPENDIX C Near Site Organization(s)

Notifications

...............................................................

15 APPENDIX D Shift Manager/Site Emergency Director -Assembly And Accountability Actions ........................................................................

18 APPENDIX E Nuclear Security -Assembly And Accountability Actions ..................................

21 APPENDIX F Radiological Control -Assembly And Accountability Actions ...........

................

25 APPENDIX G Shift Manager/Site Emergency Site Evacuation Actions .............

.......................

26 APPENDIX H Nuclear Security -Evacuation Actions .................................................................

30 APPENDIX I Radiological Control -Evacuation Actions ............................................................

33 PAGE 3 OF 34 REVISION 18 WBN PERSONNEL ACCOUNTABILITY AND I EPI EVACUATION EPIP-8

1.0 INTRODUCTION

1.1 Purpose A. This Procedure provides instructions for accounting for all onsite personnel and visitors prior to an orderly evacuation of a specific area(s) or the site during a radiological or toxic hazard emergency.

This Procedure describes the method for notifying all site personnel and gives guidance for re-entry initiation.

This Procedure also describes the method for notifying and conducting an orderly evacuation of the near site facilities within the Owner Controlled Area (OCA).B. The scope of this procedure includes emergency and non-emergency response personnel, visitors, contractor/construction personnel and other persons who may be within the OCA during an emergency situation.

C. This procedure will be initiated by way of an emergency classification procedure step (i.e. EPIP-2, 3, 4, and 5).

2.0 REFERENCES

2.1 Industry Documents 1. NUREG-0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants 2. CFR 50.47, Code of Federal Regulations

3. NRC Information Notice 2002-14, Ensuring a Capability to Evacuate Individuals, Including Members of the Public, from the Owner-Controlled Area 2.2 Plant Instructions
1. TVA Radiological Emergency Plan 2. EPIP-2, Notification of Unusual Event 3. EPIP-3, Alert 4. EPIP-4, Site Area Emergency 5. EPIP-5, General Emergency 6. EPIP-6, Activation And Operation Of The Technical Support Center (TSC)7. EPIP-7, Activation And Operation Of The Operations Support Center (OSC)8. EPIP-1 1, Security and Access Control 9. EPIP-14, Radiological Control Response 10. EPIP-16, Termination Of The Emergency And Recovery PAGE 4 OF 34 REVISION 18 I WBN PERSONNEL ACCOUNTABILITY AND EVACUATION

_PIPFra I 3.0 INSTRUCTIONS 3.1 General Personnel Information A. Normal Entering and Exiting of the Plant Protected Area (PA).1. Individuals entering the plant PA shall: Swipe their badge into the entry card reader,* Enter the PA in accordance with security procedures.

2. Individuals exiting the PA shall: Swipe their badge into the exit card reader in the appropriate exit portals.* Exit the PA in accordance with security procedures.
3. Exit card readers function as accountability card readers for personnel exiting the PA.4. Protected Area assembly/Accountability card reader locations are identified in Appendix A.3.2 Activating the Assembly and Accountability Process A. Shift Manager/Site Emergency Director 1. The Shift Manager (SM) or Site Emergency Director (SED) shall initiate the activation of the assembly and accountability process.a. The SM\SED can delegate a designee to carry out the actions of this process, but can not delegate the decision to activate the process.2. Refer to Appendix D for activation.

PAGE 5 OF 34 REVISION 18 C WBN PERSONNEL ACCOUNTABILITY AND I EPIP-8 l lEVACUATION 3.0 INSTRUCTIONS (continued) 3.3 Site Assembly and Accountability A three-minute undulating siren (a siren that raises and lowers in volume and pitch) or public address announcements are the general methods for notifying personnel that emergency conditions exists requiring the assembly and accountability of site personnel.

Upon recognition that the assembly and accountability process has been activated, all personnel shall begin immediately to take applicable actions.A. Non-Emergency Responders inside the PA 1. Upon recognition of the assembly and accountability process, non-emergency responders, shall proceed immediately to their designated assembly areas as listed on Appendix A.2. Arriving at the assembly area, personnel shall: a. Swipe their badge into the accountability card reader (applies only to those assembly areas within the protected area).b. Remain in the designated assembly prea until released by the (SED) or a plant evacuation is ordered, following the instructions on the plant address system or through Nuclear Security.B. Non-Emergency Responders outside the PA Note: Specific areas outside the PA (See Appendix B) have designated assembly areas posted.1. Non-Emergency Responders outside the PA represent unescorted visitors, contractors/construction personnel, and others persons in public access areas on or passing within the OCA.2. Upon recognition of the assembly and accountability process, non-emergency responders shall proceed immediately to the closest designated assembly area.3. Nuclear Security will attempt to direct observed personnel to an assembly area as conditions permit.4. Nuclear Security will provide further instructions to personnel in the designated assembly areas.PAGE 6 OF 34 REVISION 18 I WBN PERSONNEL ACCOUNTABILITY AND l I EVACUATION E _P P-8 3.0 INSTRUCTIONS (continued)

C. Emergency Responders Note: Emergency Responders should already be in (or in route to) their assigned Response Facility as a result of pager notification.

1. Upon recognition of the Assembly and Accountability process, emergency responders, shall proceed immediately to their assigned Response Facility (TSC or OSC)(REFER TO EPIP-6 or EPIP-7)2. Arriving at the assigned Response Facility, personnel shall: A. Swipe their badge into the accountability card reader.B. Sign the facility Sign-in Roster.C. Review their emergency responsibilities and begin work.D. If a plant evacuation is ordered, all emergency responders will remain in their assigned Response Facility.D. Emergency Responders Having Escort Responsibilities
1. Emergency Responders will take the applicable steps to have their visitor transferred to a non-emergency responder for relocation to an appropriate assembly area.E. Visitors 1. Visitors shall remain with escorts and swipe their badge into the appropriate accountability card reader.F. Special Conditions Concerning Assembly and Accountability
1. If a person cannot reach his designated assembly area within 20 minutes, he should go to the nearest designated area and swipe his badge into the card reader. He should remain in that assembly area. Review Appendix A for a list of Protected Area (PA) assembly area locations.
2. If the accountability card reader will not accept a badge or an assembly area cannot be accessed, Nuclear Security should be contacted immediately at ext. 8464 or ext. 8495.G. Shift Manager (SM)/Site Emergency Director (SED)1. When conditions have been met that require the activation of the assembly and accountability process, the SM/SED will implement Appendix D of this procedure.

PAGE 7 OF 34 REVISION 18 WBN PERSONNEL ACCOUNTABILITY AND EPIP 8 EVACUATION l 3.0 INSTRUCTIONS (continued)

H. Nuclear Security (NS)1. When notified that conditions have been met that require the activation of the assembly and accountability process, or upon indications that assembly and accountability has been initiated, Nuclear Security will implement Appendix E of this procedure.

2. REFER TO EPIP-1 1, Security And Access Control.I. Radiological Control (RADCON)1. When notified that entry conditions have been met that require the activation of the assembly and accountability process, or upon indication that assembly and accountability has been initiated, Radiological Control will implement Appendix F of this procedure.
2. REFER TO EPIP-14, Radiological Control Response.3.4 Particular Limited Area Evacuation CAUTION: KNOWN HAZARDOUS CONDITIONS require Operations or TSC to evacuate a particular plant area(s). Follow announced directions PROMPTLY and EXACTLY.A. The SM/SED or designee shall make a public address (PA) announcement and follow the instructions in Appendix G.B. Personnel in the affected area(s), upon hearing the public address announcement or being notified of the particular area evacuation by any means shall do the following:
1. If working in a contaminated zone, exit the zone in accordance with Radiological Control (RADCON) procedures, unless instructed otherwise by RADCON.2. Exit the affected area in an orderly manner.C. Personnel not in the affected area(s) should continue assigned tasks if not instructed otherwise and should not enter the affected area(s) until the "All Clear" has been announced or directed through emergency response processes.

PAGE 8 OF 34 REVISION 18 WBN PERSONNEL ACCOUNTABILITY AND EVACUATION E _P 3.0 INSTRUCTIONS (continued) 3.5 Evacuation of Site Non-Emergency Response Personnel 1. A site evacuation will be conducted upon an order issued by the SM/SED.This Order will be issued to the TSC Nuclear Security Manager or the Nuclear Security Shift Supervisor or their designee, following the completion of Assembly and Accountability.

A. Non-Emergency Responders Within the Plant Protected Area.1. All personnel assembled in designated assembly areas within the protected area shall remain in those areas until released for the purpose of evacuation.

Visitors shall remain with escorts until they have exited the protected area.2. The TSC or NS will by public address announcement(s) or dispatching Security personnel, brief and release persons in assembly areas.3. Once released, personnel shall go immediately to the protected area exit portal. Personnel shall swipe their badge into the exit card reader or as instructed by NS. The protected area shall be exited in accordance with security procedures unless otherwise instructed.

a. If for any reason personnel can not go directly to the Protected Area exit portal, NS should be contacted immediately.
b. If for any reason the exit card reader will not properly acknowledge a badge, NS should be contacted immediately.
4. Personnel shall proceed to their vehicle and evacuate from the site to their lace of residence or if needed to one of the remote assembly area(a), following all briefing information provided to them by the TSC or NS. Exit routes leading away from the plant will be identified.
5. All personnel evacuating should anticipate that the Owner Controlled Area (OCA) Security Check Point will be established and if conditions require, RADCON will be monitoring vehicles and personnel as they exit.6. Upon exiting the OCA, personnel shall follow all guidance of state and local authorities.

B. Non-Emergency Responders Within the OCA 1. All personnel assembled in designated assembly areas outside the PA and within the OCA shall remain in those areas until released for the purpose of evacuation.

2. NS will notify by phone or dispatch security personnel directly to OCA Assembly Areas, brief and release assembled personnel.
3. Once released, personnel shall proceed to their vehicle and evacuate from the site to their place of residence or if needed to one of the remote assembly area(s), following all briefing information provided to them by NS. Exit routes leading away from the plant will be identified.
4. If for any reason personnel can not proceed directly to their vehicle and evacuate the site NS shall be contacted immediately.
5. All personnel exiting the site Protected Area should anticipate that OCA Security Check Point will be established and if conditions require, RADCON will be monitoring vehicles and personnel as they exit.6. Upon exiting the OCA, personnel shall follow all guidance of state and local authorities.

PAGE 9 OF 34 REVISION 18 WBN PERSONNEL ACCOUNTABILITY AND EVACUATION lEPIP 3.0 INSTRUCTIONS (continued)

C. Emergency Responders shall remain in Emergency Centers and shall not evacuate from the site.D. The Shift Manager/Site Emergency Director will implement Appendix G of this procedure.

E. Nuclear Security (NS) will implement Appendices B. C, & H of this procedure.

F. Radiological Control (RADCON) will implement Appendix I of this procedure.

4.0 RECORD RETENTION 4.1 Records of Classified Emergencies The materials generated in support of key actions during an actual emergency requiring personnel accountability or evacuation are considered Lifetime retention Non-QA records. Materials shall be forwarded to the EP Manager who shall submit any records deemed necessary to demonstrate-performance to the Corporate EP Manager for storage.4.2 Drill and Exercise Records The materials deemed necessary to demonstrate performance of key actions during drills are considered Non-QA records. These records shall be forwarded to the EP Manager who shall retain records deemed necessary to demonstrate six-year plan performance for six years. The EP Manager shall retain other records in this category for three years.PAGE 10 OF 34 REVISION 18 WBN PERSONNEL ACCOUNTABILITY AND EVACUATION E 1IP APPENDIX A PROTECTED AREA ASSEMBLY AREAS Page 1 of 1 LOCATION REPORTING ORGANIZATION(S)

El. 713' Mechanical Maintenance Shop Mechanical Maintenance personnel El. 713' Chem Lab Chemistry Laboratory personnel El. 713' RADCON Lab RADCON personnel, AUOs, OSC responders, Fire Operators/others El. 729' Electrical Maintenance Shop Electrical Maintenance personnel El. 729' Instrument Maintenance Shop Instrument Maintenance personnel El. 729' MOB Maintenance Engineering Maintenance Planning/Engineering/others Support Office El. 741' Ops. Procedures Office Procedure Writers/NRC Office/others El. 755' Technical Support Center TSC emergency responders (TSC)El. 755' Main Control Room Control Room and Operations personnel Plant Assembly Room Main Office Building occupants/others EQB, Vending Area EQB and MDB Occupants, MODS personnel/others PAGE 11 OF 34 REVISION 18 WBN PERSONNEL ACCOUNTABILITY AND EVACUATION I EPIP APPENDIX B ASSEMBLY AREA(S) (OUTSIDE THE PROTECTED AREA) NOTIFICATIONS (Page 1 of 3)Nuclear Security (NS) will provide the information from this appendix to all assembly areas outside the protected area (listed below) as it becomes available or as directed by the SMISED or TSC Security Manager.* Initial contact should be by phone with Fax message used for follow-up.

  • Should phone contact not be made, (i.e. off-hours

/ weekends / phone trouble) direct the outside OCA Security Motor Patrol to check the area(s) for personnel and provide information as needed.* After evacuation orders have been initiated, the OCA Security Motor Patrol will ensure all non essential personnel have left the area(s).WBN Training Center Mgr. Office (cafeteria) x3758, x1216, or x8962 x3797 Administration Building Vending Area, Office Area(s) x8767 x1 924 Conference Room(s) or x8768 Main Warehouse Conference Room Area x1 436 x3233 PAGE 12 OF 34 REVISION 18 WBN PERSONNEL ACCOUNTABILITY AND EVACUATION EPI P APPENDIX B (continued)

ASSEMBLY AREAS (OUTSIDE THE PROTECTED AREA) NOTIFICATIONS (Page 2 of 3)Time: Date: A. M This is a Drill- Repeat LI This is an Actual Event -Repeat --This is an Actual Event This is a Drill B. WBN has declared a emergency.(enter emergency classification.)

C. Radiological conditions are: El Minor releases within federally approved limits'E1 Releases above federally approved limits 1 El Release information not known ( 'Tech Specs)D. Please convey the following instructions to all people in your assembly area(s): Stay indoors.* Close off HVAC Systems.* Check out doors or in adjacent buildings and direct all personnel to the Assembly Area to await instructions.

  • Follow general instructions for the assembly area.E. .Additional instructions/information:

F. Site Evacuation has been ordered by the SED. YES El El El El G. Remain calm and exit the site by your normal route unless otherwise directed.NO YES NO El El El El H. You will be informed when it is safe to return to work. 0* WBN Training Center* Administration Building* Main Warehouse PAGE 13 OF 34 REVISION 18 WBN PERSONNEL ACCOUNTABILITY AND EDIP EVACUATION EPIP-8 APPENDIX B (continued)

ASSEMBLY AREAS (OUTSIDE THE PROTECTED AREA) NOTIFICATIONS (Page 3 of 3)"FOR RADIOLOGICAL EMERGENCY" ASSEMBLY AREA -GENERAL INSTRUCTIONS (OUTSIDE THE PROTECTED AREA)1) START ASSEMBLING PERSONNEL 2) CLOSE ALL DOORS AND WINDOWS El 3) SHUT DOWN VENTILATION SYSTEM l4) NO EATING, DRINKING OR SMOKING LI 5) CALL IN PEOPLE FROM OUTSIDE LOCATIONS OR SURROUNDING BUILDINGS TO THE ASSEMBLY AREA El 6) KEEP PAGE SYSTEM AND PHONES CLEAR FOR USE DURING THE EMERGENCY LI 7) LISTEN FOR INSTRUCTIONS LI 8) IF EVACUATION OF SITE IS DIRECTED, LEAVE IN A SAFE AND ORDERLY MANNER BY THE MAIN ACCESS ROUTE OR ALTERNATE ROUTE: PAGE 14 OF 34 REVISION 18 WBN PERSONNEL ACCOUNTABILITY AND EVACUATION l EPIPr8 _]APPENDIX C NEAR SITE ORGANIZATION(S)

NOTIFICATIONS (Page 1 of 3)Nuclear Security (NS) will provide the following information to the near site organizations listed below when directed by the SMISED or TSC Security Manager.RADCON will provide technicians to monitor personnel (if necessary).

  • These contacts should be made by phone with Fax Message for follow-up.
  • Should phone contact not be made, (i.e. off-hours/weekends/phone trouble) direct the OCA Security Motor Patrol to check the area for personnel and provide information as needed.* After evacuation orders have been initiated, the OCA Security Motor Patrol will ensure all non essential personnel have left the area(s).WBN Weapons Range 9-365-1 400 NA WBN Grounds Maintenance 9-365-3334

.NA WBN Facilities Trailer(s) 9-365-1890 or 1895 9-365-1710 Watts Bar Dam (Hydro) 9-365-7600 or 6300 9-365-7640 TVA Police/iVA TPS Building 9-365-3776 or 3778 or 1965 9-365-3873

___________________________or 8450 _________Watts Bar Maintenance Facility 9-365-8720 or 8722 or 7849 9-365-8709 WBN Environmental Data Station 9-365-8484 NA (not normally manned)Reservoir Property (Maintenance Base) 9-365-5256 N/A Lock Master (Watts Bar) 9-365-7634 or 9-1-423-334-4521 9-1-423-334-3522 Watts Bar Dam Spill Way fishing Area .NO PHONE IN THIS NA AREA OCA SECURITY MOTOR PATROL OR TVA POLICE SHALL NOTIFY PEOPLE TO LEAVE THE AREA.PAGE 15 OF 34 REVISION 18 WBN PERSONNEL ACCOUNTABILITY AND EVACUATION I EPI APPENDIX C (continued)

NEAR SITE ORGANIZATION(S)

NOTIFICATIONS (Page 2 of 3)Time: Date: A. Li This is a Drill- Repeat LI This is an Actual Event -Repeat -This is an Actual Event This is a Drill B. WBN has declared a emergency.(enter emergency classification.)

C. Radiological conditions are: El Minor releases within federally approved limits'El Releases above federally approved limits'El Release information not known ('Tech Specs)D. Please convey the following instructions to all people in your assembly area(s):* Stay indoors. g* Close off HVAC Systems. ,* Check out doors or in adjacent buildings and direct all personnel to the Assembly Area to await instructions.

E.Follow general instructions for the assembly area. U E. Additional instructions are as follows:.Return to work. l.Remain in assembly area. 0.Additional instructions/information:

F. Site Evacuation has been ordered by the SED. YES El NO U G. Remain calm and initiate an evacuation of your YES U organization unless otherwise directed.

NO U H. You will be informed when it is safe to return to work. U* Watts Bar Dam (Hydro)

  • Reservoir Property (Maintenance Base)* WBN Weapons Range .WBN Grounds Maintenance
  • Watts Bar Maintenance Facility .WBN Environmental Data Station* Lock Master (Wafts Bar) .TVA POLICEITVA TPS Building* WBN Facilities Trailer(s)

PAGE 16 OF 34 REVISION 18 WBN PERSONNEL ACCOUNTABILITY AND EVACUATION I EPI APPENDIX C (continued)

NEAR SITE ORGANIZATION(S)

NOTIFICATIONS (Page 3 of 3)II"FOR RADIOLOGICAL EMERGENCY" GENERAL INSTRUCTIONS (NEARSITE ORGANIZATIONS)

1) START ASSEMBLING PERSONNEL L 2) CLOSE ALL DOORS AND WINDOWS L 3) SHUT DOWN VENTILATION SYSTEM El 4) NO EATING, DRINKING OR SMOKING o 5) CALL IN PEOPLE FROM OUTSIDE LOCATIONS OR SURROUNDING BUILDINGS TO A ASSEMBLY AREA O 6) KEEP PAGE SYSTEM AND PHONES CLEAR FOR USE DURING THE EMERGENCY El 7). LISTEN FOR INSTRUCTIONS O 8) IF EVACUATION OF SITE IS DIRECTED, LEAVE IN A SAFE AND ORDERLY MANNER BY THE MAIN ACCESS ROUTE OR ALTERNATE ROUTE: PAGE 17OF 34 REVISION 18 WBN PERSONNEL ACCOUNTABILITY AND EPIP-8 EVACUATION I _APPENDIX D I SHIFT MANAGER/SITE EMERGENCY DIRECTOR -ASSEMBLY AND ACCOUNTABILITY ACTIONS Page 1 of 3 The following appendix shall be utilized by the Shift Manager(SM)/Site Emergency Director(SED)

OR DESIGNEE for the purpose of conducting site assembly and accountability actions.Note: IF onsite activities (i.e. Security Event 'Adversary Attack") would put people at risk or in Harm's way, THEN Do Not conduct this action until the concern is resolved.

NOTIFY site personnel to "Take Cover/Specific Action and await further instructions".

IF this situation does not apply, THEN proceed with Assembly and Accountability.

1. The SM/SED has determined that conditions require the activation of the assembly and accountability siren system and process.2. NOTIFY Nuclear Security (NS) at ext. 8464 or 8495 that: A. The assembly and accountability sirens will be activated immediately.

AND B. NS should implement Appendix E.Initials Time El 3. NOTIFY Radiological Control (RADCON) at ext. 7865 that: A. The assembly and accountability sirens will be activated immediately.

AND B. RADCON should implement Appendix F.F]4. MAKE a public address announcement similar to: "Attention all plant personnel, the site assembly and accountability process has been initiated.

All personnel report immediately to your assigned assembly areas." (REPEAT)Fl 5. ACTIVATE the assembly and accountability sirens.Initials Time REVISION 18 PAGE 18 OF 34 WBN PERSONNEL ACCOUNTABILITY AND l l EVACUATION I l APPENDIX D (continued SHIFT MANAGER/SITE EMERGENCY DIRECVOR -ASSEMBLY AND ACCOUNTABILITY ACTIONS Page 2 of 3 6. WHEN the Assembly and Accountability Sirens have completed the 3-minute cycle and silenced, THEN MAKE a PA announcement similar to: °uAftention all plant personnel, the site assembly and accountability process has been initiated.

All personnel report immediately to your assigned assembly areas and be accounted for.(REPEAT)NOTE IF at any time during the assembly and accountability process RADCON determines that radiation guidelines for an assembly area(s) have been exceeded, THEN REQUEST NS to re-locate affected personnel to another assembly area OR evacuate affected personnel off-site.7. NOTIFY Central Emergency Control Center (CECC) Director I either by the direct ring-down telephone in the TSC or at ext. 751-1614.OR If the CECC Director can not be reached, notify the Operations Duty Specialist (ODS) at ext.751-1700 that: A. The assembly and accountability sirens have been activated.

AND B. WBN EPIP-8 is currently being implemented for assembly and accountability.

8. REFER TO EPIP-2 through EPIP-5 for remaining actions while 0I Accountability is being performed.
9. WHEN Notified by NS that the assembly and accountability D process has been completed, THEN MAKE a public address announcement similar to: "Attention all plant personnel, the site assembly and accountability process has been completed.

AD personnel remain in your assigned assembly areas and await further instructions.(REPEAT)PAGE 19 OF 34 REVISION 18 WBN PERSONNEL ACCOUNTABILITY AND EVACUATION EPIFra APPENDIX D (continued SHIFT MANAGERISITE EMERGENCY DIRECTOR -ASSEMBLY AND ACCOUNTABILITY ACTIONS Page 3 of3 NOTE: The TSC Security Manager may approve the following transfer(s) or exit(s).10. WHEN required, Ii THEN APPROVE personnel to transfer from one assembly area to another. The transit route must be approved and followed.

Security shall be notified of approved transfer(s).

Transferring personnel shall be directed to card in upon arrival and remain in that area until released.11. WHEN required, LI THEN APPROVE personnel to transfer from their assembly area (or Emergency Response Facility) to exit the site. The transit route must be approved and followed.

Security shall be notified of approved exit(s).Exiting personnel shall be directed to card out upon exiting and to immediately leave the Owner Controlled Area by an approved route.12. PROVIDE periodic briefings to the personnel in assembly areas. The Public Address System is accessible at extension 487 from selected TSC phones, or via plant paging in the MCR.13. EVALUATE the long term needs of personnel in the assembly areas: L.Food and Water (especially food controlled diabetics)

.Medication

  • Special needs 14. .VERIFY whether conditions at this time require an order to evacuate all non-emergency response personnel from the Owner Initials Controlled Area(OCA) or not. Time 15. IF Conditions at this time DO require an order to evacuate all non- I emergency response personnel from the OCA, THEN Initiate Appendix G of this procedure.
16. IF Conditions at this time DO NOT require an order to evacuate all non- E emergency response personnel from the OCA, THEN MONITOR evacuation criteria.

Re-enter this procedure at Appendix G when it has been determined by the SM/SED that conditions require an order to evacuate all non-emergency response personnel.

PAGE 20 OF 34 REVISION 18 WBN PERSONNEL ACCOUNTABILITY AND EVACUATION EPI P-8 APPENDIX E NUCLEAR SECURITY -ASSEMBLY AND ACCOUNTABILITY ACTIONS Page 1 of 4 The following appendix shall be utilized by the TSC Security Manager (or if unavailable the Security Shift Supervisor or designee) for the purpose of conducting Site Assembly and Accountability actions.NOTE: IF a Security Event (i.e. adversary attack) would put people at risk or in Harm's way, THEN NOTIFY the SM\SED prior to commencing assembly and accountability.

IF this does not apply, proceed with accountability operations.

1 RECORD notification that activation of the assembly and accountability process and actions has been initiated by the SM/SED or designee.Initials Time 2. CONTROL and RESTRICT access to the Protected Area, except for D those individuals designated for emergency response, per the Emergency Response Organization Call List or as authorized for emergency response by the SM/SED or TSC Security Manager or OSC Security Advisor.3. MAINTAIN Owner Controlled Area (OCA) traffic controls at the OCA D traffic control point.4. NOTIFY the TSC or RADCON at ext.7865 that, OCA traffic control L actions are being maintained.

AND REQUEST TSC or RADCON dispatch personnel to the OCA Emergency Survey Point #15 (if determined by RADCON) that survey conditions requiring vehicle survey, exist.5. CONTROL and RESTRICT access to the Owner Controlled Area, EII except for those individuals designated for emergency response, per the Emergency Response Organization Call List or as authorized for emergency response by the SM/SED or TSC Security Manager or OSC Security Advisor.6. COMPLETE (Appendices B and C) and upon direction from the TSC LI Security Manager or SM/SED, initiate the cal s, and Fax the information to the designated locations.

PAGE 21 OF 34 REVISION 18 WBN PERSONNEL ACCOUNTABILITY AND EVACUATION EPIP-8 APPENDIX E (continued)

NUCLEAR SECURITY -ASSEMBLY AND ACCOUNTABILITY ACTIONS Page 2 of 4 7. DISPATCH officer(s) to search areas (as needed) within the OCA outside the Protected Area (see Appendices B & C).A. IF Visitors, contractors/construction personnel, and other persons in public access areas on or passing within the OCA and not assigned a designated assembly area(s): THEN NS will: Wam and advise individuals of current actions at the station.Advise individuals on exits routes and request that they immediately exit the OCA.B. IF Visitors, contractors/construction personnel, and other persons in public access areas on or passing within the OCA are assigned a designated assembly area(s): THEN NS will: Wam and advise individuals of current actions to conduct assembly and accountability.

Advise personnel to report immediately to their designated emergency assembly center.C. IF Employees having emergency response assignments are D located: THEN NS will: Warn and advise individuals of current actions to conduct assembly and accountability, Advise personnel to report immediately to their designated emergency response center.D. IF Employees not having emergency response assignments are 0 located THEN NS will: Wam and advise individuals of current actions to conduct assembly and accountability.

Advise personnel to report immediately to a designated assembly area location outside the Protected Area. (See Appendices B and C).8. REPORT the results of accountability to the SMISED within 30 minutes I after the assembly and accountability sirens have sounded. Initials 7 -me PAGE 22 OF 34 REVISION 18 .43 WBN PERSONNEL ACCOUNTABILITY AND I EPI EVACUATION EPI P-8 APPENDIX E (continued)

NUCLEAR SECURITY -ASSEMBLY AND ACCOUNTABILITY ACTIONS Page 3 of 4 9. UNACCOUNTED FOR INDIVIDUALS 0 IF Individuals remain unaccounted for (45) minutes following the activation of the assembly and accountability sirens, THEN NOTIFY the TSC Security Manager or SM/SED that search teams will be needed to locate the missing individual(s), AND RADCON will assist search teams (as needed).10. TWO PERSON (LINE OF SIGHT) RULE PUBLIC ADDRESS ANNOUNCEMENT A. WHEN Assembly and Accountability-has been completed, AND NS has determined that the Two Person (Line of Sight)Rule is required.THEN REQUEST permission from the TSC Security /Manager or SM/SED to make the following Public Address Initials Time Announcement: "ATTENTION ALL SITE PERSONNEL, THIS IS A SECURITY ALERT ACTION.EFFECTIVE IMMEDIATELY, THE TWO MAN RULE HAS BEEN ORDERED.""ENTRY TO VITAL AREAS NOW REQUIRES CONTINOUS LINE OF SIGHT BETWEEN TWO (2) PERSONNEL." (REPEAT)PAGE 23 OF 34 REVISION 18 WBN PERSONNEL ACCOUNTABILITY AND EPIP EVACUATION EPI P-8 APPENDIX E (continued)

NUCLEAR SECURITY -ASSEMBLY AND ACCOUNTABILITY ACTIONS Page 4 of 4 11. AUTOMATED ACCOUNTABILITY SYSTEM FAILURE GUIDELINES In the event the automated accountability system is unable to accomplish its designed function, NS will recommend the following methods to account for onsite personnel to the SM or TSC SED for action.A. NOTIFY personnel in the Assembly Area(s) (within the Protected Area)to remain where they are until the Accountability System can be reactivated.

B. IF plant conditions require immediate action (i.e., danger to health or safety), the SED will order all nonessential onsite personnel to exit the protected area and report to the Watts Bar Training Center. Once all nonessential personnel have left the protected area, a verbal review of the remaining onsite emergency responders will be conducted.

C. Walk-downs within the protected area will be conducted to ensure all non-essential personnel have left the plant. These actions and search and rescue efforts (if needed) will be coordinated by the TSC Security Manager or SM/SED.PAGE 24 OF 34 REVISION 18 WBN PERSONNEL ACCOUNTABILITY AND I EPI EVACUATION APPENDIX F I RADIOLOGICAL CONTROL -ASSEMBLY AND ACCOUNTABILITY ACTIONS Page 1 of 1 The following Appendix shall be utilized by the TSC Radiological Control Manager or if he is unavailable the Radiological Control Shift Supervisor or designee, for the purpose of conducting a site assembly and accountability actions.1. Notified that activation of the assembly and accountability process and actions has been initiated by the SM/SED or designee.

Iniitials Time 2. IF in plant Radiological conditions require additional monitoring, l THEN ESTABLISH a survey routine for all assembly areas, including the Emergency Centers.3. IF Radiological conditions in any assembly area(s) meet or exceed 0 the listed guidelines:

  • Radiation levels that would result in a radiation dose of 100 mrem in one hour, or* airborne radioactivity above 1OCFR 20.1201 DAC limits.THEN NOTIFY the SM/SED and recommend that the personnel within the affected area be re-located to another assembly area or evacuated from the site.4. WHEN Notified by Nuclear Security that Owner Controlled Area TCP /is being maintained.

Initials Time THEN EVALUATE radiological conditions to determine if a RADCON survey checkpoint at the OCA (Emergency Survey Point # 15) should be established.

5. IF Radiological conditions require that a RADCON survey checkpoint Li be establis ed, THEN DISPATCH RADCON personnel to the OCA (Emergency Survey Point # 15).AND ESTABLISH a RADCON survey checkpoint.
6. RADCON personnel will be dispatched by the OSC or SM/SED to EL assist Protected Area search teams (as needed).PAGE 25 OF 34 REVISION 18 WBN PERSONNEL ACCOUNTABILITY AND I l EVACUATION EPI APPENDIX G SHIFT MANAGER/SITE EMERGENCY DIRECTOR -SITE EVACUATION ACTIONS Page 1 of 4 Limited AREA EVACUATION/TAKE COVER ACTIONS A. MAKE a Public Address (PA) announcement similar to the following D"This is a real emergency." [I1 OR 'This is a drill." E: "ATTENTION All Site Personnel, conditions in the (area[s] to be evacuated) warrant an evacuation of the area. Leave the (area[s] to be evacuated) immediately and remain clear until further notice." OR"ATTENTION All Site Personnel, conditions in (area[s] of concern)warrant you to take cover in this area. Take Coverin the (area[s] of concern)immediately and remain there until further notice.'B. IF necessary, FORM a team composed of Operations and 0 Radiological Control (RADCON) personnel to ensure evacuation of high noise areas.C. DIRECT Operations/RADCON

/Others to SEARCH the evacuated area to ensure all personnel have left the area.D. REPORT results to the TSC (if activated).

LI E. INFORM NS of the situation and direct assistance as needed. 0 F. PERFORM other duties as needed. E]PAGE 26 OF 34 REVISION 18 WBN PERSONNEL ACCOUNTABILITY AND EVACUATION

.I EPI P-8 I APPENDIX G (continued)

SHIFT MANAGER/SITE EMERGENCY DIRECTOR -SITE EVACUATION ACTIONS Page 2 of 4 The following appendix shall be utilized by the Shift Manager(SM)/Site Emergency Director(SED) or designee for the purpose of conducting a evacuation of site non-emergency response personnel.

Note 1: The implementation of a site evacuation should be based on the protective actions which will result in the lowest personal exposure.

In a radiological or hazardous material emergency, evacuation should be initiated either before or after the passage of the release. Evacuation routes should be chosen to lead personnel away from the path of the plume or danger.Note 2: Based on ongoing emergency activities in the local communities (if activated) discussions with the CECC, Meigs, Rhea, and McMinn Counties, EOC officials may be warranted to identify traffic conditions, road weather conditions, or any other hazards that would effect evacuation.

1. RECORD notification that conditions have been met that require an Initials Time order to evacuate site non-emergency response personnel.
2. VERIFY Assembly and accountability have been completed.

E 3. NOTIFY the Central Emergency Control Center (CECC) Director of the impending evacuation.

(5-751-1614) (IF not staffed, NOTIFY the Operations Duty Specialist, 5-751-1700).

4. CONSIDER first the precautionary evacuation of all non-essential personnel (outside the Protected Area) from the site. These personnel will be assembled in their designated assembly areas. (Appendices B and C)Once completed, non-essential personnel within the Protected Area can be evacuated (Appendix A).5. PROVIDE any special instructions to assembly area(s) through PA announcements, Emergency Dispatches or NS communications.

Coordination with RADCON may be necessary prior to these announcements.

6. NOTIFY Nuclear Security (NS) at ext. 8464 or 8495 that: E A. An order to evacuate site non-emergency response personnel has been issued.AND B. NS Should implement Appendix H.7. NOTIFY Radiological Control at ext.7865 that: A. An order to evacuate site non-emergency response personnel has been issued, AND B. RADCON should implement Appendix I.PAGE 27 OF 34 REVISION 18 WBN PERSONNEL ACCOUNTABILITY AND I l l l EVACUATION EPIP-8 1 APPENDIX G (continued)

SHIFT MANAGER/SITE EMERGENCY DIRECTOR -SITE EVACUATION ACTIONS Page 3 of 4 8. IN the event of a total plant EVACUATION, determine the need for LI non-essential personnel and vehicles to pass through a RADCON check point (if deemed necessary) prior to being released from the site.This point will be set up at Emergency Survey Point # 15 9. EVACUATION of onsite non-contaminated individuals should take E place along normal exit routes away from the site, conditions permitting.

10. DIRECT NS to provide appropriate personnel to direct traffic on to ii Route 68.IF plant conditions preclude radiological decontamination, THEN evacuees will be informed of transportation, sheltering, and decontamination arrangements prior to leaving the site. The primary evacuation shelter for onsite contaminated personnel will be Sequoyah Nuclear Plant (SQN), approximately 50 miles south of Watts Bar Nuclear Plant (WBN).11. IF conditions warrant, THEN Support personnel may be sent home or i directed/staged to other offsite locations (if necessary).

Two possible locations are: 1. Englewood Elementary School -if directing personnel to this school, notify McMinn Co. EMA (day hours, Monday -Friday) at 9-1 -423-744-2724;or McMinn Co. 911 Communications (off hour, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />), at 9-1-423-744-2721.

Also notify the Tennessee EMA at 9-1-615-741-0001.

K 2. Roane County High School -if directing personnel to this school, D notify the Roane Co. 911 Dispatch Center at 9-1-865-354-8045 and request Roane Co. EMA be notified.

Also notify the Tennessee EMA at 9-1-615-741

-0001.12. ANNOUNCE Site Evacuation with the following message, AND E REPEAT as needed: "ATTENTION ALL SITE PERSONNEL.

ATTENTION ALL SITE PERSONNEL.

The SED has ordered a site evacuation.

All personnel except those with emergency assignments shall exit by their normal exit route/altemate to their home(s) and/or other directed destination until further notice." 13. IF an evacuation is ordered, THEN DIRECT Nuclear Security (NS) to notify the Assembly Areas Outside the Protected Area (Appendix B)and the Near site organizations (Appendix C) of ongoing site actions.14. IF site personnel require transportation or sheltering, THEN coordinate arrangements for assistance with the TSC/CECC.

L 15. Conditions permitting, you may recall evacuated people as needed. EL 16. KEEP the CECC informed of site activities L PAGE 28 OF 34 REVISION 18 WBN PERSONNEL ACCOUNTABILITY AND EVACUATION I EPI APPENDIX G (continued)

MAP TO ROANE COUNTY HIGH SCHOOL AND ENGLEWOOD ELEMENTARY SCHOOL From WBN, take route 68 west to route 27 north.Follow 27 north and go through the city of Rockwood.

At the 6th traffic light (last light) the road Ys to the right. The road to the right is route 70. Follow route 70 for 12 miles to Kingston.Cross the Clinch River bridge and go approximately one mile and you will see Roane County High School on the left.(Page 4 of 4)From WBN, follow 68 east to route 58 south.Follow 58 south to Decatur. At the traffic light next to the County Court House make a left on to route 30 east. Follow 30 east (10 miles) and go through Athens. Tum left onto route 39 east to Englewood.

Follow 39 to Englewood, cross over railroad tracks and go past the first red light; you will see the Englewood Elementary School one block up on the left.PAGE 29 OF 34 REVISION 18 WBN PERSONNEL ACCOUNTABILITY AND I EPIP 8 EVACUATION APPENDIX H NUCLEAR SECURITY -EVACUATION ACTIONS Page 1 of 3 The following appendix shall be utilized by the TSC Security Manager or if unavailable the Security Shift Supervisor or designee for the purpose of conducting a evacuation of site non-emergency response personnel.

1. RECORD notification that an order to evacuate site non-emergency

_response personnel has been initiated by the SM /SED. Initials Time 2. CONTINUE to control and restrict access to the Plant Protected Area LI (PA), except for those individuals designated for emergency response, per the Emergency Response Organization Call List or as authorized for emergency response by the TSC Security Manager, OSC Security Advisor or SM/SED.3. CONTINUE to maintain OCA on-site traffic controls.

LI 4. CONTINUE to control and restrict access to the Owner Controlled LI (OCA) Area, except for those individuals designated for emergency response, per the Emergency Response Organization Call List or as authorized for emergency response by the TSC Security Manager, OSC Security Advisor or SM/SED.5. NOTIFY RADCON at ext. 7865 that, OCA on-site traffic control actions LI are in progress, AND REQUEST RADCON dispatch personnel to the Owner Controlled Area Traffic Control point (if determined by RADCON)that conditions requiring vehicle survey(s) exist.6. EVALUATE evacuation route: A. Consult with RADCON information concerning off-site Initials Time environmental radiological hazards (potential plume pathways).

B. Consider local weather information to determine if hazardous weather conditions exist.C. Consider, all information concerning terrorist activity within a 10 mile radius of the site.PAGE 30 OF 34 REVISION 18 WBN PERSONNEL ACCOUNTABILITY AND EVACUATION EPIP-APPENDIX H (continued NUCLEAR SECURITY -EVACUATION ACTIONS Page 2 of 3 7. DETERMINE evacuation route based upon information obtained in step (6) of this appendix: 8. VERIFY that all prior listed items are complete before continuing in this action list.ED D~NOTE: Brief and advise all individuals in Assembly Areas Outside the Protected Area and Near Site Organizations areas (Appendices B & C) of: 1 ) Current actions to conduct an evacuation of all non-emergency response personnel, AND 2) Recommended exits routes, directing all personnel to follow the instructions of local law enforcement officers upon leaving the Owner Controlled Area (OCA).0 9. DISPATCH Security personnel to assist (as needed) and verify in the site evacuation.

Initials Time CONSIDER first the precautionary evacuation of all non-essential personnel (outside the Protected Area) from the site. These personnel will be assembled in their designated near site assembly areas (Appendices B & C). Once completed, non-essential personnel within the Protected Area can be evacuated (Appendix A).10. NOTIFY the TSC Security Manager or SM/SED upon completion of evacuation of site non-essential personnel.

Initials Time PAGE 31 OF 34 REVISION 18 WBN PERSONNEL ACCOUNTABILITY AND EPIl EVACUATION I APPENDIX H (continued)

PROTECTED SITE PERIMETERIOWNER CONTROLLED AREA MAP (Page 3 of 3)PAGE 32OF 34 REVISION 18 WBN _ PERSONNEL ACCOUNTABILITY AND EVACUATION I EPIP APPENDIX I I RADIOLOGICAL CONTROL -EVACUATION ACTIONS Page 1 of 2 The following appendix shall be utilized by the TSC Radiological Control Manager, or if he is unavailable, the Radiological Control Shift Supervisor or designee, for the purpose of conducting a site evacuation.

1. RECORD notification that an order to evacuate site non-emergency response personnel has been initiated by the SM /SED.2. IF a radiological survey checkpoint is needed and has not been established at the Owner Controlled Area (OCA), THEN: Initials Time LI DISPATCH RADCON personnel to the OCA Emergency Survey Point # 15.AND ESTABLISH a RADCON survey checkpoint.
3. IF Radiological concerns merit the spraying down of vehicles prior to site exiting, THEN NOTIFY the TSC or SM/SED ta have the Fire Truck dispatched to this location.

Hydrant # 0 HYD 026-3108 is near the emergency survey point and adequate water run-off to drainage is available 4. IF plant conditions preclude radiological decontamination, THEN evacuees will be informed of transportation, sheltering, and decontamination arrangements prior to leaving the site. The primary evacuation shelter for onsite contaminated personnel will be Sequoyah* Nuclear Plant (SQN), approximately 50 miles south of Watts Bar Nuclear Plant (WBN). RADCON personnel from the plant site, SQN, and CECC will respond to SQN to support personnel decontamination activities if there is a need.Initials Time PAGE 33 OF 34 REVISION 18 WBN PERSONNEL ACCOUNTABILITY AND EDIPD8 EVACUATION EPI P-8 APPENDIX I (continued)

RADCON ASSEMBLY/ACCOUNTABILITY/EVACUATION (Page 2 of 2)DIRECTIONS TO (SQN) SEQUOYAH NUCLEAR PLANT GUIDELINES ssmUOYAH --NUCLEAR PLANT US SzO CHATTANOOGA..

PAGE 34 OF 34 REVISION 18

-em TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT EMERGENGY PLAN IMPLEMENTING PROCEDURE EPIP-1 0 MEDICAL EMERGENCY RESPONSE Revision 16 Unit 0 PREPARED BY: James F. Hagy SPONSORING ORGANIZATION:

Emergency Planning APPROVED BY: Frank L. Pavlechko Effective Date: 03/31/2003 LEVEL OF USE: REFERENCE NON-QUALITY RELATED I WBN I MEDICAL EMERGENCY RESPONSE I EPIP 0 REVISION DESCRIPTION:

Revision 1 Implementation Pages Description of Revision Number l Date Affected 11 02/08/00 All Non-intent Changes. Revised phone numbers to McMinn Hospital and REAC/TS. Revised map to McMinn Hospital using new State Route 305.12 06/14/00 All Non Intent change. Phone number to Fire Protection revised.Reference number revised. Typographical error corrected.

Physician's designee added to the procedure for EMS consultation on medical response.

This revision resolves problems identified in WBN PER, 006394.13 09/25/01 APlan effectiveness determinations revisions indicate the following revisions do not reduce the level of effectiveness of pg. 6, 10, 18 the procedure of REP: Intent change. Procedure revised to Non-Quality related per requirements of NQAP & pending revision to SPP-2.2. The coversheet and records section of the procedure was revised to reflect this change.Non-intent change. Removed reference to TVA Physician and replaced with Site Physician or designee 14 01/24/02 All Plan effectiveness determinations revisions indicate the following revisions do not reduce the level of effectiveness of pg. 3, 12 the procedure of REP: Non-intent change. Added emergency room notification to l_ Appendix D.15 06/05/02 All Plan effectiveness determinations on these changes indicate the following revisions do not reduce the level of effectiveness 3, 8, 10 11 & of the procedure or REP.20 Non-intent change(s):

Added location of the 911 phone in app.B & C. Revised phone number to Industrial Safety, RADCON and MCR. Removed zip codes from Appendix C. Added OSHA notification requirements within (8) hours after a catastrophic accident and corrected two typo(s) in the l_ procedure.

16 03/31/2003 All Plan effectiveness determinations on these changes indicate the following revisions do not reduce the level of effectiveness of the procedure or REP.Non-intent change(s):

Updated format for intersite consistency.

Deleted Source Notes. Updated phone numbers.PAGE 2 of 24 REVISION 16 I WBN I MEDICAL EMERGENCY RESPONSE lTEPIP-1 0lTable of Contents Table of Contents .................................................................

3

1.0 INTRODUCTION

.................................................................

4

2.0 REFERENCES

.................................................................

4 3.0 INSTRUCTIONS

.................................................................

5 3.1 Initial Response .................................................................

5 3.2 Control Room Response .................................................................

5 3.3 Shift Manager Response .................................................................

5 3.4 Incident Commander Response .................................................................

6 3.5 MERT Response .................................................................

6 3.6 Medical Services Nurse Response .................................................................

6 3.7 RADCON Response .................................................................

6 3.8 Nuclear Security and Standby AUO Response .........................................................

6 3.9 Supplies .................................................................

6 4.0 RECORDS .................................................................

7 APPENDIX A Control Room Operator Medical Response Checklist

.........................................

8 APPENDIX B Shift Manager (SM) Medical Response Checklist

...............................................

9 APPENDIX C Notification List ................................................................

11 APPENDIX D Hospital Notification Report ................................................................

12 APPENDIX E Incident Commander

-Designated US Medical Response Guidelines

.............

13 APPENDIX F EMS Leader/Emt Medical Response Guidelines

..............................................

15 APPENDIX G Radiological Control (RADCON) Medical Response Guidelines

......................

17 APPENDIX H Medical Services (Nurse) Medical Response Guidelines

.................................

19 APPENDIX I Nuclear Security/AUOs (on Standby) Medical Response GUIDELINES

............

20 APPENDIX J Transit Maps ................................................................

21 APPENDIX K Blood Clean-Up at Watts Bar Nuclear Plant .....................................................

24 PAGE 3 of 24 REVISION 16 I WBN I MEDICAL EMERGENCY RESPONSE I EPIP 0

1.0 INTRODUCTION

At WBN the Medical Emergency Response Team (MERT) is an organized group of onsite personnel designated as the primary responders in a medical emergency.

Emergency medical treatment involves treatment of a patient in areas other than the Medical Services facility.

The MERT shall consist of the following list of personnel:

  • Operations (Designated Unit Supervisor (US) and available AUOs)* Fire Protection Section* Radiological Control (RADCON) Technicians
  • Medical Services -Nurse as requested* Nuclear Security This procedure outlines the actions to be followed during medical emergencies by the Medical Emergency Response Team (MERT) and other onsite support personnel.

The Shift Manager (SM) and the MERT team members are primarily responsible to ensure that the actions outlined in this procedure are implemented.

2.0 REFERENCES

2.1 Source Documents 1. NUREG 0654, FEMA-REP-1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in support of Nuclear Power Plants 2. NUREG 0696, Functional Criteria for Emergency Response Facilities, Final Report 2.2 Interfacing Documents 1. NP Radiological Emergency Plan (REP)2. WBN-EPIP-2 Notification of Unusual Event 3. WBN-EPIP-3 Alert 4. WBN-EPIP-4 Site Area Emergency 5. WBN-EPIP-5 General Emergency 6. WBN-EPIP-12, Emergency Equipment and Supplies 7. SPP-3.1 Corrective Action Program 8. SPP-3.5 Regulatory Reporting Requirements

9. ANSI Standard N.18.7-19762.0 PAGE 4 of 24 REVISION 16 WBN MEDICAL EMERGENCY RESPONSE EPIP-1 0 3.0 INSTRUCTIONS 3.1 Initial Response Upon discovering an ill or injured person, ALL WBN personnel shall A. ADMINISTER immediate aid for any life threatening situation (IF TRAINED).B. SUMMON assistance from available personnel in the immediate area.C. NOTIFY the Control Room Ext. 3911 and state that a medical emergency has occurred and RESPOND to ALL Questions.

NOTE Individuals not involved in the emergency are to remain at their work stations, refrain from using the phone, portable radio, and elevators, and continue working unless called upon for assistance or told to move to another location.CAUTION Patients known or suspected of being in medical distress shall not be allowed to walk, especially when the cause of distress may be aggravated by exertion.3.2 Control Room Response Upon receipt of medical emergency notification, Control Room personnel shall perform APPENDIX A, Control Room Operator Medical Response Checklist.

3.3 Shift Manager Response Upon receipt of medical emergency notification, the Shift Manager shall perform APPENDIX B, Shift Manager (SM) Medical Response Checklist.

IF Offsite Hospital assistance is required, THEN the Shift Manager shall perform APPENDIX D, Hospital Notification Report.PAGE 5 of 24 REVISION 16 I WBN I MEDICAL EMERGENCY RESPONSE I EPIP 0 3.0 Instructions (continued) 3.4 Incident Commander Response Upon receipt of medical emergency notification, the Incident Commander (US) shall perform APPENDIX E, Incident Commander (US) Medical Response Guidelines.

3.5 MERT Response Upon receipt of medical emergency notification, the MERT shall perform APPENDIX F, EMS Leader/EMT Medical Response Guidelines.

3.6 Medical Services Nurse Response Upon receipt of medical emergency notification, the Medical Services Nurse shall perform APPENDIX H, Medical Services Nurse Medical Response Guidelines.

3.7 RADCON Response Upon receipt of medical emergency notification, RADCON shall perform APPENDIX G, Radiological Control (RADCON) Medical Response Guidelines.

3.8 Nuclear Security and Standby AUO Response Upon receipt of medical emergency notification, Nuclear Security and Standby AUO(s) shall perform APPENDIX I, Nuclear Security/AUOs (on Standby) Medical Response Guidelines.

3.9 Supplies Radiological Emergency Supply Cabinets are located at the agreement hospitals and are stocked in accordance with EPIP-12, Emergency Equipment And Supplies.

Specialized replacement items can be obtained in coordination with the WBN EP Manager as required.PAGE 6 of 24 REVISION 16 I WBN I MEDICAL EMERGENCY RESPONSE EPIP-10 4.0 RECORDS 4.1 Records of Classified Emergencies The materials generated in support of key actions during an actual Medical Emergency are considered Lifetime retention Non-QA records. Materials shall be forwarded to the EP Manager who shall submit any records deemed necessary to demonstrate performance to the Corporate EP Manager for storage.4.2 Drill and Exercise Records The materials deemed necessary to demonstrate performance of key actions during drills are considered Non-QA records. These records shall be forwarded to the EP Manager who shall retain records deemed necessary to demonstrate six-year plan performance for six years. The EP Manager shall retain other records in this category for three years.PAGE 7 of 24 REVISION 16 I WBN MEDICAL EMERGENCY RESPONSE I EPIP 0 APPENDIX A CONTROL ROOM OPERATOR MEDICAL RESPONSE CHECKLIST (Page 1 of 1)Control room personnel will USE the following checklist in their RESPONSE to an onsite medical emergency.

A. Obtain NAME of caller_B. LOCATION (Bldg., Elev., Column) _C. Type of Medical Emergency_

D. Number of Personnel Involved E E. Immediate Area Hazards (Radiological, Safety)El F. Telephone Number of Caller E G. ALERT and DISPATCH MERT PERSONNEL E H. Make the following plant announcement with public address: El"ATTENTION ALL SITE PERSONNEL.""ATTENTION ALL SITE PERSONNEL.""A MEDICAL emergency has been reported.

The MERT is to ACTIVATE and RESPOND to the following LOCATION:..I. CONFIRM that the Shift Manager (SM) has been notified.

El J. CONFIRM that the Fire Protection Section Duty Shift E Supervisor (Fire Brigade Leader) was notified by: Radio or Telephone (extension

  1. 3311 or #3355) and Pocket Pager #40566 K. CONFIRM/COORDINATE MERT response (via radio or phone) E until Incident Commander assumes control.PAGE 8 of 24 REVISION 16 WBN MEDICAL EMERGENCY RESPONSE EPIP 0 APPENDIX B SHIFT MANAGER (SM) MEDICAL RESPONSE CHECKLIST (Paqe 1 of 2)SMs will use the following checklists in Appendix B in response to an onsite SMs will use the following checklists in Appendix B in response to an onsite Medical Emergency:

INITIAL RESPONSE CHECKLIST A. ESTABLISH and MAINTAIN communications with the a designated Incident Commander.

B. ENSURE the Onsite Medical Services Personnel (if staffed) El have been notified to STANDBY. (#3254)C. OBTAIN victim's name(s) and company or section. D Name Co. Section_D. IF NEEDED, EXPEDITE offsite ambulance and hospital El support by immediately completing the Hospital Notification Report in Appendix D and going to steps in TRANSPORTING OFFSITE of this Appendix.PAGE 9 of 24 REVISION 16 I WBN I MEDICAL EMERGENCY RESPONSE I EPIP 0 APPENDIX B SHIFT MANAGER (SM) MEDICAL RESPONSE CHECKLIST (Page 2 of 2)TRANSPORTING OFFSITE A OBTAIN medical transports, as requested by the Incident Commander, E Primary ambulance number: 9-775-2141, back-up 911 (outside bell line on SM desk)Life Force Helicopter:

9-778-5433, contact radio frequency is 155.205 IF Life Force is called, ALSO call Rhea County Ambulance for additional medical support B ADVISE ambulance dispatcher of radiological conditions, type of I medical emergency, type of transport needed (emergency or non-emergency), and point of site entry.C ENSURE the receiving hospital is notified, and has the information identified on D APPENDIX D.NOTE 1 All WBN employees with service related traumatic injuries should be transported to an agreement facility.

IF in shock or the condition is life threatening, he or she should be taken to the nearest facility, (Rhea Medical Center)NOTE 2 IF the patient is suspected or known to have been over exposed or contaminated with radioactive material, use an agreement hospital and ambulance IF use of the WBN ambulance is not preferred.

D NOTIFY Nuclear Security to escort the ambulance onsite or prepare the landing C zone and advise of its Estimated Time of Arrival (ETA)FOLLOW-UP ACTIONS A. PERFORM reporting functions required by SPP-3 01 and SPP-3.5.B IF it is determined that the patient's "Emergency Contact" (located on the a employee's Form TVA 9880, Employee Status and Information Record) needs to be notified, ENSURE that Employee Relations

& Development is contacted during regular hours and the employee's Supervisor is contacted during off-hours C. IF the victim was determined to be a non-TVA employee, ensure that their supervision has been notified D. NOTIFY the site Physician (or designee) any time TVA personnel receive radiation E doses in excess of the TVA occupational dose limits at the first opportunity and as information becomes available

(#3254)E NOTIFY Industrial Safety (if on duty) (#3418) or at home if the medical emergency 0 has resulted in a fatality or catastrophic injury (i e three (3) or more hospitalized.

OSHA notification needs to be made within eight (8) hours after these types of accidents by the site Industrial Safety Manager or duty Plant Manager.PAGE 10 of 24 REVISION 16 I WBN I MEDICAL EMERGENCY RESPONSE I EPIP 0 APPENDIX C NOTIFICATION LIST (Page 1 of 1)WATTS BAR ONSITE EMERGENCY CONTACTS Medical Emergency/TVA Ambulance

-3911 Medical Office (WBN Training Center) -3254 Nuclear Security -8544 Shift Manager -7860 RADCON -7865, 1862 Fire Protection Section -3311 (3355, Back-up), FPS Pocket Pager for Duty FPS/SS at 40566 Site Safety Manager -3418 AMBULANCE Primary: Primary contact: 9-775-2141 (Dayton)Rhea County Ambulance Service 911 (Backup, outside bell line SM Desk)Highway 27, North Dayton, Tennessee Secondary contact: 9-365-9500 (Spring City)Life Force Helicopter Primary contact: 9-778-5433 (Chattanooga)

RADIOLOGICAL AGREEMENT HOSPITALS Rhea Medical Center (Primary Hosp) Athens Reg. Med. Center (Secondary Hosp)Highway 27, North 111 W. Madison Ave.Dayton, Tennessee Athens, TN 9-775-1121 9-1-(423)-745-1411 9-775-8542 (ER) 9-1-(423)-744-3260 (ER)9-775-8589 (ER) 9-1-(423)-744-3227 (ER)RADIOLOGICAL/TRAUMA Erlanger Medical Center 975 E. Third St.Chattanooga, TN 9-778-7296 (Emergency Room)NOTE Erlanger provides Trauma/Radiological Backup services to TVA when directed by one of our Agreement Hospitals.

REAC/TS, OAK RIDGE, TENNESSEE 24-Hour Hospital Disaster Network Commercial 9-1-(865) 576-3131 9-1-(865) 576-1005.PAGE 11 of 24 REVISION 16 I WBN I MEDICAL EMERGENCY RESPONSE I EPIP 0 APPENDIX D HOSPITAL NOTIFICATION REPORT (Page 1 of 1)(Non-QA Record)The Shift Manager shall complete this form and NOTIFY the destination hospital as soon as the need for offsite transportation is determined by calling: Primary, Rhea Medical Center (9-775-1121 or 9-775-8542), or Secondary, Athens Regional Medical Center (9-1-(423)-745-141 1 or 9-1-(423)-744-3227)."This is the Shift Manager at the Watts Bar Nuclear Plant." (Connect me with the Emergency Room)Date I / Time Hospital_Person Contacted Title MESSAGE"Watts Bar Nuclear Plant will be sending _ (number) injured person(s) to your hospital Emergency Department.

The victim(s) is/are (names): Patient Condition: (Check one)o "NOT a Radiation Accident Victim(s).

No radiological hazards." O "Contaminated with radioactive material. (External/lInternal)" o "Radiation overexposure only, no contamination" O "Contaminated and Overexposed" O "Potentially Contaminated, Medical injuries prevent a complete body survey.""Contamination Levels are: O Unknown at this time o Counts Per Minute (Report as maximum level identified)_

o Millirem/hour

"_"Check appropriate type of radiation:

0 Alpha 0 Beta 0 Gamma REM exposure MREM exposure""The nature of injury(ies) are:__"The medical condition of the victim is: ';"An Estimated Time of Arrival (ETA) will be provided by the ambulance EMT upon departure from Watts Bar.""Please call me back at to verify and confirm the validity of this medical emergency call." (The SM should prepare to receive an immediate confirmation call-back from the Hospital.)

PAGE 12 of 24 REVISION 16 I WBN I MEDICAL EMERGENCY RESPONSE I EPIP-10 APPENDIX E INCIDENT COMMANDER

-DESIGNATED US MEDICAL RESPONSE GUIDELINES (Page 1 of 2)Incident Commander's will UTILIZE the following Guidelines in responding to an onsite Medical Emergency:

NOTE 1 The following steps may be performed in varying sequences as needed.NOTE 2 If personnel contamination with injury has occurred, necessary medical treatment will take precedence over decontamination efforts.INITIAL RESPONSE A ESTABLISH communications with the SM and EMS leader. E B. RESPOND to the incident and ESTABLISH a COMMAND POST. a C. DIRECT initial first-aid MERT efforts until the EMS Leader arrives. D D. DIRECT personnel in support of the medical response (i.e., RADCON, 0 Nuclear Security, AUOs, Nurse).E. ADVISE the SM of the victim's name and organization.

El F. ADVISE the SM on radiological conditions with the patient. C G. ADVISE the SM on which ambulance is required (per MERT Leader). 0 NOTE 3 Rhea County Ambulance is primary. TVA is secondary or for "load and go" if Rhea County Ambulance has an unacceptable ETA.PAGE 13 of 24 REVISION 16 l WBN l MEDICAL EMERGENCY RESPONSE EPIP 0 APPENDIX E INCIDENT COMMANDER

-DESIGNATED US MEDICAL RESPONSE GUIDELINES (Page 2 of 2)H. ADVISE the EMS leader on access/egress routes. C I. IF radiological conditions with the patient are confirmed or suspected, °DIRECT RADCON to accompany the patient in the ambulance and provide Radiological Control assistance.

J. DIRECT on scene Security to address site access badging needs. °K. CONTROL access to the accident scene until all hazards are removed to C the extent that the area can be returned to unrestricted access (i.e., radiological, physical, or bio-hazard blood borne pathogens).

L. IF the emergency is at the onsite Health Station and the full MERT has °not been activated, then COORDINATE necessary support (i.e., standby notice to onsite EMTs, Security escorts for responding ambulances, and notifications).

PAGE 14 of 24 REVISION 16 WBN I MEDICAL EMERGENCY RESPONSE I EPIP 0 APPENDIX F EMS LEADERIEMT MEDICAL RESPONSE GUIDELINES (Page 1 of 2)INITIAL RESPONSE NOTE I The following steps may be performed in varying sequences as needed.A. ESTABLISH communications with the Incident Commander (US).B. DIRECT the dispatch of EMTs and equipment to the scene.C. RESPOND to the scene and ASSUME direction of the EMS response.D. COORDINATE necessary support via the Incident Commander.

E. DETERMINE which ambulance (if any) is to be used. (ADVISE SM).NOTE RHEA COUNTY AMBULANCE is the PRIMARY means of ground transport unless the medical emergency is life threatening and the I the offsite ambulance is unacceptable.

LIFE FORCE helicopter ma utilized according to medical protocol.

This includes transportation contaminated and injured patients.

IF Life Force is chosen, Rhea C Ambulance should also be called as a back up for medical support.F. ADVISE the Incident Commander of the patient's destination (specific hospital, site Health Station or decon room or no further TVA care).G. IF the patient is contaminated, ENSURE the patient is wrapped in a linen sheet to contain the contamination during movement.H. IF the TVA ambulance is to be used, an EMT shall ride with the injured person. REFER TO Appendix J, Transit Maps, for driving directions.

El 0 0 0 0 ETA of ,y be of County El El El NOTE 3 One TVA EMT from the Fire Protection Section or a nurse shall remain onsite at all times, except in life-threatening situations as determined by the site Physician (or designee) or EMS Leader, in consultation with the SM.PAGE 15 of 24 REVISION 16 I WBN I MEDICAL EMERGENCY RESPONSE l EPIP 0 APPENDIX F EMS LEADER/EMT MEDICAL RESPONSE GUIDELINES (Page 2 of 2)The EMT shall CONTACT the receiving hospital from the C ambulance to provide an updated report and Estimated Time of Arrival.J. OBTAIN SM concurrence if a TVA ambulance is to be taken offsite, C out-of-service, or when an employee treated by a TVA EMT is taken offsite for medical treatment due to service-related injury or illness.K. ENSURE necessary actions are taken for blood-borne pathogen controls a at the accident scene. REFER TO Appendix K, Blood Cleanup at Watts Bar Nuclear Plant. Assistance may be available from siteHealth Services.ADVISE the Incident Commander of clean-up status.PAGE 16 of 24 REVISION 16 l- WBN I MEDICAL EMERGENCY RESPONSE I EPIP-10 APPENDIX G RADIOLOGICAL CONTROL (RADCON)MEDICAL RESPONSE GUIDELINES (Page 1 of 2)INITIAL RESPONSE A. ADVISE the MERT of radiological conditions and PROVIDE radiological support (monitoring, dosimetry, contamination control).B. ESTABLISH contamination control zones to support the EMS effort.C. COORDINATE the collection of isotopic samples for analysis.D. ASSIST in onsite patient decontamination as indicated.

NOTE 1 Essential medical care takes priority over decontamination.

NOTE 2 If the person is severely injured, they will be transported directly to agreement hospital.

However, reasonable efforts should be made t reduce the exposure level from contamination to less than 500 mrer at one foot. The patient shall be wrapped in a linen sheet to contaii contamination.

Avoid the use of plastics to prevent patient heat stre E. ACCOMPANY the patient in the ambulance (for radiological conditions).

F. ADVISE the SM if a REP Van needs to be dispatched to the hospital.G. Upon arrival at the hospital, ADVISE the hospital team leader or Radiation Safety Officer of your identity and offer assistance.

H. Unless directed otherwise, PROVIDE general radiological support (i.e., establish checkpoint, perform surveys of personnel and equipment).

El El El El an 0 m/hour 1I ss.El El El El PAGE 17 of 24 REVISION 16 I WBN IMEDICAL EMERGENCY RESPONSE I EPIP-10 APPENDIX G RADIOLOGICAL CONTROL (RADCON)MEDICAL RESPONSE GUIDELINES (Page 2 of 2)FOLLOW-UP on TLD process and isotopic analysis data to the hospital.

D J. COLLECT contaminated material from the hospital and take necessary D actions for disposal.

Transport of material shall be in accordance with the TVA Radiological Material Shipping Manual.K. Any personnel known or suspected of receiving radiation exposure in 0 excess of the TVA occupational dose limits should be reported by RADCON to the Site Physician (or designee) at the first opportunity and as information becomes available.

(#3254) a PAGE 18 of 24 REVISION 16 WBN MEDICAL EMERGENCY RESPONSE EPIP-1 0 APPENDIX H MEDICAL SERVICES (NURSE)MEDICAL RESPONSE GUIDELINES (Page 1 of 1)A. PREPARE to assist with patient care if the patient is brought to the site medical facility or onsite decontamination facility.B. RESPOND to the accident scene when requested, (Nuclear Security will provide an escort).C. COORDINATE radiological decontamination efforts with RADCON while onsite as the medical status permits.D. ACCOMPANY the EMT in the ambulance if needed.NOTE 1 If an ambulance is to be used, an EMT shall ride with the injured F A nurse may accompany the EMT.NOTE 2 One TVA EMT from the Fire Protection Section or a nurse shall re onsite at all times, except in life-threatening situations as determin the site physician or EMS Leader, in consultation with the SM.NOTE 3 Individuals who have received an acute whole body radiation exp(greater than 5 rem should have hematological studies performed I chromosomal aberrations or other changes in blood constituents.

REACTS can provide this service and can be contacted at 9-1-865-576-3131 or 9-1-865-576-1005, by the attending physiciar E. IF an emergency medical situation occurs at the Medical Station which requires EMT or ambulance assistance, REQUEST assistance using extension 3911. IF the situation is not of an emergency nature, the SM may be notified directly using a non-emergency phone number.El El El El person.zmain ed by)sure to detect-I.El PAGE 19 of 24 REVISION 16 I WBN I MEDICAL EMERGENCY RESPONSE I EPIP-10 0 APPENDIX I NUCLEAR SECURITYIAUOs (on Standby)MEDICAL RESPONSE GUIDELINES (Page 1 of 1)NUCLEAR SECURITY A. FACILITATE emergency personnel and equipment movement through El site areas, including control of the plant elevator as necessary.

B. PROVIDE crowd control (at accident scene and ambulance).

a NOTE If helipad is to be used, stage a vehicle with emergency lights to aid in the identification of the landing area to the aircraft.

DO NOT shine spotlights in the air at the aircraft and DO NOT approach the aircraft once landed. KEEP all bystanders away from aircraft.

Flight crew will handle patient loading. If there is a nearby aerial obstruction (power line, power pole, illumination by spot light is recommended.

C. COORDINATE site access badging, TLD issuance, and escort needs with E MERT members, support staff, and offsite responders.

D. PROVIDE vehicle escorts for ambulances arriving and departing the site a as necessary.

E. PROVIDE escort for site Medical Services Staff from the Medical Station E to the accident scene as required.ASSISTANT UNIT OPERATORS A. Available AUOs will report to the Service Building Fire Emergency Equipment Room, Elevation 729 and WAIT for instructions from the Incident Commander.

B. Anticipate the following needs:.Delivery of equipment and supplies to the MERT (stretchers, etc.)..Assistance on securing/operating elevators.

  • Assistance with plant equipment as related to the emergency response.* Prepare to dress-out if you may be used in the control zone or for aid in passing a contaminated patient onto an awaiting stretcher.

PAGE 20 of 24 REVISION 16 WBN I MEDICAL EMERGENCY RESPONSE I EPIP-10 APPENDIX J TRANSIT MAPS (Page 1 of 3)WATTS BAR TO RHEA MEDICAL CENTER (5.9 T (11.8 miles)nbles)(0.7 miles) I I Watts INuc IPi, Total: 18.4 miles 2-Lane Highway 0 L.0 0 PAGE 21 of 24 REVISION 16 I WBN I MEDICAL EMERGENCY RESPONSE I EPIP 0 APPENDIX J TRANSIT MAPS (Page 2 of 3)WATTS BAR TO ATHENS REGIONAL MEDICAL CENTER[Athens Regional Medical Center Contaminated Patient Preparation Total Miles to the Hospital: 26 Miles Via Hwy 30511-75 Fr PAGE 22 of 24 REVISION 16 I WBN I MEDICAL EMERGENCY RESPONSE I EPIP 0 APPENDIX J TRANSIT MAPS (Page 3 of 3)WATTS BAR TO ERLANGER MEDICAL CENTER AREA"am EMERGENCY ROOM s- 75, r. 7r_ ^xrX =.I. I: L~ II< = == -=- = =HAMPTON RD.Pnmrry Route is as Follows: Leave WBN Nuclear Plant via Rt. 68 to Highway 27 (6.3 rmale) Highway 27 to 4th Street limmediately after Tennassee River Bridge)to Eulanger Hospital via Lasrmng Street to 3rd Street (0.6 rnlel)." Corridor" RED BANK TO ATLANTA I-24 FOURTH 9 PAGE 23 of 24 REVISION 16 WBN I MEDICAL EMERGENCY RESPONSE I EPIP-10 APPENDIX K BLOOD CLEAN-UP AT WATTS BAR NUCLEAR PLANT (Page 1 of 1)Fire Operations Personnel have the responsibility of cleaning up accidentally spilled blood on site.The following methods are to be used in cleaning up spilled blood: Accidentally spilled blood in plant (including Stainless Steel piping).1. Wipe up blood, using damp cloth.2. Wipe spill area with cloth fully saturated (wet) with O-SYL Disinfectant "USE CODE II", diluted to proper strength solution (see O-SYL container for dilution ratio).3. Let stand for ten (10) minutes, maintaining a damp surface.4. Let area dry. Do not wipe up.5. Place all clean-up materials in a "Bio-Hazard" marked disposable bag.6. Take "Bio-Hazard" bag to Site Medical Services for disposal.7. Notify Chem-Lab and have them do a swipe test per CEM-601.(If blood spilled on Stainless Steel Piping)8. If swipe test does not meet CEM-601 specs, re-do steps needed until acceptable limits are met.PAGE 24 of 24 REVISION 16 TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT EMERGENGY PLAN IMPLEMENTING PROCEDURE EPIP-1 1 SECURITY AND ACCESS CONTROL Revision 1 1 Unit 0 PREPARED BY: James F. Hagy SPONSORING ORGANIZATION:

Emergency Planning APPROVED BY: Frank L. Pavlechko Effective Date: 04/23/2003 LEVEL OF USE: REFERENCE NON-QUALITY RELATED WBN SECURITY AND ACCESS CONTROL I EPIP-1 1 REVISION DESCRIPTION:

Revision Effevctive Pages Description of Revision Number Date Affected 5 2/15/97 3, 5, 6, 7, Editorial non-intent revisions made. SOS revised to SM.8,11 Records section added. Information note added to Security in i .Section 3.3. Contingency(s) titles added to Section 3.6.Owner controlled area ID added to map in Appendix A. JIC map revised.6 6/30/98 All Non-intent Change. Revised location of LNC.7 6/14/00 All Non Intent change. Revised title of WBN Communications Specialist.

This revision resolves problem identified in WBN PER, 006394.8 9125/01 All Intent change. Procedure revised to Non-Quality related pg. 7 per requirements of NQAP & pending revision to SPP-2.2.The coversheet and records section of the procedure was revised to reflect this change.9 06/05/02 All Plan effectiveness determinations on these changes indicate the following revisions do not reduce the level of 2, 6 effectiveness of the procedure or REP.Non-intent change(s):

are based on enhanced Security requirements directed by the NRC. Security actions and Media Contingencies wording enhanced in 3.6 for the disposition of media personnel arriving at the site after a REP emergency situation or when the JIC is not activated.

10 07/30/02 All Plan effectiveness determinations on these changes 2, 3, 4, 6-8 indicate the following revisions do not reduce the level of effectiveness of the procedure or REP.Intent changes made to the procedure to support the NRC Safeguards Advisory and actions associated with IN 2002-14. (ie) Specified the requirement for a declared emergency in the procedure purpose. The TCP point at Route 68 was moved to its new location.

The emergency responder car window placard was eliminated along with the appendix.

The appendices were re-designated.

EPIP-8 was referenced in the instructions.

New picture provided for appendix A.11 04/23/2003 All Plan effectiveness determinations on these changes indicate the following revisions do not reduce the level of effectiveness of the procedure or REP.Non-intent changes. Deleted source notes, reformatted for intersite consistency.

Revised records section and references.

Enhanced information on media contingencies.

PAGE 2 OF 12 REVISION 11 WBN I SECURITYANDACCESS CONTROL I EPIP-11 lTable of Contents Table of Contents ...........................................................

3 1.0 PURPOSE ...........................................................

4

2.0 REFERENCES

...........................................................

4 3.0 INSTRUCTIONS

...........................................................

5 3.1 General..........................................................................5...................................................5 3.2 Access Control to the Protected Area during Emergencies

...............................................

5 3.3 Access to the Owner Controlled/Site Perimeter Area ........................................................

6 3.4 Egress Control from the Protected Area ...........................................................

7 3.5 Egress Control from the Site Area and Owner Controlled Area .........................................

7 3.6 Security and Media Contingencies

...........................................................

7 4.0 RECORD RETENTION

...........................................................

8 K. 4.1 Records of Classified Emergencies

...........................................................

8 4.2 Drill and Exercise Records ...........................................................

8 APPENDIX A Owner Controlled/Site Perimeter and Protected Area ..........................................

........9 APPENDIX B Radiological Emergency Access Log Sheet ..........................................................

11 APPENDIX C Directions to the TVA Joint Information Center (JIC) .................................................

12 PAGE 3 OF 12 REVISION 11 I WBN I SECURITYANDACCESS CONTROL I EPIP- 11l1.0 PURPOSE A. This Procedure provides guidelines for Nuclear Security (NS) to implement access control during a Declared Radiological Emergency.

B. This EPIP does not address security problems/contingencies that may arise during a radiological emergency.

These problems shall continue to be handled in accordance with the approved Security Contingency Plan.

2.0 REFERENCES

1. Site Physical Security Plan 2. Site Security Instruction (SSI) 2.3, Security Radiological Emergency Plan Implementation
3. EPIP-8, Personnel Accountability and Evacuation
4. NP Radiological Emergency Plan (REP)5. NUREG 0654 6. Title 10 Code of Federal Regulations Part 20 and 50 7. ANSI N18.7-1976 PAGE 4 OF 12 REVISION 11 I WBN I SECURITY AND ACCESS CONTROL I EPIP-1 1 l-'3.0 INSTRUCTIONS 3.1 General NOTE: Terms denoting areas or locations are defined and depicted in Appendix A, Owner Controlled/Site Perimeter and Protected Area.A. Nuclear Security will implement these Instructions in conjunction with EPIP-8,"Personnel Accountability and Evacuation," or as directed by the Site Emergency Director (SED).B. The WBN Emergency Preparedness Manager will establish and maintain an"Emergency Response Organization Call List" comprised of current qualified responders.

This list will be provided to Nuclear Security and updated quarterly.

C. The Site Security Manager shall establish an instruction which delineates specific requirements to be performed by NS during a radiological emergency.

This instruction shall address directed requirements for the security force contained in this Procedure.

3.2 Access Control to the Protected Area during Emergencies A. If directed by the SM/SED, NS will restrict access to the Protected Area during any emergency situation at Watts Bar that has resulted in conditions within the Protected Area which warrant accountability and or evacuation (i.e., Alert, Site Area Emergency, or General Emergency.)

B. As directed by the SM/SED or TSC Security Manager, onsite hazards should be identified to the emergency responder prior to entering the Protected Area using the hazards awareness board in the Access Portal.C. Emergency responders whose names appear on the Emergency Response Organization Call List or as authorized by the SED or NS representative in the TSC or OSC Manager will be authorized access.D. NRC Personnel have authorized access.E. Personnel allowed entry will be responsible for entering into the accountability card readers as soon as possible after entering the protected area.F. Fire protection vehicles, radiological control (RADCON) monitoring vans, and other emergency vehicles and personnel will be permitted immediate access upon confirmation with the SED that an onsite emergency does exist and their service has been requested.

PAGE 5 OF 12 REVISION 11 I WBN I SECURITY AND ACCESS CONTROL IEPIP-1 1 3.3 Access to the Owner Controlled/Site Perimeter Area A. NS will control access at the OCA Traffic Control Point (Appendix A -map).Access control will be as follows: B. NS will GRANT access to those individuals who display a site or other TVA photo ID badge C. NS will GRANT access to those individuals whose names are indicated on the Emergency Response Organization Call List and/or other approved list as provided by the SED, TSC Security Manager, or OSC Manager.D. NS will GRANT access to others as verbally approved by the SED or NS representative in the TSC.E. As DIRECTED by the TSC Security Manager/Security Shift Supervisor, onsite hazards should be identified to the emergency responder prior to entering the site.NOTE 1: Personnel identification cards, uniforms, vehicle markings or letter of access may be used for identification.

NOTE 2: Appendix B, Radiological Emergency Access Log Sheet, or similar form may be used to account for individuals/vehicles gaining access to the site during a radiological emergency.

If emergency vehicles are responding to an immediate/ongoing emergency they should not be delayed but quickly identified and escorted (if security staff are available).

F. The following offsite support organizations will be permitted immediate access to the owner controlled area:* Fire protection vehicles.Ambulances

  • Tennessee Emergency Management Agency (TEMA)PAGE 6 OF 12 REVISION 11 I WBN I SECURITYAND ACCESS CONTROL I EPIP-1 1 l3.4 Egress Control from the Protected Area A. Upon hearing the assembly/accountability siren, individuals whose assembly areas are outside of the protected area will be permitted to exit the protected area.B. Emergency vehicles and personnel, including RADCON monitoring vans, will be allowed immediate egress from the protected area during an ongoing radiological emergency.

C. In the event of a Protected Area evacuation, site personnel will receive instructions from the SM or the TSC/SED concerning what actions to take prior to exiting the Protected Area. Security personnel will follow the instructions provided in EPIP-8 "Personnel Accountability and Evacuation and/or the Physical Security Plan.3.5 Egress Control from the Site Area and Owner Controlled Area NOTE: Unauthorized personnel found in the owner controlled area will be reported to the TSC Security Manager for egress instructions.

A. Egress from the owner controlled area will be authorized only after RADCON completes a survey (if radiological release has occurred) or as granted by the SED through the TSC, NS Manager.B. NS will provide traffic control (if security staff are available).

3.6 Security and Media Contingencies A. Press personnel who respond to WBN during an emergency will be directed to the Joint Information Center (JIC) in Chattanooga. (Appendix C)B. If the emergency situation has been terminated or the JIC has not been activated and Press personnel respond to the site, the Owner Controlled Area Security Traffic Control Point will notify the SM or SED. Once approval has been granted by the Plant Duty Manager and escorts are provided, the Press will be directed to the WBN Local News Center (LNC) which is classroom 19 in the Training Center to await a briefing or additional instructions.

C. The WBN Communications Specialist should be notified as soon as possible of the situation (i.e., numbers of people, from: TV, radio, etc.). The contact is listed in the Plan of the Day (POD). IF the contact is unavailable, THEN request the ODS to notify the Information Duty Officer of the situation.

PAGE 7 OF 12 REVISION 11 I WBN I SECURITY AND ACCESS CONTROL I EPIP-1 I 4.0 RECORD RETENTION 4.1 Records of Classified Emergencies The materials generated in support of key actions during an actual emergency are considered Lifetime retention Non-QA records. Materials shall be forwarded to the EP Manager who shall submit any records deemed necessary to demonstrate performance to the Corporate EP Manager for storage.4.2 Drill and Exercise Records The materials deemed necessary to demonstrate performance of key actions during drills are considered Non-QA records. These records shall be forwarded to the EP Manager who shall retain records deemed necessary to demonstrate six-year plan performance for six years. The EP Manager shall retain other records in this category for three years.PAGE 8 OF 12 REVISION 11 I WBN I SECURITYAND ACCESS CONTROL l EPIP-1 1 APPENDIX A Owner Controlled/Site Perimeter and Protected Area (Page 1 of 2)DEFINITIONS:

A. The Protected Area is the area encompassed by physical barriers (i.e. security fence) which surrounds the plant (Reactor, Auxiliary, Control, Turbine, and Service Buildings, Switchyard, Intake Pumping Station, and Diesel Generator Buildings) through which access is controlled (Page 2 of 2- map).B. The Site Perimeter is the area between the protected area and the outermost fence/buildings surrounding the plant. (Page 2 of 2- map)C. The Owner-Controlled Area is the area which lies between the site perimeter and the TVA Site boundary. (Page 2 of 2- map)PAGE 9 OF 12 REVISION 11 I WBN I SECURITYAND ACCESS CONTROL I EPIP-1 l APPENDIX A Owner Controlled/Site Perimeter and Protected Area (Page 2 of 2)PAGE 10 OF 12 REVISION 11 I WBN I SECURITYAND ACCESS CONTROL I EPIP-1 lAPPENDIX B RADIOLOGICAL EMERGENCY ACCESS LOG SHEET (Page 1 of 1)Date NS Officer:Name Section , Badg im imev h #_ _ _ _..... v____ ;__ -_ I -IN O UT it : pprop i i 4 4 + 4 4 4 i i I 4- 4 4 i 4- -Ii 4 4 i 4-i t 4-4I44.3- + 1- t 4- + i i-4 t *?-4 + i 1-I~ 4 i + i+ 4 1 i 4 4 + 1 i i 1 L ________________________

---___________

-PAGE 11 OF 12 REVISION 11 I WBN I SECURITYAND ACCESS CONTROL I EPIP-1 1 lAPPENDIX C Directions to the TVA Joint Information Center (JIC)(Page 1 of 1)Follow Rt. 68 West to Rt. 27 South. Stay on 27 South to the Martin Luther King exit.Follow Broad Street to the TVA Chattanooga Office Complex (COC). The JIC is located in the Missionary Ridge Building.PAGE 12 OF 12 REVISION 11 4 -TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT EMERGENGY PLAN IMPLEMENTING PROCEDURE EPIP-1 2 EMERGENCY EQUIPMENT AND SUPPLIES Revision 19 Unit 0 PREPARED BY: James F. Hagy SPONSORING ORGANIZATION:

Emergency Planning APPROVED BY: Frank L. Pavlechko Effective Date: 03/31/2003 LEVEL OF USE: REFERENCE NON-QUALITY RELATED I WBN I EMERGENCY EQUIPMENT AND SUPPLIES I EPIP-12 REVISION DESCRIPTION:

Revision Implementatio Pages Description of Revision Number n Date Affected 16 09/25/01 All, pg. 8 Intent change. Procedure revised to Non-Quality related per requirements of NQAP & pending revision to SPP-2.2. The coversheet and records section of l _ the procedure was revised to reflect this change.17 06/05/02 All, pg. 4, Plan effectiveness determinations on these changes 10, 1, indicate the following revisions do not reduce the 15-17 level of effectiveness of the procedure or REP.Non-intent change(s):

Revised Appendix A RADCON Emergency Equipment and Appendix E Rhea Medical Center and Athens Regional Medical Center Emergency Cabinet Inventory to met TVAN standardized examples per direction of the EP PEER Team. Added WOG-99-064 Emergency Response Guidelines (ERGs) Background Information, to the Appendix F, TSC Inventory.

Deleted the FRED reference from the TSC inventory.

This function is performed by the CECC per TVAN EP PEER Team standardization direction.

18 12/16/2002 All Plan effectiveness determinations on these changes indicate the following revisions do not reduce the level of effectiveness of the procedure or REP.Non-intent changes. Formatted procedure and appendices for inter-site consistency.

Enhanced work order tracking.

Restructured appendices to correspond to inspection frequencies.

Deleted source notes. Revised record retention period.Added Tritium Air Monitor for EDC-50629.

19 03/31/2003 2, 6, 24, Plan effectiveness determinations on these changes 28-40 indicate the following revisions do not reduce the level of effectiveness of the procedure or REP.Non-intent changes. Deleted Codes, Alarm, and Paging System details which are contained in SOI-100.01. Editorial corrections.

Page 2 of 41 Revision 19 I WBN I EMERGENCY EQUIPMENT AND SUPPLIES I EPIP-12 TABLE OF CONTENTS Section Title Page TABLE OF CONTENTS ...............................................................

3 1.0 PURPOSE ...............................................................

4

2.0 REFERENCES

...............................................................

4 3.0 INSTRUCTIONS

..............................................................

5 3.1 General Instructions

..............................................................

5 3.2 Completion of Appendices

...............................................................

8 4.0 RECORDS ...............................................................

8 Appendix A Monthly Medical/Emergency Supplies ...............................................................

9 Appendix B Quarterly Medical Emergency Supplies ..............................................................

10 Appendix C Monthly Emergency Use Pressure Demand Self-Contained Respiratory Equipment

..............................................................

11 Appendix D Monthly RADCON Emergency Equipment

............................................................

12 Appendix E Quarterly Rad Monitoring Van Emergency Equipment

...........................................

14 Appendix F Quarterly Hospital Inventory

..............................................................

15 Appendix G Quarterly Technical Support Center (TSC) Emergency Supplies .......................

16 Appendix H Quarterly Operations Support Center (OSC) Emergency Supplies .....................

18 Appendix I Monthly Communications/Equipment Test ............................................................

20 Appendix J Quarterly Communications/Equipment Test ..........................................................

28 Page 3 of 41 Revision 19 I WBN I EMERGENCY EQUIPMENT AND SUPPLIES I EPIP-12 I 1.0 PURPOSE This instruction is used to comply with the requirements of the Radiological Emergency Plan for periodic inspection and maintenance of equipment and supplies.

2.0 REFERENCES

2.1 Interfacing Documents 1. RCDP-8, Radiological Control Departmental Procedure: "Radiological Instrumentation and Equipment Controls" 2. NP Radiological Emergency Plan (REP)3. ANSI Standard N18.7-1976

4. WBN FSAR Chapter Six 2.2 Other Documents 1. NUREG 0654, Revision 1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants Page 4 of 41 Revision 19 WBN EMERGENCY EQUIPMENT AND SUPPLIES I EPIP-12 l3.0 INSTRUCTIONS 3.1 General Instructions
1. Responsible Organizations (as designated below) shall conduct inventory at the specified frequencies For the purposes of these inventories, monthly is defined as once per calendar month, quarterly is defined as once per calendar quarter, and annual is defined as once per calendar year. Similar frequency definitions as customarily used by performing organizations are acceptable.

RESPONSIBILITIES FOR EMERGENCY EQUIPMENT AND SUPPLIES INVENTORY AND MAINTENANCE

SUMMARY

APPENDIX FREQUENCY DESCRIPTION RESPONSIBLE A Monthly Monthly Medical/Emergency Fire Protection Supplies B Quarterly Quarterly Medical/Emergency Fire Protection Supplies C Monthly Self-Contained Respiratory Fire Protection Equipment D Monthly Radiological Control Lab Radiological Control E Quarterly Emergency Van Radiological Control F Quarterly Hospital Emergency Room EP Program Manager Cabinet G Quarterly Technical Support Center EP Program Manager Cabinets References

&Supplies H Quarterly Operations Support Center EP Program Manager Cabinets References

&Supplies I Monthly Monthly Communications/

EP Program Manager Equipment Test J Quarterly Quarterly Communications/

EP Program Manager Equipment Test 2. The individuals performing the inspection shall complete the appendices and make arrangements to correct deficiencies.

3. List any deviations and the disposition on the appropriate Appendix Data Sheet.Deficient, outdated or missing items shall be replaced.Page 5of41 Revision 19 I WBN I EMERGENCY EQUIPMENT AND SUPPLIES I EPIP-12l 3.1 General Instructions (cont.)4. Fire Protection (FP) shall be responsible for the inventory or inspection of equipment and supplies listed in Appendices A, B, and C.5. Medical Services is responsible for providing supplies to Fire Protection (as needed) in Appendices A and B.NOTE Radiological equipment identified in Appendix D is considered available for use and not dedicated equipment.

This equipment can also be utilized for routine plant operations.

6. Radiological Control (RADCON) shall be responsible for inventory or inspection of equipment listed in Appendices D and E.NOTE Appendix F shall be performed for EACH hospital facility.7. EP shall be responsible for inventory or inspection of equipment and supplies listed in Appendices F, G, H, I, and J.8. Special checks of certain material(s) in the cabinets shall be performed as follows: A. Copies of procedures maintained at the emergency response facilities (see Appendices) shall be checked/maintained by DCRM to verify latest revisions.

B. TSC and OSC position activity books are maintained/verified by EP.C. SCBA units and spare bottles shall be verified ready for use.D. Protective clothing and heat or moisture-sensitive items shall be checked for deterioration.

E. Flashlights shall be checked for power/operability, and batteries verified within expiration date.F. As necessary, replace batteries with fresh batteries from Power Stores.(Flashlight batteries may be discarded with ordinary refuse. Return calculator or other batteries to the Toolroom for disposal.)

G. Potassium Iodide (KI) in the OSC medical supply cabinet shall be checked for expiration date as indicated on Appendix H. Stock should be replaced if it expires prior to next projected inventory

(#Pkgs * #Tablets/pkg

= #doses).H. Seals or break-away locking devices are in place on cabinets which are not routinely used to provide a means of determining if a cabinet has been opened.Page 6 of 41 Revision 19 WBN EMERGENCY EQUIPMENT AND SUPPLIES I EPIP-12 3.1 General Instructions (cont.)9. Emergency Preparedness shall ensure that the contents of emergency equipment and supply cabinets in the emergency facilities are inventoried, inspected, and checked for operability and/or material condition each calendar quarter unless otherwise specified.

After drills, exercises, or real emergencies, equipment and supplies will be replenished as soon as possible by WBN Emergency Preparedness.

10. Portable radiation monitoring instruments shall be inventoried and calibrated routinely in accordance with RCDP-8. Instruments should be replaced if they require service/calibration prior to the date of the next inventory.

These instruments are inventoried on a calendar monthly basis.11.The WBN EP Manager shall review completed inventory lists (Appendices), investigate deficiencies, provide signature (if required) and maintain file copies.Page 7of41 Revision 19 I WBN I EMERGENCY EQUIPMENT AND SUPPLIES I EPIP-12 l 3.2 Completion of Appendices

1. If the particular items are present and in sufficient quantities and, when applicable, in good working condition, then check the "Yes" or "Sat" column.2. If a deficiency is noted, then check the "No" or " Unsat" column and replace deficient items. All deficiencies must be corrected as soon as possible.

If circumstances do not allow deficiencies to be corrected, then the appropriate supervisor shall be notified.3. Under the "Remarks" column, explain the corrective actions taken.4. All comments in the "Remarks" column should be detailed enough to leave no doubt as to the actions taken.5. Signatures of persons performing inventory and/or inspection are obtained as required.6. Completed Appendices are submitted to the Emergency Preparedness (EP)Manager.4.0 RECORDS The inventory(s)/inspection(s) in this instruction are Non-QA documents and will be retained by the WBN Emergency Planning Manager for at least three years.Page 8of41 Revision 19 WBN EMERGENCY EQUIPMENT AND SUPPLIES I EPIP-12 I Appendix A MONTHLY MEDICAUEMERGENCY SUPPLIES RESPONSIBILITY

-FIRE PROTECTION

1. This Appendix documents the performance of the following Preventive Maintenance (PM) instructions.

RECORD associated Work Implementing Document (WID) number.WID PM-0-FPS-510-AMB, File 1, Ambulance PM-0-FPS-510-0010, Fire Truck(s)PM-0-FPS-510-005, File 1, Stretcher Cabinets Inspection Performed By Date EP Manager Review Date Page 9of41 Revision 19 I WBN I EMERGENCY EQUIPMENT AND SUPPLIES I EPIP-12 Appendix B QUARTERLY MEDICAL EMERGENCY SUPPLIES RESPONSIBILITY

-FIRE PROTECTION This Appendix documents the performance of the following Preventive Maintenance (PM) instruction.

RECORD associated Work Implementing Document (WID) number.WID PM0-FPS-777-EQUIP, File 1, Fire Cages Inspection Performed By Date EP Manager Review Date Page 10 of 41 Revision 19 I WBN I EMERGENCY EQUIPMENT AND SUPPLIES I EPIP-12 l Appendix C MONTHLY EMERGENCY USE PRESSURE DEMAND SELF-CONTAINED RESPIRATORY EQUIPMENT RESPONSIBILITY

-FIRE PROTECTION Self-contained Breathing Apparatus (SCBA) equipment used for radiological emergency conditions are stored at the following locations:

REQUIRED NUMBER LOCATION SCBA KITS SPARE BOTTLES 1. Main Control Room 10 0 (located in El. 755 Relay Room)2. Auxiliary Building, El 757', Fire Cage 6 6 3. Service Building, El 729', Fire Cage 6 6 4. Service Building, El 713', Racks 20 20 5. Fire Truck and other Response Vehicles 5 4 (fire protection)

6. This Appendix documents the performance of the following Preventive Maintenance (PM) instruction.

RECORD associated Work Implementing Document (WID) number.WID PM-0-FPS-510-SCBA, File 1 Inspection Performed By Date EP Manager Review Date Page 11 of 41 Revision 19 WBN EMERGENCY EQUIPMENT AND SUPPLIES EPIP-12 Appendix D MONTHLY RADCON EMERGENCY EQUIPMENT (Page 1 of 2)RESPONSIBILITY

-RADCON Location:

Radiological Control Laboratory and support areas-Service Building, EL;QUANTITY DESCRIPTION YES NO F 1 Alpha survey meter (range 500,000 cpm)1 Neutron dose rate survey meter (0.025 eV-1 0 MeV range 5000 mR)2 High Range Survey Instrument (1,000 R/hr with extendable probe) (Perform source check)6 ION Chamber survey meter (50 R/hr)1 ION Chamber survey meter (20,000 R/hr)5 High volume air samplers &support equipment 5 Low volume air samplers (and support equipment) 10 Frisker type survey meters (50,000 cpm)2 Tritium Air Monitor (Model 309A)2 Particulate air filters (box)1 Disc smears (box)I Portable scaler 5 Calculators 10 Silver Zeolite cartridges 71 3" REMARKS 5 1 2000 Marinelli beakers Shielded Detector Potassium Iodide Tablets (14 tablets per package)Expiration:

Expiration:

Page 12 of 41 Revision 19 I WBN I EMERGENCY EQUIPMENT AND SUPPLIES I EPIP-12 l Appendix D MONTHLY RADCON EMERGENCY EQUIPMENT (continued)(Page 2 of 2)ITEM YES NO REMARKS QUANTITY 2 boxes 2 boxes 12 2 bottle 12 2 bottles 5 bars 1 container 1 box 1 can 5 1 box 25 1 5 each 2 rolls 10 pair 1 each 1 box Disposable Gloves (hypo allergenic)

Gauze Pads Cotton Swabs Saline Solution (list expiration date)Surgical Brushes Shampoo Soap Soap (liquid abrasive /mechanics)

Laundry Detergent Shaving Cream Razors Paper bath towels Towels Scissors Petri dish Duct tape Paper coveralls Shoes (sizes 7-12, half sizes OK)Facial tissue---Inspection Performed By EP Manager Review Date Date Page 13 of 41 Revision 19 WBN I EMERGENCY EQUIPMENT AND SUPPLIES EPIP-12 Appendix E QUARTERLY RAD MONITORING VAN EMERGENCY EQUIPMENT RESPONSIBILITY

-RADCON 1. See CECC-EPIP-9, Attachment J.2. A copy of Attachment J (completed) will be forwarded to the WBN EP Manager, WTC 1 P-WBN, for review and retention in the WBN EP files.3. CECC Attachment J reviewed and filed.Inspection Performed By Date EP Manager Review _ Date Page 14 of 41 Revision 19 WBN EMERGENCY EQUIPMENT AND SUPPLIES I EPIP-12 l Appendix F QUARTERLY HOSPITAL INVENTORY Watts Bar Hospital Supply Cabinet Inventory I LI I Rhea Medical Center I L I Athens Regional Medical Center SAT I Quantity I Description Remarks Protective Clothing_10 air Shoe covers 10 pkgs. Dress out packages (coveralls, booties, aloves)3___ea. Surg ical gowns 2 boxes Surqical gloves= 4 rolls Surgical tape for dressout -2 inch Facility Preparation 1 set Floor coverings (see hospital specific booklet) .-20 ft mi n. ypeav ut aper (min. 3'foot wide)2 rolls 2 inch duct tape__ 11-- roll Radiation Warning symbol tape (2" inch)2 ea. Step off pads 5 ea. Radiological barrier posting signs 1T LspoI Radiological barrier rope or ribbonl 5 ea. Traffic cones 1 iea. Large rad waste plastic bags (trash can size)10 ea. Medium rad waste plastic bags 2 copies Hospital specific booklet (1 at desk, 1 in Last Update: TVA cabinet) esK_ _ _1 roll Radioactive material label tape Decontamination Supplies 1 assy. Decontamination table, backboard and bottles (min. total capacity of 10 gallons)1Flexible funnel with drain hose_ ea. Decontamination media /soap product_ 1 ea. NCRP #65 Reference HandbooK 10 ea. Cotton swabs 270 ea. Zip lock bags for sample collection 10 ea. Labels for sample bags 2 pair Scissors _1 ea. Wall poster with decontamination steps Health Physics Supplies (Serial # and cal due)1 eaBicron ISM or-5or50 S/N I Cal._ 1 ea. Bicron Surveyor 50 S/N Cal.1_ Iea. Bicron Surveyor 50 S/N Cal.1F__ ea. Wound probe with cable 10 ~ea. TLDs 10 ea. Electronic dosimeters 100 ea. Smears 12 ea. Radioactive Material tags_1 I assy. Masslin mop and 20 cloths Inspection Performed By EP Manager Review Page 15 of 41 Date Date Revision 19 I WBN I EMERGENCY EQUIPMENT AND SUPPLIES I EPIP-12 l Appendix G QUARTERLY TECHNICAL SUPPORT CENTER (TSC)SUPPLIES EMERGENCY (Page 1 of 2)QUANTITY DESCRIPTION DOCUMENTS PLANT DRAWINGS (verify existence only, DCRM Controls Listing)1 ASME Steam tables 2 Meteorological Data Display Programs User's Manual 1 Meteorological Data Print Program User's Manual 1 WBN Environmental Data Station Manual 3 Emergency Paging System User's Manual (1 in MCR)3 NP REP (Radiological Emergency Plan)2 REND (Radiological Emergency Notification Directory) 2 CECC EPIPs 4 WBN EPIPs 1 set Position Activity Books (latest Procedure Rev.)1 set SOls (System Operating Instructions) 3 copies Unit 1 Technical Specifications 1 copy Function Restoration Instructions 2 copies Emergency Instructions 1 copy Emergency Contingency Actions 1 Safety and Health Manual 10 WBN Phone Directories (latest edition)10 TVA Phone Directories (latest edition)1 WBN FSAR (Updated)1 State of Tennessee Multijurisdictional REP Response Plan I WBN ODCM 2 sets AOls (Abnormal Operating Instructions) 1 set Tis (Technical Instructions)(Index/EPP Selected)I set GOls (General Operating Instructions)

I set Master Fuse List, Vol. 1 & 2 1 set System Description Manual 3 ICS System User's Guide 1 set Annunciator Response Instructions I WOG, ERG Maintenance Direct Work Item DW-97-002 Response (Emergency Response Guidelines, Background Information).

Page 16 of 41 YES NO REMARKS Revision 19 I WBN I EMERGENCY EQUIPMENT AND SUPPLIES I EPIP-12 I Appendix G QUARTERLY TECHNICAL SUPPORT CENTER (TSC) EMERGENCY SUPPLIES (Paae 2 of 2)I ..QUANTITY DESCRIPTION 2 books RCIs (Radiological Control Instructions) 1 ECIs Environmental Control Instructions (EPP Selected)1 Chemistry Manual (EPP Selected)1 Periodic Instructions (EPP Selected)7 SAMGs 3 SAMG Set Point and Comp Aid Basis 1 Chattanooga Phone Directory (current edition)1 Knoxville Phone Directory (current edition)YES NO REMARKS Communications Equipment

& Calculators 3 Communications Head Sets 1 Telephone (Cordless) (ac power)6 TI-55 Calculators (or equivalent) 1 Spectralink Phone System I Video Recorder 10 Emergency TLDs (RECORD Expiration Date)1 Satellite Phone and Accessories Supplies 2 rolls 1 Assorted Dryboard Supplies Assorted Desk Top Supplies Assorted Office Supplies Keys to TSC in Main Control Room Thermal Paper Cellular Telephone (available for facility/EP use)Inspection Performed By EP Manager Review Date Date Page 17 of 41 Revision 19 I WBN I EMERGENCY EQUIPMENT AND SUPPLIES I EPIP-12 l Appendix H QUARTERLY OPERATIONS SUPPORT CENTER (OSC) EMERGENCY SUPPLIES (Page 1 of 2)RESPONSIBILITY

-EP QUANTITY DESCRIPTION YES NO REMARKS DOCUMENTS PLANT DRAWINGS (verify existence only, DCRM Controls Listing)1 set Position Activity Books (latest revision)1 set WBN EPIPs 10 WBN Telephone Book (latest edition)5 TVA Telephone Book (latest edition)1 Nuclear Power Safety and Health Manual (NPSHM)1 set Vendor Manual Cross References I set Maintenance Instructions (Mls) (selected, see EPP)1 set Emergency Contingency Actions (ECAs)1 set Abnormal Operating Instructions (AOIs)1 set System Operating Instructions (SOls)1 set Emergency Instructions (Els)1 set Functional Restorations Instructions (FRs)2 ICS System User's Guide 1 Master Fuse List Vol. 1 & 2 1 BP-364, Control of Portable Two-way Radios 1 CHEM 13.0 & 13.15 1 set SAMGs Communications Equipment 3 Auto dial telephones 1 Fax machine 2 ICS Terminals 3 Computer Terminals 1 Computer Printer 4 Portable Phones 1 HIS-20 Terminal 1 Cellular Telephone (available for facility/EP use)Page 18 of 41 Revision 19 I WBN I EMERGENCY EQUIPMENT AND SUPPLIES I EPIP-12 l Appendix H QUARTERLY OPERATIONS SUPPORT CENTER EMERGENCY (Page 2 of 2)SUPPLIES-QUANTITY DESCRIPTION SUPPLIES Keys to OSC in Main Control Room 2 Easels Assorted desktop supplies for all positions 6 Status Boards Assorted Dryboard Supplies Assorted Office Supplies 1 Book of Current OSC Briefing/Debriefing Forms 5 Calculators EQUIPMENT OSC (Tool Kits) Tool Room Boilermakers Limitorque Mechanical/Machinist Instrument Electrical Steam Fitters Safety equipment Medical Supply Cabinet First Aid Kit 2,000 tablets of KI(Expires

/ I )KI Issuance Instructions Inserts OSC Staging Area(s)Tables and chairs Rex Terminal Anti C clothing/supplies Speaker System Overnight Cots & Sleeping Bags Inspection Performed By EP Manager Review YES NO REMARKS Date Date Page 19 of 41 Revision 19 WBN EMERGENCY EQUIPMENT AND SUPPLIES I EPIP-12 l Appendix I MONTHLY COMMUNICATIONS/EQUIPMENT TEST (Page 1 of 8)1.0 PRECAUTIONS

& LIMITATIONS A. This Appendix involves contact with NRC's Incident Response Center through the Emergency Notification System (red phone). The SM should be notified prior to testing the red phone to inform him that it is in use and to ensure proper response if NRC calls back for acknowledgment.

B. This Appendix may be performed during any Operational Mode.C. Test steps can be ran out of sequence on this Appendix.2.0 PREREQUISITE ACTIONS[1] OBTAIN permission from the SM prior to testing NRC, ENS phone, communications diesel, and Information Services (I S) diesel.[2] ARRANGE (as needed) for an individual to assist in communication test between facilities.

3.0 PERFORMANCE 3.1 TSC EMERGENCY NOTIFICATION SYSTEM (ENS) -RED PHONE NOTE 1 The TSC ENS has two connections in the TSC #337-1422.

NOTE 2 Report failures of ENS to the SM immediately.

If the ENS is out of order from the TSC and the MCR, call the NRC Operations Center immediately on the commercial telephone.

NRC commercial numbers are (301) 816-5100 and (301) 951-0550.NRC/Site telecommunications will make arrangements to have the failed system returned to normal operation.

[1] WHEN notifying the NRC, IDENTIFY yourself and PROVIDE the plant name and location.EXPLAIN that this is a test of the ENS and ASK the Operations Officer to call you back (REFER to Note 1). RETURN handset to phone.ENS SAT UNSAT REMARKS Page 20 of 41 Revision 19 WBN EMERGENCY EQUIPMENT AND SUPPLIES I EPIP-12 l Appendix I MONTHLY COMMUNICATIONS/EQUIPMENT TEST (Page 2 of 8)3.2 NRC HEALTH PHYSICS NETWORK (HPN)NOTE 1 The HPN is a labeled single line telephone in the TSC, NRC Conference Room, and at the RADCON Response position, #337-1423.

NOTE 2 IF there is failure of the HPN, THEN REPORT the failure to site Telecommunications who will coordinate repairs for the service. REPORT to NRC Operations Center via the ENS or commercial telephone that the HPN is inoperable.

REPORT to NRC by the HPN line when the telephone is returned to service. The commercial telephone numbers for NRC are (301) 816-5100 or (301) 951-0550.[1] TEST the HPN phones by calling any local commercial number and requesting a call back.HPN SAT UNSAT REMARKS 3.3 The NRC (PMCL), (MCL), (RSCL) and (LAN)These are single line telephones located in the TSC and are labeled.[1] TEST these lines by phoning any local commercial number and requesting a call back.PMCL#365-1425 SAT UNSAT REMARKS MCL#365-1426 SAT UNSAT REMARKS LAN#365-1427 SAT UNSAT REMARKS RSCL#365-1424 SAT UNSAT REMARKS Failures should be reported to Telecommunications.

Page 21 of 41 Revision 19 WBN EMERGENCY EQUIPMENT AND SUPPLIES I EPIP-12 Appendix I MONTHLY COMMUNICATIONS/EQUIPMENT TEST (Page 3 of 8)3.4 SATELLITE PHONE (TSC, OSC, MCR)[1] TEST portable phone per SOI 100.01 (stored in TSC).[2] NOTIFY telecommunications to test the permanent satellite phone circuit.[3] CALL long distance number(s) to verify operability.

[4] REPORT any problems to EP.SATELLITE PHONE SAT UNSAT REMARKS 3.5 MCR ENS TELEPHONE (RED PHONE)NOTE I IF the CR Operator has called NRC over the ENS on the day of the test, THEN CONSIDER the test complete and DO NOT PROCEED with the following steps.NOTE 2 REPORT failures of ENS to the SM immediately.

If the ENS is out of order, call the NRC Operations Center immediately on the commercial telephone.

NRC commercial numbers are (301) 816-5100 or (301) 951-0550.

NRC/Site Telecommunications will make arrangements to have the failed system returned to normal operation.

MCRENS SAT UNSAT REMARKS Page 22 of 41 Revision 19 I WBN I EMERGENCY EQUIPMENT AND SUPPLIES I EPIP-12 l Appendix I MONTHLY COMMUNICATIONS/EQUIPMENT TEST (Page 4 of 8)3.6 TEST DIESEL GENERATOR/BATTERY POWER SUPPLY FOR THE NODE 2 TELECOMMUNICATIONS BUILDING[1] NOTIFY the Telephone Services Specialist in the NODE Building (x7900) to initiate the diesel/battery test, OR PERFORM the following:

A. NOTIFY the SM and ODS that the diesel generator is being started to provide backup power to the NODE building.

/ _ /SM Time ODS Time B. CHECK the fuel and oil level.C. CHECK the area around the diesel unit for leaks or other problem indications.

D. NOTIFY the Shift Manager (SM) if problems are found.E. CHECK the power cable for a secure connection to the NODE Building outlet.F. CHECK the generator start cable for a secure connection at the Cutler-Hammer Genswitch G. RECORD hour meter reading and time. /Reading Time H. START the diesel by moving the switch on the Cutler-Hammer Genswitch to the test position.I. WATCH the frequency meter to settle on 60 hz and WAIT for the Genswitch to automatically switch to the diesel power (5 to 10 minutes).J. MONITOR the oil pressure and temperature gauge on the diesel.K. MONITOR the temperature in the building to ensure the air handlers are working.L. MONITOR the Rectifiers to ensure the batteries are not discharging.

Page 23 of 41 Revision 19 WBN EMERGENCY EQUIPMENT AND SUPPLIES EPIP-12 l Appendix I MONTHLY COMMUNICATIONS/EQUIPMENT TEST (Page 5 of 8)3.6 TEST DIESEL GENERATOR/BATTERY POWER SUPPLY FOR THE NODE 2 TELECOMMUNICATIONS BUILDING (cont.)STEPS TO RETURN THE NODE BUILDING TO COMMERICAL AC: A. OPERATE the Cutler-Hammer Genswitch to the auto position.B. WAIT for the Genswitch to automatically switch to the Commercial AC power (10 to 15 minutes).C. RECORD the hour meter reading and time. /Reading Time D. ENSURE that the air handlers in the NODE Building are working properly.E. NOTIFY the SM, ODS, and WBN EP Manager that normal ac has been restarted to the NODE Building.

I / /SM Time ODS Time EP Time F. ENSURE satellite phone tested. Tested by: G. RECORD last diesel service date. Service Date: Remarks: H. RECORD last UPS batteries service date. Service Date: Remarks: I. RECORD last air handler service date. Service Date: Remarks: Performed by Telephone Services Specialist Date: OR Performed by EP Date: EP Manager Review Date REMARKS: Page 24 of 41 Revision 19 WBN EMERGENCY EQUIPMENT AND SUPPLIES EPIP-12 I Appendix I MONTHLY COMMUNICATIONS/EQUIPMENT TEST (Page 6 of 8)3.7 TEST DIESEL GENERATOR POWER SUPPLY FOR THE COMPUTER ROOM (MDB) and UPS BACKUP for the PRODUCTION SERVER IN THE TRAINING CENTER (TC).[1] NOTIFY the Computer Services Manager/Specialist (x3811 1 3814) in the NODE Building to initiate the diesel backup to the computer room and UPS server test, OR PERFORM the following:

A. NOTIFY the SM that the diesel generator is being started to provide backup power to the main computer room.B. CHECK the fuel and oil levels and the block heater.C. CHECK the area around the diesel unit for leaks or other problem indications.

D. NOTIFY TVA Heavy Equipment or site maintenance if problems are found.E. CHECK the power cable for a secure connection to the MDB Building outlet.F. RECORD hour meter reading and time. /Reading Time G. START the diesel by holding down the auto/test switch on the transfer switch box to the test position for approximately 15 seconds.H. WATCH the frequency meter to settle on 60 hz. (1 to 5 minutes).I. MONITOR the oil pressure and temperature gauge on the diesel.J. MONITOR the temperature in the computer room to ensure the air handlers are working.Page 25 of 41 Revision 19 I WBN I EMERGENCY EQUIPMENT AND SUPPLIES I EPIP-12 I Appendix I MONTHLY COMMUNICATIONS/EQUIPMENT TEST (Page 7 of 8)3.7 TEST DIESEL GENERATOR POWER SUPPLY FOR THE COMPUTER ROOM (MDB)and UPS BACKUP for the PRODUCTION SERVER IN THE TRAINING CENTER (TC)(cont.).STEPS TO RETURN THE MAIN COMPUTER ROOM TO COMMERICAL AC: A. Record the hour meter reading and time. I/Reading Time B. CHECK thermostat to ensure it is secured.C. ENSURE air handlers in the Computer Room are working properly.D. NOTIFY the SM, and WBN EP Manager that normal ac has been restarted to the Computer Room.E. RECORD last diesel service date. Service Date: STEPS TO CHECK THE UPS FOR THE BACKUP PRODUCTION SERVER IN THE NODE 2 BUILDING A. RECORD the UPS BATTERY power supply time limit displayed on the front of the UPS equipment.

IF the unit has less then 10 minutes of available battery life notify facilities

/maintenance for assistance.

Current Reading:_B. UNPLUG/SWITCH the UPS from AC power and monitor the units ability for approx. 5 minutes to ensure it is working properly.C. PLUG/SWITCH UPS back up to AC Power and monitor the unit is working properly and charging.D. RECORD last UPS service date. Service Date: Performed by Computer Services Manager/Specialist Date: OR Performed by EP Date: EP Manager Review Date REMARKS: Page 26 of 41 Revision 19 WBN EMERGENCY EQUIPMENT AND SUPPLIES l EPIP-12 l Appendix I MONTHLY COMMUNICATIONS/EQUIPMENT TEST (Page 8 of 8)3.8 EP EMERGENCY FACILITY AND PORTABLE RADIO TESTS NOTE There should be 10 radios and 2 chargers ready at all times.[1] VERIFY that all portable radios are fully charged, in the process of being charged or being conditioned.

[2] MONITOR reception on channels "Fl" and "F2".[3] TEST reception between selected units.[4] TEST charging units to make certain they are capable of charging radio batteries.

Red light will appear until they are charged, then turn to green.[5] BLINKING red or yellow lights indicate a potential problem with the radio battery and should be reported to radio support personnel and replaced as necessary.

[6] USE conditioning unit as needed to recondition batteries.

Portable Radios SAT UNSAT REMARKS REMARKS.Inspection Performed By EP Manager Review Date Date Page 27 of 41 Revision 19 I WBN I EMERGENCY EQUIPMENT AND SUPPLIES I EPIP-12 l Appendix J QUARTERLY COMMUNICATIONS/EQUIPMENT TEST (Page 1 of 14)1.0 PRECAUTIONS

& LIMITATIONS A. This Appendix involves testing of emergency facility communications and data equipment.

The SM should be notified prior to testing.B. This Appendix may be performed during any Operational Mode.C. Test steps may be performed out of sequence on this Appendix.D. Other precautions are noted within the Appendix.2.0 PREREQUISITE ACTIONS[1] OBTAIN permission from the SM prior to testing.[2] ARRANGE (as needed) for an individual to assist in communication test between facilities.

3.0 PERFORMANCE 3.1 TSC TELEPHONE TESTS[1] VERIFY Key Phones for TSC are functional by calling each number listed in the REND and checking on a copy of the REND page.TSC PHONES SAT UNSAT REMARKS 3.2 TSC FAX MACHINES[1] SEND and RECEIVE faxes using each machine.[2] IDENTIFY the received copies and ATTACH them to data package.[3] CHECK for sufficient supplies of fax/copy paper TSC supply cabinet/copy machine.3865 SAT UNSAT REMARKS 3866 SAT UNSAT REMARKS Page 28 of 41 Revision 19 WBN EMERGENCY EQUIPMENT AND SUPPLIES I EPIP-12 Appendix J QUARTERLY COMMUNICATIONS/EQUIPMENT TEST (Page 2 of 14)3.3 TSC COPIER[1 ] RUN a copy of Attachment 1 to check for proper operation.

TSC COPIER SAT UNSAT REMARKS[2] IDENTIFY and ATTACH copy to data package.[3] CHECK for sufficient supplies of copy paper and toner in copier cabinet.COPIER SAT _ UNSAT REMARKS 3.4 TSC/DRILL ICS TERMINALS[1] PRINT sample ICS data group or screen.[2] IDENTIFY the printout and ATTACH it to data package.TSC ICS Terminals (3) SAT UNSAT REMARKS Page 29 of 41 Revision 19 I WBN I EMERGENCY EQUIPMENT AND SUPPLIES I EPIP-12 l Appendix J QUARTERLY COMMUNICATIONSIEQUIPMENT TEST (Page 3 of 14)3.5 TSC CLASSIFICATION CLOCK[1] VERIFY the time is correct on each clock.[2] VERIFY that a battery UPS is installed at the clock and clock display continues after clock is unplugged from AC power.[3] IF needed, THEN CALL Naval Observatory for correct time.(202-762-1401).

TSC Clock SAT UNSAT REMARKS 3.6 TSC CECC TERMINAL AND PRINTER[1] PRINT met data from CECC terminal.[2] ATTACH met data printout to Data Sheet for documentation.

TSC CECC Terminal and Printer SAT UNSAT REMARKS 3.7 TSC PA SYSTEM[1] CONTACT Assistant in the OSC and request that he monitor the OSC PA speakers for audibility.

[2] TEST system for operation.

[3] CONFIRM OSC operability with assistant.

TSC PA System SAT UNSAT REMARKS Page 30 of 41 Revision 19 WBN I EMERGENCY EQUIPMENT AND SUPPLIES I EPIP-12 I Appendix J QUARTERLY COMMUNICATIONS/EQUIPMENT TEST (Page 4 of 14)3.8 TSC -CECC DIRECTOR RINGDOWN PHONE[1] ARRANGE for coverage on the CECC phone from the Corporate EP group (9-751-8580).

[2] VERIFY CECC Director Ringdown phone operation.

CECC Director Ringdown SAT UNSAT REMARKS 3.9 OSC TELEPHONE TEST[1] VERIFY Key Phones for OSC are functional by calling each number listed in the REND and checking on a copy of the REND page.oSC phones SAT _ UNSAT REMARKS 3.10 Portable Phones[1] VERIFY that the phones are charged and functional.

Portable phones SAT UNSAT REMARKS 3.11 OSC FAX MACHINE[1] SEND and RECEIVE a fax using OSC fax machine.[2] IDENTIFY the received copy and ATTACH it to data package.[3] CHECK for sufficient supplies of fax/copy paper OSC supply cabinet/copy machine.8006 SAT UNSAT REMARKS Page 31 of 41 Revision 19 WBN EMERGENCY EQUIPMENT AND SUPPLIES EPIP-12 Appendix J QUARTERLY COMMUNICATIONS/EQUIPMENT TEST (Page 5 of 14)3.12 OSC/RADCON LAB COPIERIOSC CLASSIFICATION CLOCK[1] VERIFY the copier is available for EP use.[2] VERIFY the time is correct on the clock.[3] VERIFY that a battery UPS is installed to the clock and display continues when clock is unplugged from AC power.[4] IF needed, THEN CALL Naval Observatory for correct time.(202-762-1401).

OSC Clock SAT UNSAT REMARKS 3.13 OSC ICS TERMINALS[1] PRINT sample ICS data group or screen.[2] IDENTIFY the printout and ATTACH it to data package.OSC ICS Terminals (2) SAT UNSAT REMARKS Page 32 of 41 Revision 19 WBN EMERGENCY EQUIPMENT AND SUPPLIES EPIP-12 Appendix J QUARTERLY COMMUNICATIONSIEQUIPMENT TEST (Page 6 of 14)3.14 OSC PA SYSTEM[1] CONTACT Assistant in the OSC Staging Area and request that he monitor the OSC Staging Area PA speakers for audibility.

[2] TEST system for operation.

[3] CONFIRM OSC Staging Area operability with assistant.

OSC PA System SAT UNSAT REMARKS 3.15 MCR (MAIN CONTROL ROOM) FAX MACHINE[1] SEND and RECEIVE a fax using MCR fax machine.[2] IDENTIFY the received copy and ATTACH it to data package.[3] CHECK for sufficient supplies of fax/copy paper MCR supply cabinet/copy machine.8463 SAT UNSAT REMARKS 3.16 MCR -ODS RINGDOWN PHONE[1] VERIFY ODS Ringdown phone operation.

CR ODS Ringdown SAT UNSAT REMARKS Page 33 of 41 Revision 19 WBN EMERGENCY EQUIPMENT AND SUPPLIES EPIP-12 Appendix J QUARTERLY COMMUNICATIONS/EQUIPMENT TEST (Page 7 of 14)3.17 EMERGENCY PAGING SYSTEM (EPS)NOTE I The EPS is located adjacent to the SM's station. The operability of the EPS is monitored by Information Systems network control. When not in use, the EPS may be tested by ensuring that the border around the screen blinks intermittently (about every 10 seconds).

If the border does not blink or the screen is completely black, it may be assumed that the data link is down.NOTE 2 The EPS is activated and monitored from a dedicated touch screen CRT in the MCR.The 'TOUCH" command means leaving the finger on the screen until it is acknowledged.

[1] TOUCH the screen within the rectangular border. The following screen will appear: PAGER TEST DRILL EMERGENCY STAGING AREA ABORT[2] TOUCH "Abort"[3] IF the EPS CRT screen displays a series of numbers and will not function when touched, UNPLUG the CRT electrical supply. After 30 seconds, RESTORE electrical power to the CRT. If the screen border appears, the CRT is functional.

If the border does not appear and flashes every 20 seconds, EPS is inoperable.

EPS SAT UNSAT REMARKS Page 34 of 41 Revision 19 WBN EMERGENCY EQUIPMENT AND SUPPLIES I EPIP-12 l Appendix J QUARTERLY COMMUNICATIONS/EQUIPMENT TEST (Page 8 of 14)3.18 STATION EMERGENCY ALARM TEST (Accountability and Fire)[1] OBTAIN permission from the SM to test the alarms.[2] This test should be performed the first Wednesday of every quarter with any deficiencies reported to Work Control.3.18.1 PURPOSE To provide a method for periodic operability testing of the site fire, assembly and accountability, alarms.3.18.2 RESPONSIBILITY This test should be conducted after 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br /> the first Wednesday of each quarter.The Shift Manager (SM) or the Unit Supervisor (US) should approve the performance of the test.3.18.3 INSTRUCTIONS NOTEI If plant operations would be adversely impacted by the test, then it should be delayed.NOTE 2 If the test cannot be performed on the first Wednesday, then it should be performed at an appropriate time which least disrupts station operations.

NOTE3 Operation of the Codes, Alarms and Paging System is in accordance with SOI-100.01, "Communications Systems."[1] ANNOUNCE to the plant, "Attention all site personnel, attention all site personnel, the following is a test of the site Fire and Assembly and Accountability emergency alarms." (REPEAT)[2] ACTUATE the fire alarm for approximately five seconds, then terminate the alarm.Page 35 of 41 Revision 19 I WBN I EMERGENCY EQUIPMENT AND SUPPLIES I EPIP-12 l Appendix J QUARTERLY COMMUNICATIONS/EQUIPMENT TEST (Page 9 of 14)NOTE Full three minute testing of this alarm should be performed quarterly, and is recommended during periods of minimal station activity interruption..

[3] ACTUATE the (manual) Assembly and Accountability alarm.[4] ANNOUNCE to the plant, "Attention all site personnel, attention all site personnel, the proceeding was a test of the site's emergency alarms." (REPEAT).If you know of any area having difficulty hearing this test, please report it to Emergency Planning at extensions 3232 or 8004. (REPEAT)[5] Log test "complete" date here. REPORT any difficulties to Work Control.[6] List deficiencies reported to Work Control: Page 36 of 41 Revision 19 I WBN I EMERGENCY EQUIPMENT AND SUPPLIES I EPIP-12 l Appendix J QUARTERLY COMMUNICATIONS/EQUIPMENT TEST (Page 10 of 14)3.19 MCR COMMUNICATOR PORTABLE UNIT(S), AND CIRCUIT NOTE Portable unit(s) may be stored in TSC.[1] OBTAIN permission from US to test.[2] CONTACT assistant and COMMUNICATE with him on the "4101" and "4102" bridges.[3] CHECK for audibility and sound quality at different locations in the Ul horseshoe.

[4] SIGN OFF and REPLACE unit in charging cradle.Portable phones SAT UNSAT REMARKS Page 37 of 41 Revision 19 WBN I EMERGENCY EQUIPMENT AND SUPPLIES I EPIP-12 l Appendix J QUARTERLY COMMUNICATIONSIEQUIPMENT TEST (Page 11 of 14)3.20 LRC CECC TERMINAL AND PRINTER[1] PRINT met data from CECC terminal.[2] ATTACH met data printout to Data Sheet for documentation.

LRC Computer SAT UNSAT REMARKS 3.21 LRC TELEPHONE LINES TEST telephone lines 365-3717, 3719, 3726, and 3683 by dialing any outside commercial telephone number.LRC Phones SAT UNSAT REMARKS 3.22 LNC TELEPHONE LINE AND FAX MACHINE.TEST telephone lines by dialing any outside commercial telephone number.LNC Fax Machine[1] SEND and RECEIVE a fax using LNC fax machine.[2] IDENTIFY the received copy and ATTACH it to data package.[3] CHECK for sufficient supplies of fax/copy paper LNC supply cabinet/copy machine.LNCFAX SAT UNSAT REMARKS Page 38 of 41 Revision 19 I WBN I EMERGENCY EQUIPMENT AND SUPPLIES I EPIP-12 Appendix J QUARTERLY COMMUNICATIONS/EQUIPMENT TEST (Page 12 of 14)3.23 SIMULATOR

-ODS RINGDOWN PHONES[1] LIFT the handsets, press XXX then AUTODIAL the ODS and WAIT for the ODS in Chattanooga to answer.[2] IDENTIFY yourself and GIVE the plant name and location.[3] EXPLAIN that this is a test; ASK the ODS to call you back[4] THANK the answering party for the assistance; and HANG UP.[5] CHECK auto dial to the simulator instructor booth.Simulator ODS Ringdowns SAT UNSAT REMARKS 3.24 SIMULATOR FAX MACHINE[1] SEND and RECEIVE a fax using Simulator fax machine.[2] IDENTIFY the received copy and ATTACH it to data package.[3] CHECK for sufficient supplies of fax/copy paper Simulator supply cabinet/copy machine.8363 SAT UNSAT REMARKS Page 39 of 41 Revision 19 I WBN I EMERGENCY EQUIPMENT AND SUPPLIES I EPIP-12 l Appendix J QUARTERLY COMMUNICATIONS/EQUIPMENT TEST (Page 13 of 14)3.25 SIMULATOR CONTROL ROOM COMMUNICATOR PORTABLE UNIT, AND CIRCUIT[1] OBTAIN headset/phone from holding unit and put it on.[2] CONTACT assistant and COMMUNICATE with him in the "4101" and "4102" bridges.[3] CHECK for audibility and sound quality at different locations in the Simulator horseshoe.

[4] SIGN OFF and REPLACE phone in holding unit.Simulator CR Comm Circuit SAT UNSAT REMARKS Inspection Performed By Date EP Manager Review Date Page 40 of 41 Revision 19 I WBN I EMERGENCY EQUIPMENT AND SUPPLIES I EPIP-12 l Appendix J QUARTERLY COMMUNICATIONS/EQUIPMENT TEST (Page 14 of 14)ATTACHMENT 1 COPIER AND FACSIMILE MACHINE TEST VERIFICATION This is a test from the Watts Bar Technical Support Center, Operations Support Center, Control Room, or Simulator.

When transmissions are complete, identify the received copies and attach them to the appropriate data sheet.COPIER LOCATION TSC ORIGINATING FACSIMILE MACHINE (Transmitted From)TSC Incoming 8365 TSC Outgoing 8366 OSC 8006 Control Room 8463 WBN Simulator 8363 Inspector Date Page 41 of 41 Revision 19 TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT EMERGENGY PLAN IMPLEMENTING PROCEDURE EPIP-14 RADIOLOGICAL CONTROL RESPONSE Revision 16 Unit 0 PREPARED BY: James F. Hagy SPONSORING ORGANIZATION:

Emergency Planning APPROVED BY: Frank L. Pavlechko Effective Date: 04/23/2003 LEVEL OF USE: REFERENCE NON-QUALITY RELATED WBN RADIOLOGICAL CONTROL RESPONSE EPIP-14 REVISION LOG Revision l Effective l Pages Description of Revision Number Date Affected 13 6/14/00 All Non Intent change. Clarified number of Radcon personnel to be called in, in addition to onshift staff. Included use of RWP 911 and 912 to cover entry teams in drills and emergencies.

Added a step in the Alert actions to notify SQN, Radcon to dispatch their monitoring van (as needed) to support WBN. Added the OSC to the emergency paging printout locations for easier access by the Radcon SS. Replaced KI bottle information to reflect new packaging.

Revised medical center title for Rhea Hospital.

Revised reference of ANSI qualified "Techs" to"personnel" to clarify acceptable staffing.

This revision resolves problems identified in WBN PER006394.

14 01/24/01 All Plan effectiveness determination reviews indicated the following revisions do not reduce level of effectiveness of the procedure or REP: Pg. Clarified use of RWP 911 & 912 to match wording in RCDP-3 Section 5,8,12,15 3.6.7 ,19,21 Typographical addition () made to elevation 713'.Deleted reference to RE-90-280

& RE-290-293 per direction of DCN 50482-A & SA WBP LEE-00-052.

Non-intent change.15 09/25/01 All Intent change. Procedure revised to Non-Quality related per requirements of NQAP & pending revision to SPP-2.2. The Pg. 6, 17 coversheet and records section of the procedure was revised to reflect this change.Non-intent change. Corrected Appendix C typo. RCI-120 Attachments 1 & 2 revised to Appendix A & B.16 04/23/2003 All Plan effectiveness determinations on these changes indicate the following revisions do not reduce the level of effectiveness of the procedure or REP.Non-intent changes. Deleted source notes, reformatted for intersite consistency.

Updated references and records sections.

Corrected RWP numbers. Clarified Appendix B information.

Relocated l_ information to new Appendix H.PAGE 2 OF 26 REVISION 16 I WBN IRADIOLOGICAL CONTROL RESPONSE EPIP-1 4 Table of Contents 1.0 PURPOSE .......................................................

4

2.0 REFERENCES

.......................................................

4 3.0 INSTRUCTIONS

.......................................................

5 3.1 General Instructions

.......................................................

5 3.2 Precautions and Limitations

.......................................................

6 3.3 Response Classification Guidelines

.......................................................

8 3.4 Duties of RADCON Personnel Assigned to the TSC ...............................................

11 3.5 Duties of RADCON Personnel Assigned to the RADCON Lab ................................

12 3.6 Issuance of Potassium Iodide (KI) ......................................................

13 3.7 Radioiodine Sample Acquisition

......................................................

14 3.8 Personnel Decontamination and Facilities

......................................................

16 4.0 RECORD RETENTION

......................................................

17 4.1 Records of Classified Emergencies

......................................................

17 4.2 Drill and Exercise Records ......................................................

17 APPENDIX A RADCON Shift Supervisor Checklist

......................................................

18 APPENDIX B Alternate RADCON LAB/OSC Location ......................................................

19 A APPENDIX C Radiological Conditions Tracking ......................................................

20 APPENDIX D Occupational Dose from Inhalation of lodine-1 31 ..............................................

22 APPENDIX E Potassium Iodide (KI) Administration Instructions

..............................................

23 APPENDIX F Potassium Iodide (KI) Issue Report ......................................................

24 APPENDIX G RADCON Emergency Staffing Functions/Times

................................................

25 APPENDIX H Emergency Respirator Issue Guidelines

......................................................

26 PAGE 3 OF 26 REVISION 16 I WBN I RADIOLOGICAL CONTROL RESPONSE I EPIP-14 1.0 PURPOSE This Procedure describes the actions and responsibilities of the Watts Bar Radiological Control (RADCON) Section in the event of a radiological emergency.

2.0 REFERENCES

2.1 Interfacing Documents 1. CECC-EPIP-9, "Emergency Radiological Monitoring Procedures" 2. EPIP-6, "Activation and Operation of the Technical Support Center (TSC)" 3. EPIP-7, "Activation and Operation of the Operations Support Center (OSC)" 4. EPIP-8, " Personnel Accountability and Evacuation" 5. EPIP-10, "Medical Emergency Response" 6. EPIP-1 1 "Security and Access Control" 7. EPIP-12, "Emergency Equipment and Supplies" 8. EPIP-13, " Initial Dose Assessment for Radiological Emergencies" 9. EPIP-15, "Emergency Exposure Guidelines" 10. EPIP-16, 'Termination of the Emergency and Recovery" 11. NRC Information Notice 90-08, Kr-85 Hazards from Decayed Fuel 2.2 Developmental Documents 1. CFR 50.72 Immediate Notification Requirements for Operating Nuclear Power Reactors 2. NUREG 0654, FEMA-REP-1, Rev. 1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants 3. RCI-101, Radiation Contamination, and Airborne Surveys 4. RCI-120, Respirator Minimization Process 5. RCI-130, Personnel Decontamination

6. ANSI N18.7-1976
7. CFR 20 Standards for Protection Against Radiation 8. EPA 400-R-92-001, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents 9. ICS System User's Guide PAGE 4 OF 26 REVISION 16 I WBN I RADIOLOGICAL CONTROL RESPONSE I EPIP-141 y> 3.0 INSTRUCTIONS 3.1 General Instructions 3.1.1 The response to radiological emergencies by RADCON personnel will depend upon the type and magnitude of the existing emergency condition.

This can range from a minimal response requiring one or two people to a total manpower mobilization.

In addition, it should be noted radiological problems may not be associated with a given emergency

[as defined in the Radiological Emergency Plan (REP)]. Natural phenomena, security threats, or other events not involving radiological problems could be the cause for the emergency status.3.1.2 IF an ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY is classified, RADCON is required to assemble a specific number of personnel as described below.A. During normal and off-shifts, an ALERT will be announced over the public address system and the emergency pagers will be activated. (In the event of a SITE AREA EMERGENCY or GENERAL EMERGENCY, the offsite sirens will be activated by the state.)B. The RADCON Lab will be contacted by the SM/SED, or designee.

The Radiological Control Shift Supervisor (RCSS) will determine the number of RADCON personnel currently onsite and will ensure at least a total of seven (7) additional are available onsite within approximately 60 minutes.PAGE 5 OF 26 REVISION 16 I WBN I RADIOLOGICAL CONTROL RESPONSE EPIP-14 3.0 INSTRUCTIONS (continued) 3.2 Precautions and Limitations During a radiological emergency, established radiological control procedures will normally be utilized to cover most situations.

Since the magnitude of the problem(s) may be more severe, it is imperative that all requirements for entry into affected plant areas be met. This section summarizes items that will need to be addressed prior to entry into the affected areas and during recovery operations.

3.2.1 Plant accidents involving core damage may produce excessive dose rates and airborne activity concentrations within plant areas.Radiological precautions must be followed under these conditions until available data indicates otherwise.

3.2.2 These precautions could include the following:

  • The use of respiratory equipment.
  • Issuance of KI.* Multiple layers of protective clothing.* The use of electronic dosimeters, multiple TLDs and extremity TLDs as appropriate.
  • The use of RWP (911) for drills and (3911) for actual emergencies should be utilized to cover the entry team(s).* Personnel will be instructed to monitor their dosimetry frequently to prevent overexposure.

3.2.3 IF core damage is suspected or if for any other reason elevated airborne activity concentrations are present, then appropriate respiratory protection will be required.

Initial entry will probably require the use of respiratory equipment, since iodines may be present in significant quantities.

CAUTION IF spent fuel damage is involved, be aware of the potential for significant skin doses from Kr-85. After spent fuel has decayed greater than 190 days, Kr-85 is the predominant gaseous nuclide.Consequently, the dose to the skin could be approximately 150 times the whole body dose.PAGE 6OF 26 REVISION 16 I WBN I RADIOLOGICAL CONTROL RESPONSE I EPIP-14 4 3.0 INSTRUCTIONS (continued) 3.2.4 The respiratory guidelines in Appendix H will be considered during emergency incidents.

3.2.5 Special precautions must be taken when obtaining samples. Smears may have significant dose rates (in the REM/hr range). High airborne activity could result in significant activity concentrations being collected onto the filter media. FOLLOW standard RADCON procedures, should samples be considered radiological hazards.3.2.6 ENSURE all electronic dosimeters are properly processed for each worker. MAKE arrangements to have TLDs read, as soon as possible.IF possible, RESTRICT repetitive entries of workers. SUBSTITUTE other qualified personnel for team members, on reentry's, to distribute exposures.

Employee's remaining allowable dose shall be verified by RADCON prior to entry into plant areas.3.2.7 IF plant conditions are such that radiological conditions are changing rapidly, it may not be possible to use previous data in order to determine protective requirements.

This factor must be considered prior to allowing survey teams into affected plant areas.3.2.8 The "Buddy System" shall be utilized for initial entries into any area where radiological conditions are not known or any area where radiological conditions could be changing due to plant conditions.

At least one person of the buddy system must be qualified in radiological controls procedures.

Monitoring teams should maintain communication capabilities with the RADCON Lab.3.2.9 Habitability surveys of OSC, TSC, and assembly areas shall be performed as necessary.

3.2.10 Advanced Radiation Worker (ARW) trained REP responders will respond (upon request) to the Radiological Control Shift Supervisor during a radiological emergency and provide support and surveillance as needed during the initial phase.PAGE 7 OF 26 REVISION 16 WBN RADIOLOGICAL CONTROL RESPONSE EPIP-1 4 3.0 INSTRUCTIONS (continued) 3.3 Response Classification Guidelines 3.3.1 NOTIFICATION OF UNUSUAL EVENT A. No offsite radiological problems are postulated during a NOTIFICATION OF UNUSUAL EVENT.B. These events require a certain notification to be made to offsite agencies.

These events will not have any major impact on RADCON.C. RADCON will follow standard practices and procedures during response work.3.3.2 ALERT A. A limited radiological release is possible during an ALERT situation.

Onsite emergency teams will be activated and offsite agencies contacted.

B. IF the assembly alarm is activated, RADCON personnel shall secure work in a safe manner and report to the 713' RADCON Lab for assembly and accountability.

C. RADCON Techs. will be dispatched to survey assembly and accountability areas as necessary.

D. It should be noted that an ALERT situation may require the evacuation of a certain plant area and/or building.

RADCON shall ensure these areas are properly posted and arrangements are made with Nuclear Site Security to restrict all unauthorized access to the affected area(s).E. RADCON personnel will assist in the development of all recovery plans as necessary.

Recommendations will be made to keep exposures As Low As Reasonably Achievable (ALARA) and to approve recovery activities.

F. An offsite survey team may be dispatched from SQN, if coverage is necessary.

Site RCSS will contact SQN Radcon Lab as soon as possible for assistance (Refer to CECC EPIP-9).PAGE 8 OF 26 REVISION 16 WBN RADIOLOGICAL CONTROL RESPONSE I EPIP 4 3.0 INSTRUCTIONS (continued) 3.3.3 SITE AREA EMERGENCY A. During a SITE AREA EMERGENCY, there may be releases to the environment requiring RADCON response.B. A SITE AREA EMERGENCY may require the evacuation of a plant building or buildings.

C. Personnel will be notified to assemble for accountability.

RADCON shall secure work in a safe manner and proceed to the 713' RADCON Lab for assembly and accountability.

D. An accountability will be made in accordance with EPIP-8. Information shall be gathered describing the emergency situation; RADCON representatives shall be sent to the assembly areas to determine if any workers were in the affected plant areas at the time of the event. These people shall be separated from other plant workers and personnel contamination surveys initiated for affected personnel.

E. As reports become available regarding the details of the emergency, RADCON personnel shall prepare all necessary equipment needed and ready a survey team(s) for entry into the affected area(s).F. Upon notification from the Technical Support Center (TSC), survey team(s) may be dispatched from the OSC to various areas of the plant.It should be noted that depending on the type of accident, initial survey(s) may not be performed until hours or days after an event. In this case, procedures may be developed describing the reentry steps to be followed.G. A site boundary survey may be required.

The details of the survey shall be coordinated with the TSC. The emergency van should be utilized while performing these surveys.H. An offsite survey team may be dispatched from SQN, if coverage is necessary.

Site RCSS will contact the SQN RADCON Lab as soon as possible for assistance. (REFER TO CECC EPIP-9.)I. Precautions may be required to prevent personnel overexposures.

These exposures could result directly from radiation emitted from the plume and/or due to submersion in the plume. [REFER TO Section 3.6, Issuance of Potassium Iodide (Kl)]PAGE 9 OF 26 REVISION 16 WBN RADIOLOGICAL CONTROL RESPONSE EPIP-1 4 3.0 INSTRUCTIONS (continued) 3.3.3 SITE AREA EMERGENCY (continued)

J. RECORD all survey results. All findings shall be reported to the TSC or Central Emergency Control Center (CECC) (if activated).

If results indicate offsite contamination, the survey areas may need to be extended.

OBTAIN further instructions and PERFORM required surveillance(s).

K. Additional manpower support and equipment may be obtained from other TVA nuclear facilities.

3.3.4 GENERAL EMERGENCY A. During a GENERAL EMERGENCY, there may be radiation releases to the environment requiring RADCON response.

These releases may require the implementation of evacuation procedures.

B. An extensive RADCON response will be required during a GENERAL EMERGENCY.

C. The actions described under SITE AREA EMERGENCY will be applicable to a GENERAL EMERGENCY condition as well.D. During a GENERAL EMERGENCY, conditions in the RADCON Lab may be such that evacuation is warranted.

If this situation develops, REFER TO Appendix B.E. All subsequent offsite activities will be coordinated with offsite support agency survey teams to make the best use of available manpower.REPORT all survey results as soon as possible to the TSC or CECC (if activated) so recommendations to the proper agencies can be made to initiate any required protective actions.PAGE 10 OF 26 REVISION 16 WBN RADIOLOGICAL CONTROL RESPONSE EPIP-14 3.0 INSTRUCTIONS (continued) 3.4 Duties of RADCON Personnel Assigned to the TSC 3.4.1 The TSC is activated during an ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY, and may be activated during a NOTIFICATION OF UNUSUAL EVENT.3.4.2 The RADCON Manager is the designated RADCON TSC Manager.Approved alternates rotate this Emergency Responder Organization (ERO) duty. Additional, suitably trained and qualified personnel are listed on the ERO call list. It should be noted that the duty RCSS may serve as the TSC representative during the initial stages of an emergency until relieved by a duly qualified individual 3.4.3 The responsibilities and duties of the TSC RADCON Manager are summarized in EPIP-6.PAGE 11 OF 26 REVISION 16 I WBN I RADIOLOGICAL CONTROL RESPONSE I EPIP-1 4 3.0 INSTRUCTIONS (continued) 3.5 Duties of RADCON Personnel Assigned to the RADCON Lab.3.5.1 The RADCON Shift Supervisor (RCSS) or qualified designee is responsible for managing the activities of the 713' Lab. Appendix A of this procedure can be used as a guide by the RCSS during REP activities.

3.5.2 Survey teams are dispatched from the OSC staging areas. The RCSS is responsible for ensuring survey teams are properly equipped and protected and are aware of any special precautions, plant conditions, or requirements, (e.g., RWP).3.5.3 The RCSS will ensure all entries are properly coordinated and approved by the OSC.3.5.4 The RCSS is responsible for ensuring adequate numbers of RADCON personnel are available to support emergency activities.

When an Alert or higher emergency has been classified, ensure seven (7) additional RADCON personnel have responded to the emergency page (printout in OSC/TSC).

For a summary of minimal assignments during emergency see Appendix G of this Procedure.

3.5.5 The RCSS is responsible for preparing and designating an onsite RADCON monitoring team. Team members will prepare the monitoring van in accordance with CECC-EPIP-9.

For immediate offsite monitoring, the RCSS should request assistance from SQN.3.5.6 The RCSS will dispatch survey teams to assembly areas, the OSC, and TSC to evaluate radiological conditions and monitor radiation levels as conditions dictate. These survey teams will be responsible for monitoring contamination levels (both on personnel and floor/equipment areas) and implementing corrective actions (e.g., decontamination or zoning) as necessary.

3.5.7 The RCSS will monitor the 713' Lab for habitability and will coordinate evacuation activities to the alternate lab location (Appendix B) if warranted.

3.5.8 The RCSS may use ICS or Appendix C to track radiological conditions in the plant.PAGE 12 OF 26 REVISION 16 WBN RADIOLOGICAL CONTROL RESPONSE I EPIP- 4 3.0 INSTRUCTIONS (continued) 3.6 Issuance of Potassium Iodide (KI)3.6.1 IF the TSC RADCON Manager or designee has reason to believe a person's projected cumulative dose to the thyroid from inhalation of radioactive iodine might exceed 10 rem, the exposed person should be started immediately on a dose regimen of potassium iodide (KI). Anyone authorized to administer KI shall be familiar with the Food and Drug Administration's approved package insert and be sure each proposed recipient is similarly informed.

KI recipients will acknowledge their understanding of the consequences of taking or refusing KI by signing-in on Appendix F, Potassium Iodide (KI) Issue Report. The initial dose of KI should not be delayed and those who begin therapy should continue the 1 0-day course of KI unless their thyroid dose is determined not to have exceeded 10 rem. An adequate supply of KI for the site is stored at the OSC staging area. FOLLOW dosage schedules as outlined on the package insert.3.6.2 Projected cumulative doses to the thyroid from inhalation of radioactive iodine can be determined using Appendix D, "Occupational Dose from Inhalation of Iodine-131." 3.6.3 KI is stored in the Emergency Medical Supply cabinet (OSC staging area). KI has an approved shelf-life with the expiration date listed on each tablet package. Expiration date verification and necessary replacement are performed in EPIP-12.3.6.4 A copy of the Food and Drug Administration approved package insert shall accompany the issuance of K1. Dosage schedules and other pertinent information are outlined on the package insert and should be followed closely (Appendix E).3.6.5 The issuing agent shall complete Appendix F, Potassium Iodide (KI)Issue Report, when KI is issued. A copy of this report will be routed to the TSC RADCON Manager in a timely manner.PAGE 13 OF 26 REVISION 16 I WBN I RADIOLOGICAL CONTROL RESPONSE I EPIP-14 3.0 INSTRUCTIONS (continued) 3.7 Radioiodine Sample Acquisition CAUTION 1 RCI-101 should be referenced for hazards associated with Silver Zeolite cartridge use.CAUTION 2 Sample cartridges may exhibit high dose rates after sampling during accident conditions.

Exercise good ALARA practices when handling, storing, and disposing of these cartridges.

3.7.1 During accident conditions, noble gas concentrations may be present in significant quantities.

The collection of these noble gases on charcoal cartridges during iodine sampling will interfere with subsequent iodine analysis.

Silver zeolite (AgZ) cartridges are provided for use during periods of high noble gas concentrations.

3.7.2 Radioiodine samples should be collected at 30 liters per minute (LPM)for daily or weekly samples. Grab samples may be collected at 30 or 60 LPM based upon the type of air sampler used and the conditions in the sample location.3.7.3 Radioiodine sample volumes of less than 900 liters may be performed if it is known or suspected that dose rates on the AgZ cartridges will exceed 10 mrem/hr. During these instances, sample duration's may be reduced to 5 minutes. Sample duration's less than 5 minutes may be used for ALARA purposes but shall be pre-approved by the RCSS.3.7.4 Upon completion of sampling activities, the air sample should be returned to the RADCON Lab for analysis as soon as possible.

A radiation survey of the sample head shall be performed to determine the contact dose rate. The results of this survey shall determine any special handling or packaging requirements during analysis.PAGE 14 OF 26 REVISION 16 I WBN I RADIOLOGICAL CONTROL RESPONSE I EPIP-1 4 3.0 INSTRUCTIONS (continued) 3.7 Radioiodine Sample Acquisition (continued) 3.7.5 IF the iodine sample activity is 1 mrem/hr., a contact dose rate should be taken by using a Ludlum 14-C or equivalent GM survey instrument with the beta window CLOSED. The radioiodine air activity can be approximated by using the following formula:[Average of the Front and Back Contact laCi/ml = Dose Rate (mrem/hr)

X 5.1 E-3]Volume (liters)3.7.6 Radioiodine cartridges with contact gamma dose rates greater than or equal to 100 mrem/hr shall not be delivered to the Chemistry Lab without prior approval of the Chemistry Count Room Supervisor and the RCSS.3.7.7 RADCON personnel shall inform Chemistry personnel of the contact dose rates of the samples. RADCON personnel should provide radiological coverage during handling, analysis and disposal if samples read greater than 100 mrem/hr. The RCSS will approve disposal methods and location for all samples reading greater than 100 mrem/hr.3.7.8 Gamma analysis results shall be reported to the RCSS as soon as possible.3.7.9 Accident related radioiodine samples should be documented and analyzed in accordance with RCI-101 or CECC-EPIP-9 as appropriate.

PAGE 15 OF 26 REVISION 16 I WBN I RADIOLOGICAL CONTROL RESPONSE I EPIP 4 3.0 INSTRUCTIONS (continued) 3.8 Personnel Decontamination and Facilities 3.8.1 RCI-130 describes the procedures to be used for personnel decontamination.

3.8.2 Contaminated personnel are normally decontaminated at the 713'elevation decon facility.

This facility is equipped with a wash sink, shower, and all necessary supplies.

These supplies normally include various decontamination agents and soaps, towels, clean clothing, and other miscellaneous supplies.3.8.3 Concerning radiation injuries, grossly contaminated personnel with injuries are normally treated at the 713' elevation prior to transfer to an offsite medical facility unless the injury requires immediate transportation (REFER TO EPIP-10).3.8.4 Contaminated personnel requiring offsite medical attention are treated at either of the agreement hospitals (Rhea County Medical Center [Dayton]or Athens Regional Medical Center [Athens]).

The hospital(s) have a complete staff and have been trained in the handling and care of contaminated patients.

Watts Bar maintains a supply cabinet at each hospitals' Emergency Room which contains posting materials and various other supplies.

Refer to EPIP-10 for guidance on transporting contaminated and radiation injuries to REACTs in Oak Ridge or Erlanger Medical Center in Chattanooga.

PAGE 16 OF 26 REVISION 16 I WBN I RADIOLOGICAL CONTROL RESPONSE I EPIP-14 4.0 RECORD RETENTION 4.1 Records of Classified Emergencies The materials generated in support of key actions during an actual emergency are considered Lifetime retention Non-QA records. Materials shall be forwarded to the EP Manager who shall submit any records deemed necessary to demonstrate performance to the Corporate EP Manager for storage.4.2 Drill and Exercise Records The materials deemed necessary to demonstrate performance of key actions during drills are considered Non-QA records. These records shall be forwarded to the EP Manager who shall retain records deemed necessary to demonstrate six-year plan performance for six years. The EP Manager shall retain other records in this category for three years.PAGE 17 OF 26 REVISION 16 I WBN I RADIOLOGICAL CONTROL RESPONSE I EPIP-14 APPENDIX A RADCON SHIFT SUPERVISOR CHECKLIST Page 1 of 1 IF The RCSS has been notified of a REP activation, the following checklist may be used as a guide to complete actions.1. INITIATE immediate requested actions by the Main Control Room (MCR). O 2. IF activation is ALERT or higher, ensure seven (7) additional ANSI Qualified O RADCON personnel have responded to the emergency page. (Printout in OSC/TSC).Follow FFD directions for call-in of unscheduled work per EPIP-7. O 3. CONTACT SQN to dispatch Offsite survey team per CECC-EPIP-9.

O 4. IF time allows, prepare the Radiological Sampling Van to be dispatched O per CECC-EPIP-9.

5. INITIATE CECC-EPIP-9, as requested by the SM, TSC or CECC. O 6. IF the following 2 conditions are met, go to the TSC and perform TSC O RADCON Manager's functions until relieved. (Ref. EPIP-6)O RCSS functions can be performed from the TSC.E TSC RADCON Manager is not in the TSC.7. IF Assembly Alarm has been activated, dispatch RADCON personnel to O assembly areas (as needed) per EPIP-8 to survey assembly areas.8. DISPATCH RADCON personnel for search and rescue teams into the plant l (as needed) per EPIP-8.9. ENSURE radiological habitability in the MCR, TSC and OSC throughout E the REP activation.
10. DIRECT radiological field monitoring teams until relieved by TSC E RADCON Manager.11. IF evacuation of the RADCON Lab is required, REFER TO Appendix B E of this procedure.

PAGE 18 OF 26 REVISION 16 I WBN I RADIOLOGICAL CONTROL RESPONSE EPIP-1 4 APPENDIX B ALTERNATE RADCON LAB/OSC LOCATION Page 1 of 1 The location of the Alternate RADCON Lab/OSC will depend on inplant radiological conditions.

The TSC RADCON Manager, after consultation with the SED, will make the decision on location transfer.

Possible locations that will be considered are:* Alternate OSC in the Main Office Building Team Room* Relay Room 755' level next to the Control Room and the TSC* Staging Area, WBN Training Center, Classroom 19 (LNC).Essential equipment will be moved to the alternate RADCON Lab if conditions warrant the evacuation of the 713' Lab. REFER TO EPIP-12 Appendix D, for suggested equipment.

PAGE 19 OF 26 REVISION 16 WBN RADIOLOGICAL CONTROL RESPONSE EPIP-14 APPENDIX C RADIOLOGICAL CONDITIONS TRACKING Page 1 of 2 RADCON personnel should first utilize the Integrated Computer System (ICS) to assist them in tracking in-plant radiological conditions.

Key radiation monitoring information can be found in the following TSC Mimics or ICS system group:* 4RM1 In-plant radiation monitors* 4RM2 In-plant radiation monitors* EFF1 Radiation monitors associated with the plant's release paths* Group -System Group Menu -SYS-90-RAD MON Questions on the ICS can be referenced in the ICS User's Manual which are located in the TSC/OSC.Should the ICS not be available, then the worksheets of this appendix can be utilized (as needed) to track in-plant radiological conditions.

SELECTED KEY IN-PLANT RADIATION MONITORS UPDATED READINGS, CPM, mR/Hr., or RIHr.DESCRIPTION IDENTIFIER BACKGROUND Date Date Date Date O-M-12 READING Time Time Time Time Spent Fuel Pit Area (El. 757) 1&2-RE-90-1 Upper Containment RB (El. 757) 1-RE-90-2 Spent Fuel Pool Skimmer Filter Area O-RE-90-5 Monitor (El. 737)CCW Heat Exchangers (El 737) 1 &2-RE-90-6 Hot Sample Room (El. 713) 1&2-RE-90-7 AFW Pump Area (El 713) 1&2-RE-90-8 Waste Condensate Tanks (El 692) O-RE-90-9 CVCS Board Area (El. 692) 1&2-RE-90-10 CS & RHR Pump Area ( El. 676) O-RE-90-11 RB Low Compt Inst Rm (El 736) 1-RE-90-61 PAGE 20 OF 26 REVISION 16 I WBN I RADIOLOGICAL CONTROL RESPONSE I EPIP-14 APPENDIX C RADIOLOGICAL CONDITIONS TRACKING Page 2 of 2 SELECTED KEY IN-PLANT RADIATION MONITORS UPDATED READINGS, CPM, mRIHr., or R/Hr DESCRIPTION IDENTIFIER BACKGROUND Date Date Date Date READING Time Time Time Time Inside RB-Upper Containment 1-RE-90-112 (Located in AB, El 737)Inside RB-Lower Containment 1-RE-90-106 (Located in AB, El 737)Condensate Demin (TB, El. 685) 0-RE-90-230 0-RE-90-231 (Space for additional monitors)PAGE 21 OF26 REVISION 16 I WBN I RADIOLOGICAL CONTROL RESPONSE I EPIP-14 APPENDIX D Occupational Dose from Inhalation of lodine-131 Page 1 of 1 Occupational Thyroid Dose from Inhalation of 1-131 1 .OOE-03 I .OOE-04 0 a, 0 S...U C 0-1.OOE-06 1 .OOE-07.__________________

6.__________

I 0 50 rem e 25 rein 10 rem 6 3 rem-B- rem I ------.-.--

4----.--------

4 ----t-1.OOE-09 l 0.1_______________________________________I 1 1 10 Exposure Time (hours)100 PAGE 22 OF 26 REVISION 16 (C((7-Oa z-U C)m 0 a)IOSAT Y Tablets jOSATr Tablets tPnltnuelutt Ididm T.blats, U.l P.)(Pronounced pous-TASS-re-urn EYE-ohdyed) tAhbrouleted KRI TAKE POTASSIUM IODIDE ONLY WHEN PUBIUC HEALTl OFFICIALS TELL YOU IN A RADIATION EMERGENCY RADIOACTIVE IODINE COULD BE EILZEASED INTOTHE Al n-POTASSIUM IODIDE (A FORM OF IODINE) CAtt HELP PROTECT YOU.IF YOU ARE TOLOTO TAKE THIS MED1,CINE, TAKE IT ONE TIME EVERY 24 HOURS DO NlOT TAKE IT MORE OFTEN MORE WILL NOT HELP YOU AND MAY It tNREASE THF RISK OF SIDE FFEFCTS Do NOT TAKE TllS DRUG IF YOU KNOW YOU ARE ALLERGIC TO IODIDE (SEE SIDE EFFECTS BELOW)lis between 1 l sed SrC (S9 to S7T) Keep pascke dry cad fil paKlels Inadc.WARININ POTASSIUM IODIDE SHOULD NOT BE USEoD iY PEOPLE ALLERGIC TO lODIDE Keep out ol the reach et clndn hr case at ovrerdose or a terrto roacin, confect a phyalcan or pub-lo hecIlh autaxlly DESCRIPTION Eah IOSATI' Thhlim coamelica 13C nig of polraeium Wodde, NOW PsoTASSIUM IODIDE WORKS Causm loran- of lodlno hatf ypour lhyrotd gbld work rit Mostoa paora e9 thre Indinr they need lromr foot Ike lditted aotn or nthac ti try-rold crm 'nore rar hold anlr a erdtaln aronueat at Iodine In a radiation eonergency rwdlvaote lad'ms may br retlsted In trhe 8r.Tho mrrntcal may be breatd or Iwalbowdt .ay erier trhe thyrard gland end darnme It Tire deia. -rouI probably ntM show tIal? for years. Ctltdren eora morn Ikr to heve Vr-old daronage It you lake petsaturn todide. It ! AIS up yoer VlWrold glerd Tr'redac.t thcasnom that harulrn rruadiaorvaunew

-antm rte Itcyrld gland WO SHOULD NOTTAKE POTASSIUM IODIDE Tre only people One should lnt 1lak- p alum adid- ear area.pil who krenw they ala to lodide.Nou may take, poluskss Iodide evrn 1 you re takIng meclcks tar a thyrord problem (tir exaParp. a lthyrold hormone or enwrllytuld drug) Prergant and nuref wrrmean arnd babes avid chilrrean may bleo take IN. drug-HOW AND WHJI TO TAKC POTASSIUM lOOIS Pottlaeaum bdkb sheuld be tAkrafs as ssn as posstio after pul>tc health fabfcl tat you Ve aluild take oan doss every 24 hcours. Moro nd rvn holp you bootout thre thyrnold can Ihrk only tinted amounts di indira tsgr dres a1t Incaase Ire rIsk of*Ide effects You Il probaUy hs tid not to telce the drug Our mare Sin 10 dey SlD! EFFECTS Usabyf saide steds et potagsshm Itdka happen when people take hliher donzeset a long ems. 'ru should tie caretulr not to talk more than the recanmended dose or take 4 lot anger tren you am told SkElel eafts era tunhtry beaauee al ike Irm does and the short SanW yor trI be takkg the drug Poo1leb aIds rsatme hIclude akin rache.. wttilng oat the -r.rwy araisn.t and inodosm (rrlotb lotre-. burinfg mouth end throat.ears loath end gurm. symptoms ot a heed cold. a*nd *rsnelrs stomnach upset end diarrhea)A law people her en aangla -re acn mIt morae aitrja syivp-toms Thesa caMd be liac endont paeor aWottg nd paras Oa the lnav or body and at ns aver ashortness o breath rerpir Ing kWnidler-medIcal atleniron Tbkhwj bic. rapy rarely crr o " nvlvr the arlynki grend.Undretyety oat the tyri ar, or rsmtegrnnt ot tiule tltroid gral (gahor)WHATTO 00 IF SIDE EFFECTS OCCUR I the site eltet ate aeseta art you have .dangle reaccon, stop takinrrg Possium ta1ks Then, n posiblo. cot a doctor oa pubic health autle fry Itrnstrnctons NoW S4IPPtIED IOSATThblats (I'ewta-lum Indite Tabvota. U S P) pacr"stel 14 tabels (NtCS1803-OS-O1 013 Eedr whhe. raundw scored tibl aontatns 130 mav poeblium loa.Ctilrlbuied by ANSOx, IttC.t5W 7511 St H. N vitk. N Y 1002-U 0-m Co C 5 m o Z-I 5 Z Co A-z 0 Z Co a 0 r-0-C)5 g r 0 z-I 0 r-m Co m INDICATIONS THYROID BLOCKING IN A RADIATION EMEFIOENCY ONLY DIRECTIONS FOR USE tne only as nllracted by Slake or tonal pita- health aulIrihas In the ewnt of a readallo onrgrnno DOSE ADULTS AND CIIILDREN ONE YEAR OF AnCE Otl Or EI One (1) tablet ore a day Cruth tar sraIl cliltrrn, BABIES UNnD ONEYEAn OF AGE Ohe4welf (ltsabeta OnesC a day Crsh frst DOA50. ThknIcar t dey ultese directed oelsrerrtr by Elate or loal pt.l trei acthorlhia Sore at controlled roar lainaet .m C', z-a a, INDICATIONS:

THYROID BLOCKING IN A RADIATION EMERGENCY ONLY.m-Q I-ah UA I WBN I RADIOLOGICAL CONTROL RESPONSE IEPIP1 4 APPENDIX F POTASSIUM IODIDE (KI) ISSUE REPORT Page 1 of 1 ISSUED TO SOCIAL KNOWN ALLERGY PACKAGE TIME OF DATE OF SIGNATURE SECURITY TO IODINE? (If INSERT INITIAL KI INITIAL KI ISSUED BY NUMBER yes, do not issue) PROVIDED DOSE DOSE t + i..i 4 I 1 4 I I i i 4- i; I I i i 4- 1 I 1¶ t 4 4- 4-I 4 4 4 .1-I 4 4 I I 4 .4 41 1. I tI .4 4 t 4 v 4 4 I-+ 4 i I I+ i I I-t p I I I-t + 4 1 i I AUTHORIZED BY: TITLE'Route to Emergency Preparedness Manager.PAGE 24 OF 26 REVISION 16 WBN RADIOLOGICAL CONTROL RESPONSE EPIP-14 APPENDIX G RADCON EMERGENCY STAFFING FUNCTIONS/TIMES Page 1 of 1 Maior Task On Shift 30 minutes 60 minutes A. In-Plant Surveys 1 1 1 B. Radiation Protection:*

2** 2** 2 1. Access Control 2. HP Coverage for Repair Corrective Action, Search and Rescue, First Aid and Fire fighting 3. Personnel Monitoring

4. Dosimetry C. Onsite (Out-of-Plant) 1 1 D. Offsite Surveys 2* 20 E Senior Health Physics 1 Expertise*May be provided by Shift personnel assigned other functions.
    • May be provided by task specific trained personnel.
      • Driver may be other than a RADCON Tech if enough RADCON Techs. are not available.
    • RCSS will report to TSC if able to manage the RADCON Lab from there.(D Coverage can be provided by the SQN RADCON Monitoring Van.PAGE 25 OF 26 REVISION 16 WBN RADIOLOGICAL CONTROL RESPONSE EPIP-1 4 APPENDIX H EMERGENCY RESPIRATOR ISSUE GUIDELINES Page 1 of 1 NOTE: THESE GUIDELINES ARE RECOMMENDATIONS ONLY, SUBJECT TO THE JUDGEMENT OF RADCON AND EMERGENCY MANAGEMENT PERSONNEL.

THESE GUIDELINES ARE APPLICABLE ONLY TO PROTECTION FROM AIRBORNE RADIOACTIVE MATERIAL AND DO NOT APPLY TO RESPIRATORS/SCBAs ISSUED FOR PROTECTION FROM INDUSTRIAL OR CHEMICAL HAZARDS OR ATMOSPHERES IMMEDIATELY HAZARDOUS TO LIFE OR HEALTH.TASKS TO SAVE A LIFE OR Respirator/SCBA not required to enter airborne PREVENT SIGNIFICANT radioactivity areas provided resulting internal dose DAMAGE TO PLANT plus external dose will not result in TEDE exceeding NRC dose limits or, if approved by the SED, doses up to the TVA emergency dose limits (i.e., up to 25 rem/10 rem) (this can include uptakes > 1 ALI)HIGH PRIORITY TASKS

  • Respirator/SCBA not required to enter airborne (priority 1 or 2) areas if the the following are true: NOTE: IF INDIVIDUAL'S TOTAL
  • Individual's internal dose plus external dose will INTAKE FOR THE YEAR not result in TEDE exceeding NRC annual dose TO DATE EXCEEDS 200 limit; and DAC-HRS., DOSE
  • Delays or hindrances caused by issuing or wearing RESULTING FROM ALL respirators/SCBAs will jeopardize the success or INTAKES FOR THE YEAR timeliness of the task; or ASSESSED IN
  • Use of a respirator/SCBA will result in a higher DETERMINING THE TEDE. TEDE to the responding individuals.

LOW or MID PRIORITY TASKS Use RCI-120 for respirator issue guidance.NOTE: Protective requirements may be revised at the discretion of the TSC RADCON Manager as sample data becomes available.

PAGE 26 OF 26 REVISION 16 TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT EMERGENGY PLAN IMPLEMENTING PROCEDURE EPIP-1 5 EMERGENCY EXPOSURE GUIDELINES Revision 1 1 Unit 0 PREPARED BY: James F. Hagy SPONSORING ORGANIZATION:

Emergency Planning APPROVED BY: Frank L. Pavlechko Effective Date: 04/23/2003 LEVEL OF USE: REFERENCE NON-QUALITY RELATED WBN EMERGENCY EXPOSURE GUIDELINES EPIP-1 5 REVISION LOG Revision Effective Pages Description of Revision Number Date Affected I 8 2/15/97 5, 6, 8, 9, Editorial (non-intent) revisions made. Format 13, 14, 15 enhancement made to section 4.1.Title of section 4.2 revised to reflect the actions identified in the instruction.

PAG information added to Appendix A.Authorization form in Appendix B re-titled to match procedure description.

Appendix C revised to update procedural references on respirator use so that they corresponded with guidance provided in RCI-120.9 6/14/00 All Non Intent change. Revised App. C to reflect 10 CFR 20 Respirator Protection Factors. Typographic errors corrected.

Reference added. This revision resolves problem identified in WBN PER, 00-006394-000.

10 9/25/01 All, 7, 8, Intent change. Procedure revised to Non-Quality 14 related per requirements of NQAP & pending revision to SPP-2.2. The coversheet and records section of the procedure was revised to reflect this change.Non-lntent change. Corrected Appendix C typo. RCI-120 Attachments 1 & 2 revised to Appendix A & B.l_ _ _Added RCI-120 to references.

11 04/23/2003 All Plan effectiveness determinations on these changes indicate the following revisions do not reduce the level of effectiveness of the procedure or REP.Non-intent changes. Deleted source notes, reformatted for intersite consistency.

Updated references and records sections.

Relocated definitions to new Appendix D. Relocated form from App. B to lI App. B-1 PAGE 2 OF 16 REVISION 11 I WBN I EMERGENCY EXPOSURE GUIDELINES I EPIP-15 5 Table Of Contents 1.0 Purpose ..4 2.0 References

..4 2.1 Performance References

.4 2.2 Developmental References

..4 3.0 Instructions

..5 3.1 Exposure Limitations

.5 3.1.1 Actions For Life Saving Or Protection Of The Public ..5 3.1.2 Actions For Immediate Repair Or To Prevent The Failure Of Equipment

.6 3.1.3 Internal Exposure (Emergency Workers) ..6 3.1.4 Post-Exposure Evaluations

..7 3.1.5 Emergency Dose Extensions

..7 3.1.6 Additional Instructions

..7 4.0 Record Retention

..8 4.1 Records of Classified Emergencies

.8 4.2 Drill and Exercise Records ..8 APPENDIX A Watts Bar Emergency Exposure Reference

..9 APPENDIX B General Instructions For Emergency Exposures

..10 K APPENDIX B-1 Authorization To Exceed Occupational Dose Limits Form .. 13 APPENDIX C Emergency Respirator Issue Guidelines

..14 APPENDIX D Definitions

..16 PAGE 3 OF 16 REVISION 11 I WBN I EMERGENCY EXPOSURE GUIDELINES IEPIP1 5 1.0 PURPOSE This Procedure provides guidance for planning occupational exposures under emergency conditions consistent with EPA-400, "Manual of Protective Action Guides and Protective Actions for Nuclear Incidents." These limits apply only to emergency exposure authorizations and not to spontaneous reactions by individuals attempting to mitigate an emergency situation.

2.0 REFERENCES

2.1 Performance References

1. SPP-5.1, Radiological Controls 2. WBN EPIP-10, Medical Emergency Response 3. WBN-RCI-120 Respirator Minimization Process" 2.2 Developmental References
1. ICRP Publication 26, "Recommendation of the International Commission on Radiological Protection" 2. ICRP Publication 28, "The Principles and General Procedures for Handling Emergency and Accidental Exposures of Workers" 3. TVA NP Radiological Emergency Plan 4. EPA 400-R-92/001, and subsequent revisions, "Manual of Protective Action Guides and Protective Actions for Nuclear Incidents" 5. NUREG-0654/FEMA-REP-1, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" 6. Title 10, Code of Federal Regulations, Parts 20 and 50 7. ANSI Standard N.18.7-1976
8. ANSI Standard N.13.11 PAGE 4 OF 16 REVISION 11 I WBN I EMERGENCY EXPOSURE GUIDELINES I EPIP-1 56 3.0 INSTRUCTIONS NOTE: Specific definitions as used in this procedure are contained in Appendix D.A. The Site Emergency Director (SED) is the only individual responsible for authorizing Emergency dose limits in excess of TVA Administrative dose limits and 10 CFR 20.1201. Appendix A and B shall be used to provide written authorization.

NOTE: As defined by the emergency situation, this approval may be relayed verbally and documented later.B. The Radiological Control (RADCON) Group is responsible for completing Appendix B-1, "Authorization to Exceed Occupational Dose Limits," obtaining the Site Emergency Director's approval and will perform radiological surveys or other assessments to estimate the radiation doses.C. In all cases, the site RADCON Manager shall be informed of any emergency exposure immediately so that a determination of the total quarterly exposure can be made. Based on the results of the determination, the worker may be restricted from further dose.3.1 EXPOSURE LIMITATIONS 3.1.1 ACTIONS FOR LIFE SAVING OR PROTECTION OF THE PUBLIC A. For immediate activities up to 25 rad which are necessary to: (1) Save Human Life.For lifesaving operations situations may occur in which a dose in excess of 25 rad would be required.

It is not possible to prejudge the risk that one person should be allowed to take to save the life of another. However, persons undertaking an emergency mission in which the dose would exceed 25 rad to the whole body should do so only on a voluntary basis and with full awareness of the risks involved.(2) Restore equipment necessary to maintain critical safety functions or to establish and maintain a safe shutdown, (3) Prevent or Mitigate a release of radioactivity to the environment for which off-site protective measures may be required.

For these activities, the TEDE of personnel directly involved shall not exceed 25 rad. This limit is applicable only if actions establishing adequate or equivalent protection, with less dose, are not readily available.

PAGE 5 OF 16 REVISION 11 I WBN I EMERGENCY EXPOSURE GUIDELINES I EPIP-15 5 3.1.1 ACTIONS FOR LIFE SAVING OR PROTECTION OF THE PUBLIC (cont.)B. Limit for lens of eye is 75 rad, or three (3) times the TEDE value.C. Limit for any other organ (including skin and body extremities) is 250 rad, or ten (10)times the TEDE value.3.1.2 ACTIONS FOR IMMEDIATE REPAIR OR TO PREVENT THE FAILURE OF EQUIPMENT A. For activities performed on an immediate basis to prevent the failure of equipment necessary to protect the public health and safety, the TEDE of personnel directly involved shall not exceed 10 rem. This limit is applicable only if actions establishing adequate or equivalent protection, with a less dose consequence, are not readily available.

B. Limit for lens of eye of 30 rad, three (3) times the TEDE limit.C. Limit for any other organ (including skin and body extremities) of 100 rad, or ten (10)times the TEDE limit.j 3.1.3 INTERNAL EXPOSURE (EMERGENCY WORKERS)A. Guidelines for internal exposure controls of WBN emergency workers are provided in Appendix C.PAGE 6 OF 16 REVISION 11 I WBN I EMERGENCY EXPOSURE GUIDELINES I EPIP-1 5 3.1.4 POST-EXPOSURE EVALUATIONS A. Personnel receiving emergency or accident exposures should be restricted from further occupational exposure pending the outcome of exposure evaluations and, if necessary, medical surveillance.

B. An exposure evaluation shall be performed to determine the individual dose.RADCON shall conduct post exposure dose assessments for exposed individuals, with particular attention to determining the adequacy of administrative dosimeter correction factors for TEDE doses resulting from internal and external exposures.

This evaluation should be based on observed area dose rates, airborne activity measurements, and dosimetry results. The evaluation shall be documented in an appropriate format and filed with the individual's exposure records. Appropriate reports shall be submitted to RADCON and the US NRC.C. Any exposures above 5 rem TEDE shall be reported to a TVA physician or designee.

It is the responsibility of the physician to determine appropriate medical evaluations and required care. Cross reference guidance is in EPIP-10.3.1.5 EMERGENCY DOSE EXTENSIONS K> A. In REP emergency situations, planned doses to radiological workers can be extended beyond the TVA administrative limits to the 10 CFR 20 regulatory limits.3.1.6 ADDITIONAL INSTRUCTIONS A. Refer to Appendix A and B of this procedure.

PAGE 7 OF 16 REVISION 11 I WBN I EMERGENCY EXPOSURE GUIDELINES I EPIP-15 5 4.0 RECORD RETENTION 4.1 Records of Classified Emergencies The materials generated in support of key actions during an actual emergency involving Emergency Exposure are considered Lifetime retention Non-QA records. Materials shall be forwarded to the EP Manager who shall submit any records deemed necessary to demonstrate performance to the Corporate EP Manager for storage.4.2 Drill and Exercise Records The materials deemed necessary to demonstrate performance of key actions during drills are considered Non-QA records. These records shall be forwarded to the EP Manager who shall retain records deemed necessary to demonstrate six-year plan performance for six years. The EP Manager shall retain other records in this category for three years.PAGE 8 OF 16 REVISION 11 I WBN I EMERGENCY EXPOSURE GUIDELINES I EPIP-15 5 APPENDIX A WATTS BAR EMERGENCY EXPOSURE REFERENCE (Page 1 of 1)Emergency responders are volunteers who are qualified radiation4 workers at TVA and have not declared pregnancy.

I N awl YES '.Limit Exposure to:/ essary to 25 RAD TEDE ave ahuman life 75 RAD Lens of Eye or Stop radioactive release(s) 250 RAD Organ CDE comparable to EPA PAGs YES o r ..........Restore plant equipment necessary for Personnel shall be maintaining critical briefed on the risk\ Safety /of exposure in excess Functions of 25 RAD, should they choose this action.No Limit Exposure to: Exposure necessary 1 REM Ex e (i / to prevent failure of equipmen YES i necessary for protection of the 30 ;AD Lens of Eye\ ~~public /l3 A eso y 100 RAD Organ CDE No lLimit Exposure to: No F 5 REM TEDE 3 NOTES I (im If conditions are not known, I then answer NO.G2' EPA PAGs are 1 REM TEDE or 5 REM Thyroid CDE () Continue assessing and modify exposure actions are necessary 15 RAD Lens of Eye 50 RAD Organ CDE 3+UPON DETERMINATION OF EXPOSURE LIMIT -REFER TO INSTRUCTIONS PRIOR TO AUTHORIZING EXPOSRUE PAGE 9 OF 16 REVISION 11 WBN I EMERGENCY EXPOSURE GUIDELINES I EPIP-15 APPENDIX B GENERAL INSTRUCTIONS FOR EMERGENCY EXPOSURES (Page 1 of 3)A. These (emergency) limits are in excess of 10 CFR 20 limits. These limits apply only to planned exposures and not to spontaneous reactions by individuals attempting to mitigate the accident.B. Emergency exposure limits apply only to TVA personnel, who are qualified as radiation workers at the plant and have been issued dosimetry.

C. Personnel who have received previous accident or emergency exposure in excess of 25 rad TEDE shall not participate in further emergency exposure situations.

D. Personnel who have declared pregnancy in accordance with other site procedures, shall not participate in emergency exposure situations.

E. Receipt of emergency dose limits shall be on a voluntary basis. Other factors being equal, older volunteers should be selected first.F. Personnel receiving emergency exposures, in excess of 25 rad, shall be informed of the risks involved, including the numerical levels of dose at which acute effects of radiation will be incurred, and numerical estimates of the risk of delayed effects.EPA tables are provided following these general instructions for this purpose.G. Personnel shall not enter any area where dose rates are unknown or unmeasurable with instruments and dosimetry immediately available.

H. Internal exposure should be minimized by the use of respiratory protection equipment.

Respirator Issue Guidelines are given in Appendix C. Protective clothing should be used to minimize personal contamination.

I. The dose of personnel authorized to receive emergency exposures shall be monitored and recorded as provided for in the Site RADCON procedures.

J. The exposure of personnel during emergency operations shall be maintained as low as reasonably achievable (ALARA).PAGE 10 OF 16 REVISION 11 I WBN I EMERGENCY EXPOSURE GUIDELINES I EPIP-15 5 APPENDIX B GENERAL INSTRUCTIONS FOR EMERGENCY EXPOSURES (Page 2 of 3)K. The dose limits specified in this procedure are intended as upper limits for guidance during emergency situations, and planned doses for rescue and emergency repairs.Recovery operations shall not exceed these limits.L. If a projected dose to the thyroid is expected to exceed 10 rem during a radiological emergency, Potassium Iodide (KI) should be issued in accordance with WBN, EPIP-14 to on-site personnel as a protective measure. The SED shall be informed prior to issuance.M. The RADCON Group will prepare Appendix B-1, Authorization to Exceed Occupational Dose Limits, and obtain the Site Emergency Director's approval.N. Following the exposure, these individuals must be removed from areas where they can receive additional dose.NOTE 1: Until isotopic assessments of airborne radioactivity are available, an administrative correction factor of 2 should be used to estimate TEDE exposures in airborne activity areas: Estimated TEDE = dosimeter reading x 2 NOTE 2: The above value corresponds to the ratio of external (measured) dose to estimated TEDE dose, in accordance with default values in the TVA's Dose Assessment model. When accident specific nuclide assessments are available, more definitive dose assessments should be performed to adjust the correction factors.PAGE 11 OF 16 REVISION 11 I WBN I EMERGENCY EXPOSURE GUIDELINES I EPIP-1 5 APPENDIX B GENERAL INSTRUCTIONS FOR EMERGENCY EXPOSURES (Page 3 of 3)EPA EMERGENCY EXPOSURE RISK INFORMATION (for personnel briefing on emergency exposures of 25 rad TEDE)I. Approximate Cancer Risk to Average Individuals from 25 rad Effective Dose Fni ivniont DlnivPred Prnmntlv-Age at Exposure (years) Risk of Premature Death Average years of life (deaths per 1,000 lost if premature death persons exposed) occurs (years)20to30 9.1 24 30to40 7.2 19 40 to 50 5.3 15 50 to 60 3.5 11-.._ .X r _ _ ---_ .-:___L- A:-- A J-NOTE: Tables referenced from tne Environmental FrutectiouuI

/yecy b"Manual of Protective Action Guides and Protective Actions for Nuclear Incidents," (EPA-400), October 15, 1991, page 2-18.II. Health Effects Associated with Whole Body Absorbed Doses Received Within a Few Hours.Whole Body Early Fatalities 2 Whole Body Prodromal Effects 3 Absorbed Dose (percent)

Absorbed Dose (percent)(rad) (rad)140 5 50 2 200 15 100 15 300 50 150 50 400 85 200 85 460 95 250 98 Risks will be lower for protracted exposure periods.2 Supportive medical treatment may increase the dose at which these frequencies occur by approximately 50 percent.3 Forewarning symptoms of more serious health effects associated with large doses of radiation.

PAGE 12 OF 16 REVISION 11 WBN EMERGENCY EXPOSURE GUIDELINES I EPIP-15 5 APPENDIX B-1 AUTHORIZATION TO EXCEED OCCUPATIONAL DOSE LIMITS FORM (Page 1 of 1)The persons listed below are authorized to exceed the TVA dose limits for the whole body and extremities during the evaluation or mitigation of an emergency situation.

Emergency limits are in excess of 10 CFR 20.1201 limits.The persons listed below acknowledge they have volunteered for this assignment, and have been briefed on the emergency situation, and have been made aware of possible consequences of the estimated radiation dose(s).Hand carry or FAX to the TSC for SED Signature Hand carry or FAX to the OSC after SED signs.PAGE 13 OF 16 REVISION 11 WBN EMERGENCY EXPOSURE GUIDELINES EPIP-1 5 APPENDIX C EMERGENCY RESPIRATOR ISSUE GUIDELINES Page 1 of 2 NOTE: THESE GUIDELINES ARE RECOMMENDATIONS ONLY, SUBJECT TO THE JUDGEMENT OF RADCON AND EMERGENCY MANAGEMENT PERSONNEL.

THESE GUIDELINES ARE APPLICABLE ONLY TO PROTECTION FROM AIRBORNE RADIOACTIVE MATERIAL AND DO NOT APPLY TO RESPIRATORSISCBAs ISSUED FOR PROTECTION FROM INDUSTRIAL OR CHEMICAL HAZARDS OR ATMOSPHERES IMMEDIATELY HAZARDOUS TO LIFE OR HEALTH.TASKS TO SAVE A LIFE OR RespiratorlSCBA not required to enter airborne PREVENT SIGNIFICANT radioactivity areas provided resulting internal dose DAMAGE TO PLANT plus external dose will not result in TEDE exceeding NRC dose limits or, if approved by the SED, doses up to the TVA emergency dose limits (i.e., up to 25 rem/10 rem) (this can include uptakes > I ALI)HIGH PRIORITY TASKS

  • RespiratorlSCBA not required to enter airborne (priority I or 2) areas if the the following are true: NOTE: IF INDIVIDUAL'S TOTAL .Individual's internal dose plus external dose will INTAKE FOR THE YEAR not result in TEDE exceeding NRC annual dose TO DATE EXCEEDS 200 limit; and DAC-HRS., DOSE .Delays or hindrances caused by issuing or wearing RESULTING FROM ALL respirators/SCBAs will jeopardize the success or INTAKES FOR THE YEAR timeliness of the task; or ASSESSED IN .Use of a respirator/SCBA will result in a higher DETERMINING THE TEDE. TEDE to the responding individuals.

LOW or MID PRIORITY TASKS Use RCI-120 for respirator issue guidance.NOTE: Protective requirements may be revised at the discretion of the TSC RADCON Manager as sample data becomes available.

PAGE 14 OF 16 REVISION 11

((E RESPIRATOR EVALUATION CHIART (7 RE: RCI-120 OJ z Documented TEDE ALARA evaluation required above 40 DAC-Ilrsicntry ASSUMPTIONS:

1. Inefficiency factor = 1.25 2. Respirator P.F. > 100 3. Use of respirator eliminates internal dose component.

10,000 1,000-o G)m 0 In 100 V Ai- 1+F T-T-F H.USE SPHADM PRO'n:CT ou 7- FI-I L F-ATOR.PROTEC N III PMENT--H t M (0 (D 0-4, m m G)m z m cn 0 cn X Cn m I-z m C,-r m cn:D m z x m G)m x-u 0 C,)C G)C m 1-1 C,)10 1 01 I 10 100 1,000 10,000 100,000 DOSE RATE (mrem/hour)

NOTE: This chart should be used: I) Low to middle priority tasks.;x1 2) Conditions do not mandate formal evaluation (see page 2).M 3) IndustrialUEnvironmental hazards or conditions are not concerns.cn 0 m-u-U I I WBN I EMERGENCY EXPOSURE GUIDELINES EPIP- 5 APPENDIX D DEFINITIONS Page 1 of 1 Accident Exposure -Exposure to radiation or radioactive materials that results from an unexpected event. Accident exposure refers to the immediate consequences of the unexpected event and the immediate corrective/mitigative actions of personnel present at the scene where the event occurred.

Accident exposures are not controlled by the Radiological Emergency Plan (REP), and may be reportable to the NRC under 10 CFR 20 and/or 10 CFR 50.72.CDE -Committed Dose Equivalent CEDE -Committed Effective Dose Equivalent DAC -Derived Air Concentration DDE -Deep Dose Equivalent Emergency Exposure -Exposure to radiation or radioactive materials that is the result of actions taken in response to an emergency condition classified and declared pursuant to the Watts Bar Radiological Emergency Plan (REP). Emergency exposure refers to radiation exposure caused by those assessment, corrective, and mitigative actions that are required on an immediate basis to protect human lives, or to prevent or minimize the collective exposure of large populations.

Such activities are directed by the Control Room or by the TSC.LDE -Eye Dose Equivalent Life Saving Action -Those actions related to the search and rescue of injured persons.Planned Special Exposure (PSE) -As defined in 10 CFR 20, an infrequent exposure to radiation, separate from and in addition to the annual dose limits. PSEs might be warranted in the recovery phase. However, it is unlikely that the PSE requirements could be met during the initial phases of the emergency.

RAD/REM -For purposes of this implementing procedure, radiation exposure as expressed in units of R/hr and subunits, thereof, is equivalent to dose (rad) and dose equivalent (rem) based on ANSI N 13.11 development and terminology.

Any acute dose greater than 10 rem is generally denoted in units of rad, since that level is considered as the accident range of personnel exposure.

Any dose less than that level is considered the protective range of personnel exposure.

For purposes of this procedure the assumption of 1 rad = 1 rem is assumed for all levels of exposure.SDE -Shallow Dose Equivalent TEDE -Total Effective Dose Equivalent PAGE 16OF 16 REVISION 11 TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT EMERGENGY PLAN IMPLEMENTING PROCEDURE EPIP-1 6 TERMINATION OF THE EMERGENCY AND RECOVERY Revision 16 Unit 0 PREPARED BY: James F. Hagy SPONSORING ORGANIZATION:

Emergency Planning APPROVED BY: Frank L. Pavlechko Effective Date: 03131/2003 LEVEL OF USE: REFERENCE NON-QUALITY RELATED WBN TERMINATION OF THE EMERGENCY EPIP-1 6 AND RECOVERY REVISION LOG Revision Implementation Pages Description of Revision Number Date Affected 15 12/16/2002 All Plan effectiveness determination reviews indicate the following revisions do not reduce the level of effectiveness of the procedure or REP: Non Intent change. Renumbered instruction for inter-site consistency, formerly EPIP-13. For historical data, source notes, etc., see EPIP-13, Revision7.

Editorial revisions.

Deleted source notes, added table of contents, renumbered sections.16 03/31/2003 2, 4, 8-13 Plan effectiveness determination reviews indicate the following revisions do not reduce the level of effectiveness of the procedure or REP: Non Intent change. Added Offsite ERO capability verification for NRC Administrative Letter 97-03.Editorial corrections, updated Appendix A for inter-site consistency.

Added insurance notification.

PAGE 2 OF 15 REVISION 16 WBN TERMINATION OF THE EMERGENCY EPIP-1 6 AND RECOVERY 1.0 PURPOSE ...................................................

4

2.0 REFERENCES

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4 2.1 Interfacing Documents

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4 2.2 Other Documents

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4 3.0 INSTRUCTIONS

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5 3.1 TERMINATION

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5 3.2 RECOVERY ...................................................

5 4.0 RECORDS ...................................................

7 4.1 Records of Classified Emergencies

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7 4.2 Drill and Exercise Records ....................................................

7 APPENDIX A Termination Guidelines

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8 APPENDIX B Recovery Guidelines

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10 APPENDIX C LRC Location ...................................................

14 APPENDIX D ContractorNendor Augmentation Personnel Assignment

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15 PAGE 3 OF 15 REVISION 16 WBN TERMINATION OF THE EMERGENCY EPIP-1 6 AND RECOVERY 1.0 PURPOSE This procedure provides guidance and criteria for terminating a declared emergency classification and the development of recovery procedures to efficiently utilize resources and keep radiation doses As Low As Reasonably Achievable.

NOTE This procedure is not applicable for emergency conditions that were reported but not declared (totally resolved prior to declaration) per EPIP-1.

2.0 REFERENCES

2.1 Interfacing Documents 1. EPIP-2, Notification of Unusual Event 2. EPIP-3, Alert 3. EPIP-4, Site Area Emergency 4. EPIP-5, General Emergency 5. EPIP-6, Activation and Operation of the Technical Support Center 6. EPIP-7, Activation and Operation of the Operations Support Center 7. EPIP-15, Emergency Exposure Guidelines

8. CECC-EPIP-6, CECC Plant Assessment Staff Procedure for Alert, Site Area Emergency, and General Emergency 9. NP Radiological Emergency Plan (REP)10. SPP-4.1, Procurement of Materials, Labor, and Services 2.2 Other Documents 1. NUREG 0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants.2. NRC Administrative Letter 97-03, Plant Restart Discussions Following Natural Disasters 3. CFR 50.47 Emergency Plans and Part 50 Appendix E 4. CFR 20 Standards for Protection Against Radiation 5. ANSI N.18.7-1976 PAGE 4 OF 15 REVISION 16 WBN TERMINATION OF THE EMERGENCY EPIP-16 AND RECOVERY 3.0 INSTRUCTIONS 3.1 TERMINATION 3.1.1 In extended emergency events the Site Emergency Director (SED) in conjunction with the Central Emergency Control Center (CECC) Director and State Emergency Operations Center (when activated) will make the determination of when an emergency condition is resolved in accordance with the following criteria and may declare the onsite termination of the emergency.

The recovery organization duties are the responsibility of the Plant Manager and the WBN Vice President.

3.1.2 The termination of an emergency will be dependent on the nature of the emergency and the status of the plant systems following corrective measures.The provisions within this procedure are expected to be applicable to all long term emergencies (i.e., Alert, Site Area Emergency, General Emergency) where the TSC and CECC have activated.

It may be necessary to supplement this guidance with provisions specific to the emergency at hand.3.1.3 The decision to terminate the emergency will be based upon a comprehensive review of plant parameters and completion of Appendix A of this procedure.

3.1.4 Should an emergency situation recur following a termination, the SED will reactivate the emergency response organization.

3.2 RECOVERY 3.2.1 The overall goals of the recovery effort are to assess the in plant consequences of the emergency, perform clean up and repair operations, and restore the plant to a pre-determined status.3.2.2. The decision to enter the recovery phase will be made by the SED with concurrence from the CECC Director and the Senior Vice President, Nuclear Operations.

Following the decision to enter into the recovery phase, the Senior Vice President, Nuclear Operations or his designee will direct the overall recovery effort.PAGE 5 OF 15 REVISION 16 WBN TERMINATION OF THE EMERGENCY EPIP-1 6 AND RECOVERY 3.2 RECOVERY (cont.)3.2.3 If the recovery phase is expected to be a long-term process, the Site Vice President may form a team to be responsible for continuous control of the recovery operation.

The organizational structure of such a team would be contingent upon the emergency situation and procedures required for recovery.The Local Recovery Center (LRC) or other appropriate facilities will be made available to provide additional office space near (or on) the site for the recovery team.3.2.4 All major post accident onsite recovery measures shall be performed in accordance with written procedures.

3.2.5 Personnel protective measures shall be taken on initial entries and throughout the assessment and recovery operation to limit exposures As Low As Reasonable Achievable (ALARA) in accordance with EPIP-15, Emergency Exposure Guidelines.

3.2.6 The State of Tennessee has the authority for actions taken offsite however, TVA will serve as an important source of technical and analytical assistance for the State in offsite monitoring and sampling.

The Senior Vice President, Nuclear Operations, or his designee will serve as the State's contact for coordination of TVA's efforts in offsite monitoring, sampling and recovery.3.2.7 Should an emergency situation recur in the recovery phase, the SED will reactivate the emergency response organization and any recovery efforts will be suspended until the SED and CECC Director allow them to resume.3.2.8 Recovery operations will continue until the plant is returned to its pre-emergency status or as determined by the WBN Vice President or his designee.PAGE 6 OF 15 REVISION 16 WBN TERMINATION OF THE EMERGENCY EPIP-1 6 AND RECOVERY 4.0 RECORDS 4.1 Records of Classified Emergencies The materials generated in support of key actions during an actual emergency termination or recovery are considered Lifetime retention Non-QA records. Materials shall be forwarded to the EP Manager who shall submit any records deemed necessary to demonstrate performance to the Corporate EP Manager for storage.4.2 Drill and Exercise Records The materials deemed necessary to demonstrate performance of key actions during drills are considered Non-QA records. These records shall be forwarded to the EP Manager who shall retain records deemed necessary to demonstrate six-year plan performance for six years. The EP Manager shall retain other records in this category for three years.PAGE 7 OF 15 REVISION 16 WBN TERMINATION OF THE EMERGENCY EPIP-1 6 AND RECOVERY -APPENDIX A TERMINATION GUIDELINES (Page 1 of 2)1. The Site Technical Staff has evaluated the plant status and recommends that O YES termination guidelines be initiated.

E NO Comments:

D NA 2. The reactor is stable, in a safe condition, the shutdown margin for the core has 0 YES been verified, and long-term core cooling is available as required.

O NO Comments:

D NA 3. Equipment Status and Plant Parameters are within technical specification E YES requirements applicable for the existing mode of operation.

E NO Comments:

D NA 4. All planned releases of radioactive material will meet ODCM limits. E YES Comments:

O NO D NA 5. Radiation levels in the affected in-plant areas are stable at or dropping to below E YES acceptable levels. D NO Comments:

D NA 6. A minimum of one (1) offsite power source exists for operation of emergency E YES equipment.

O NO Comments:

NA 7. Access to radiologically controlled areas of the plant necessary for operation E YES during recovery are being monitored by RADCON and ALARA principles are in E NO effect. D NA Comments: PAGE 8 OF 15 REVISION 16 WBN TERMINATION OF THE EMERGENCY EPIP-1 6 AND RECOVERY APPENDIX A TERMINATION GUIDELINES (Page 2 of 2)8. Externally induced (tornado, flood, earthquake, or similar) emergency conditions 0 YES are controlled or have ceased. O NO Comments:

0 NA 9. All emergency steps in EPIPs 2-5 (as applicable) have been completed.

0 YES Comments:

0 NO D NA 10. There is no longer a need for staffing emergency response facilities, except for E YES facilities necessary for the Recovery Organization, and normal plant staffing is O NO available and adequate.

D1 NA Comments: 11. The CECC Director and the SED have held discussions with the Nuclear O YES Regulatory Commission, State and local organizations, and agreement has been E NO reached to terminate the emergency.

Capability of Offsite Emergency E NA Preparedness Organizations has been verified with the NRC Regional Administrator by the CECC.Comments: 12. A recovery organization has been established, (if considered necessary) by the E YES Site Emergency Director and Site Vice President.

D NO Comments:

D NA 13. Termination notification has been completed and the Communications Media E YES Relations Organization/JIC has been notified to make a press release on the El NO termination of the emergency (and the start of recovery efforts).

Nuclear E NA Insurance Support notification has been completed (CECC-EPIP-6).

Comments: Time/Date SED Signature PAGE 9 OF 15 REVISION 16 WBN TERMINATION OF THE EMERGENCY EPIP-16 AND RECOVERY APPENDIX B RECOVERY GUIDELINES (Page 1 of 4)1. Recovery efforts may require the marshaling of additional TVA resources and E1 YES interfacing with outside agencies.

These efforts shall be coordinated through the E NO Site Vice President and the Senior Vice President Nuclear Operations/Executive Cl NA Vice President Nuclear.2. All major post incident recovery measures shall be performed in accordance with E YES written procedures.

Recovery activities not covered by existing/approved O NO procedures shall be pre-planned and reviewed/approved by the PORC prior to El NA their implementation.

These procedures may include but not be limited to the following:

A. First entry operation in the Auxiliary, Reactor or Containment buildings.

B. Damage evaluation of affected plant systems.C. Decontamination efforts.D. Disassembly of an affected plant system.E. Repair/restart of an affected plant system.F. Waste Disposal.G. Any procedure waivers instituted during the emergency shall be terminated or formally documented by approved procedure changes.3. Communications Media Relations shall continue news release and press E YES briefings needed to keep the public informed of activities at the plant. El NO l NA 4. Emergency organization personnel should be directed to assemble all D YES documents generated during the emergency and to submit them to the Manager E NO of Emergency Planning.

Cl NA PAGE 10 OF 15 REVISION 16 WBN TERMINATION OF THE EMERGENCY EPIP-1 6 AND RECOVERY APPENDIX B RECOVERY GUIDELINES (Page 2 of 4)5. Any portable equipment used during the emergency shall be serviced as E YES necessary, and returned to designated storage locations.

Any damaged or E NO defective equipment shall be brought to the attention of individuals responsible 0 NA for its maintenance.

Consumable materials (i.e., procedure forms, bags, batteries, etc.) shall be restocked as soon as possible.6. If a long-term recovery operation is indicated, a recovery organization duty roster E YES will be established.

O NO E NA 7. If applicable, The Radiological Emergency Plan (REP) should be evaluated to E YES ensure that an adequate emergency preparedness stature can be maintained in E NO light of degraded plant conditions (i.e., inaccessibility of onsite E NA evacuation/assembly areas, inoperative emergency instrumentation and equipment as it relates to the REP) and appropriate corrective measures implemented.

8. Station recovery activities shall be in accordance with the station technical E YES specifications and other license conditions.

Specifically, during recovery E NO operations, the radiation exposure limits of 10 CFR 20 shall apply. Compliance El NA with these limits shall be the responsibility of the plant RADCON Manager via the Radiation Control Section.PAGE 11 OF 15 REVISION 16 WBN TERMINATION OF THE EMERGENCY EPIP-1 6 AND RECOVERY APPENDIX B RECOVERY GUIDELINES (Page 3 of 4)9. Radiation Dose management shall include but not be limited to the following E YES precautions:

I NO A. RADCON personnel will provide monitoring services and dosimetry and El NA prescribe the protective equipment to be used during the recovery of personnel or equipment.

B. Before entry to the affected area is attempted, RADCON will estimate airborne and direct radiation levels in the recovery area. From the information obtained, respiratory protection and occupancy times will be established.

C. RADCON personnel will accompany the recovery personnel on the initial entry to confirm that the airborne radioactivity and radiation levels are as expected.D. Dose to recovery personnel will be kept within the limits described in EPIP-15, and NP-REP. Respiratory protection factors given in EPIP-15 will be used in determining appropriate respiratory protection for the entry team.NOTE The SQN TLD Process Center is utilized by WBN to process Site TLD badges.E. TLD badges worn by recovery personnel will be processed by TVA.Process time for a badge would be approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.F. Although an emergency situation transcends the normal requirements of limiting exposure, there are suggested levels in NP-REP, EPIP-15 for exposure to be accepted in emergencies.

However, every reasonable effort to minimize exposure to ALARA should be made, even in emergencies.

10. Recovery actions that plan for or may result in radioactivity releases will be El YES evaluated by the CECC as far in advance of the event as is possible.

Such Cl NO releases and data pertaining to the releases will be reported to the appropriate El NA offsite emergency response organizations and agencies in advance, even if the release is within normal technical specifications, for as long as the recovery operation continues.

PAGE 12 OF 15 REVISION 16 WBN TERMINATION OF THE EMERGENCY EPIP-1 6 AND RECOVERY APPENDIX B RECOVERY GUIDELINES (Page 4 of 4)11. The Corporate/Site EP Managers should review the various reports on the B YES emergency to identify deficiencies in the Radiological Emergency Plan and O NO Implementing Procedures, and should initiate appropriate corrective action (if l NA necessary) as soon as possible.12. Local Recovery Center (LRC) D YES The purpose of the LRC, located at the WBN Training Center (see Appendix C), O NA is to provide a nearsite facility for TVA recovery management as well as NRC emergency response personnel and other emergency and/or recovery personnel.

The LRC provides adequate space for TVA and others who may locate there to support the site should additional office space near the site become necessary during the recovery phase.The LRC will provide dedicated space for NRC personnel containing adequate supplies, communications, and data necessary for them to carry out appropriate functions.

13. Contractor or Vendor Augmentation personnel, if utilized in the site recovery 0 YES efforts, should have the information provided in Appendix D (optional) completed E NO and understood.

D NA PAGE 13 OF 15 REVISION 16 WBN TERMINATION OF THE EMERGENCY EPIP-16 AND RECOVERY APPENDIX C LRC LOCATION (Page 1 of 1)The NRC Local Recovery Center (LRC)is in the Watts Bar Training Center in Classroom 6.The Emergency Staging Area is in the Watts Bar Training Center in Classroom 19.0~w =~ L 6 C a a j.1X i Simulator Lull 1 = I-F It'L- I .L=I U F-00G-C PAGE 14 OF 15 REVISION 16 WBN TERMINATION OF THE EMERGENCY EPIP-1 6 AND RECOVERY APPENDIX D CONTRACTORNENDOR AUGMENTATION PERSONNEL ASSIGNMENT (Page I of 1)(OPTIONAL)

Name:_SSN: Parent Company:.Occupation or Title: You have been assigned to assist in emergency response activities at: (Location)

At this location, you will report to: Title You are expected to report at am/pm on Name 20 You will serve in the following capacity: You will (will not) attend training at on 20 at am/pm.NOTE While you are performing emergency response or recovery efforts at the Watts Bar Nuclear Plant (WBN) you will be expected to follow approved WBN procedures, unless otherwise directed by Site Supervisory personnel.

Vendor procedures and/or procedures of other utilities shall not be used at WBN unless their use is specifically approved by the Plant Operations Review Committee (PORC). THERE SHALL BE NO EXCEPTION TO THIS RULE. No onsite information shall be released to the news media or to members of the public except by TVA Nuclear Communications personnel.

If you are approached by news media personnel, refer all questions to the Joint Information Center. Refer to SPP-4.1 Procurement of Materials, Labor, and Services for additional requirements.

PAGE 15 OF 15 REVISION 16 TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT EMERGENGY PLAN IMPLEMENTING PROCEDURE EPIP-1 7 FIRE EMERGENCY PROCEDURE Revision 0 Unit 0 PREPARED BY: James F. Hagy SPONSORING ORGANIZATION:

Emergency Planning APPROVED BY: Frank L. Pavlechko Effective Date: 03/31/2003 LEVEL OF USE: REFERENCE NON-QUALITY RELATED "I WBN FIRE EMERGENCY PROCEDURE I EPIP-17 Revision History Revision Implementation I Pages I Description of Revision Number I Date I Affected l 0 03/31/2003 All Plan effectiveness determinations on these changes indicate the following revisions do not reduce the level of effectiveness of the procedure or REP.l_ Intent. Initial issue for intersite consistency.

PAGE 2 of 4 REVISION 0 WBN FIRE EMERGENCY PROCEDURE EPIP-17lTable of Contents X 1.0 PURPOSE ..........................................................................

4

2.0 REFERENCES

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4 3.0 INSTRUCTIONS

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4 4.0 RECORDS RETENTION

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4 PAGE 3 of 4 REVISION 0

-#I WBN l FIRE EMERGENCY PROCEDURE I EPIP-1 7 1.0 PURPOSE To provide timely response to fire emergencies at Watts Bar Nuclear Plant and a mechanism to notify additional emergency personnel or resources as needed

2.0 REFERENCES

2.1 Interface Documents[1][2][3]AO1-30.1, "Plant Fires," EPIP-1, "Emergency Plan Classification Flowchart" EPIP-10, "Medical Emergency Response" 3.0 INSTRUCTIONS

1. ENSURE AO1-30.1, "Plant Fires," IMPLEMENTED.
2. IF there are personnel injuries, THEN IMPLEMENT EPIP-1 0, "Medical Emergency Response.

" 3. REFER TO EPIP-1, "Emergency Plan Classification Flowchart."[I[I LI1 4.0 RECORD RETENTION 4.1 No records are contained in this procedure.

PAGE 4 of 4 REVISION 0

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