ML17128A179
| ML17128A179 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 03/30/2017 |
| From: | Entergy Corp |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17128A173 | List: |
| References | |
| Download: ML17128A179 (384) | |
Text
{{#Wiki_filter:WATERFORD 3 SES EMERGENCY PLAN REVISION 048 EFFECTIVE DATE: 4/4/2017 PREPARED BY/DATE: Donald Vincent £4~ /;? APPROVED BY/DATE: * ) -3D-f APPROVED BY/DATE: _R_a_n_G_il_m_or_e_ _ _.**~.._c_/. . . ..._..r:?_.__.0_'
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_____3_~_3_0_,,,_l....;.9-_ _ (OSRC CHAIRMAN) APPROVED BY/DATE: Donald Brenton (GENERAL MANAGER PLANT OPERATIONS)
REQUEST/APPROVAL PAGE ';~ Form -Typical (W2:109)
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WATERFORD 3 SES EMERGENCY PLAN LIST OF EFFECTIVE PAGES WATERFORD 3 STEAM ELECTRIC STATION EMERGENCY PLAN Section Revision Title Page\ Rev. 048 List of Effective Pages i&ii Rev.048 Table of Contents 1 through6 Rev. 048 1.0 Glossary 1-1 through 1-12 Rev.048 2.0 Applicability and Scope 2-1 through 2-4 Rev. 048 A-2-1 through A-2-8 Rev.048 3.0 Summary of the Emergency Planning 3-1 through 3-5 Rev. 048 Program 4.0 Classification of Emergencies 4-1 through 4-5 Rev. 048 A-4-1 through A-4-19 Rev. 048 5.0 Organizational Control of Emergencies 5-1 through 5-30 Rev. 048 A-5-1A through A-5-21 Rev. 048 6.0 Emergency Response Measures 6-1 through 6-22 Rev. 048 A-6-1 through A-6-4 Rev. 048 7.0 Emergency Response Facilities and 7-1 through 7-29 Rev.048 Equipment A-7-1 through A-7-27 Rev.048 8.0 Maintenance of Emergency 8-1 through 8-9 Rev.048 Preparedness 9.0 Recovery 9-1 through 9-5 Rev. 048 A-9-1 Rev.048 Appendices Appendix A A-1 Rev. 048 Appendix B B-1 Rev. 048 Appendix C C-1 through C-2 Rev. 048 Appendix D D-1 Rev. 048 Appendix E E-1 Rev. 048 Appendix F F-1 Rev. 048 Appendix G G-1 through G-9 Rev. 048 Rev.048 (
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WATERFORD 3 SES EMERGENCY PLAN LIST OF EFFECTIVE PAGES WATERFORD 3 STEAM ELECTRIC STATION EMERGENCY PLAN Section Page# Revision Appendix H H-1 through H-4 Rev. 048 Appendix I 1-1 through 1-12 Rev. 048,-- Appendix J
- J-1 through J-9 Rev. 048 Appendix K K-1 Rev. 048 ii Rev.048
WATERFORD 3 SES EMERGENCY PLAN TABLE OF CONTENTS WATERFORD 3 STEAM ELECTRIC STATION EMERGENCY PLAN Plan Section Page No. 1.0 Glossary 1.1 Key Term Index 1-1 r" 1.2 Abbreviations Listing 1-10 2.0 Applicability and Scope 2.1 Purposes and Objectives 2-1 2.2 Location Description 2-2 2.3 Population Distribution 2-3 2.4 Planning Description 2-3 2.5 Plan Interrelationships 2-4 Figures, Tables and Charts Figure 2-1, Waterford Property A-2-1 Figure 2-2, Low Population Zone Cultural Features A-2-2 Figure 2-3, Waterford 3 Site A-2-3 Figure 2-4, Permanent Residents Within 10 Mile EPZ A-2-4 Figure 2-5, Permanent Residents Within 50 Mile EPZ A-2-5 Figure 2-6, The Region Within 10 Miles of Waterford 3 A-2-6 Figure 2-7, The Region Within 50 Miles of Waterford 3 A-2-7 Figure 2-8, Exclusion Area Boundary A-2-8 3.0 Summary of the Emergency Planning Program 3.1 Classification and Implementation 3-2 3.1.1 Emergency Classifications 3-2 3.1.2 Implementation 3-2 3.2 Response Actions 3-4 3.3 Recovery Actions 3-4 3.4 Maintenance of the Planning Program 3-5 Figures, Tables and Charts None 4.0 Classification of Emergencies 4.1 Waterford 3 Classification System 4-1 4.1.1 Unusual Event 4-2 4.1.2 Alert 4-2 4.1.3 Site Area Emergency 4-3 4.1 .4 General Emergency 4-3 4.2 State and Parish Classification System 4-4 1 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN Plan Section Page No. 4.3 Spectrum of Postulated Accidents 4-4 4.3.1 Classification of Postulated Accidents 4-4 4.3.2 Detection of Postulated Accidents 4-5 4.3.3 *. Toxic Chemical Releases 4-5 Figures, Tables and Charts Table 4-1, Summary of Initiating Conditions A-4-1 Table 4-2, Exclusion Area Boundary Calculated Exposures A-4-10 Table 4-3, Monitors A-4-11 Table 4-4, Instruments for Accident Detection A-4-16 5.0 Organizational Control of Emergencies 5.1 Waterford 3 Organizations 5-1 5.1.1 Normal Organizations 5-1 5.1.2 Emergency Organizations 5-2 5.2 Supporting Organizations 5-20 5.2.1 Wes.tinghouse Electric Company LLC 5-20 5.2.2 Institute of Nuclear Power Operations (INPO) 5-20 5.2.3 Entergy Operations, Inc. Headquarters 5-21 5.2.4 Entergy Services - Transmission System 5-22 5.2.5 Entergy Services - Fossil 5-22 5.2.6 American Nuclear Insurers l5-22 5.3 Governmental Organizations 5-23 5.3.1 Local Parishes 5-23 5.3.2 State0 Agencies 5-24 5.3.3 Federal Agencies 5-28 5.3.4 Local Agencies 5-28 5.4 Manpower and Timing Considerations 5-30 Figures, Tables and Charts Figure 5-1A, Entergy Operations, Inc. Waterford 3 Organization A-5-1A Figure 5-1 B, Normal Shift Organization A-5-18 Figure 5-1 C, Onshift Emergency Organization A-5-1C Figure 5-2, Onsite Emergency Organization A-5-2
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Figure 5-3, Nearsite Emergency Organization A-5-3 Figure 5-4, Joint Information Center Organization A-5-4 Figure 5-5, Emergency Organization Interfaces A-5-5 Table 5-1, Minimum Staffing and Augmentation Capabilities for Emergencies A-5-6 Table 5-2, Emergency Function and Responsibility Chart A-5-8 2 Rev.048
WATERFORD 3 SES EMERGENCY PLAN Plan Section ,Page No. Table 5-3, Facility Responsibilities A-5-10 Table 5-4, Control Room' (Shift) Responsibilities A-5-12 Table 5-5, Technical Support Center Responsibilities A-5-14 Table 5-6, Operational Support Center Responsibilities A-5-17
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Table 5-7, Emergency Operations Facility Responsibilities A-5-18 Table 5-8, Joint Information Center (JIC) Responsibilities A-5-20 6.0 Emergency Response Measures 6.1 Pre-Classification Assessment and Declaration of an Emergency
- 6-1
. 6.1.1 Recognition 6-1 6.1.2 Assessment 6-1 6.1.3 Classification .and Declaration 6-1 6.2 Activation of Emergency Organization 6-2 6.2.1 Notification 6-2 6.2.2 Mobilization of Emergency Organization 6-4 6.3 Assessment Actions 6-7 6.3.1 Assessment Actions for Unusual Events 6-8 6.3.2 Assessment Actions for Alerts 6-8 6.3.3 Assessment Actions for Site Area Emergencies 6-8
- I 6.3.4 Assessment Actions for General Emergencies 6-9 6.4 Radiological Assessment and Monitoring 6-9 6.4.1 Field Monitoring 6-9 6.4.2 Radiological Assessment 6-10 6.4.3 Transfer of Radiological Assessment Responsibility 6-11 6.5 Corrective Actions 6-11 6.6 Protective Actions 6-12 6.6.1 Evacuation, Personnel Accountability 6-12 6.6.2 Use of Onsite Radiological Protective Equipment and Supplies 6-17 6.6.3 Radiological Contamination Control Measures 6-17 6.7 Aid to Affected Personnel 6-18 6.7.1 Emergency Personnel Exposure 6-18 6.7.2 Thyroid Blocking 6-20 6.7.3 First Aid and Decontamination 6-20 6.7.4 Medical Transportation 6-21 6.7.5 Medical Treatment 6-21 6.8 Public AlerUNotification and Public Information 6-22 6.8.1 Public AlerUNotification 6-22 6.8.2 Public Information 6-22 3 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN Plan Section Page No. Figures, Tables and Charts Figure 6-1, Waterford 3 Emergency Organization Activation Scheme A-6-1 Figure 6-2, Notification Message Form (Typical) A-6-2 Figure 6-3, Initial Notification Personnel Scheme A-6-3 Figure 6-4, Effectiveness of Shelters A-6-4 7.0 Emergency Response Facilities and Equipment 7.1 Waterford 3 Onsite Emergency Facilities 7-1 7.1.1 Control Room 7-1 7.1.2 Technical Support Center 7-2 7.1.3 Operational Support Center 7-3 7.2 Waterford 3 Nearsite and Offsite Emergency Facilities 7-4 7.2.1 Emergency Operations Facility 7-4 7.2.2 Joint Information Center 7-5 7.3 State, Parish and Other Emergency Facilities 7-6 7.3.1 Parish Emergency Operations Center 7-6 7.3.2 State Emergency Operations Center 7-6 7.3.3 Louisiana Department of Environmental Quality 7-6 7.3.4 Other Response Facilities 7-7 7.4 Assessment Facilities and Equipment 7-7 7.4.1 Control Room Instrumentation 7-7 7.4.2 Fixed and Portable Radiation Monitoring Systems 7-7 7.4.3 Laboratory Facilities 7-10 7.4.4 Environmental and Offsite Monitoring Equipment and Facilities 7-11 7.4.5 Meteorological Detection 7-12 7.4.6 Fire Protection and Detection 7-14 7.4.7 Seismographic and Hydrologic Equipment 7-15 7.4.8 Protective Facilities and Equipment 7-16 7.4.9 Damage Control Equipment 7-17 7.4.10 First Aid and Medical Facilities 7-17 7.4.11 Assessment Capabilities 7-17 7.4.12 Post Accident Liquid Effluent Sampling 7-22 7.4.13 Post Accident Stack Gas Sampling 7-22 7.5 Communications Systems 7-22 7.5.1 Normal Communications Systems at Waterford 3 7-22 J 7.5.2 Emergency Communications Systems 7-26 7.5.3 Onsite Emergency Notification System 7-29 4 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN Plan Section Page No. 7.5.4 Offsite Emergency Notification System 7-29 Figures, Tables and Charts Figure 7-1, Emergency Response Facilities Locations A-7-1 Figure 7-2, Onsite Emergency Facilities Locations A-7-2 Figure 7-3, Waterford 3 Energy Education Center A-7-3 Figure?-4, Emergency Operations Facility (EOF) A-7-4 Figure 7-5, Control Room Layout A-7-5 Figure 7-6, Technical Support Center Layout A-7-6 Figure 7-7, OSC Floor Plan Maintenance Support Building First Floor A-7-7 Figure 7-8, Support Facilities Locations A-7-8 Figure 7-9, Offsite Evacuation Assembly Areas A-7-9 Figure 7-9A; REMP Sample Locations Within 2 Miles of Waterford 3 A-7-10 Figure 7-98, REMP Sample Locations Within 10 Miles of Waterford 3 A-7-11 Figure 7-9C, REMP Sample Locations Within 50 Miles of Waterford 3 A-7-12 Figure 7-9D, Emergency Environmental Monitoring Points A-7-13 Figure 7-10, Containment Radiation Plot A-7-14 Table 7-1, Control Room Plant Systems Instrumentation A-7-15 Table 7-2, Process and Effluent Radiological Monitors/Samplers A-7-16 Table 7-3, Area Radiation Monitors A-7-18 Table 7-4, Airborne Radiation Monitors A-7-19 Table 7-5, Radiation Survey/Monitoring Instrumentation A-7-20 Table 7-6, Laboratory Facility Equipment List (Typical) A-7-21 Table 7-7, Health Physics Equipment A-7-22 Table 7-8, Emergency Erwironmental Sampling A-7-.23 Table 7-9, Summary of Onsite Communication System Capabilities and A-7-24 Noise Consideration During Transients and/or Accidents Table 7-10, Emergency Response Facilities Communications A-7-25 8.0 Maintenance of Emergency Preparedness 8.1 Organizational Preparedness 8-1 8.1.1 Training 8-1 8.1.2 Drills and Exercises 8-4 8.2 Educational Information to the Public 8-8 8.3 Review and Updating of the Emergency Plan and Implementing Documents, .8-8 8.4 Maintenance and Inventory of Emergency Equipment and Supplies 8-9 8.5 Review/Audit of Emergency Prepared'ness Program 8-9 Figures, Tables and Charts None 5 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN Plan Section Page No. 9.0 Recovery 9.1 Transition from Emergency Organization to Recovery Organization 9:-1 9.2 Hecovery Organization 9-2 9.2.1 Responsibility for Establishing Recovery Organization 9-2 9.2.2 Objectives of Recovery Organization 9-2 9.3 Mode of Operations 9-3 9.3.1 Recovery Organization 9-4 9.3.2 Reentry 9-5 9.3.3 Restoration 9-5 , Figures, Tables and Charts Figure 9-1, Long-Term Recovery Organization A-9-1 Appendices Appendix A Mutual Assistance Plan (Deleted, superseded by the INPO Emergency Resources Manual) Appendix B Evacuation Time Study (Provided as a separate document) Appendix C 'Letters of Agreement (Deleted. Letters of Agreement are maintained in Emergency Planning Department files.) Appendix D Louisiana Peacetime Radiological Response Plan (Provided as a separate document) Appendix E Louisiana Peacetime Radiological Response Plan - Attachment 1 (Provided as a separate document) Appendix F Memorandum of Understanding with the Louisiana Department of Environmental Quality (Deleted, superseded by State Law)
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Appendix G Typical Emergency Response Equipment Lists Appendix H Procedure Cross Reference Between the Emergency Plan Implementing Procedures and the Emergency Plan Appendix I Emergency Medical Assistance Program (EMAP) AppendixJ NUREG-0654 Cross Reference Appendix K Waterford 3 Steam Electric Station AlerUNotification System Report (Summary) (Report provided as a separate document) 6 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN 1.0 GLOSSARY 1.1 Key Term Index The following is a list of key terms and their definitions, as used in the Waterford Steam Electric Station Unit No. 3 Emergency Plan. Terms capitalized within these definitions are defined elsewhere in this Glossary. Footnotes are located at the end of Section 1.1. 1.1.1 Accident - An unforeseen and unintentional event which may result in an emergency. 1.1.2 Activation - An Emergency Response Facility (ERF) is activated when the minimum staff is available and the facility is ready to assume its assigned functions under the Emergency Plan and relieve the on-shift staff of those functions. Although the facility may be ready, the on-shift relief may be postponed in the interest of completing critical tasks prior to turnover. 1.1.3 Adverse Meteorology - The five percent probability atmosphere dispersion condition which corresponds to a one hour X/Q value of 6.3 x 10-4 sec/m3 at the 1 EXCLUSION AREA BOUNDARY.
- 1.1.4 Alert - Events are in process or have occurred which involve an actual or potential substantial degradation of the level of the safety of the Waterford 3 Steam Electric Station (W3SES) or a security event that involves probable life threatening risk to site personnel or damage to site equipment because of intentional malicious dedicated efforts of a HOSTILE ACTION. Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels. 7 1.1.5 Assessment Actions - Those actions taken during or after an ACCIDENT to obtain and process information necessary to make decisions in order to 2
implement specific emergency actions. 1.1.6 Augmentation - Actions taken to support onshift personnel prior to emergency facilities becoming OPERATIONAL. 1.1. 7 Clean Area - Any.area or room which contains contamination levels less than the limits specified for a CONTAMINATION AREA. 1.1.8 Committed Dose Equivalent (COE) - The dose equivalent to organs or tissues of reference that will be received from an intake of radioactive material by an individual during the 50-year period following the intake. 1.1.9 Committed Effective Dose Equivalent (CEDE) - Sum of the products of the weighting factors applicable to each of the body organs or tissues which are irradiated and the COMMITTED DOSE EQUIVALENTS for these organs or tissues. 1.1.10 Company Spokesperson - Designated individual operating from the JIC with the primary responsibility for the content and timing of all information releases. 1.1.11 Contamination Area - An area where removable surface contamination is greater than or equal to 1000 dpm/100 cm 2 beta gamma or greater than or equal to 20 dpm/100 cm 2 alpha but is less than 100,000 dpm/100 cm 2 beta gamma. 1-1 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN 1.1.12 Control Room (CR) - An area at Waterford 3 located at+ 46.0 ft. MSL elevation of the Reactor Auxiliary Building (RAB) where the reactor and its auxiliary systems are controlled. 1.1.13 Control Room Supervisor - An individual who is part of the station supervisory staff, is licensed by the NRC as a Senior Reactor Operator and is authorized to direct the manipulation of reactor controls. The Control Room Supervisor (CRS) is accountable to the SHIFT MANAGER. He is responsible for directing the activities in the CONTROL ROOM. 1.1 ;14 Corrective Actions - Those emergency measures taken to mitigate or terminate an EMERGENCY situation at or near the source of the problem in order to prevent an uncontrolled release of radioactive material, e.g., reactor shutdown, equipment repair, etc. 1.1.15 Duty Plant Manager (DPM) - Designated individual in plant management assigned in accordance with the current duty roster the duties of the General Manager Plant Operations for weekends, backshift and periods when the General Manager Plant Operations is unavailable. 1.1.16 Emergency - Situation or condition which may result in damage to property or undue risk to the health and safety of the general public and/or site personnel. 1 .1.17 Emergency Actions - Those emergency measures taken to assess an emergency situation arid insure appropriate CORRECTIVE and/or PROTECTIVE ACTIONS. 1.1.18 Emergency Action Level (EAL) - A pre-determined, site-specific, observable threshold for a plant INITIATING CONDITION that places the plant in a given
, EMERGENCY CLASS. An EAL can be: an instrument reading; an equipment
'status indicator; a measurable parameter (on site or offsite ); a discrete, observable event; results of analyses; entry into specific emergency operating procedures; or another phenomenon which, if it occurs, indicates entr}t into a particular EM~RGENCY CLASS.
1.1.19 Emergency-Class - One of a minimum set of names or titles, established by the Nuclear Regulatory Commission-(NRC), for grouping off-normal nuclear power plant conditions according to (1) their relative radiological seriousness, and (2) the time-sensitive onsite and off-site radiological emergency preparedness actions necessary to respond to such conditions. The existing radiological emergency classes, in ascending order of seriousness, are called: (1) NOTIFICATION OF UNUSUAL EVENT (UNUSUAL EVENT), (2) ALERT, (3) SITE AREA EMERGENCY, and 4) GENERAL EMERGENCY. Hereinafter may be referred to as Emergency Classification. 1.1.20 Emergency Director (ED) - The designated individual in the onshift (and NEARSITE) emergency organization with overall responsibility and authority for ONSITE emergency response including initial OFFSITE PROTECTIVE ACTION RECOMMENDATIONS and OFFSITE notifications 1.1.21 Emergency Core Cooling System (ECCS) - System which includes the pertinent pumps, piping, valves, etc., of the Decay Heat Removal System, Core Flooding System and the make-up portion of the Make-up and Purification System. 1.1.22 Emergency Operations Center (EOC) - Designated State and local emergency management headquarters facilities especially designed and equipped for the purpose of exercising effective coordination and control over disaster operations 2 carried out within their jurisdiction. 1-2 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN 1.1.23 Emergency Operations Facility (EOF) - Designat~d facility for the management of overall Waterford 3 emergency response, coordination of OFFSITE radiological and environmental assessments, determination of OFFSITE PROTECTIVE ACTION RECOMMENDATIONS and OFFSITE notifications. The capability to perform the following functions is required in order to declare the EOF OPERATIONAL:
- Management of overall licensee emergency response,
- Coordination of radiological and environmental assessment,
- Determination of recommended public protective actions, and
- Coordination of emergency response activities with Federal, State and local agencies. 3 1.1.24 Emergency Plan (EP) - The ENTERGY OPERATIONS, INC. plan for response to emergencies at Waterford 3.
1.1.25 Emergency Planning Coordinator (EPC) - Individual responsible for the overall coordination of emergency planning required at the Waterford 3 SES. The Emergency Planning Manager is the designated Emergency Planning Coordinator. 1.1.26 Emergency Planning Zone (EPZ) - Two Emergency Planning Zones have been established. The first is an area about 10 miles in radius around the Waterford 3 SES for which emergency planning consideration of the PLUME EXPOSURE PATHWAY has been given in order to assure that prompt and effective actions
~ can be taken to protect the public in the event of an ACCIDENT. The second is an area approximately 50 miles in radius around the Waterford 3 SES for which emergency planning consideration of the INGESTION EXPOSURE PATHWAY has been given.4 1.1.27 Emergency Plan Implementing Instructions - Specific procedures providing step-by-step actions for using the INITIATING CONDITIONS to classify an emergency condition. These procedures also provide step-by-step actions for implementing the EMERGENCY PLAN at each EMERGENCY CLASSIFICATION. .
1.1.28 Emergency Plan Implementing Procedures - Specific procedures providing step-by-step actions to implement emergency plans, in order to mitigate or terminate an EMERGENCY situation 1.1.29 Emergency Plan Supporting Procedures - Specific procedures outlining the actions necessary to maintain the state of emergency readiness as defined in the EMERGENCY PLAN. 1.1.30 Emergency Response Data System (EROS) - A direct, near real-time, electronic data link between the Waterford 3 plant computer system and the NRC Operations Center that provides for the automated transmission of a limited data set of selected parameters. 1.1.31 Entergy Corporation - Entergy Louisiana, LLC, and ENTERGY OPERATIONS, INC., parent company 1.1.32 Entergy Operations, Inc. - Company responsible for operating the Waterford 3 Steam Electric Station 1.1.33 Essential Personnel - Those individuals who are assigned and trained to perform emergency duties as outlined within the Waterford 3 SES EMERGENCY PLAN. 1-3 Rev.048
WATERFORD 3 SES EMERGENCY PLAN 1.1.34 Exclusion Area (EA) or Exclusion Zone (EZ) - Area surrounding the reactor in which ENTERGY OPERATIONS, INC. has the authority to determine all activities including exclusion or removal of personnel and property from the area. 5 1.1.35 Exclusion Area Boundary (EAB) - The border of the EXCLUSION AREA or an area corresponding to a distance of 914 meters from the Waterford 3 reactor. 1.1.36 General Emergency - Events are in process or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity or HOSTILE ACTION that results in an actual loss of physical control of the facility. Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels offsite for more than the immediate site area. 7 . 1.1.37 Governor's Office of Homeland Security & Emergency Preparedness (GOHSEP) - The Louisiana Governor's Office of Homeland Security & Emergency Preparedness 1.1.38 High Contamination Area - An area where the removable surface contamination is greater than or equal to 100,000 dpm/100 cm 2 beta gamma. 1.1.39 High Radiation Area - An area, accessible to individuals, in which radiation levels could result in an individual receiving a deep dose equivalent of greater than or equal to 100 millirem (1 mSv) in 1 hour at 30 centimeters (-12 inches) from the radiation source or from any surface that the radiation penetrates. 5 1.1.40 Hostile Action - An act toward a Nuclear Power Plant or its personnel that includes the use of violent force to destroy equipment, take hostages, and/or intimidate the licensee to achieve an end. This includes attack by air, land, or water using guns, explosives, projectiles, vehicles, or other devices used to deliver destructive force. Other acts that satisfy the overall intent may be included. HOSTILE ACTION should not be construed to include acts of civil disobedience or felonious acts that are not part of a concerted attack on the NPP. Non-terrorism-based EALs should be used to address such activities, (i.e., this ma¥ include violent acts between individuals in'the OWNER CONTROLLED AREA.) 1.1.41 Hostile Force - One or more individuals who are engaged in a determined assault, overtly or by stealth and deception, equipped with suitable weapons capable of killing, maiming, or causing destruction. 7 1.1.42 Implementing Documents - The EMERGENCY PLAN IMPLEMENTING PROCEDURES, plant procedures, Departmental Procedures, Training lesson plans or any other document which is used to implement the emergency response philosophy as described in the EMERGENCY PLAN. 1.1.43 Ingestion Exposure Pathway - The mechanism by which radiation is dispersed through the E;)nvironment subjecting the general public to exposure principally from ingestion of contaminated water or food, such as milk or fresh vegetables 1.1.44 Initiating Condition (IC) - One of a predetermined subset of nuclear power plant conditions where either the potential exists for a radiological emergency, or such an emergency has occurred. 1.1.45 Joint Information Center (JIC) - The facility which serves as the single-point contact for disseminating Plant information to the public. 1-4 Rev.048
WATERFORD 3 SES EMERGENCY PLAN 1.1.46 Locked High Radiation Area - An area, accessible to individuals, in which radiation levels could result in an individual receiving a deep dose equivalent greater than or equal to 1000 mR/hr (10 mSv) in one hour at 30 cm (-12 inches) 5 from the radiation source or from any surface that the radiation penetrates. 1.1.47 Louisiana Peacetime Radiological Response Plan - State of Louisiana Emergency Response Plan for all radiological emergencies in the State or near its borders 1.1.48 Louisiana Peacetime Radiological Response Plan Waterford 3 Attachment - State of Louisiana Emergency Response Plan with specific reference to actions to be carried out by St. Charles and St. John the Baptist Parishes in response to a situation at Waterford 3. 1.1.49 Louisiana Department of Environmental Quality (LDEQ) - State of Louisiana department with jurisdiction over matters affecting the environment including the regulation and control of radiation and development and implementation of emergency response plans for fixed nuclear facility accidents. 1.1.50 Low Population Zone (LPZ) - The area immediately surrounding the EXCLUSION AREA which contains residents, the total nur:nber and density of which are such that there is a reasonable probability that appropriate PROTECTIVE ACTIONS could be taken in their behalf in the event of a serious ACCIDENT. 1.1.51 Non-Essential Personnel - Those individuals (including members of the general public who may be in public access areas within the EXCLUSION and OWNER CONTROLLED AREAS) who are not assigned to the emergency organization and have access to the Waterford 3 Site.
- 1.1.52 Notification of Unusual Event - Events are in process or have occurred which indicate a potential degradation of the level of the safety of the W3SES or indicate a security threat to facility protection. No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs. Hereinafter defined for the Waterford 3 SES as an UNUSUAL EVENT7 * ,
1.1.53 Nuclear Auxiliary Operators (NAO) - Individuals who operate plant systems outside the CONTROL ROOM to assist the REACTOR OPERATOR in carrying out their duties. 1.1.54 Offsite - Any area outside of the plant perimeter fence 1.1.55 Onsite - Any area within the plant perimeter fence 1.1.56 Operable/Operability - A system, subsystem, train, component or device shall be . operable or have operability when it is capable of performing its specified function(s), and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function(s) are also capable of performing their related support function(s). 1.1.57 Operational - Status of an emergency facility declared by the appropriate facility manager upon determining that the facility is adequately staffed and equipment is setup and available to perform the emergency functions assigned to that facility. This definition meets the intent of the term "fully operational" as described in Supplement 1 to NUREG-0737. Hereinafter OPERATIONAL and "fully operational" may be used interchangeably. 1-5 Rev.048
WATERFORD 3 SES EMERGENCY PLAN 1.1.58 Operational Modes - Mode 1 Power Operation Mode2 Startup Mode3 Hot Standby Mode4 Hot Shutdown Mode5 Cold Shutdown \ Mode6 Refueling Defueled Although not an Operational Mode, "defueled" is listed here because it is a plant condition used in the EALs. See Waterford 3 Technical Specifications, Table 1.2 for more detailed information.
- 1. t.59 Operational Support Center (OSC) - ONSITE assembly area located in the Maintenance Support Building where Waterford 3 operations support personnel will muster for subsequent assignment to duties in support of emergency operations. The capability to perform the following functions is required in order to declare the OSC OPERATIONAL:
- Provide a location where plant logistic support can be coordinated during an emergency, and '
- Restrict CONTROL ROOM access to those support personnel specifically requested by the SHIFT MANAGER. 3 1.1.60 Owner Controlled Area (OCA) - The external area contiguous to the PROTECTED AREA extending outward to Entergy Louisiana, LLC Property lines. .
1.1.61 Personnel Monitoring Equipment - Devices designed to be worn or carried by an individual for the assessment of dose equivalent (e.g., pocket dosimeter~. direct reading electronic dosimeters, DLRs, etc.). 5 1.1.62 Plume Exposure Pathway - The means by which a radioactive plume can expose the general public and/or ONSITE personnel to radiation. The time of potential exposure could range from hours to days. The principal exposure sources from this pathway are: ( 1) external exposure to gamma radiation from the radioactive plume and from deposited material, and (2) inhalation exposure from the passing radioactive plume. 1.1.63 Population Center Distance - The distance from the reactor to the nearest boundary of a densely populated center containing more than 25,000 residents. 5 1.1.64 Projected Dose - Estimate of the radiation dose that affected populations may potentially receive if PROTECTIVE ACTIONS are not taken. 6 1.1.65 Protected Area - The area encompassed by physical barriers (the security fence) and to which access is controlled into the VITAL AREAS of the Plant. ) 1.1.66 Protective Actions (PA) - Action(s) taken to avoid or reduce the possibility of exposure to the PROJECTED DOSE. 6 - I' 1-6 Rev.048
WATERFORD 3 SES EMERGENCY PLAN 1.1.67 Protective Action Guides (PAG) - Projected radiological dose or dose commitment values to individuals in the general population and to emergency workers that warrant PROTECTIVE ACTIONS before or after a release of radioactive material. 6 1.1.68 Protective Action Recommendation (PAR) - The PROTECTIVE ACTIONS given to OFFSITE agencies that are deemed appropriate by Waterford 3 SES emergency response personnel to protect the health and safety of the public. " 1.1.69 Radiation Area - An area, accessible to individuals, in which radiation levels could result in an individual receiving a deep dose equivalent greater than or equal to 5 mRem (0.05mSv) in 1 hour at 30 cm(= 12 inches) from the radiation source or from any surface that the radiation penetrates. 1.1. 70 Radiologically Controlled Area (RCA) - Any area where full radiological controls are in effect (i.e., Provides controlled personnel access/egress and contamination monitoring for personnel and/or equipment upon exit), for the purpose of providing protection and information to the individual. These areas normally include but are not limited to the following: The Reactor Containment Building, Fuel ~andling Building and portions of the Reactor Auxiliary Building. 1.1. 71 Reactor Operator (RO) - An individual, licensed by the NRC as a Reactor Operator or Senior Reaetor Operator, who is authorized to manipulate the reactor controls. 1.1. 72 Recovery - Those actions taken after the EMERGENCY to restore the plant as nearly as possible to its pre-emergency condition 1.1.73 Recovery Manager - lndividuaLresponsible for overall RECOVERY activities 1.1. 74 Restricted Area - As applicable to 10CFR20, Restricted Area is defined as that area enclosed by the Security PROTECTED AREA fence and the fenced in area enclosing the Low Level Radioactive Waste Facility. 1.1. 75 Security Condition - Any security event as listed in the approved security contingency plan that constitutes a threat/compromise to site security, threat/risk to site personnel, or a potential degradation to the level of the safety of the plant. A Security Condition does not involve a HOSTILE ACTION. 1.1.76 Shift Manager (SM) -An individual who is part of the station supervisory staff, is licensed by the NRC as a Senior Reactor Operator and is authorized to direct the manipulation of the reactor controls. The SM is designated by the Operations Manager to be the senior member of the shift organization. As such, the Shift Manager is the senior ENTERGY OPERATIONS, INC. management representative with respect to plant operation and is the General Manager Plant Operations' representative on shift. He is directly responsible for all activities on site. 1.1. 77 Site Area Emergency - Events are in process or have occurred which involve an actual or likely major failures of plant functions needed for protection of the public or HOSTILE ACTION that results in intentional damage or malicious acts; (1) toward site personnel or equipment that could lead to 1the likely failure of or; (2) that prevents effective access to equipment needed for the protection of the public. Any releases are not expected to result in exposure levels which exceed EPA Protective Action Guideline exposure levels beyond the site boundary. 7 1.1. 78 Site Evacuation - A controlled, preplanned evolution, which can be initiated by the EMERGENCY PLANT MANAGER, that ensures all NON-ESSENTIAL 1-7 Rev.048
WATERFORD 3 SES EMERGENCY PLAN PERSONNEL are safely and expeditiously evacuated from the WATERFORD 3 SES SITE area to predetermined OFFSITE assembly areas. 1.1. 79 State - The State of Louisiana 1.1.80 Technical Support Center (TSC) - ONSITE facility located at the +46.0 ft. MSL elevation in the Reactor Auxiliary Building, separate from the CONTROL ROOM which provides plant management and technical support to the reactor operating personnel in the CONTROL ROOM during emergency conditions. The capability to perform the following functions is required in order to declare the TSC OPERATIONAL:
- Provide plant management and technical support to plant operations per~onnel during emergency conditions.
- Relieve the reactor operators of peripheral duties and communications not directly related to reactor system manipulations.
- Prevent congestion in the CONTROL ROOM.
- Perform EOF functions as necessary until these functions are transferred to the EOF. 3 1.1.81 Total Effective Dose Equivalent (TEDE) - The sum of the effective dose equivalent or the deep dose equivalent (for external exposures) and the COMMITTED EFFECTIVE DOSE EQUIVALENT (for internal exposures).
1.1.82 Unrestricted Area - Any area, access to which is neither limited nor controlled by ENTERGY OPERATIONS, INC., in order to protect individuals from exposure to radiation and radioactive materials. 5 1.1.83 Unusual Event - Events are in process or have occurred which indicate a potential degradation of the level of the safety of the W3SES or indicate a security threat to facility protection. No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs. 7 1.1.84 Very High Radiation Area - An area, accessible to individuals, in which radiation levels could result in an individual receiving an absorbed dose in excess of 500 rads in one hour at 1 meter (- 3ft.) from the radiation source or any surface that the radiation penetrates5 . 1.1.85 Vital Areas -Any area which contains VITAL EQUIPMENT. 5 1.1.86 Vital Equipment - Any equipment, system, device or material, the failure, destruction, or release of which could directly or indirectly endanger the public health and safety by exposure to radiation. Equipment or systems which would be required to function to protect public health and safety following such failure, destruction or release are also considered to be vital. 5 1.1.87 Waterford 3 SES Site - That area bounded by the plant perimeter fence. 1-8 Rev.048
WATERFORD 3 SES EMERGENCY PLAN Footnote References for Definitions - 1 Final Safety Analysis Report (FSAR) Waterford Steam Electric Station, Unit No. 3. 2 NUREG 0654/FEMA-REP-I, Rev. I, Criteria for Preparation and Evaluation of Radiological Emergency. Response Plans and Preparedness in Support of Nuclear Power Plants 3 NUREG 0696, Functional Criteria for Emergency Response Facilities, NRC, 1981. 4
\ NUREG 0396 (EPA 520/l-78-016), Planning Basis for the Development of State and Local Government Radiological Emergency Response Plans in Support of Light Water Nuclear Power Plants.
5 Title 10, Code of Federal Regulations. 6 EPA 400-R-92-001, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents. 7 NEl-99-01, Methodology for Development of Emergency ACtion Levels, Revision 5 1-9 Rev. 048 L_ \
WATERFORD 3 SES EMERGENCY PLAN 1.2 Abbreviations Listing 1.2.1 CCW - Component Cooling Water 1.2.2 COE - Committed Dose Equivalent 1.2.3 CEDE - Committed Effective Dose Equivalent 1.2.4 CFR - Code of Federal Regulations 1.2.5 CR - Control Room 1.2.6 CRS - Control Room Supervisor 1.2.7 CVCS - Chemical Volume Control System 1.2.8 DA - Dose Assessor 1.2.9 DLR - Dosimeter of Legal Record 1.2.10 DOE - Department of Energy . J I 1.2.11 EA - Exclusion Area 1.2.12 EAB - Exclusion Area Boundary 1.2.13 EAL - Emergency Action Level 1.2.14 ECCS - Emergency Core Cooling System 1.2.15 ED - Emergency Director 1.2.16 EFAT - Emergency First Aid Team 1.2.17 EMA - Emergency Management Agency 1.2.18 EMAP - Emergency Medical Assistance Program 1.2.19 *ENS - Emergency Notification System 1.2.20 EOC - Emergency Operations Center 1.2.21 EOF - Emergency Operations Facility 1.2.22 EP - Emergency Plan 1.2.23 EPA - Environmental Protection Agency 1.2.24 EPM - Emergency Plant Manager 1.2.25 EPIP - Emergency Plan Implementing Procedure 1.2.26 EPZ - Emergency Planning Zone 1.2.27 EZ - Exclusion Zone 1.2.28 FEMA - Federg.I Emergency Management Agency 1.2.2~ FSAR - Final Safety Analysis Report 1-10 Rev.048
WATERFORD 3 SES EMERGENCY PLAN 1.2.30 GOHSEP - Governor's Office of Homeland Security & Emergency Preparedness 1.2.31 HPN - Health Physics Network 1.2.32 IC - Initiating Condition 1.2.33 INPO - Institute of Nuclear Power Operations 1.2.34 IPARMS - In-Plant Airborne Radiation Monitoring System 1.2.35 JIC - Joint Information Center 1.2.36 LPZ - Low Population Zone 1.2.37 LDEQ - Louisiana Department of Environmental Quality 1.2.38 LSP - Louisiana State Police 1.2.39 MARMOND - Meteorological and Radiation Monitoring Data Processing System 1.2.40 MSL - Mean Sea Level 1.2.41 NAO - Nuclear Auxiliary Operator 1.2.42 NIMS - National Incident Management System 1.2.43 NRC - Nuclear Regulatory Commission 1.2.44 NWS - National Weather Service 1.2.45 OSC - Operational Support Center 1.2.46 OSRC - Onsite Safety Review Committee 1.2.47 OTA- Offsite Technical Advisor 1.2.48 PA - Protective Action 1.2.49 PAG - Protective Action Guides 1.2.50 PAR - Protective Action Recommendation 1.2.51 RAB - Reactor Auxiliary Building 1.2.52 RAC - Radiological Assessment Coordinator 1.2.53 RAP - Radiation Assistance Program 1.2.54 RC - Radiological Coordinator 1.2.55 RCA - Radiologically Controlled Area 1.2.56 RCC - Rad/Chem Coordinator 1.2.57 RCS - Reactor Coolant System 1.2.58 RO- Reactor Operator 1.2.59 RPS - Reactor Protective System I 1-11 Rev.048
WATERFORD 3 SES EMERGENCY PLAN 1.2.60 SES - Steam Electric Station 1.2.61 SDS - Satellite Display System 1.2.62 SI - Safety Injection System 1.2.63 SM - Shift Manager 1.2.64 SRD - Self-Reading Dosimeter 1.2.65 SRO - Senior Reactor Operator 1.2.66 SSEB - Southern States Energy Board 1.2.67 SSS - Security Shift Supervisor 1.2.68 STA- Shift Technical Advisor 1.2.69 TEDE - Total Effective Dose Equivalent 1.2.70 TLD - Thermoluminescent Dosimeter 1.2. 71 TSC - Technical Support Center 1.2. 72 W3SES - Waterford 3 Steam Electric Station 1.2. 73 XJQ - Wind Dispersion Factor (Chi/Q) 1-12 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN 2.0 APPLICABILITY AND SCOPE 2.1 Purposes and Objectives The purpose of emergency preparedness is to provide direction for response to emergencies varying in severity from personnel injuries to situations involving real or potential offsite radiological hazards and to ensure that necessary equipment, supplies and essential services are available. The following plan has been developed for the Waterford Steam Electric Station Unit No. 3 (W3SES), as a detailed expansion of the Final Safety Analysis Report, Section 13.3. Section 13.3 of the FSAR is provided in order to satisfy submittal requirements of Section 50.34 to Title 10 of the Code of Federal Regulations ( 10 CFR 50.34) "Contents of Applications; Technical Information". Further, this document satisfies the criteria of 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." Supplemental guidance has been provided by additional documents, samples of which are listed below:
- a. NUREG 0737
- b. NUREG 0696
- c. REG Guide 1.97 The primary objective of emergency planning is to develop and maintain a plan and implementing procedures to ensure emergency preparedness and provide a means for mitigating the consequences of emergencies in order to protect the health and safety of the general public and site personnel, and to prevent damage to property.
As such, objectives of the Emergency Plan are as follows:
- a. To establish procedures to identify and classify emergency conditions.
- b. To establish procedures to reclassify an emergency condition should the severity increase or decrease.
- c. To detail the normal and emergency operating organizations and to assign responsibilities in order to direct the response to an emergency situation or radiological incident.
- d. To provide guidelines and specific details of offsite support organizations' assistance (to include governmental organizations) and availability.
- e. To evaluate the necessity for public protective actions deemed appropriate to 1
protect the general public and site personnel.
- f. To terminate or mitigate the consequences of an emergency both onsite and offsite.
- g. To establish and provide specific details on emergency facilities, assessment facilities, communication systems availability, and their utilization by normal and emergency operating organizations.
- h. To provide for the training of all essential personnel.
2-1 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN
- i. To outline the most effective course of action in order to protect the general public and site personnel in the event of an emergency.
2.2 Location Description The Waterford Steam Electric Station Unit No. 3 (W3SES), is owned by Entergy Louisiana, LLC., and operated by Entergy Operations, Inc. It is a pressurized water reactor steam supply system furnished by ABB Combustion Engineering and is designed for a core thermal output of 3716 megawatts. The Waterford property is.shown on Figure 2-1. The property is owned by Entergy Louisiana, LLC., and includes 3,561.3 acres. The Waterford 3 site is defined as that area bounded by the plant perimeter fence. The Waterford 3 site is shown in Figure 2'...3. The site area includes station structures for Waterford 3 and a branch of the Riverland Credit Union. It does not include any recreational or other industrial structures. It does include certain facilities for temporary housing which may be used by transient population as conditions warrant. On the Waterford property, approximately one mile southwest of the Waterford 3 site, the James M. Cain Energy Educ.ation Center is located (see Figure 2-1). The James M. Cain Energy Education Center is accessed from LA 3127 and houses the Waterford 3 Emergency Operations Facility (EOF). This area includes certain facilities for temporary housing which may be used by transient population as conditions warrant. The Waterford 3 site is located on the west (right descending) bank of the Mississippi River between Baton Rouge, Louisiana, and New Orleans, Louisiana. The site is in the northwestern section of St. Charles Parish, Louisiana, near the towns of Killona'and Taft. Figure 2-7 shows the site in relation to the region within 50 miles; Figure 2-6 shows the area within 10 miles of the site. The Waterford 3 site is located adjacent to the Mississippi River, at River Mile 129.6. The River itself is the most prominent natural feature of the region. Other important natural features include Lac des Allemands, about 5.5 miles southwest of the site, and Lake Pontchartrain, about 7 miles northeast of the site. The land slopes gently from its high points near the River (+10 to 15 ft. MSL) to extensive wetlands located about 1.5 to 2.5 miles inland from the River. Most of the man-made features are located on the narrow strip of dry land between the Mississippi River and the wetlands. Near the Waterford site are several large industrial facilities, including Waterford SES Units 1 and 2 (0.4 mile west-northwest of Waterford 3), Little Gypsy SES Units 1, 2 and 3 (0.8 mile north-northeast of the site, across the River), Mosaic Phosphates, a fertilizer manufacturer (0.6 mile east-southeast). The above-mentioned generating stations are owned by Entergy Louisiana, LLC., and operated by Entergy Services, Inc. Other large- industries are located along the Mississippi River both north and south of the site as far as Baton Rouge and New Orleans. These industries are predominantly refineries, petrochemical manufacturers, sugar manufacturers, and grain elevators.
- Transportation facilities near the Waterford site include the Mississippi River (0.2 mile from the site), Louisiana Highway 18 (0.1 mile north-northeast), Louisiana Highway 3127 (1.1 miles south-southwest), Louisiana Highway 628 (0.7 mile riorth-northeast, across the River) and the Union Pacific Railroad (0.5 mile south-southwest).
Important urban centers in the region of the site include New Orleans (25 miles east-southeast) and Baton Rouge (50 miles west-northwest). Communities near the site include Killona (0.9 mile west-northwest), Montz (1.0 mile north), Norco (1.9 miles east), Destrehan (7.0 miles northeast), Hahnville (3.7 miles east-southeast), and LaPlace (4.7 2-2 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN miles north). All except LaPlace are located in St. Charles Parish. LaPlace is located in St. John the Baptist Parish. 1 2-3 Rev.048
WATERFORD 3 SES EMERGENCY PLAN 2.2 (Cont'd.} Other prominent man-made features include the Mississippi River levee system, which at its closest point is 0.1 mile from the Waterford site, and the Bonnet Carre Spillway, a
- flood control structure 1.3 miles east-northeast of the site.
2.3 Population Distribution A 2-mile radius surrounding the Waterford 3 site has been defined as the Low Population Zone (LPZ). The residents in this area are distributed such that there is a reasonable probability that appropriate protective measures could be taken in their behalf in the event of a serious accident. There are no schools within this zone. The Nelson Coleman St. Charles Parish Correctional Center, a 600-bed facility operated by the St. Charles Parish Sheriffs Department is in this zone. There are seven chemical plants located in this zone. These plants are located to the East and Southeast of Waterford-3. Figure 2-2 shows the cultural features of this zone including the locations of the chemical plants. The area within 10 miles of the plant includes St. Charles and St. John the Baptist Parishes. The estimated 2010 population in St. Charles and St. John the Baptist Parishes is 87 ,877 persons concentrated mainly in towns along the banks of the Mississippi River. St. Charles Parish has an estimated 10 mile EPZ population of 43,676 persons, while St. John the Baptist Parish's estimated 10 mile EPZ population is 44,201. These population figures reflect the total population within the risk Parishes that is expected to evacuate in
' a Waterford-3 emergency whether or not they are located within the 10 mile radius.
Figure 2-4 shows a population breakdown by compass sector and distance within 10 miles of the plant. The additional population located outside the 10 mile radius is conservatively included in the 5-10 mile ring. Between 10 and 50 miles from Waterford 3, estimated 2010 population is 1,910, 133 persons or 95.6 percent of the population within 50 miles of the plant. Figure 2-5 shows a population breakdown by compass sector and distance within 50 miles of the plant. 2.4 Planning Description
*Entergy Operations, Inc., in defining the Emergency Planning Zones (EPZ) for the Waterford 3 Steam Electric Station, has taken into consideration the information and data provided above, organizational capabilities, methods of implementation of the W3SES Emergency Plan and the availability of onsite and offsite emergency facilities and equipment.
Two primary zones have been identified for the purpose of development and implementation of the emergency plan. The first EPZ established has a radius of about 10 miles and is referred to as the plume exposure pathway emergency planning zone. Within this zone evacuation and/or sheltering may be used as immediate protective actions to protect the general public. The principal concern with the plume exposure pathway is that of external exposure and/or exposure to the thyroid due to inhalation and ingestion. The second EPZ established has a radius of about 50 miles and is referred to as the ingestion exposure pathway emergency planning zone. Beyond the 10-mile radius, this pathway is most significant. The principal concern with the ingestion exposure pathway is from ingestion of contaminated water or foods such as milk or fresh vegetables. Figures 2-6 and 2-7 indicate the areas involved or within the 10-mile and 50-mile EPZ, respectively. 2-4 Rev.048
WATERFORD 3 SES EMERGENCY PLAN 2.5 Plan Interrelationships The W3SES Emergency Plan should not be used alone in response to an emergency, but in conjunction and coordination with procedures, other plans and emergency arrangements. These interrelationships are summarized as follows:
- a. Emergency Plan Implementing Procedures provide detailed actions to be taken by individuals in response to onsite emergency situations. These procedures direct the implementation of the Emergency Plan. Implementing Procedures incorporate certain aspects of the site's operating procedures, radiological control procedures and industrial security procedures, where they are required for clarification.*
- b. Emergency Operating Procedures are utilized to control plant operations during abnormal conditions.
- c. Security Plan and Procedures have been coordinated to ensure that appropriate emergency actions can be taken. For example, the Security Plan and Procedures have provisions for emergency response personnel and vehicle access when required by the Emergency Plan Implementing Procedures.
- d. The W3SES Radiation Protection Procedures define administrative controls and procedures such as radiological control limits and precautions, use of personnel monitoring devices and protective clothing, personnel decontamination, etc. The procedures also provide instructions on performing surveys, analyzing samples, operating radiation protection equipment, etc. The pertinent information and details provided in these documents have either been incorporated into the W3SES Emergency Plan and/or Implementing Procedures, or have been appropriately referenced.
- e. Coordination and liaison with offsite organizations and agencies having radiological emergency responsibilities insures compatibility and proper interfacing with this plan.
- f. Governmental agency interrelationships with the W3SES Emergency Plan include:
- 1. St. Charles Parish Emergency Operations Plan.
I
- 2. St. John the Baptist Parish Preparedness Plan for Emergency Operations.
- 3. State of Louisiana, Louisiana Peacetime Radiological Response Plan and Waterford 3 Attachment.
- 4. U.S. Nuclear Regulatory Commission, Region IV Response Plan.
- 5. U.S. Department of Energy, Federal Radiological and Monitoring Assessment Plan.
- 6. Federal Emergency Management Agency, Region VI, Emergency Response Team Plcin.
2-5 Rev. 048
W3SESEMERGENCYPLAN FIGURE 2-1 WATERFORD PROPE.R TY A-2-1 Rev. 048
W3 SES EMERGENCY PLAN FIGURE 2*2 LOW POPULATION ZONE CULTURAL FEATURES DSDD I < I @
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W3 SES EMERGENCY PLAN FIGURE 2-3 WATERFORD 3 SITE la 1 l l I 1 l I I I I I l l
- 1. Reactor Contain.men! Bldg.
- 2. Reactor Auxiliaiy Bldg.
- 3. TUrblne Genera1°' Bldg,
- 4. Condensate Polisher Bldg.
- 5. Service Bldg. (Partial)
- 6. Protected Area
- 7. Maintenance Support Bldg.
- 8. Parking Area 1
- 9. Parking Atea 2 10'. Construction Area 11 . Administration Bldg.
- 12. Fuel Handlfng Bldg.
- 13. Fire Pump House
- 14. Watar Treatment Bldg.
- 15. Chlllar*Stdg.
- 16. PAB
- 17. In Processing Bldg,
- 18. Credit Union Bldg.
- 19. Temporary Assembly Bldg,
- 20. Warehouse 2B
- 21. Warehouse 78
- 22. Skills Tr.iln!ng Center
- 23. RIVerRoad (LA 18)
- 24. Heficopler Landing Pad
- 25. Plant Perimeter Fence
- 26. Access Road
- 27. Radioadive Waste Storage
- 28. Goneration Support Bldg,
- 29. Parking Area 3
- 30. Parklng Area 4
- 31. Parking Area 5
- 32. Information Tech~y
- 33. Low Li:!Vel Radioactive Waste Bldg.
- 34. construction Support Bldg.
- 35. Westsid$Access
- 36. Plant Entrance
- 37. Old Steam Genera or Storage Bldg.
- 38. Vehfde Trap
- 39. Parking Area 6
- 40. Parl<lng Area 7 41 . Parking Area 8
- 42. RCA Materials Area
- 43. ISFSI
W3 SES EMERGENCY PLAN FIGURE 2-4 PERMANENT RESIDENTS WITHIN 10 MILE EPZ
- ~m9ston ,J / ./ / N Ascension /. NNW /
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Permanent Resi dents within 10 Mile EPZ Miles Subtotal by Ring Cum ul ative Total 0-2 1 682 1682 2 -5 12,477 14,159 5-10 71,060 85,219 10 - EPZ 2,658 87,877 Total: 87,877 A-2-4 Rev. 048
W3SESEMERGENCYPLAN FIGURE 2-5 PERMANENT RESIDENTS WITHIN 50 MILE EPZ
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!II 115,134 1 NNW I East Feliciana I ~
I Peart River Permanent Residents within 50 M ile EPZ Miles Subtotal by RI ng Cumulative Total 0 - EPZ 87,877 87,877 EPZ- 20 284,017 371,894 20-30 635,007 1,006,901 30-40 481,513 1,488,414 40-50 509,596 1,998,010 Total : 1,998,010 A-2-5 Rev. 048
W3 SES EMERGENCY PLAN FIGURE 2-6 THE REGION WITHIN 10 MILES OF WATERFORD 3
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W3 SES EMERGENCY PLAN FIGURE 2-8 EXCLUSION AREA BOUNDARY (EMERGENCY PLANNING SITE BOUNDARY) NORTH NNE N
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WATERFORD 3 SES EMERGENCY PLAN 3.0
SUMMARY
OF THE EMERGENCY PLANNING PROGRAM The W3SES Emergency Planning Program consists of three coordinated documents. A description of each document, and a content outline of the Emergency Plan and Implementing Document are listed below.
- Final Safety Analysis Report Section 13.3. This document clearly states Entergy Operations, Inc.
policies and commitments to nuclear accident response, satisfying submittal requirements of 10CFR50.34, and Appendix E to 10CFR50. Emergency Plan This document establishes the concepts, evaluation and assessment criteria and protective actions necessary in order to limit and mitigate the cpnsequences .of potential or actual emergencies. It incorporates necessary prearrangements, direction and organizations to mitigate the consequences of a W3SES emergency in order to protect the health and safety of the general public and site personnel.
- a. Emergency Plan content In general the Emergency Plan contains information concerning:
- 1. Detection of an emergency.
- 2. Classification of an eme~gency.
- 3. Notification of responding organizations.
- 4. Activation of responding organizations.
- 5. Assessment actions.
- 6. Protective actions.
- 7. Corrective actions.
- 8. Rescue and reentry operations.
- 9. ~ecovery operations.
I
- 10. Emergency preparedness maintenance.
Emergency Plan Implementing Document. These documents provide detailed significant information for the use of the various emergency response and maintenance organizations. Also, it consolidates and integrates: specific material detailed in such documents as the Waterford 3 Emergency Plan, and State and Parish Emergency Plans.
- a. Implementing Document Content ~-,**
In general the Implementing Document provides procedures or instructions which describe:
- 1. The criteria or spe<;:ific emergency action levels to be used to recognize and declare each ~m,ef:gency classification.*
- 2. W3SES emergency communications and notifications system.
3-1 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN 3.0 (Cont'd.)
- 3. Emergency actions to be taken by appropriate plant personnel to assess the emergency conditions and provide steps to be taken to correct and/or mitigate the situation.
- 4. Detailed emergency organizations, duties and responsibilities of essential personnel, facilities, equipment, etc., necessary to implement the Emergency Plan.
- 5. Actions to be taken for emergency assistance.
- 6. Actions necessary to maintain a state of emergency readiness.
3.1 Classification and Implementation 3.1.1 Emergency Classifications Emergencies are grouped into a four-level, mutually exclusive classification scheme. The four classes of emergencies are: (1) Unusual Event, (2) Alert, (3) Site Area Emergency and (4) General Emergency. Section 4.0 contains a more detailed discussion of the classifications of emergencies. It also contains examples of specific initiating emergency conditions and emergency action levels. 3.1.2 Implementation The Emergency Plan establishes an organization capable of responding to the entire spectrum of emergencies from minor localized emergencies to major emergencies involving action by the offsite response agencies. Implementation of the Emergency Plan and its associated Implementing Document is accomplished through organizational control and coordination of emergency
,response organizations. Provisions are made for rapid notification of appropriate portions of the response organization and for expanding the response organization if the situation dictates.
3.1.2.1 Emergency Coordination - Initial Initial authority and responsibility to coordinate the implementation of the Emergency Plan is with the Shift Manager (SM) who becomes the Emergency Director (ED). The SM also has the responsibility and authority for coordinating all emergency management activities until relieved by the EOF Emergency Director, who then becomes the ED. Upon arrival of the Duty EOF Emergency Director, the overall authority and responsibility to coordinate the implementation of the Emergency Plan are transferred from the SM to the Duty EOF Emergency Director. The Duty EOF Emergency Director, as the Emergency Director, has the responsibility and authority for coordinating all emergency management activities. Onsite responsibilities are carried out by the Emergency Plant Manager who reports to the Emergency Director. Responsibilities of the Emergency Director include: 3-2 Rev. 048
I WATERFORD 3 SES EMERGENCY PLAN 3.1.2.1 (Cont'd.)
- a. Accident Assessment - Assessment is based on plant systems, data, effluent parameter values, other specific information and judgment of the Emergency Plant Manager who reports to the Emergency Director. It also considers reports from emergency teams and from supporting organizations which continue throughout the emergency.
- b. Accident Control - The normal operating organization is initially responsible for implementing emergency actions in accordance with assigned response functions. Emergency response functions are also assigned to additional plant staff personnel who are rapidly alerted and mobilized to augment, or relieve, the operating personnel of emergenc~ duties as deemed appropriate by the Emergency Plant Manager who reports to the Emergency Director and in accordance with the Emergency Plan Implementing Procedures.
- c. Personnel Protection - Elery effort will be made to minimize the risk to persons onsite and offsite.
*;
(1) Onsite - Personnel will be evacuated from any high radiation or hazardous area. Personnel entering high radiation areas to perform emergency functions will utilize appropriate radiation protection equipment, and exposure will be as low as reasonably achievable. The Emergency Plant Manager and Emergency Director are responsible for authorizing emergency workers to receive doses in excess of 10CFR20 limits and, to the extent practicable, coordinating with the NRC prior to issuing such authorization. Onsite facilities are available for monitoring, decontamination, and first aid. In addition, special arrangements have been made with local hospitals for the treatment of injured and/or contaminated or overexposed personnel. (2) Offsite - When an event occurs which falls within one of the four emergency classes described in Section 3.1.1, Louisiana Department of Environmental Quality (LDEQ), Governor's Office of Homeland Security & Emergency Preparedness (GOHSEP) and the risk parishes (St. Charles and St. John the Baptist) Office of Emergency Preparedness will be contacted and appropriate protective action recommendations made. If protective actions for the public are in order, the Emergency Director will make appropriate recommendations to the risk parishes (St. Charles and St. John the Baptist), the Governor's Office of Homeland ' Security & Emergency Preparedness and the Louisiana Department of Environmental Quality. 3-3 Rev.048 c
WATERFORD 3 SES EMERGENCY PLAN 3.1.2.2 Emergency Coordination - Support When required, additional support is provided by the Waterford 3 Nearsite Emergency Organization, which is responsible for coordinating offsite emergency management activities and providing or obtaining assistance for the Waterford 3 Onsite Emergency Organization. The Emergency Director directs the Nearsite Emergency Organization. He is responsible for activating and directing the Emergency Operations Facility and ensuring that the functional groups provide a coordinated response in support of the Onsite Emergency Organization. 3.1.2.3 Offsite Agency Support The Emergency Director is initially responsible for notifying and coordinating the response of the local services support groups and agencies. When the emergency situation warrants, the EOF Emergency Director will declare the Emergency Operations Facility operational and assume the responsibility for offsite agency coordination. I The Secretary of the Department of Environmental Quality, through the Louisiana Departmental of Environmental Quality (LDEQ), is responsible for recommendation of the necessary protective actions specified in the State of Louisiana Peacetime Radiological Response Plan and its Waterford 3 Attachment, including notification and coordination of Federal, State and local assistance agencies. A description of the assistance expected from Offsite Response Organizations (OROs), including hostile action events as required by 10 CFR 50 Appendix E.iv.A.7 is included in Appendix C. Section 5.0 contains a more detailed description of the duties and responsibilities of the above organizations and individuals. 3.2 Response Actions - Specific measures are taken for each of the four classes of emergency defined in Section 4.0 of this plan. The performance of these emergency measures follows a predetermined logic. In all cases, emergency measures begin with recognition, assessment and declaration of the emergency. This includes prompt action to evaluate any potential risk to public health and safety. Notification and activation of onsite and offsite response organizations follows. Upon notification, Utility response organizations have the capability to immediately support and perform tasks delineated in the Implementing Document, while offsite response organizations have the authority and capability to take immediate predetermined actions based on Utility information and recommendations. Detailed explanations of emergency measures for both onsite and offsite organizations are found in Section 6.0 of this Emergency Plan. 3.3 Recoverv Actions - Recovery actions are directed toward restoring the plant to pre-emergency conditions once corrective and protective actions have established control of the emergency situation. A recovery organization will be established by combining resources of both onsite and offsite emergency organizations. The structure of this organization will be determined by the nature and magnitude of the emergency. For example, for events of a minor nature, normal plant organizations may be adequate, 3-4 Rev. 048 L__
WATERFORD 3 SES EMERGENCY PLAN whereas a significantly larger event may require Federal and private support. Detailed explanations of Recovery concepts are found in Section 9.0 of this Emergency Plan. 3.4 Maintenance of the Planning Program - Planning program maintenance consists of mechanisms designed to ensure a high state of emergency preparedness. All aspects of onsite and offsite response are regularly reviewed and tested in accordance with appropriate procedures and applicable State and Federal regulations. Almost all of the various departments at W3SES are involved in the planning program maintenance mechanism. The Vice President, Operations, Waterford 3, however, has ultimate responsibility for Emergency Plan management and direction. Actual maintenance coordination is the responsibility of the Emergency Planning Coordinator. He shall ensure, as a minimum, the following:
- 1. Emergency Plan and Implementing Document are reviewed on an "on-going basis."
- 2. Emergency Plan, Implementing Document and FSAR Section 13.3 are reviewed for correctness and compliance with applicable State and Federal regulations at least annually.
,_ 3. Ensure NRC review of revisions, as required.
- 4. Ensure a comprehensive training program is maintained for all onsite and offsite response personnel.
- 5. All emergency-oriented equipment, emergency kits, communications devices, radiation monitoring devices, designated vehicles, etc., are complete, maintained in operating condition, and calibrated where necessary.
- 6. Practice drills are held on a regular basis, in order to perform training and locate deficiencies.
- 7. Communications links are tested at required intervals.
- 8. Offsite warning systems are tested at required intervals and are maintained in operating condition.
- 9. Letters of agreement between the Utility and offsite agencies/organizations are reconfirmed annually.
- 10. A review/audit of emergency preparedness is conducted by persons who have no direct responsibility for the implementation of the emergency preparedness program. A review will be performed as necessary, based on an assessment by the licensee against performance indicators, and as soon as reasonably practicable after a change occurs in personnel, procedures, equipment, or facilities that potentially could adversely affect emergency preparedness, but no longer than 12 months after the change. In any case, all elements of the emergency preparedness program must be reviewed at least once every 24 months.
All deficiencies found during inventories, inspections, drills, audits, etc., will either be resolved immediately or documented for corrective action by the Emergency Planning Coordinator. A report of each inventory, inspection, drill, audit, etc., ircluding documented deficiencies will be prepared and reviewed by the Emergency Planning Coordinator (or designee). As required by the Emergency Plan Supporting Procedures, the Emergency Planning Coordinator will submit appropriate reports to management. 3-5 Rev.048
WATERFORD 3 SES EMERGENCY PLAN Cognizant department heads will assign personnel to correct deficiencies and shall ensure that corrective actions are initiated within 30 days of the assignment of the deficiency to their department. 3.4 (Cont'd) The Emergency Planning Coordinator shall ensure all elements of the onsite and offsite emergency organization receive the appropriate controlled revisions to the Emergency Plan and Implementing Document in a timely manner. 3-6 Rev.048
WATERFORD 3 SES EMERGENCY PLAN 4.0 CLASSIFICATION OF EMERGENCIES For the purpose of classifying emergencies, Waterford 3 and the State of Louisiana utilize a method outlined in NEI 99-01, in which emergencies are grouped into a four-level response scheme. This approach to classification has been expanded and detailed to encompass the entire spectrum of possible emergency situations that may arise at Waterford 3. Each of the four classifications is associated with a particular set of immediate actions to be taken. The Waterford-3 Emergency Action Levels are reviewed with State and Parish authorities on an annual basis. The four emergency classes are: (1) Unusual Event, (2) Alert, (3) Site Area Emergency and (4) General Emergency. Each represents a predetermined response approach, for both onsite as well as offsite personnel and for agencies, consistent with Federal guidelines for minimum level protective action mobilization. The emergency classifications have not been selected so as to infer any immediate need to implement protective actions, but rather to ensure that adequate time is available to confirm in-plant readings through implementation of assessment measures. However, distinct ties between the emergency classification scheme and protective action recommendations to offsite agencies at a General Emergency are found in the Implementing Procedures. Dose assessment values, along with other plant status assessment findings, are reported to offsite officials as inputs for their decision methodology relating to whether protective actions for the public are to be implemented. The plant method for relating radionuclide releases to protective action guidelines (PAGs) is specified in the Emergency Plan Implementing Procedures. Waterford-3 maintains the capability to assess, classify and declare an emergency condition within 15 minutes after the availability of indications to plant operators that an emergency action level has been exceeded. Additionally, personnel are trained to promptly declare the emergency condition as soon as. possible following identification of the appropriate emergency classification level. 4.1 Waterford 3 Classification System The four emergency classes for Waterford 3 are as stated above: Unusual Event, Alert, Site Area Emergency and General Emergency. Each classification is characterized by Initiating Conditions (ICs). ICs consist of plant conditions and specific plant parameters (i.e., instrument readings and system status indications, etc.) that are used to denote the emergency classification and require the implementation of emergency measures such as notifications and mobilization of resources. Generally, the ICs pertain to degradation of the reactor coolant system and/or its safety-related systems. Many of the ICs refer to the plant Technical Specifications or are based on problems arising within the Protected Area or vital areas. Many accidents may be classified at first in a lower category and then escalated to a higher classification if the situation deteriorates; however, a conservative philosophy for classification is used to declare the highest classification for which an IC has been exceeded. For example, a Site Area Emergency is declared immediately if a Site Area Emergency IC is exceeded, without having previously declared an Unusual Event or Alert. Also, following the restoration of normal plant conditions from an upper grade emergency, declassification of the emergency should take place with an associated reduction in the emergency response organizations. The classification system for Waterford 3 is intended to provide early and prompt notification of events which could lead to serious consequences, both onsite and/or offsite, such that appropriate response actions can be taken. 4-1 Rev.048
WATERFORD 3 SES EMERGENCY PLAN 4.1.1 Unusual Event This classification is characterized by events in progress or which have occurred indicating a potential degradation of the level of safety of the plant or indicate a security threat to facility protection has been initiated. No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs. Its purpose is to: (1) ensure that the first step in any response later found to be necessary has been carried out (i.e., offsite notification), (2}bring the operating staff to a state of readiness and (3) provide systematic handling of Unusual Event information traffic and decision-making. The occurrence of an Unusual Event normally involves only response from the plant staff personnel, but can involve assistance from offsite groups such as medical facilities, law enforcement agencies and fire departments. Agreements have been reached with these groups to provide assistance, if required. The Louisiana Department of Environmental Quality, Governor's Office of Homeland Security & Emergency Preparedness, St. Charles Parish, St. John the Baptist Parish and NRC would receive notification of an Unusual Event. The initiating conditions are listed in Table 4-1; however, the Shift Manager can declare an Unusual Event if in his judgment the plant status warrants such a declaration. Training stresses the need to analyze all minor events in the light of their potential for further degradation of the level of safety of the plant and not to hesitate to declare this particular emergency class. Actions to be taken for this emergency class are described in detail in Section 6.0 of this plan. 4.1.2 Alert This classification is characterized by events in progress or which have occurred involving an actual or potential substantial degradation of the level of safety of the plant or a security event that involves probable life threatening risk to site personnel or damage to site equipment because of hostile action. Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels. Its purpose is to: (1) assure that emergency personnel are readily available to respond if the situation becomes more serious, or available to perform confirmatory radiation monitoring if required, and (2) provide offsite authorities current status information. An Alert involves activation of the Onsite Emergency Organization and the Nearsite Emergency Organization. The Louisiana Department of Environmental Quality, Governor's Office of Homeland Security & Emergency Preparedness, St. Charles Parish, St. John the Baptist Parish, NRC and other offsite agencies would ~e notified. Agreements have been reached with these offsite groups to provide assistance, if required. The initiating conditions are listed in Table 4-1; however, the Shift Manager/Emergency Director can declare an Alert if in his judgment the plant status warrants such a declaration. The Emergency Director specifically considers escalation from the Unusual Event to the Alert class if, in his judgment, the situation is not likely to be resolved rapidly or it is likely to deteriora~e. 4-2 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN 4.1.3 Site Area Emergency This classification is characterized by events in progress or which have occurred involving actual or likely major failures of plant functions needed for protection of the public or hostile action that results in intentional damage or malicious acts; 1) toward site personnel or equipment that could lead to the likely failure of or; 2) that prevent effective access to equipment needed for the protection of the public. Any releases are not expected to result in exposure levels which exceed EPA Protective Action Guideline exposure levels beyond the site boundary. Its purpose is to: (1) ensure that response centers are manned; (2) ensure that monitoring teams are dispatched, as appropriate; (3) ensure that personnel required for evacuation of nearsite areas are at duty stations, if the situation becomes more serious; (4) provide consultation with offsite authorities; and (5) provide updates for the public through offsite authorities. A Site Area Emergency involves response from all Waterford 3 emergency organizations as well as assistance from other offsite organizations. The Louisiana Department of Environmental Quality, Governor's Office of Homeland Security & Emergency Preparedness, St. Charles Parish, St. John the Baptist Parish, NRG and other offsite agencies would be notified. The initiating conditions are listed in Table 4-1; however, the Emergency Director, when the EOF becomes operational and responsibility is transferred, declares a Site Area Emergency when in his judgment plant conditions exist that warrant the activation of emergency response centers and precautionary public notification. 4.1.4 General Emergency This classification is characterized by events in progress or which have occurred involving actual or imminent substantial core degradation or melting with potential for loss of containment integrity or hostile action that results in an actual loss of physical control of the facility. Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels offsite for more than the immediate site area. Its purpose is to: (1) initiate predetermined protective actions for the public, (2) provide continuous assessment of the information from licensee and offsite organization measurements, (3) initiate additional measures as indicated by actual or potential releases, (4) provide consultation with offsite authorities and (5) provide updates for the public through offsite authorities. A General Emergency involves response from offsite agencies in accordance with the Louisiana Peacetime Radiological Response Plan. The Louisiana Depa.rtment of Environmental Quality, Governor's Office of Homeland Security & Emergency Preparedness, St. Charles Parish, St. John the Baptist Parish, NRC, and other offsite agencies will be notified. The Nearsite Emergency Organization response would be as described in Section 6.0. The initiating conditions are listed in Table 4-1; however, the EOF Emergency Director, when the EOF becomes operational and responsibility is transferred, declares a General Emergency if in his judgment the plant status warrants such a declaration. 4-3 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN 4.2 State and Parish Classification System The State of Louisiana, St. Charles Parish, and St. John the Baptist Parish within the 10-mile Emergency Planning Zone of Waterford 3 use the same system to classify incidents from a fixed nuclear reactor facility as the one described above for Waterford 3 (i.e., Unusual Event, Alert, Site Area Emergency and General Emergency). They are correlated to the EPA Protective Action Guidelines, and in a sense mainly apply to radiological offsite emergencies. However, response actions developed for this category of emergency may enhance and even improve upon response capabilities of the State and local governments for other types of emergencies that may occur. The State of Louisiana has prepared a Peacetime Radiological Response Plan that in its entirety is a supplement to the Louisiana Emergency Operations Plan. The Louisiana Peacetime Radiological Response Plan - Attachment 1, maintained as a separate document, is site-specific to Waterford 3 and is intended to provide offsite coordination of emergency response .. 4.3 Spectrum of Postulated Accidents A broad range of possible off-normal and accident conditions has been postulated and taken into consideration in deriving response actions to occur at the Waterford site. These include radiological and non-radiological events that range from minor occurrences, which may be anticipated during the life of the plant, to highly improbable events, which could affect members of the general public. Chapter 15 of the Waterford 3 Steam Electric Station Final Safety Analysis Report (FSAR) contains a summary of the events that have been postulated for the site. 4.3.1 Classification of Postulated Accidents The events postulated in Chapter 15 of the Waterford 3 Steam Electric Station FSAR may be categorized by one of the four emergency classifications. In many cases, the classification assigned initially may undergo escalation to the next higher classification depending on the severity of the accident. A complete discussion of these events may be found in the FSAR. The operating shift personnel under the direction of the Shift Manager perform the initial assessment and classification of potential in-plant and offsite consequences. These assessment times should last no longer than 15 minutes. The shift personnel then activate the Onsite Emergency Organization in accordance with the level of emergency response required, thereby providing additional manpower as the emergency evolves. Maps indicating the EAB, 10-mile EPZ, and the 50-mile EPZ are included in Section 7 of the Emergency Plan. Table 4-3 relates these accidents to detection capabilities. 4-4 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN 4.3.2 Detection of Postulated Accidents The detection of abnormal conditions, abnormal situations and accidents by station personnel may be a result of alarms, instrumentation readings, activation of interlocks, offsite information, personal observation, recognition through experience or a combination thereof. The first person to detect such conditions
- has been trained to immediately notify the Shift Manager who is charged with the responsibility for initial evaluation and classification of the emergency.
Table 4-4 lists hypothesized accidents, and the important instrumentation that is utilized to detect each of the various classifications of accidents. 4.3.3 Toxic Chemical Releases A comprehensive evaluation of the quantities and location of toxic chemicals stored or transported in the vicinity of the site has been performed and presented in detail in Section 2.2 of the FSAR. Approximately 200 sources of potentially toxic chemicals were identified. An analysis to determine the possible concentration of these chemicals that would occur onsite and in the Control Room as a result of a postulated release to the environment was performed. The analysis included an estimate of the concentration onsite and in the Control Room as a function of time after release for a broad range of meteorological conditions. For those chemicals which are presented in Table 2.2.4 of the FSAR, special design and/or emergency planning provisions have been made to: (1) ensure the safety of workers, and (2) ensure the habitability of the Control Room. For those events where the acute toxicity limits could be exceeded in the Control Room and the time between human detection and the acute toxicity limits is less than two minutes, special design provisions for automatic Control Room isolation and monitoring of the toxic chemicals have been provided. Only sources of chlorine and anhydrous ammonia have this potential, and both chlorine and ammonia detectors have been provided which can automatically isolate the Control Room and record chemical concentrations at their locations. The detectors and their mode of operation are described in subsection 6.4.4.2 of the FSAR. 4-5 Rev.048
WATERFORD 3 SES EMERGENCY PLAN TABLE 4-1
SUMMARY
OF INITIATING CONDITIONS Category A-Abnormal Radiation Levels/Radiological Effluents This category encompasses the spectrum of potential uncontrolled radionuclide releases via liquid or gaseous effluents for all modes of operation. It also includes other incidents related to high levels of radioactivity, but which may not result in a release to the environment. Potential sources of radionuclide releases are from the Reactor Auxiliary Building (RAB), Reactor Containment Building (RCB) and Fuel Handling Building (FHB). Monitored gaseous release paths include the plant vent stack, FHB exhaust plenums and secondary steam piping. Monitored liquid release paths include the liquid waste management discharge, circulating water discharge, dry cooling tower sumps and industrial waste sump. The ICs iliithin this category are keyed to Radiation Monitoring System (RMS) indications, radiological survey results and offsite dose assessment calculations. The initiating conditions within this category are as follows: UNUSUAL EVENT
- 1. Any release of gaseous or liquid radioactivity to the environment :>- 2 times the radiological effluent ODCM limits for.:::_ 60 minutes. *
- 2. Unplanned rise in plant radiation levels.
ALERT
- 1. Any release of gaseous or liquid radioactivity to the 1 environment> 200 times the radiological effluent ODCM limits for .:::_15 minutes.
- 2. Damage to irradiated fuel or loss of water level that has resulted or will result in uncovering of irradiated fuel outside the reactor vessel.
- 3. Rise in radiation levels within the facility that impedes operation of systems required to maintain plant safety functions.
SITE AREA EMERGENCY
- 1. Offsite dose resulting from an actual or imminent release of gaseous radioactivity > 100 m R TEDE or 500 mR CDE Thyroid for the actual or projected duration of the release.
GENERAL EMERGENCY
- 1. Offsite dose resulting from an actual or imminent release of gaseous radioactivity>
1000 mR TEDE or 5000 mR CDE Thyroid for the actual or projected duration of the release using actual meteorology. Rev.048 A-4-1 (1 of 9)
WATERFORD 3 SES EMERGENCY PLAN TABLE 4-1 (Continued)
SUMMARY
OF INITIATING CONDITIONS CATEGORY C- Cold Shutdown/Refueling System Malfunction
\
This category encompasses the spectrum of events related to the reactor and its supporting systems that may occur in the shutdown and refueling modes. These include RCS leakage and loss of reactor vessel inventory events as well as those events dealing with power losses. This category also encompasses events that directly affect the integrity of the reactor core when in cold shutdown or refueling. This includes inadvertent criticality and loss of decay heat removal capability. The initiating conditions within this category are as follows: UNUSUAL EVENT
- 1. RCS leakage.
- 2. Unplanned loss of RCS/reactor vessel inventory.
- 3. Unplanned loss of decay heat removalcapability with irradiated fuel in the reactor vessel.
- 4. AC power capability to safety busses reduced to a single power source~ 15 minutes such that any additional single failure would result in station blackout.
- 5. Loss of required DC power ~ 15 minutes.
- 6. Inadvertent criticality.
- 7. Loss of all onsite or offsite communications capabilities.
ALERT
- 1. Loss of RCS/reactor vessel inventory.
- 2. Inability to maintain plant in cold shutdown.
- 3. Loss of all offsite and all onsite AC power to safety busses ~ 15 minutes.
Rev.048 A-4-2 (2 of 9)
WATERFORD 3 SES EMERGENCY PLAN TABLE 4-1 (Continued)
SUMMARY
OF INITIATING CONDITIONS CATEGORY .C- Cold Shutdown/Refueling System Malfunction (Cont'd) SITE AREA EMERGENCY
- 1. Loss of RCS/reactor vessel inventory affecting core decay heat removal capability.
GENERAL EMERGENCY
- 1. Loss of RCS/reactor vessel inventory affecting fuel clad integrity with containment challenged.
Rev.048
- A-4-3 (3 of 9)
WATERFORD 3 SES EMERGENCY PLAN TABLE 4-1 (Continued)
SUMMARY
OF INITIATING CONDITIONS CATEGORY E - ISFSI Malfunction This category addresses events of sufficient magnitude that a loaded spent fuel dry cask storage confinement boundary is damaged or violated .. UNUSUAL EVENT
- 1. Damage to a loaded cask confinement boundary.
r I
,/
Rev.048 A-4-4 (4 of 9)
WATERFORD 3 SES EMERGENCY PLAN TABLE 4-1 (Continued)
SUMMARY
OF INITIATING CONDITIONS CATEGORY F - Fission Product Barrier Degradation This category addresses losses and potential losses of the three fission product barriers - fuel clad, RCS and containment. The category is designed for events in the power operations, startup, hot standby and hot shutdown m odes of operation. The initiating conditions within this category are as follows: UNUSUAL EVENT
- 1.
- Any Loss or any potential loss of containment.
ALERT
- 1. Any Loss or any potential loss of either fuel clad or RCS.
SITE AREA EMERGENCY
- 1. Loss or potential loss of any two barriers.
GENERAL EMERGENCY
- 1. Loss of any two barriers and loss or potential loss of the third barrier.
Rev. 048 A-4-5 (5 of 9)
WATERFORD 3 SES EMERGENCY PLAN TABLE 4-1 (Continued)
SUMMARY
OF INITIATING CONDITIONS CATEGORY H - Hazards and Other Conditions Affecting Plant Safety This category encompasses the spectrum of man-caused or non-naturally occurring hazards that jeopardize the level of safety of the plant in all modes of operation. The ICs are keyed to offsite notifications or personal observation and assessment. This category also encompasses the spectrum of naturally occurring events that jeopardize the level of safety of the plant. The ICs are keyed to specific instrument indications, offsite notifications or personal observation and assessment. This category also encompasses the spectrum of security infractions as addressed in the Security Contingency Plan. The ICs are keyed to notification from the security force or another credible source of a site specific credible threat. This category is the location for the miscellaneous ICs that are provided to al low for Emergency Director judgment classifications. The initiating conditions within this category are as follows: UNUSUAL EVENT
- 1. Confirmed security condition or threat which indicates a potential degradation in the level of safety of the plant.
- 2. Other conditions exist which in the judgment of the Emergency Director warrant declaration of an Unusual Event.
- 3. Fire within the Protected Area not extinguished within 15 minutes of detection or explosion within the Protected Area.
- 4. Release of toxic, corrosive, asphyxiant or flammable gases deemed detrimental to normal plant operations.
- 5. Natural or destructive phenomena affecting the Protected Area.
ALERT I
- 1. Hostile Action within the Owner Controlled Area or airborne attack threat.
- 2. Other conditions exist which in the judgment of the Emergency Director warrant declaration of an Alert.
- 3. Control Room evacuation has been initiated.
- 4. Fire or Explosion affecting the operability of plant safety systems required to establish or maintain safe shutdown.
Rev.048 A-4-6 (6 of 9)
WATERFORD 3 SES EMERGENCY PLAN TABLE 4-1 (Continued)
SUMMARY
OF INITIATING CONDITIONS CATEGORY H - Hazards and Other Conditions Affecting Plant Safety (Cont'd) ALERT (Cont'd)
- 5. Access to a Vital Area is prohibited due to toxic, corrosive, asphyxiant or flammable gases which jeopardize operation of operable equipment required to maintain safe operations or safely shutdown the reactor.
- 6. Natural or destructive phenomena affecting Vital Areas.
SITE AREA EMERGENCY
- 1. Hostile Action within the Protected Area.
- 2. Other conditions exist which in the judgment of the Emergency Director warrant declaration of a Site Area Emergency.
- 3. Control Room evacuation has been initiated and plant control cannot be established.
GENERAL EMERGENCY
- 1. Hostile Action resulting in loss of physical control of the facility.
- 2. Other conditions exist which in the judgment of the Emergency Director warrant declaration of a General Emergency.
Rev.048 A-4-7 (7 of 9)
WATERFORD 3 SES EMERGENCY PLAN TABLE 4-1 (Continued)
SUMMARY
OF INITIATING CONDITIONS CATEGORY S-System Malfunction This category encompasses the spectrum of events related to the reactor and its supporting systems that may occur in the power operations, startup, hot standby and hot shutdown operating modes. In general, the ICs relate to equipment or system malfunctions or failures. The ICs include RCS leakage, loss of Control Room instrument indiqations and failure of the Reactor Protection System as well as those events dealing with power losses. This category also includes inadvertent criticality and loss of decay heat removal capability ICs. The initiating conditions within this category are as follows: UNUSUAL EVENT
- 1. Loss of all offsite AC power to safety busses :::, 15 minutes.
- 2. Unplanned loss of safety system annunciation or indication in the Control Room:::, 15 minutes.
- 3. RCS Leakage.
- 4. Loss of all onsite or offsite communications capabilities .
. 5. Fuel clad degradation.
- 6. Inadvertent criticality.
- 7. lnaoility to reach required operating mode within Technical Specification limits.
ALERT
- 1. AC power capability to safety busses reduced to a single power source:::. 15 minutes such that any additional single failure would result in station blackout.
- 2. Automatic trip fails to shutdown the reactor and the manual actions taken from the reactor control console are successful in shutting down the reactor.
- 3. Unplanned loss of safety system annunciation or indication in the Control Room with either (1) a Significant Transient in progress, or (2) compensatory indicators unavailable.
Rev. 048 A-4-8 (8 of 9)
WATERFORD 3 SES EMERGENCY PLAN TABLE 4-1 (Continued)
SUMMARY
OF INITIATING CONDITIONS CATEGORY S - System Malfunction (Continued) SITE AREA EMERGENCY
- 1. Loss of all offsite and all onsite AC power to safety busses ~ 15 minutes.
- 2. Automatic trip fails to shutdown the reactor and manual actions taken from the reactor control console are not successful in shutting down the reactor.
- 3. Loss of all vital DC power ~ 15 minutes.
- 4. Inability to monitor a Significant Transient in progress.
GENERAL EMERGENCY
- 1. Prolonged loss of all offsite and all onsite AC power to safety busses.
- 2. Automatic trip and all manual actions fail to shutdown the reactor and indication of an extreme challenge to the ability to cool the core exists.
Rev. 048 A-4-9 (9 of 9)
WATERFORD 3 SES EMERGENCY PLAN TABLE 4-2 EXCLUSION AREA BOUNDARY CALCULATED EXPOSURES Information which resided here in earlier revisions has been deleted. This information is located in the Waterford 3 FSAR Chapter 15. Rev.048 A-4-10 (1 of 1)
Rev. 048 A-4-11 (1 of 5) WATERFORD 3 SES EMERGENCY PLAN TABLE 4-3 (Continued) MONITORS Event Readout Isotopic Concentrations or FSAR Accidents Tugg Range Function Location Location Dose Rate at Monitor Location
- 5. Containment High 1 -101:1 R/hr. Monitor Continuously +99 ft. MSL containment at 90° 1o:i R/hr.
Range Accident containment record and alarm and 270°. Monitors. accident in Control Room. conditions.
- 3. Decrease in Reactor Coolant System Inventory a) Failure of Letdown 1. Area monitors (see .01 to 1000 Alarm at 5 Alarm and -4 ft. MSL in the CVCS area of 3 x 10:i mR/hr (104 Ci in 10:i ft.;;s and Line Outside Table mR/hr. mR/hr. continuously RAB (see Figure 12.3-3 of 0.5 MeV/dis and 0.1 finite cloud Containment' with 12.3-2 of FSAR). record in Control FSAR). correction).
Spike Room. Alarm locally.
- 2. Plant Stack 10- 1 to10- 1 Continuous Plant Alarm and Plant Stack downstream of filters. Noble gases: 3 uCi/cc Iodines:
effluent monitor. uCi/cc of noble Stack effluent continuously 0.3 uCi/cc (1 o4 Ci of NG and 1o3 Ci gases; 10-9 to monitor. record in Control of iodines in 105 ft. 3 and no filter). 10-3 uCi/cc of Terminate Room. Alarm iodines. containment locally. purge.
- 3. Airborne duct 10- 1 to 10-1 Alarm at Alarm and RAB monitor B (west of col M- Noble gases: l uCi/cc Iodines:
monitor (see Item uCi/cc of noble 2 x 1a*8 uCi/cc of continuously 5A, see Figure 12.3-3 of FSAR). 0.3 uCi/cc (same as above). 8 of Table 12.3-3 gases; 10-9 to iodines in RAB. record in Control ofFSAR). 10-3 uCi/cc of Room Alarm iodines. locally.
- 4. Plant Stack Wide 10- 1 to 1o:i Monitor Plant Continuously On +46 MSL Plant Stack 3 uCi/cc of NG.
Range Gas uCi/cc of noble Stack Gas record and alarm downstream of filters. Accident Monitor gas. activity. in Control Room. b) Loss of Coolant 1. Area Monitors 5x1o:i mR/hr Isolate Alarm and On +46 and +21 ft. MSL of outer 1al:! mR/hr (1 al:! Ci mixed in 10° ft.;;s Accident ARM-IRE-5024S to containment continuously wall of steam generator shield with 0.5 MeV/dis and 0.1 finite cloud 5027S (see Table purge. record in Control (see Figure 12.3-6 and 7 of correction). 12.3-2 ofFSAR). Room.Alarm FSAR). locally.
- 2. SBVS Exhaust 10- 1 to10- 1 Monitor plant Alarm and Plant Stack downstream of filters. Noble Gases: 10 uCi/cc Monitor (same as uCi/cc of noble effluent. continuously Iodines: 0.1 uCi/cc (1 o9 Ci of NG and Plant Stack) gases; 10-9 to Terminate record in Control iodines_ in 106 ft.3 and leaking of 10-3 uCi/cc of containment Room. Alarm 0.5%/day into an exhaust of 104 cfm ibdines. purge. locally. through SBVS filters with a DF=100).
Rev. 048 A-4-12 (2 of 5)
WATERFORD 3 SES EMERGENCY PLAN TABLE 4-3 (Continued) MONITORS Event Readout Isotopic Concentrations or FSAR Accidents ~ Range Function Location Location Dose Rate at Monitor Location
- 3. Containment 10-r to 10-1 Monitor airborne Alarm and Continuously draws air sample Noble Gases: 3 x 104 uCi/cc Atmosphere uCi/cc of noble activity. Alarni continuously from containment air, RAB -4 Iodines: 3 x 1o4 uCi/cc (1 o9 of NG Monitors (see Item gases; 1o-9 to locally and in record in Control west side wing area. and iodines in 106 ft. 3 at t=O}.
1, Table 12.3-3 of 10-3 uCi/cc of Control Room. Room. Alarm FSAR}. iodines. locally.
- 4. Plant Stack Wide 10-t to 10t>
- Monitor Plant Continuously On +46 MSL Plant Stack 1O uCi/cc of NG.
Range Gas uCi/cc of noble Stack Gas record and alarm downstream of filters. Accident Monitor. gas. activity. in Control Room.
- s. Containment High 1 -10!l R/hr. Monitor Continuously +99 ft. MSL containment at 90° 10° R/hr.
Range Accident containment record and alarm and 270°. Monitors accident in Control Room. conditions. c) Steam Generator 1. Main Steam Line 1 - 1ot> mR/hr. Monitor Main Alarm and On +46 MSL upstream of 1o mR/hr (10 4 Ci of NG and Iodines Tube Rupture Monitors Steam activity. continuously Atmospheric Dump Valves and released from the affected steam Alarm in Control records in Relief Valves. generator in 0-2 hour period). Room. Control Room.
- 4. Radioactive release from a subsystem or
-component a) Gaseous Radwaste 1. Area monitors S022A: .1 -104 Alarm at 30 Continuously Corridors north and west of gas 3 x 10° mR/hr (10b Ci in 10t> ft.J with Tank Failure ARM-IRE-S022A mR/hr. mR/hr. record and alarm decay tank cubicles, respectively O.S MeV/dis and 0.1 finite cloud and 5023 (see so23: .01 - 1o3 locally and in (see Figure 12.3-4). correction).
Table 12.3-2 of mR/hr. Control Room. FSAR}.
- 2. Plant Stack 10-r to 10-1 Continuous Continuously Plant Stack downstream of filters. Noble gases: 30 uCi/cc effluent monitor. uCi/cc of noble monitor of plant record and alarm Iodines: 3 x 1o-4 uCi/cc (1 oS Ci of gases; 10-9 to effluent and locally and in NG and 1 Ci of iodines in 1as ft. 3).
10-3 uCi/cc of terminate Control Room. iodines containment purge.
- 3. RAB airborne 10-r to 10-1 Alarm at 1 x 1o-4 Local and Located in ductwork of RAB Noble gases: 30 uCi/cc radiation duct uCi/cc of noble uCi/cc of noble Control Room elevation -4 ft. MSL. Iodines: 3 x 10-4 uCi/cc (10S Ci of monitors for noble gases; 10-9 to gases. alarm and NG and 1 Ci of iodines in 1 O~ ft.3}.
gases, iodines and 10-3 uCi/cc of continuously particulates iodines record. Monitor A (See Table 12.3-3 of FSAR}. Rev.048 A-4-13 (3 of 5)
WATERFORD 3 SES EMERGENCY PLAN TABLE 4-3 (Continued) MONITORS Event Readout Isotopic Concentrations or FSAR Accidents ~ Range Function Location Location Dose Rafe at Monitor Location
- 4. Plant Stack Wide 10- 1 to10° Monitor Plant Continuously On +46 MSL Plant Stack 30 uCi/cc of NG.
Range Gas uCi/cc of noble Stack Gas record and alarm downstream of filters. Accident Monitor. gases. activity. in Control Room. b) Failure of Liquid 1. Area Monitor ARM- .01 -1000 Local alarm at 5 Continuously In RAB, elevation -35 ft. MSL. 60 mR/hr (10 Ci of iodines with a PF Waste Tank IRE-5009 (See mR/hr. mR/hr. record and alarm = 0.1 and diluted in 104 ft.3 and finite Table 12.3-2 of locally and in cloud correction of0.1 ). FSAR). Control Room.
- 2. Airborne monitor of 10-t to 10-1 Alarm at setpoini Alarm and In RAB, elevation -4 ft. MSL. 3 x 1o-0 uCi/cc iodines (1 o Ci of activity in uCi/cc of noble of continuously iodines with a PF = 0.01 in 1o5 ft. 3j.
ductwork. gases; 10-9 to 1 x 1o-4 uCi/cc record in Control Monitors for noble 10-3 uCi/cc of of noble gases. Room.Alarm gases, iodines and iodines. locally. particulates. Monitor A (see Table 12.3-3 of FSAR).
- 3. Plant Stack 10-t to 10-1 Continuous Alarm and Plant Stack downstream of filters. 3.5 x 1o- 0 uCi/cc iodines (1 o Ci of effluent monitor. uCi/cc of noble monitor of plant continuously iodines PF= .01 diluted in 105 ft.3 gases; 10-9 to discharge. record in Control and no credit for filters.
10-3 uCi/cc of Terminate Room.Alarm iodines. containment locally. purge . c) Fuel Handling 1. Area Monitor ARM- .1 - 104 mR/hr. Isolate FHB and Continuously Adjacent to spent fuel pool 3 x 104 mR/hr (104 Ci in 10° ft.;:s with Accident IRE-0300.1 S, start emergency record and alarm 0.5 MeV/dis and finite cloud 0300.2S, 0300.3S FHB exhaust locally and in correction of0.1). and 0300.4S (see filters. Control Room. Table 12.3-2 of FSAR).
- 2. Area monitors .01 - 1o
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W3SESEMERGENCYPLAN FIGURE 5-5 EMERGENCY ORGANIZATION INTERFACES I CONTROL ROOM I I I NRC I TECHNICAL SUPPORT CENTER I I I I I OPERATIONAL HAHNVILLE EMERGENCY OCHSNER STCHARLES WEST SUPPORT FIRE OPERATIONS CLINIC PARISH JEFFERSON CENTER DEPARTMENT FACILITY FOUNDATION HOSPITAL MEDICAL (A) (A) (A) CENTER (A) I I I I ONSITE JOINT GOHSEP LDEQ PARISH U.S. UNION RESPONSE INFORMATION EMERGENCY OPERATIONAL EMERGENCY COAST PACIFIC TEAM CENTER OPERATIONS HEADQUARTERS OPERATIONS GUARD RAILROAD CENTER CENTER(C)(D) (B) (B) OTHER FEDERAL& STATE STATE LOCAL AGENCIES TECHNICAL RESOURCES
&FEMA RESOURCES (A) ADDITIONAL OFFSITE ASSISTANCE (8) SECONDARY NOTIFICATION (C) ST JOHN THE BAPTIST PARISH CIVIL DEFENSE/SHERIFF (D) ST CHARLES PARISH EMERGENCY PREPARDENESS/SHERIFF FEDERAL & STATE TECHNICAL RESOURCES (1) DEPT. OF PUBLIC SAFETY & CORRECTIONS (2)
- DEPT OF WILDLIFE & FISHERIES (3) DEPT OF HEALTH & HOSPITALS (4) DEPT OF AGRICULTURE (5) NRG (6)DOE (7) EPA LOCAL RESOURCES (1) FIRE DEPARTMENTS (2) AMBULANCE SERVICE (3) TRANSPORTATION SERVICES A-5-5 Rev.048
W3 SES EMERGENCY PLAN TABLE 5-1 MINIMUM STAFFING AND AUGMENTATION CAPABILITIES FOR EMERGENCIES Major Position Title On Capability for Additions i::.
.. I Area Emergency Tasks Shift 75Min Or Expertise Location Plant Operations and Emergency Direction and Control Shift Manager (SRO) CR 1 -
Assessment of TSC Duty Emergency Plant Manager TSC - 1(e) Operational Aspects control Room Supervisor (SRO) CR 1 - Reactor Operator (RO) CR 2 - Nuclear Auxiliary Operator CR 5 - Remote Shutdown Operator CR 1(b)* - Firefighting, firefighting communications Shift Personnel (Operations) CR 5(a) Provided by offsite fire department personnel Technical Support and CorefThermal Shift Technical Advisor CR 1(c) - Hydraulics(d) CorefThermal Hydraulics TSC Reactor Engineer TSC - 1(e) Notification/ Offsite Notifications (State, Local, Federal) and Emergency Communicator CR 1 - Communication maintain communications, Notification of plant EOF Offsite Communicator OR ENS CR/EOF - 3(e) On-call emergency personnel Communicator Radiological Accident EOF Direction and Control Emergency Director EOF - 1(e) Assessment and _, Support of Operational Offsite Dose Assessment Shift Personnel (Operations) CR 1(a) - Accident Assessment Radiological Assessment Coordinator OR EOF - 1(e) Dose Assessor OR Offsite Team Coordinator Chemistry/Radio-Chemistry Chemistry Technician osc 1 1 (e) Plant System Technical Support Electrical/l&C Engineer TSC - 1 (e) Engineering Mechanical Engineer TSC - 1 (e) Repair and Corrective Mechanical Maintenance osc - 2 (e) Actions Electrical Maintenance osc 1(f) 2 (e) l&C Maintenance osc 1(f) 2 (e) THE CONTROL ROOM (SHIFT) RESPONSIBILITIES WERE REVISED TO SATISFY THE REQUIREMENTS OF THE ON-SHIFT ERO STAFFING ANALYSIS CONDUCTED IN ACCORDANCE WITH NEI 10-05 AND REQUIRED BY 10CFR50 APPENDIX E, SECTION IV.A AS DOCUMENTED IN THE WATERFORD 3 STATION ON-SHIFT STAFFING ANALYSIS FINAL REPORT REVISION 0 DECEMBER 2012.
- THE ADDITION OF THE REMOTE SHUTDOWN OPERATORS TO MINIMUM STAFFING IS EFFECTIVE ON JANUARY 18, 2013 Revision 048 A-5-6 Page (1 of 2)
W3,SES EMERGENCY PLAN TABLE 5-1 MINIMUM STAFFING AND AUGMENTATION CAPABILITIES FOR EMERGENCIES Major Position Title On Capability for Additions Functional Area Emergency Tasks or Expertise Location Shift 75Min Radiation Protection -Access Control Health Physics Technician osc 1(g) 11(b) (e)
-HP coverage for repair, corrective actions, search and rescue/first-aid, and firefighting Radiation Protection Department Personnel 1(b)
-Personnel monitoring I
-Dosimetry
-Surveys (offsite, onsite, and in-plant surveys on as-needed basis only)
Rescue I First aid Emergency First Aid Team osc 2(a) Provided by support hospitals Security Security, personnel accountability Security Personnel (See Security Plan) Totals: 16 27 Notes: (a) May be provided by Shift Personnel assigned other duties. (b) Must be trained for the Emergency Task being performed. (c) STA staffing in accordance with Waterford 3 Technical Specification. (d) Core/Thermal Hydraulics is part of normal STA duties as listed in the Updated Final Safety Analysis Report and Technical Specifications. (e) These personnel will report and augment shift personnel in 75 minutes (45 minutes if onsite). (f) Maintenance onshift staffing includes one technician from either Electrical Maintenance or l&C Maintenance. (g) The Health Physics Technician onshift is a qualified Senior Health Physics Technician. THE CONTROL ROOM (SHIFT) RESPONSIBILITIES WERE REVISED TO SATISFY THE REQUIREMENTS OF THE ON-SHIFT ERO STAFFING ANALYSIS CONDUCTED IN ACCORDANCE WITH NEI 10-05 AND REQUIRED BY 10CFR50 APPENDIX E, SECTION IV.A AS DOCUMENTED IN THE WATERFORD 3 STATION ON-SHIFT STAFFING ANALYSIS FINAL REPORT REVISION 0 DECEMBER 2012. Revision 048 A-5-7 Page (2 of 2)
WATERFORD 3 SES EMERGENCY PLAN TABLE 5-2 EMERGENCY FUNCTION AND RESPONSIBILITY CHART (A) ENTERGY (G) SUPPORT PARISHES (B) ST. CHARLES PARISH (H) HAHNVILLE FIRE COMPANY (C) ST. JOHN PARISH (I) OCHSNER CLINIC FOUNDATION/WEST JEFF. MED.CENTER (D) LDEQ (J) ST. CHARLES PARISH AMBULANCE/HOSPITAL (E) GOHSEP (K) OCHSNER FLIGHT CARE (F) STATE AGENCIES (A) (B) IC) (D) IE) IF) {G) {H) {I) . (J) {Kl PLANT CONTROL p OFFSITE DIRECTION & p p s s CONTROL NOTIFICATION p s s s s s s COMMUNICATIONS p p p s p s s PUBLIC p p s s ALERT/NOTIFICATION PUBLIC INFORMATION p p p p p ACCIDENT p s ASSESSMENT PUBLIC HEALTH s s p SOCIAL SERVICES s s p s ONSITE FIRE & p s s RESCUE TRAFFIC CONTROL p p s s ACCESS CONTROL p p s s EMERGENCY s s s p p p MEDICAL SERVICES LAW ENFORCEMENT p p s TRANSPORTATION p p s PROTECTIVE s p p s s
RESPONSE
P= PRIMARY S = SECONDARY L Rev.048 A-5-8 (1 of 2)
WATERFORD 3 SES EMERGENCY PLAN TABLE 5-2 (Continued) EMERGENCY FUNCTION AND RESPONSIBILITY CHART (A) ENTERGY (G) SUPPORT PARISHES (B) ST. CHARLES PARISH (H) HAHNVILLE FIRE COMPANY (C) ST. JOHN PARISH (I) OCHSNER CLINIC FOUNDATION/WEST JEFF. MED.CENTER (D) LDEQ (J) ST. CHARLES PARISH AMBULANCE/HOSPITAL (E) GOHSEP (K) OCHSNER FLIGHT CARE (F) STATE AGENCIES IA) (8) IC) (D) I El I Fl IGl IH) m IJ) IK) RADIOLOGICAL p s s p s s s EXPOSURE CONTROL FOOD & WATER p s PURITY SHELTER & CARE s p FIELD SAMPLING p p s HIGHWAY p p s MAINTENANCE SECURITY p s s s FUEL DISTRIBUTION s s p POWER p s s s RESTORATION OFFSITE RECOVERY p p s s s s s s s EMERGENCY s p s MEDICAL TRANSPORTATION ACCIDENT p CLASSIFICATION PLANT OPERATIONS p POWER SUPPLY p LIABILITY & CLAIMS p s P= PRIMARY S = SECONDARY Rev.048 A-5-9 (2 of 2)
. WATERFORD 3 SES EMERGENCY PLAN TABLE 5-3 FACILITY RESPONSIBILITIES CONTROL JOINT INFORMATION ACTIVITY ROOM TSC osc EOF CENTER
\
\
Plant Control and Manipulations p Manaqement of Plant Operations P(1) p Overall Emeraencv Resoonse Manaaement P(2) p Manaoement of Enterav Resources P(2) p In-Plant And Onsite Radioloqical Monitorinq P(1) p s Offsite Radioloqical Monitorinq p
~
Dose Projections P(2) p Public Information p Approval of Technical Content of Information p s Releases Approval of Non-Technical Content of Information p /s Releases Rumor Control p Technical Assessment p s
\
Event Classification P(2) p Initial Offsite Notifications p Follow-up Offsite Notifications/Communications P(2) p Loaistics Sunnort p Site Securitv P(1) s p s Coordination of Security Matters with Offsite Law P(1) s p s Enforcement Officials p Primary Responsibility s Support Responsibility (1) - Until relieved by the Onsite Organization (2) - Until relieved by the EOF Rev.048 A-5-10 (1 of 2)
WATERFORD 3 SES EMERGENCY PLAN TABLE 5-3 (Continued} FACILITY RESPONSIBILITIES CONTROL JOINT ACTIVITY ROOM TSC osc EOF INFORMATION CENTER Coordination of Offsite Traffic Control with Offsite P(1) P(2) p Law Enforcement Officials Protective Action Recommendations P(2) p Ememencv Repair/Operations s p Coordination with Offsite Officials P(2) p Power Production and Distribution P* Financial Support p Coordination of Technical Information with Offsite p EOCs Coordination of Non-Technical Information Offsite s p Procurement and Contractina p Handlina Insurance Claims p Transportation Coordination p Governmental Liaison ' P(3) Direct Recoverv Operation P(1) p P Primary Responsibility S Support Responsibility (1) - Until relieved by the Onsite Organization (2) - Until relieved by the EOF (3) - Coordinated with Corporate Emergency Center
- - The EOF has primary responsibility to coordinate these activities as they relate to the Waterford 3 site emergency. The primary responsibility for performing power production, power restoration and distribution activities lies with other Entergy Business Units coordinated through the EOF.
Rev.048 A-5-11 (2 of 2)
WATERFORD 3 SES EMERGENCY PLAN TABLE 5-4 CONTROL ROOM (SHIFT) RESPONSIBILITIES (A) EMERGENCY DIRECTOR (SHIFT MANAGER) (F) RADIATION PROTECTION TECHNICIAN (B) CONTROL ROOM SUPERVISOR (G) CHEMISTRY TECHNICIAN (C) REACTOR OPERATORS (H) MAINTENANCE TECHNICIAN(S) (D) NUCLEAR AUXILIARY OPERATORS (I) SECURITY (E) SHIFT TECHNICAL ADVISOR (J) REMOTE SHUTDOWN OPERATOR+ ACTIVITY (A) (B) (C) (D) (E) (F) (G) (H) (I) (J) INITIAL ACCIDENT EVALUATION AND p s s s ASSESSMENT MANAGEMENT OF PLANT OPERATIONS p s OVERALL EMERGENCY RESPONSE p s MANAGEMENT EVENT RECOGNITION s p s EVENT CLASSIFICATION p s s EMERGENCY RESPONSE ORGANIZATION ACTIVATION OF ADDITIONAL RESOURCES p s s CONTACT DUTY PLANT MANAGER p s OFFSITE PROTECTIVE ACTION P. s RECOMMENDATIONS ONSITE PROTECTIVE ACTIONS p s PLANT CONTROL & OPERATIONS p s s p DOSE PROJECTIONS p s s s s s ENGINEERING ANALYSIS & REACTOR p s A SAFETY FIRE BRIGADE** P*** P PRIMARY S - SECONDARY A - TECHNICAL ADVISOR FOR REACTOR SAFETY CONSIDERATIONS
- AS DIRECTED PRIORITY FOR ASSIGNMENTS WILL BE MADE BY THE EMERGENCY DIRECTOR WHEN CONFLICTS ARISE.
AS A MINIMUM THE FIRE BRIGADE LEADER WILL BE A FULLY QUALIFIED LEVEL A NUCLEAR AUXILIARY OPERATOR (NAO). THE CONTROL ROOM (SHIFT) RESPONSIBILITIES WERE REVISED TO SATISFY THE REQUIREMENTS OF THE ON-SHIFT ERO STAFFING ANALYSIS CONDUCTED IN ACCORDANCE WITH NEI 10-05 AND REQUIRED BY 10CFR50 APPENDIX E, SECTION IV.AAS DOCUMENTED IN THE WATERFORD 3 STATION ON-SHIFT STAFFING ANALYSIS FINAL REPORT REVISION 0 DECEMBER 2012. +THE ADDITION OF THE REMOTE SHUTDOWN OPERATORS TO MINIMUM STAFFING AND THE TRANSFER OF OFFSITE COMMUNICATIONS FROM THE SHIFT TECHNICAL ADVISORS TO THE REMOTE SHUTDOWN OPERATORS ARE EFFECTIVE ON JANUARY 18, 2013. ( Rev.048 A-5-12 (1 of 2)
( WATERFORD 3 SES EMERGENCY PLAN TABLE 5-4 (Continued) CONTROL ROOM (SHIFT) RESPONSIBILITIES (A) EMERGENCY DIRECTOR (SHIFT MANAGER) (F) RADIATION PROTECTION TECHNICIAN (B) CONTROL ROOM SUPERVISOR (G) CHEMISTRY TECHNICIAN (C) REACTOR OPERATORS (H) MAINTENANCE TECHNICIAN(S) (D) NUCLEAR AUXILIARY OPERATORS ((I) SECURITY (E) SHIFT TECHNICAL ADVISOR (J) REMOTE SHUTDOWN OPERATOR+ (F) RADIATION PROTECTION TECHNICIAN ACTIVITY (A) (Bl (Cl (D) (El (Fl (G) (H) (I) (J) EMERGENCY COMMUNICATIONS p + INITIAL & FOLLOWUP OFFSITE I p NOTIFICATION/COMMUNICATIONS INPLANT AND ONSITE RADIOLOGICAL p MONITORING/HEALTH PHYSICS CHEMISTRY p FIRST AID TEAM** s p REPAIR OPERATIONS P* SITE SECURITY/PERSONNEL p ACCOUNTABILITY COORDINATION OF SECURITY MATIERS p WITH OFFSITE LAW ENFORCEMENT OFFICIALS COORDINATION OF OFFSITE TRAFFIC p CONTROL WITH OFFSITE LAW ENFORCEMENT OFFICIALS P PRIMARY S - SECONDARY A - *TECHNICAL ADVISOR FOR REACTOR SAFETY CONSIDERATIONS
- AS DIRECTED PRIORITY FOR ASSIGNMENTS WILL BE MADE BY THE EMERGENCY COORDINATOR WHEN CONFLICTS ARISE.
AS A MINIMUM THE FIRE BRIGADE LEADER WILL BE A FULLY QUALIFIED LEVEL A NUCLEAR AUXILIARY OPERATOR (NAO). THE CONTROL ROOM (SHIFT)HESPONSIBILITIES WERE REVISED TO SATISFY THE REQUIREMENTS OF THE ON-SHIFT ERO STAFFING ANALYSIS CONDUCTED IN ACCORDANCE WITH NEI 10-05 AND REQUIRED BY 10CFR50 APPENDIX E, SECTION IV.A AS DOCUMENTED IN THE WATERFORD 3 STATION ON-SHIFT STAFFING ANALYSIS FINAL REPORT REVISION 0 DECEMBER 2012. +THE ADDITION OF THE REMOTE SHUTDOWN OPERATORS TO MINIMUM STAFFING AND THE TRANSFER OF OFFSITE COMMUNICATIONS FROM THE SHIFT TECHNICAL ADVISORS TO THE REMOTE SHUTDOWN OPERATORS ARE EFFECTIVE ON JANUARY 18, 2013. Rev. 048 A-5-13 (2 of 2)
WATERFORD 3 SES EMERGENCY PLAN TABLE 5-5 TECHNICAL SUPPORT CENTER RESPONSIBILITIES (A) EMERGENCY PLANT MANAGER (H) OPERATIONS COORDINATOR (B) TSC MANAGER (I) OPERATIONS COMMUNICATOR (C) TSC COMMUNICATOR (J) ENS COMMUNICATOR (D) RADIOLOGICAL COORDINATOR (K) TSC IT SPECIALIST (E) MAINTENANCE COORDINATOR (F) ENGINEERING COORDINATOR (G) TSC ENGINEERS ACTIVITY I Al 18) I Cl IDl IEl IF) IGl IHl m IJ) IKl MANAGEMENT OF PLANT OPERATIONS p s s OVERALL EMERGENCY RESPONSE p s MANAGEMENT ACTIVATION/OPERATl ON/DEACTIVATION OF p s TSC/OSC ONSITE PROTECTIVE ACTIONS p s COORDINATION OF EMERGENCY TEAMS p s s AUTHORIZE EXPOSURE IN EXCESS OF p 10CFR20 EMERGENCY REPAIR/OPERATIONS p s s s s s REQUEST OFFSITE ASSISTANCE p s DIRECT RECOVERY OPERATIONS s s RECORD OF EMERGENCY PLANT MANAGER p s ACTIONS (TSC LOG)/TSC ACTIVITIES P PRIMARY RESPONSIBILITY S SUPPORT RESPONSIBILITY
- 1 Rev.048 A-5-14 (1 of 3)
WATERFORD 3 SES EMERGENCY PLAN TABLE 5-5 (Continued) TECHNICAL SUPPORT CENTER RESPONSIBILITIES (A) EMERGENCY PLANT MANAGER (H) OPERATIONS COORDINATOR (B) TSC MANAGER (I) OPERATIONS COMMUNICATOR (C) TSC COMMUNICATOR (J) ENS COMMUNICATOR (D) RADIOLOGICAL COORDINATOR (K) TSC IT SPECIALIST (E) MAINTENANCE COORDINATOR (F) ENGINEERING COORDINATOR (G) TSC ENGINEERS ACTIVITY (Al (Bl (Cl (D) (El (Fl (G) (H) (I) (J) (K) COORDINATE TSC STAFFING p s COORDINATION OF TSC ENGINEERING p ACTIVITIES s COORDINATION OF TSC AND OSC ACTIVITIES p ENSURE PROPER MAINTENANCE OF ALL TSC p s s LOGS OSCffSC/EOF COMMUNICATIONS p INPLANT & ONSITE RADIOLOGICAL p MONITORING/HEALTH PHYSICS EOF RADIOLOGICAL ASSESSMENT p COORDINATOR COMMUNICATIONS MANAGEMENT OF SITE RADIATION p PROTECTION ACTIVITIES p- PRIMARY RESPONSIBILITY S SUPPORT RESPONSIBILITY Rev. 048 A-5-15 (2 of 3)
WATERFORD 3 SES EMERGENCY PLAN TABLE 5-5 (Continued) TECHNICAL SUPPORT CENTER RESPONSIBILITIES (A) EMERGENCY PLANT MANAGER (H) OPERATIONS COORDINATOR (B) TSC MANAGER (I) OPERATIONS COMMUNICATOR (C) TSC COMMUNICATOR (J) ENS COMMUNICATOR (D) RADIOLOGICAL COORDINATOR (K) TSC IT SPECIALIST (E) MAINTENANCE COORDINATOR (F) ENGINEERING COORDINATOR (G) TSC ENGINEERS ACTIVITY (A) (Bl (Cl (Dl (El (Fl (Gl (H) (I) (J) (Kl TECHNICAL ASSESSMENT s s p p MAINTAIN RC LOG, STATUS BOARDS, COMMUNICATIONS MANAGEMENT LIAISON FOR PLANT p s OPERATIONS ACTIVITIES OPERATION OF SOS P(1l s P(1l TSC PERSONNEL ACCOUNTABILITY p s
~
p s COORDINATION OF EMERGENCY CHEMISTRY ACTIVITIES p MAINTAIN CONTINUOUS CONTACT WITH THE NRC p COORDINATE COMMUNICATION SYSTEMS SUPPORT p COORDINATE COMPUTER APPLICATIONS SUPPORT P PRIMARY RESPONSIBILITY S SUPPORT RESPONSIBILITY (1) RESPONSIBILITIES ARE SHARED AMONG THE OPERATIONS COORDINATOR, ENGINEERING COORDINATOR AND TECHNICAL ASSESSMENT ENGINEERS BECAUSE THESE POSITIONS HAVE SDS CONTROL KEYBOARDS. Rev. 048 A-5-16 (3 of 3)
WATERFORD 3 SES EMERGENCY PLAN TABLE 5-6 OPERATIONAL SUPPORT CENTER RESPONSIBILITIES (A) OSC MANAGER (H) FIRST AID TEAM (B) WORK CONTROL COORDINATOR (I) EMERGENCY REPAIR/OPERATIONS TEAM (C) OSC LOGKEEPER (J) SEARCH AND RESCUE TEAM (D) ASSEMBLY AREA SUPERVISOR (K) OSC MAINTENANCE COORDINATORS (E) RAD/CHEM COORDINATOR (L) SECURITY COORDINATOR (F) IN-PLANT RADIATION PROTECTION TECHNICIANS ' (G) FIRE BRIGADE ACTIVITY (A\ (B\ IC\ ID\ IE\ IF\ (G\ IH\ (I) IJ) IK\ IL\ ACTIVATION/OPERATION OF OSC p s FORMATION, BRIEFING, DEBRIEFING OF p s s p s EMERGENCY TEAMS COMMUNICATIONS p s OSC LOG p COORDINATION OF OFFSITE ASSEMBLY AREA p
' ACTIVITIES IN-PLANT AND ONSITE RADIOLOGICAL p s MONITORING COORDINATION OF IN-PLANT RADIOLOGICAL F' s CONTROLS TSC RADIOLOGICAL COORDINATOR p s COMMUNICATIONS FORMATION, BRIEFING, DISPATCH OF s s p RADIOLOGICAL MONITORING TEAMS EMERGENCY TEAM RADIATION PROTECTION p s SUPPORT PROVIDE RADIATION PROTECTION EQUIPMENT p s FOR ASSESSMENT ACTIVITIES FIRE BRIGADE p FIRST AID TEAM p EMERGENCY REPAIR/OPERATIONS p SEARCH AND RESCUE OPERATIONS p SITE SECURITY/PERSONNEL ACCOUNTABILITY p COORDINATION WITH OFFSITE LAW p ENFORCEMENT OFFICIALS COORDINATE COMMUNICATION SYSTEMS s SUPPORT COORDINATE COMPUTER APPLICATIONS s SUPPORT P PRIMARY RESPONSIBILITY S SUPPORT RESPONSIBILITY Rev.048 .r A-5-17 (1 of 1)
WATERFORD 3 SES EMERGENCY PLAN TABLE 5-7 EMERGENCY OPERATIONS FACILITY RESPONSIBILITIES (A) EMERGENCY DIRECTOR (G) DOSE ASSESSOR (M) ST. JOHN PARISH LIAISON (B) ADMINISTRATION/LOGISTICS COORDINATOR (H) EOF MANAGER (N) ST. CHARLES PARISH LIAISON (C) ADMINISTRATIVE ASSISTANT (I) EOF TECHNICAL ADVISOR (0) STATE LIAISON (D) EOF COMMUNICATOR (J) LEAD OFFSITE LIAISON (P) HABIABILITY ASSESSOR (E) RADIOLOGICAL ASSESSMENT COORDINATOR* (K) ENTERGY SYSTEM LIAISON (Q) OFFSITE COMMUNICATOR (F) OFFSITE TEAM COORDINATOR (L) PUBLIC INFORMATION LIAISON ACTIVITY (A) (B) (C) (D) (E) (F) (G) (H) (I) (J) (K) (L) (M) (N) (0) (P) (Q) COORDINATION OF OVERALL EMERGENCY p s ACTIVATION AND OPERATION OF EOF p s s s PROTECTIVE ACTION RECOMMENDATIONS p s s s EVENT CLASSIFICATION p s s s OFFSITE RADIOLOGICAL ASSESSMENT p s s OFFSITE MONITORING TEAM COORDINATION p RADIATION PROTECTION/RADIOLOGICAL SUPPORT TO TSC p s COORDINATION OF RADIOLOGICAL ASSESSMENT WITH LDEQ p s OFFSITE MONITORING TEAM p s COMMUNICATION DOSE PROJECTION CALCULATIONS p s COORDINATION OF ONSITE AND OFFSITE s SUPPORT p s s ENSURE THAT OFFSITE ORGANIZATIONS ARE s KEPT INFORMED p s s s s OFFSITE COMMUNICATIONS COORDINATION p s EOF PERSONNEL SAFETY p s s s LIAISON AT EOF WITH NRC p APPROVING THE TECHNICAL CONTENT OF s EMERGENCY NEWS RELEASES p s COORDINATION OF TECHNICAL INFORMATION OFFSITE s p s s s s s CR/OSC/TSC/EOF COMMUNICATIONS p P PRIMARY RESPONSIBILITY S SUPPORT RESPONSIBILITY EOF TECHNICAL ADVISOR ASSISTS THE EMERGENCY DIRECTOR AND RAC IN THE PERFORMANCE OF THEIR DUTIES. Rev. 048 A-5-18 (1 of 2)
WATERFORD 3 SES EMERGENCY PLAN TABLE 5-7 (Continued) EMERGENCY OPERATIONS FACILITY RESPONSIBILITIES (A) EMERGENCY DIRECTOR (G) DOSE ASSESSOR (M) ST. JOHN PARISH LIAISON (B) ADMINISTRATION/LOGISTICS COORDINATOR (H) EOF MANAGER (N) ST. CHARLES PARISH LIAISON (C) ADMINISTRATIVE ASSISTANT (I) EOF TECHNICAL ADVISOR (0) STATE Llf.ISON (D) EOF COMMUNICATOR (J) LEAD OFFSITE LIAISON (P) HABIABILITY ASSESSOR (E) RADIOLOGICAL ASSESSMENT COORDINATOR* (K) ENTERGY SYSTEM LIAISON (Q) OFFSITE COMMUNICATOR (F) OFFSITE TEAM COORDINATOR (L) PUBLIC INFORMATION LIAISON ACTIVITY (A) (B) (C) (D) (E) (F) (G) (H) (I) (J) (K) (L) (M) (N) (0) (P) (Q) EOF TECHNICAL COORDINATION p COORDINATING SERVICES OF OTHER TECHNICAL ORGANIZATIONS s s s DEVELOPMENT OF EMERGENCY PROCEDURES s OPERATION OF SPDS/SOUND POWERED PHONES IN EOF s COORDINATING SERVICES OF OTHER ENTERGY SYSTEM BUSINESS UNITS s s p EOF SECURITY COORDINATION p s s PROCUREMENT OF MATERIALS, EQUIPMENT, SERVICES p s PROVIDE/DIRECT CLERICAL OR OTHER NON-TECHNICAL PERSONNEL p PROVIDE NECESSARY DRAWINGS, MANUALS, ETC. p ARRANGE FOR MEALS, LODGING, TRANSPORTATION p s MAINTAIN LOG OF EOF ACTIVITIES p AUTHORIZE EXPOSURE IN EXCESS OF 10CFR20 p PROTECTIVE ACTIONS FOR FOSSIL PLANT p PERSONNEL ALLOCATION OF FUNDS p s COORDINATE SECURITY SUPPORT TO THE SITE p s COORDINATE INFORMATION RELEASES WITH PARISHES p s s GOVERNMENTAL LIAISON L p P PRIMARY RESPONSIBILITY S SUPPORT RESPONSIBILITY EOF TECHNICAL ADVISOR ASSISTS THE EMERGENCY DIRECTOR AND RAC IN THE PERFORMANCE OF THEIR DUTIES. Rev.048 A-5-19 (2 of 2)
WATERFORD 3 SES EMERGENCY PLAN TABLE 5-8 JOINT INFORMATION CENTER (JIC) RESPONSIBILITIES (A) COMPANY SPOKESPERSON (G) JIC MANAGER (B) INQUIRY RESPONSE COORDINATOR (H) PRESS RELEASE WRITER (C) MEDIA MONITOR (I) PUBLIC INFORMATION LIAISON (D) ENTERGY OPERATIONS, INC. HEADQUARTERS (J) TECHNICAL ADVISOR (E) MEDIA LIASON (K) TECHNICAL ASSISTANT (F) PARISH LIAISONS (L) GOHSEP ACTIVITY (A) (B) (C) (D) (E) (F) (G) (H) (I) (J) (K) (L) OVERALL ACTIVATION AND OPERATION OF JIC s p s TIMING AND CONTENT OF INFORMATION RELEASES p s s s MODERATE PRESS BRIEFINGS p INFORM CORPORATE EMPLOYEES s p COORDINATE INFORMATION RELEASES WITH STATE, FEDERAL AGENCIES AND PARISHES p s s RESPONSE TO MEDIA INQUIRIES p s s s s s s RUMOR CONTROL p s s DRAFT INFORMATION RELEASE s s s p NEWS BRIEFING CENTER OPERATION s p P PRIMARY RESPONSIBILITY S SUPPORT RESPONSIBILITY Rev. 048 A-5-20 (1 of 2)
WATERFORD 3 SES EMERGENCY PLAN TABLE 5-8 (Continued) JOINT INFORMATION CENTER (JIC) RESPONSIBILITIES (A) COMPANY SPOKESPERSON (G) JIG MANAGER (B) INQUIRY RESPONSE COORDINATOR (H) PRESS RELEASE WRITER (C) MEDIA MONITOR (I) PUBLIC INFORMATION LIAISON (D) ENTERGY OPERATIONS, INC. HEADQUARTERS (J) TECHNICAL ADVISOR (E) MEDIA LIASON (K) TECHNICAL ASSISTANT (F) PARISH LIAISONS (L) GOHSEP ACTIVITY (A) (B) (C) (D) (E) (F) (G) (H) (I) (J) (K) (L) COORDINATE INFORMATION TO/FROM W3 SES SITE s p s s ELECTRONIC EQUIPMENT OPERATION p MONITOR INFORMATION BROADCAS.TS p s s GENERAL JIG FACILITY SUPPORT p s s COORDINATE NEWS BULLETINS WITH EMERGENCY DIRECTOR p s s MEDIA BRIEFINGS p s s APPROVAL OF INFORMATION RELEASES s s s GOVERNMENTAL LIAISON s p P PRIMARY RESPONSIBILITY S SUPPORT RESPONSIBILITY Rev. 048 A-5-21 (2 of 2)
WATERFORD 3 SES EMERGENCY PLAN 6.0 EMERGENCY RESPONSE MEASURES This section identifies the specific measures that are taken for each class of emergency defined in section 4.0 of this Plan. The logic presented in this Section is used as the basis for detailed Emergency Plan Implementing Procedures that define the emergency actions to be taken for each emergency class. In all cases, emergency measures begin with (1) the recognition, assessment and declaration of the emergency and, (2) notification and activation of the appropriate agencies and portions of the emergency response organizations. Upon the emergency organization becoming operational, the following additional measures are taken: assessment actions, corrective actions, protective actions, aid to affected personnel, early warning and public information. These measures are described in the sections below. 6.1 Pre-Classification Assessment and Declaration of an Emergency 6.1.1 Recognition Should an emergency situation (real or potential) arise, it is expected that the Reactor Operator(s) (RO) and/or the Control Room Supervisor (CRS) will be initially made aware by alarms, instrument readings, reports, the Industrial Hotline, etc. The RO(s) shall ensure that the CRS and/or Shift Manager (SM) are immediately informed. The CRS shall, if not already accomplished by the RO(s), inform the SM immediately. 6.1.2 Assessment The SM, when informed of an emergency situation, is responsible for performing the assessment of the emergency (e.g., plant systems and reactor core status, radiological conditions, etc.). He will determine what immediate actions must be taken (e.g., use of Emergency Procedures) to ensure the safe and proper operation of the plant. The Shift Technical Advisor (STA) will advise and assist the SM on matters pertaining to the safe and proper operation of the plant with regards to nuclear safety. 6.1.3 Classification and Declaration If the situation requires implementation of the Waterford 3 Emergency Plan, the SM acts to:
- a. Initially classify and declare the emergency as an Unusual Event, Alert, Site Area Emergency, or General Emergency as appropriate and implement the applicable Emergency Plan Implementing Instruction (Ref. Section 7.4.1, Control Room Instrumentation, and Section 4.1, Waterford 3 Classification System).
- b. Contact the TSC Duty Emergency Plant Manager and discuss the nature of the situation, the actions already underway and levels of additional anticipated support that may be required to mitigate the accident. The contact of the TSC Duty Emergency Plant Manager shall not be made if, in the opinion of the SM/ED, such a call is obviously going to hamper accomplishing the required notifications within the time limits as described in Section 6.2.1.
6-1 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN* 6.1.3 (Cont'd)
- c. Ensure notification of agencies and personnel are completed as described in Section 6.2.1. The initial notification message contains information about the class of emergency, whether a release of radioactive material is taking place, potentially affected populations and areas, and protective action recommendations that may be warranted. (See Figure 6-2) 6.2 Activation of Emeraency Organization 6.2.1 Notification As stated in Section 6.1.3, upon declaration of an emergency by the SM at Waterford 3, the SM directs initial notifications to agencies and personnel be made in conjunction with notification of onshift personnel. The notification scheme is a two-phase process that entails notification of offsite agencies and activation of the Emergency Response Organization. Primary offsite agencies are required to be notified within 15 minutes of emergency declaration.
6.2.1.1 Activation of the Emergency Response Organization
- Activation of the Emergency Response Organization depends largely on the nature of the incident and its classification. The Technical Support Center and Emergency Operations Facility are not activated for toxic chemical events. Offsite locations that are not affected by the toxic chemical cloud may be activated as necessary in accordance with Emergency Plan Implementing Procedures.
The level of activation of the Emergency Response Organization is determined by the SM/Emergency Director following the guidelines of Section 6.2.2.3.a. In all cases, regardless of emergency classification, the following emergency positions are notified of the emergency condition: *
- a. TSC Duty Emergency Plant Manager
- b. Duty Emergency Director ,-
- c. Duty Company Spokesperson Activation of the Waterford 3 Emergency Response Organization is conducted in parallel with the primary notifications and is in accordance with the Emergency Plan Implementing Procedures (see Figure 6-1 ).
Upon declaration of an emergency, the SM directs the Emergency Communicator to activate the Emergency Response Organization~to report to the plant to assist in handling the situation.
- Key Entergy Operations, Inc., personnel have been designated to augment the Onshift Organization within 75 minutes of the declaration of an Alert, or higher, emergency classification. (See Table 5-1) This ,is an approved exception to NUREG-0654, Table B-1.
6-2 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN 6.2.1.1 (Cont'd.) The Emergency Communicator, located in the Control Room Administrative Office, activates the Emergency Response Organization via an electronic callout system which utilizes multiple contact pathways. When the Emergency Response personnel are alerted via selected contact pathways, they are provided with emergency information including response directions. 6.2.1.2 Notification of Offsite Agencies
- a. Initial Notification Upon declaration of an emergency the SM approves a Notification Message Form similar to Figure 6-2 and directs the Emergency Communicator to initiate the offsite notifications.
Initial and subsequent notifications will include appropriate protective action recommendations. Primary offsite agencies must be notified within 15 minutes of emergency declaration, except the NRC, that must be notified immediately after the other primary agencies, not later than one hour. Secondary notifications must be made within a reasonable period of time. If requested, continuous communications will be maintained with the NRC. Information will be provided to the NRC as requested without prior approval, except that the Emergency Director must approve the transmittal of information regarding future accident mitigation activities. The following notifications to offsite agencies are primary notifications:
- 1. St. Charles Parish EOC/911 Center
- 2. St. John EOC/E-911 Center
- 3. Louisiana Department of Environmental Quality (LDEQ)
- 4. Governor's Office of Homeland Security & Emergency Preparedness (GOHSEP)
- 5. Waterford 1 and 2 SES
- 6. Nuclear Regulatory Commission, Bethesda, MD (NRC)
The following offsite notification is a secondary notification: Institute of Nuclear Power Operations (INPO) at an Alert or higher classification. The Entergy Operations Headquarters is responsible for notifying INPO and ANI. Additional secondary notifications to offsite agencies which may be affected (e.g. Union Pacific Railroad, U.S. Coast Guard) will be made as needed. 6-3 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN Figure 6-3 outlines primary and alternate positions for individuals designated to act in transmission and receipt of notification information. 6.2.1.2a (Cont'd.) In the event of an emergency requiring onsite response of offsite emergency agencies, contact with the St. Charles Parish Sheriff's Office, Hahnville Fire Department and St. Charles Parish Hospital will be made through the 911 Center using the PABX as the primary communications method. Contact with Ochsner Clinic Foundation and West Jefferson Medical Center will be made via the PABX. In the event that the emergency is declared after normal working hours (0800-1700), it is the responsibility of GOHSEP to contact and notify LDEQ of the emergency; LDEQ shall then contact Waterford 3.
- b. Subsequent Notification Following initial notifications, after any change in plant status, or if new pertinent information becomes available, the SM approves the Notification Message Form, similar to Figure 6-2, and directs the Emergency Communicator to initiate notifications to the offsite agencies. In this manner, the offsite agencies are kept informed of the emergency situation as it progresses. The offsite agencies contacted are the same as for initial notification.
6.2.2 Mobilization of Emergency Organization 6.2.2.1 Control Room Supervisor/Reactor Operators Upon declaration of an emergency by the SM, the ROs and CRS shall perform their normally assigned duties (i.e., plant operations). 6.2.2.2 Shift Manager Once the SM has declared the emergency and has directed the appropriate notifications to be made, acting in the capacity of Emergency Director, he performs the following:
- a. Ensures that appropriate alarm (Fire or Station) is sounded.
There are limited approved exceptions during declared emergencies for severe weather when response personnel are sequestered onsite.
- b. Announces the location, type and classification of the emergency on the station public address system. There are limited exceptions during declared emergencies for severe weather when response personnel are sequestered. onsite, or during an ongoing security threat, such as a hostile action.
- c. Implements the applicable Emergency Plan Implementing Instruction and associated procedures.
- d. Activates the Onshift Emergency Organization.
6-4 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN
- e. Recommends protective actions to appropriate offsite agencies for public protection as needed prior to arrival of the EOF Duty Emergency Director.
6.2.2.3 TSC Duty Emergency Plant Manager The TSC Duty Emergency Plant Manager, upon being informed that an emergency exists and has been declared by the SM, shall:
- a. Ensure that Waterford 3 emergency organizations have been activated to the extent necessary.
- 1. Unusual Event - Key individuals in the onsite, nearsite and offsite emergency organizations shall be notified.
- 2. Alert - The entire onsite and nearsite organization shall be activated. Key individuals in the offsite emergency organization shall be notified.
- 3. Site Area Emergency - The entire onsite, nearsite and offsite emergency organizations shall be activated.
- 4. General Emergency - The entire onsite, nearsite and offsite emergency organizations shall be activated.
- b. Report to the Technical Support Center and assume the position of Emergency Plant Manager in the Onsite Emergency
- Organization.
6.2.2.4 St. Charles Parish
- a. Waterford 3 provides initial notification to St. Charles Parish upon recognition that events have occurred which make notification appropriate.
- 1. Notification will come directly to the St. Charles Parish EOC Dispatch Center. The St. Charles Parish 911 Center serves as a backup to the Dispatch Center.
- 2. The EOC Dispatch Center is responsible for notifying the Emergency Preparedness Director.
- b. Upon receipt of the message on a communications circuit other than the Operational Hotline, St. Charles Parish verifies the message with Waterford 3, as deemed necessary.
- c. Following notification/verification, St. Charles Parish initiates activation of the emergency staff notification system by implementing the emergency call-out list.
- d. St. Charles Parish notifies potentially affected schools, hospitals, nursing homes, major industries, and appropriate local response organizations, as determined by the situation and emergency classjfication.
- e. St. Charles Parish is periodically updated as the situation warrants per the Emergency Plan Implementing Procedures.
6-5 Rev.048
WATERFORD 3 SES EMERGENCY PLAN 6.2.2.5 St. John the Baptist Parish
- a. Waterford 3 provides initial notification to St. John the Baptist Parish upon recognition that events have occurred which make notification appropriate.
- 1. Notification will come to the St. John the Baptist Parish Emergency 911 Communications Center.
- 2. The Emergency 911 Communic;:itions Center is responsible for notifying the Civil Defense Director. The Emergency 911 Communications Center remains active until relieved by_the EOG Communications Point.
- b. Upon receipt of the message on a communications circuit other than the Operational Hotline, St. John the Baptist Parish verifies the message with Waterford 3, as deemed necessary.
- c. Following notification/verification, St. John the Baptist Parish initiates activation of the emergency staff notification system by implementation of the call-out list.
~
- d. St. John the Baptist Parish notifies potentially affected. schools, hospitals, nursing homes, major industries, and appropriate local response organizations, as determined by the situation and the emergency classification.
- e. St. John the Baptist Parish is periodically updated as the situation warrants per Emergency Plan Implementing Procedures.
6.2.2.6 Louisiana Department of Environmental Quality (LDEQ)
- a. In the event of an accident at Waterford 3, initial notification is made by Waterford 3 to LDEQ. Upon notification, LDEQ is periodically updated as the situation warrants per the Emergency Plan Implementing Procedures.
- b. Upon notification of an accident, LDEQ activates its operational headquarters, as determined by the emergency classification.
- c. LDEQ notifies key technical support, State, and Federal agencies as determined by the emergency classification. These include:
- 1. Louisiana Department of Agriculture and Forestry
- 2. Louisiana Department of Health and Hospitals, Office of Public Health
- 3. Louisiana Department of Wildlife and Fisheries
- 4. U. S. Department of Energy (DOE) 6-6 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN 6.2.2.6 (Cont'd)
- d. LDEQ dispatches personnel to the Waterford 3 Emergency Operations Facility (EOF) as determined by the emergency classification and establishes direct communications with LDEQ headquarters.
- e. LDEQ establishes its personnel in the Waterford 3 EOF with the Field Monitoring Teams (FMT} conducting monitoring and sampling activities at predesignated sites in the plume exposure pathway EPZ. Field monitoring data is transmitted to the FMT Coordinator.
- f. LDEQ response personnel coordinate activities of the FMT, perform dose assessment activities, provide liaison with the EOF staff and provide coordination of field monitoring team activities and data with Entergy Operations, Inc.
6.2.2.7 Governor's Office of Homeland Security & Emergency Preparedness (GOH SEP)
- a. Upon notification of an emergency at Waterford 3, GOHSEP activates the State EOC as determined by the emergency classification.
- b. GOHSEP provides notification to support parishes as well as those parishes within the ingestion exposure pathway EPZ of .
Waterford 3.
- c. GOHSEP provides notification to State and Federal agencies designated to support protective response as determined by the emergency classification. These include:
- 1. FEMA Region VI
- 2. U. S. Coast Guard
- 3. FAA
- 4. Other designated state agencies
- d. GOHSEP maintains communications with affected risk and support parishes for coordination-Of requested assistance.
- e. GOHSEP is periodically updated as the situation warrants per the Emergency Plan Implementing Procedures.
6.3 Assessment Actions Those actions taken during or after an accident to obtain and process information that is necessary to make decisions to implement specific emergency measures are considered assessment actions. Effective coordination and direction of all elements of the emergency organization requires continuing assessment throughout an emergency. The details of assessment functions are incorporated into the Implementing Instructions for each emergency classification describing both the methodologies and techniques to be used by Waterford 3. Although each emergency class invokes similar assessment methods, a different magnitude of assessment effort is required for each emergency class. An outline of ass~ssment actions for each emergency class is given below. 6-7 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN 6.3.1 Assessment Actions for Unusual Events The detection of an Unusual Event arises from either meeting or exceeding a specific initiating condition for this class or by an action statement in an Emergency Procedure. Detection of the event in either case comes as a result of alarms, instrument readings, recognition through experience or a combination thereof. The continuing assessment actions to be performed for this class of emergency are in accordance with the Emergency Plan Implementing Instruction for an Unusual Event and consist of the normal monitoring of Control Room and other plant instrumentation and status indications until the situation is resolved. If a fire was the reason for the declaration of an Unusual Event, the Fire Brigade Leader, who will have reported to the fire location, makes continuing assessments based on his experience and reports to the Emergency Director on whether offsite fire fighting assistance is required. 6.3.2 Assessment Actions for Alerts Once the Emergency Director has classified an accident as an Alert, assessment actions are performed in accordance with the Emergency Plan Implementing Instruction for an Alert. These actions include: 6.3.2.1 Increased surveillance of in-plant instrumentation. 6.3.2.2 If possible, the dispatching of an Emergency Repair Team to the identified problem area for confirmation. 6.3.2.3 If necessary, the dispatching of onsite radiological monitoring team(s) to monitor for possible releases and provide rapid confirmation of correct accident classification. 6.3.2.4 If a radiological accident is occurring, surveillance of the in-plant instrumentation necessary to obtain meteorological and radiological data required for calculating or estimating projected doses will commence. The dose assessment activity continues until termination of the emergency in order that updating of initial assessments may be provided to all concerned offsite agencies and to the Emergency Director. Emergency Plan Implementing Procedures are provided to allow rapid, consistent projection of doses. 6.3.3 Assessment Actions for Site Area Emergencies The assessment actions for the Site Area Emergency class are similar to the actions for an Alert; however, due to the increased magnitude of the possible release of radioactive material, a significantly larger assessment activity occurs. The necessary personnel for this assessment effort are provided by activation of the onsite and nearsite emergency organizations, specifically: 6.3.3.1 An increased amount of plant instrumentation is monitored. In particular, indications of core status (e.g., in-core thermocouple readings) are monitored closely. 6.3.3.2 Monitoring efforts are greatly increased. Onsite and offsite monitoring teams are dispatched as necessary. In addition to beta and gamma field measurements, the changeout of Dosimeter(s) of Legal Record (DLRs) at frequent intervals is done, as necessary, air sampling and collection of other environmental media for assessment of material transport and deposition is performed as necessary. 6-8 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN 6.3.3.3 Dose assessment activities are conducted with an increased emphasis on dose projection for use as a factor in determining the necessity for protective actions. Radiological and meteorological instrumentation readings are used to project (1) dose rate at predetermined distances from the plant, and (2) an integrated dose. In reporting the dose projection to the Emergency Director or offsite agencies, the dose and the time used for the dose estimate are always provided. Any confirmation of doses by offsite teams is reflected in reporting or revising dose estimate information provided to applicable offsite agencies. 6.3.4 Assessment Actions for General Emergencies Assessment actions for the General Emergency class are the same as for the Site Area Emergency class with a possible shift of emphasis to greater offsite monitoring efforts and dose projection efforts extending to distances farther from the plant. Additionally, since, the projected doses are likely to be much closer to EPA PAGs, greater emphasis is placed on the assessment of release duration. Judgments and assumptions used for dose assessment are always reported. 6.4 Radiological Assessment and Monitoring Accidents involving releases of radioactive materials to the environment require special methods of assessment to ensure responses are appropriate for the protection of the public as well as site personnel. 6.4.1 Field Monitoring Prior to the activation of the entire Onsite Emergency Organization, the Emergency Director may dispatch an offsite radiological monitoring team. The plant has the capability to dispatch one radiological monitoring team and receive initial monitoring data within 90 minutes of the emergency declaration if necessary. This team will consist of two people, one of which is qualified in the use of the equipment contained in the field response emergency kits. When dispatched, the team will pick up field response emergency kits and be assigned designated vehicles. Teams will be equipped with radios. Portable radios are available at the Backup Operational Support Center for use in vehicles without radios or in the case of radio failure. Other means of back-up communications are available as described in the Implementing Document. After picking up an emergency vehicle and conducting an operational check of equipment, including a radio operations check, teams will proceed to their first assigned monitoring point. Field Teams will be controlled by the Offsite Team Coordinator (OTC) working from the EOF, and will report all readings to this individual. Waterford 3 field teams have the ability to measure and detect 10-7 uCi/cc airborne radioiodine under field conditions in the presence of noble gases and . background radiation. 6-9 Rev.048
WATERFORD 3 SES EMERGENCY PLAN 6.4.2 Radiological Assessment Capability to make rapid assessments of the actual or potential magnitude and locations of any radiological hazards through gaseous release pathways is provided by computerized and manual dose assessment procedures included in the Implementing Document.
- a. Radiological and Meteorological Data Sources In evaluating the impacts of an accidental release of radioactive materials, the amount of activity released is the first item that must be determined. This information is available from the Radiation Monitoring System. Systems, and their release paths, which contain or may contain radioactive materials, are monitored by the installed Radiation Monitoring System. Radiation monitor readings and other information useful in performing offsite dose calculations can be found on SPDS mimic display "MARMOND 2, the Plant Monitoring Computer and the RM-11 Radiation Monitoring computer. In addition, these systems are routinely sampled and analyzed. Radiation surveys, contamination surveys, and air samples are performed as necessary to provide support data. If actual data is not immediately available, the magnitude and duration of the release may be estimated by station personnel from plant conditions or from knowledge of the type of incident that (
occurred, and use of survey instruments. Meteorological data and summaries can be found on SPDS mimic display "MARMOND 1." Other sources of meteorological data are described in the Emergency Plan Implementing Procedures.
- b. Other Computerized and Manual Calculations For airborne releases, the first step in the assessment process is to estimate the noble gas and the iodine source release rates. To do this, the Radiation Monitoring System readings for the appropriate monitored gaseous effluent release path is converted to a noble gas and iodine release rate using source release fractions applicable to the type of accident, appropriate ventilation flow rates, instrumentation conversion factors, containment building design leak rate, and other parameters applicable to the release pathway. TEDE and CDE Thyroid dose rates are then projected by applying the appropriate meteorological dispersion factor (X/Q) for the location of interest. Dose rate calculations are normally performed with a computerized system described in the Emergency Plan Implementing Procedures. The calculations can also be done manually. Once the projections are made, the radiation monitoring teams can be directed to the location of interest to take readings and confirm the projection. Projected TEDE and CDE Thyroid dose rates are integrated over the anticipated duration of the accident to determine the TEDE and CDE Thyroid. A nominal time of two hours is assumed for the duration if the actual duration of the 'release cannot be estimated. These integrated doses will be compared to the protective action guides in order to recommend appropriate protective actions. The doses and recommendations will be communicated to the Louisiana Department of Environmental Quality and affected parishes.
If the instrumentation used for radiological assessment is off-scale or inoperative, contingency dose calculation methods are used. The contingency methods use conservative calculation processes using dose release factors that are based upon the expected plant source 6-10 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN 6.4.2b (Cont'd) release terms for several accident classifications. First, the dose release factor for the accident class that most closely fits the current plant conditions is selected. Then, the X/Q for the location of interest is applied to the dose release factor to project the TEDE and CDE Thyroid. Concurrently, radiation monitoring teams are sent to those locations of interest to take actual field measurements in order to refine the projections and to correlate projected versus actual results. These detailed calculation techniques can be performed using the computerized system or manually and are included in an Emergency 1 Plan Implementing Procedure.
- c. Liquid Effluent Discharge A projected dose from a liquid release, whether it is within normal limits or assumed to be an incident, can be determined through procedural methods. The concentrations of radioactivity being released can be determined from installed radiation monitors, samples, release records, or if necessary, estimated. The release rate and flow path can be determined as well. The appropriate dilution factors may be applied to the concentration in the effluent at the point of measurement to allow for the additional dilution by circulating water. Offsite consequences of liquid effluent releases can be determined through the use of plant operating procedures.
6.4.3 Transfer of Radiological Assessment Responsibility Once the nearsite emergency organization is activated, and the Emergency
/ Director declares it operational, the responsibility for offsite radiological assessment will be transferred to the EOF. The decision of when to transfer responsibility for offsite radiological monitoring will be made by the Emergency Director. A formal radio announcement at the time of this transfer will be made to all offsite monitoring teams. Upon assuming offsite radiological dose assessment, the Radiological Assessment Coordinator/Offsite Team Controller shall direct teams and perform offsite dose calculations and verifications as well as inform the Emergency Director of the results. Waterford 3 will continue to update dose projections and plant conditions, and coordinate dose assessment activities and exchange data with LDEQ personnel at the EOF.
6.5 Corrective Actions Detailed operating procedures are available to the operators for use during emergencies as well as during normal operations. Specific Emergency Procedures are provided to assist the operators in placing the plant in a safe condition and taking the necessary supplemental corrective actions. In addition, Operations personnel are trained in the operation of plant systems and their associated procedures, and are, therefore, capable of taking appropriate corrective actions based on their training, knowledge and experience. Selected Waterford 3 Steam Electric Station Personnel are trained for and assigned to emergency teams. (Reference Section 5.0, Organizational Control of Emergencies). These teams are capable of responding to situations as set forth in the Emergency Plan Implementing Instructions and Procedures in order to assess conditions and take any applicable corrective actions. Maintenance personnel provide the necessary"crafts expertise to effect repair and damage control functions. 6-11 Rev.048
)
WATERFORD 3 SES EMERGENCY PLAN 6.5 (Cont'd) Corrective actions shall normally be planned events that are taken to control or terminate the emergency situation. Planned radioactive releases or corrective actions that may result in a radioactive release are reported to the appropriate offsite emergency response organization and/or agencies. Entergy Operations, Inc. recommendations to authorities responsible for offsite emergency measures are made by the Emergency Director working from the EOF or if such recommendations are necessary prior to the EOF becoming fully operational, by the Shift Manager serving as the Emergency Director. 6.6 Protective Actions Emergency measures taken during or after an emergency situation that are intended to minimize or eliminate the hazard to the health and safety of the general public and/or site personnel are considered protective actions. Such actions taken onsite are the responsibility of Entergy Operations, Inc. while those taken offsite fall under the jurisdiction of the State of Louisiana and affected parishes. A range of protective actions to protect onsite personnel during hostile action is provided to ensure the continued ability to safely shut down the reactor and perform the functions of the Emergency Plan. A combination of restricted movement, movement to safe locations and site evacuation may be used depending on the nature of the event and available advance warning. Each Implementing Instruction used in classifying emergencies has predetermined Initiating Conditions (ICs). These ICs when met or exceeded, require that protective actions are initiated to ensure that both onsite and offsite personnel are notified and protected. 6.6.1 Evacuation, Personnel Accountability During an emergency, the relocation of persons may be required in order to prevent or minimize exposure to radiation, radioactive materials or other substances such as toxic chemicals. The following subsections discuss the policies applying to such situations. 6.6.1.1 Site Protective Measures. Site protective measures are initiated upon the declaration of a Site Area Emergency, General Emergency, or at the discretion of the Emergency Plant Manager. This action is based upon the results of assessments of existing and potential environmental conditions and consists of site evacuation. Accountability is considered a site protective measure.
- a. Site Evacuation This evacuation occurs by private vehicle via Highway 18 to St.
John the Baptist Catholic Church in Edgard, La. or to Monsanto Park in Luling, La. An announcement will be made by the Shift Manager, Emergency Plant Manager or Emergency Director specifying which assembly area will be used. The assembly area to be used is determined by the emergency organization prior to the evacuation announcement. Once at the offsite assembly area, all personnel are assembled, with trained individuals performing monitoring of personnel and vehicles for radioactive contamination. Individuals found to be contaminated are 6-12 Rev.048
WATERFORD 3 SES EMERGENCY PLAN 6.6.1.1 (Cont'd) decontaminated in accordance with applicable Radiation Protection procedures. Vehicles found to be contaminated are impounded at the assembly area to await decontamination and final disposition.
- b. Accountability Accountability of personnel within the protected area is performed by the Security Department in accordance with Security and Emergency Plan Implementing Procedures.
Utilizing the capabilities of the security computer system, accountability can be performed within 30 minutes of implementation. Should the security computer or the accountability keycard readers be inoperative, alternative methods of accountability as sp'ecified in the Emergency Plan Implementing Procedures will be utilized. Upon activation of each of the emergency response facilities, continuous accountability is performed by procedure for each facility's personnel. The movement of personnel for the purposes of accountability may be delayed if their health and safety could be in jeopardy, for cases such as severe weather or hostile action. In these cases, accountability will be completed once safe conditions have been 'established. Personnel and the general public in the Exclusion Area outside the Protected Area and selected areas where members of the public may be expected to. congregate in the Owner Controlled Area are evacuated, or if required to be in the area, are accounted for. Roving Security personnel make evacuation announcements in these areas. St. Charles Parish addresses actions in areas of the Owner Controlled Area where members of the public are generally not expected to be present. The Union Pacific Railroad will be contacted to request suspension of rail traffic through the Exclusion Area. The Coast Guard will be contacted to request suspension of river traffic within the Exclusion Area. Re-entry control will be maintained within the Exclusion Area following the evacuation. ' 6.6.1.2 Offsite Protective Action Re'commendations During emergency situations, the responsibility for providing protective action recommendations for the general public lies with Entergy Operations, Inc. Within the Entergy Operations, Inc. emergency response organization, there is at all times one individual responsible for those recommendations to State and parish agencies. Section 5.1.2.1.a of this plan defines the individual responsible to be the Shift Manager (SM) until the arrival of the Duty EOF Emergency Director who will officially relieve* the SM as the Emergency Director. When the Emergency Operations Facility (EOF) is operational, the Shift Manager acting as the Emergency Director shall transfer the responsibilities for Protective Action Recommendations. to offsite agencies to the EOF Emergency Director. 6-13 Rev. 048
*WATERFORD 3 SES EMERGENCY PLAN 6.6.1.2 (Cont'd)
Recommendations for offsite Protective Actions will be made directly to those State and Parish organizations linked to the Operational Hot Line: LDEQ, GOHSEP, St. Charles Parish, and St. John the Baptist Parish. When possible, these recommendations will be coordinated with LDEQ in the EOF. LDEQ's actions will be in accordance with the State plan. There are two general sets of Waterford 3 Protective Action Guidelines. One set is based on dose projections, and the other is based on in-plant conditions. (1) The first set of guidelines, based on dose projections, is consistent with both the USEPA PAGs and with the PAGs of the State of Louisiana Peacetime Radiological Response Plan. The PAGs are nuclear criteria based on dose projections from which pre-determined actions may be taken. These criteria are not inflexible limits nor are they "safe" levels below which no protective action is indicated. Rather, they will be used to minimize risks for an accident that is occurring or has occurred. The following guidelines will be utilized:
- a. TEDE pro}ected dose less than 1 rem or COE Thyroid projected dose less than 5 rem:
No immediate action necessary.
- b. TEDE projected dose greater than or equal to 1 rem or COE Thyroid projected dose greater than or equal to 5 rem:
Evacuation or sheltering will be recommended in affected areas. Recommendations for offsite protective actions will be made by Entergy Operations, Inc., based on projected doses. The determination of the projected dose will be based on radiological, meteorological and operational information including:
- 1. Radiation monitoring system data.
- 2. Meteorological instrumentation data.
- 3. Field monitoring team data.
- 4. FSAR design basis accident assumptions.
- 5. Reactor core temperatures.
- 6. Fission product barrier integrity.
- 7. Projected duration of release based on reactor plant status.
6-14 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN It should be understood that not all of the above information is needed to project doses. The immediately available information will be used to meet the 15-minute 6.6.1.2 (Cont'd) requirements mentioned in 6.2.1, and subsequent information will be used to modify or refine the early dose projections and corollary protective action recommendations. (2) The other basis for Waterford 3 PAGs is preemptive in nature and is not based on the release of radioactive materials, but rather on various instrument readings and plant status that indicate problems are developing which could lead to such a release. As described in Chapter 4.0 of this Plan, four emergency classes have been established for Waterford 3, along with their attendant Initiating Conditions (ICs). The ICs, where appropriate, have been flagged to instruct the responsible persons that protective action recommendations are required. Protective actions will be implemented within predesignated areas by LDEQ and the local parishes. Recommended protective actions taken may include:
- 1. Evacuation or sheltering for affected population.
- 2. Evacuation or sheltering of population within a specified predetermined section of Waterford 3.
- 3. Monitor and Prepare for the population in unaffected areas in the plume EPZ.
Following initial protective actions, subsequent dose projections and monitoring results will be used to determine the need for . extending the initial response area or increasing the scope of the initial protective actions. Monitor and Prepare is defined as a precautionary action intended to advise the public within the EPZ that a serious emergency at the nuclear power plant exists and that they should monitor the situation and prepare for the possibility of having to evacuate or Shelter in Place. Sheltering in place is defined as remaining within protective structures in order to minimize exposure to the gaseous plume and direct exposure to deposited radionuclides. The effectiveness of a structure in reducing direct external radiation exposure depends primarily on the thickness and composition of the building materials. Figure 6-4 lists representative cloud gamma attenuation factors for various types of shelters including residential and industrial buildings. The effectiveness of shelters ih reducing inhalation exposure depends on the overall building integrity, ventilation rate and filtering characteristics, including trapping and deposition in small cracks or openings. Figure 6-4 also lists the ventilation characteristics of representative residences. 6-15 Rev.048
WATERFORD 3 SES EMERGENCY PLAN In evacuation, the general public is moved out of the path of the gaseous radioactive plume. It is expected that, should evacuation be required, it will be implemented well before a radionuclide release has begun. 6.6.1.2 (Cont'd) Evacuation of members of the general public is the responsibility of the local parishes, working in conjunction with LDEQ, and will be carried out in accordance with their prearranged plans. The general steps to be followed are as follows:
- 1. Collaborative response actions will be maintained between the LDEQ Liaison Team Director located in the EOF and the parish Emergency Preparedness/Civil Defense Directors at their respective local EOC;
- 2. The area to be evacuated, the evacuation routes and reception center arrangements will be agreed upon by the State and local agencies;
- 3. The parish Sheriff's and Emergency Preparedness/Civil Defense Departments will carry out the evacuation in accordance with established procedures and isolate the evacuated area;
- 4. Reentry into the evacuated areas will be prevented until it is confirmed that radiological conditions permit unrestricted access.
6.6.1.3 Offsite Protective measures for the general public are the responsibility of the risk parishes in conjunction with LDEQ and GOHSEP. Provisions for protection of the public are outlined in the Louisiana Peacetime Radiological Response Plan and Attachment 1 to that plan which is site-specific to Waterford 3. Responsibilities of key agencies and individuals are covered below:-
- a. State
- 1. Governor of Louisiana The governor of Louisiana can order protective measures for the public if a state of disaster emergency is declared.
- 2. Secretary of the Department of Environmental Quality The Secretary of the Department of Environmental Quality is responsible for finalizing a protective response recommendation as received from LDEQ.
- 3. LDEQ The LDEQ develops protective response recommendations based on facility information and data gathered by LDEQ field monitoring teams.
6-16 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN 6.6.1.3b (Cont'd)
- 4. GOHSEP The GOHSEP coordinates state resource support for risk parishes if protective actions are required.
- b. Risk Parishes
- 1. Parish President The Parish President has the overall responsibility for the protection of the health, safety and welfare of persons living and working in the parish. He (she) is the individual responsible for making protective response recommendations to the public in the risk area.
- 2. Parish Emergency Preparedness/Civil Defense Directors Director serves as chief-of-staff for the Parish President.
Directs implementation of offsite protective response decisions.
- c. Protective Response In the event of an accident at W3SES, the decision to protect the general public, institutionalized persons and transients will be based on the U.S. Environmental Protection Agency Manual of Protective Action Guides and Protective Actions. The protective actions that may be considered include evacuation, breathing protection and sheltering in place. These actions can be taken for all predesignated parts of the plume exposure pathway EPZ.
The alert/notification of the public will be accomplished in accordance with Section 6.8.1. If protective actions are called for, provisions have been made to provide appropriate controls within the affected area. Arrangements for the reception and care of evacuees have been established in support parish plans. 6.6.2 Use of Onsite Radiological Protective Equipment and Supplies 6.6.2.1 W3SES maintains an inventory of protective clothing, respiratory equipment, survey instruments, radioprotective drugs, and other protective equipment and supplies to provide adequate contamination control for all personnel expected to be onsite who might be affected in the event of an emergency. A brief description of the types of equipment that might be found in emergency equipment lockers is provided in Section 7.4.8. The actual inventory and location of their storage is listed in the Implementing Documents. 6.6.2.2 Procedures for -the distribution and use of radioprotective drugs for emergency workers are incorporated into the Emergency Plan Implementing Procedures. 6.6.3 Radiological Contamination Control Measures 6-17 Rev. 048 _)
WATERFORD 3 SES EMERGENCY PLAN This section describes provisions for preventing or minimizing direct or subsequent ingestion exposure to radioactive materials deposited on the ground or other surfaces. 6.6.3.1 Onsite and Exclusion Area Waterford 3 SES has onsite contamination control procedures that provide for monitoring, access control, decontamination and using techniques for minimizing the spread of contamination. Any individual found to have contamination levels in excess of 100-cpm/probe area above background, as measured by a pancake-type GM Tube, is considered to be contaminated. Onsite measures are taken to prevent or minimize the ingestion of radioactive materials deposited on the ground or other surfaces. As necessary, food supplies grown within the exclusion area are isolated. Drinking water is normally supplied by the St. Charles Parish Waterworks. As the situation warrants, bottled drinking water is brought onto the site. Additionally, there are procedures to monitor for contamination during emergency and recovery phases in areas designated for eating and drinking. Eating and drinking are prohibited in all other areas during the incident. The Emergency Plant Manager may request assistance from such organizations as the St. Charles Parish Sheriffs Office, the Louisiana State Police, LDEQ, the Union Pacific Railroad Company, the United States Coast Guard and others as necessary to move personnel and to isolate and control access to affected areas within the Exclusion Area boundary. The movement of onsite personnel to unaffected areas is initiated for their protection should radiation or airborne activity levels in their immediate environment warrant such actions. Specific criteria for permitting return of areas to normal use are included in the Emergency Plan Implementing Procedures. Reentry into affected- areas is a controlled process performed under the procedures described in the Emergency Plan Implementing Procedures. Surveys are performed in areas posted and/or decontaminated. Environmental samples are obtained and analyzed. Entergy Operations, Inc. maintains control over the Exclusion Area as required, and restores affected onsite areas to acceptable conditions for access where possible. Waste generated as a result of decontamination activities during and after an accident is handled in the same manner as during normal operation, in accordance with Radiation Protection Procedures. Entergy Operations, Inc. requests assistance from and uses guidance provided by LDEQ in handling food crops and water supplies within the area. 6.6.3.2 Offsite Actions taken offsite for the control of contamination are the responsibility of LDEQ. Any response to such incidents by LDEQ is in accordance with the Louisiana Peacetime Radiological Response Plan and its Waterford 3 SES Attachment. Entergy Operations, Inc. provides information and data pertinent to such incidents, makes recommendations for offsite actions as appropriate, and, when possible, provides assistance. 6-18 Rev. 048
WATERFORD .3 SES EMERGENCY PLAN
- 6. 7 Aid to Affected Personnel This section of the plan describes the measures that are used by Waterford 3 to provide necessary assistance to persons injured or exposed to radiation and radioactive material.
6.7.1 Emergency Personnel Exposure Emergency personnel, including those involved in removal of injured persons, undertaking corrective actions, performing assessment actions, providing first
- aid, performing personnel decontamination, and providing ambulance services, will have their exposure kept as low as reasonably achievable. This is accomplished through normal radiological control practices onsite. When personnel are called in from offsite, qualified Radiation Protection technicians are provided as necessary to support the offsite teams. For example, a Radiation Protection technician may be assigned to the offsite fire teams to monitor and control radiation exposures and evaluate radiological hazards. Emergency measures may warrant the acceptance of above normal radiation exposures (doses).
Saving of life, measures to circumvent substantial exposures to population groups or other accident-mitigating activities may all be sufficient cause for above normal exposures. The following are the exposure guidelines for these emergency activities:
- 1. Life-saving action - 25 rem TEDE, 250 rem Extremities, 250 rem Thyroid, 75 rem Lens of Eye
- 2. Corrective action - 10 rem TEDE, 100 rem Extremities, 100 rem Thyroid, 30 rem Lens of Eye The Emergency Director (or Emergency Plant Manager for in-plant conditions) is the designated individual who can authorize emergency workers to receive doses as defined above in excess of 10CFR20 limits. These workers must be volunteers, and as such, sign a letter of understanding, and are required to closely adhere to the controls specified in applicable procedures. Declared pregnant females shall be excluded from activities involving emergency exposure. The Emergency Director or EPM, to the extent practicable, coordinates with the NRC prior to authorizing exposures in excess of 10CFR20 limits. In authorizing onsite volunteers to receive radiation exposure in the course of carrying out lifesaving activities, the Emergency Director balances the risks from such exposures against the benefits to be received from the lifesaving activities. Risks are determined and decisions are made to expedite lifesaving activities based upon advance radiation surveys done at the affected areas to determine stay times, shielding requirements, or the possibility of dispatching a "scouting" team to assess actual conditions. Personnel are briefed on stay times, use of protective equipment, potential hazards and communication requirements. Measures are utilized to aid in exposure reduction and the Emergency Plant Manager, in consideration of advice from the Radiological Coordinator, shall assure that all possible measures are taken to minimize other exposures (such as internal exposures) during the activities. Exposure records are maintained for all station personnel, and such information is used in determining emergency team assignments. It is not possible to predict the time and place an accident will occur; however, personnel in areas where there 6-19 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN' is the possibility of exposure to radioactive material are required to wear personnel monitoring devices in accordance with 10CFR20. If an accident occurs, assistance may be required from personnel available at the scene or from emergency teams. Responding emergency teams obtain personnel monitoring devices that are required for the area or for the situation. 6.7.1 (Cont'd) Extremity monitoring devices are located at the Reactor Auxiliary Building - Controlled Access Area Access Control Point. Whole body monitoring devices are available at the Security Primary Access Point. Personnel monitoring is performed in accordance with the Emergency Plan Implementing Procedures. Capability to determine the doses received by emergency personnel and volunteers on a 24-hour/day basis is provided. Additionally, dosimetry is read at appropriat~ intervals for maintaining dose records for emergency workers. 6.7.2 Thyroid Blocking A ready supply of suitable thyroid blocking agent is maintained and available for use by emergency workers. Guidance for administration of the blocking agent is specified in applicable Emergency Plan Implementing Procedures. 6.7.3 First Aid and Decontamination Emergency medical care to injured/ill personnel is initiated regardless as to whether the injury/illness is radiation or non-radiation associated. First aid/emergency medical care, conforming to procedures specified in applicable Emergency Plan Implementing Procedures and Appendix I, Emergency Medical Assistance Plan (EMAP), is provided at the accident scene. In the event of a serious injury, the medical treatment takes precedence over decontamination. Provisions for any required personnel decontamination are provided in the Radiation Protection area which contains showers, sinks, eyewash supplies, cleaning agents and materials, contamination monitoring equipment, and materials to control the spread of contamination, along with the necessary first', aid/emergency care supplies specified in the Implementing Document. Ideally, injured/ill or contaminated personnel exiting the controlled access area are monitored and* decontaminated prior to being transported to support medical facilities. However, in cases of life threatening trauma/illness or persistent contamination, where patients must be transported to support medical facilities prior to complete decontamination, measures are taken to minimize the spread of contamination in accordance with Radiation Protection Procedures. A Radiation Protection technician will accompany contaminated patient(s) to the supporting hospital to supervise control of contamination and serve in an advisory capacity. Personnel leaving the controlled access area are monitored by appropriate portal monitors, counters or friskers. During emergencies, personnel onsite will, as necessary, be checked for contamination based on specific criteria found in the Implementing Document. Personnel found to be contaminated are decontaminated under the direction of Radiation Protection personnel. Measures taken to prevent the spread of contamination include isolating affected areas, placing contaminated personnel in "clean" protective clothing prior to moving, and decontaminating affected personnel, their clothing, and equipment before release. Details for personnel decontamination are included in Radiation Protection Procedures. 6-20 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN For managing first aid and emergency medical care for life-threatening medical emergencies, wo_und decontamination, treatment requiring administration of radioprotective drugs, overexposure or persistent contamination, medical consultation and/or onsite physician assistance is available through qualified medical personnel at Ochsner Clinic Foundation, West Jefferson Medical Center or the Radiation Emergency Assistance Center/Training Site (REAC/TS).
- 6. 7.3 (Cont'd)
Non-life-threatening, minor injuries/illnesses are managed consistent with the training of the first aid team personnel and based on specific guidelines provided in the Implementing Document. Waste generated during decontamination activities following an accident is handled the same as during normal operation. In accordance with Radiation Protection Procedures, the waste is packaged in accordance with NRC and DOT regulations. Waste containers will be stored onsite, in a secure area having adequate shielding, awaiting shipment to a commercial low-level waste disposal facility. 6.7.4 Medical Transportation Entergy Operations, Inc. maintains agreement with the St. Charles Parish Hospital Ambulance Service, an advanced life support staffed/equipped service, for emergency medical care and transportation of injured personnel to offsite support medical treatment facilities. The vehicles(s) have radio communications capability to the St. Charles Parish 911 Center for dispatch and coordination and to the necessary support hospitals (Ochsner Clinic Foundation, West Jefferson Medical Center and St. Charles Parish Hospital), for appropriate medical consultation/notification, as outlined in Emergency Plan Implementing Procedures and Appendix I, Emergency Medical Assistance Plan. An agreement is in effect with Ochsner Flight Care Helicopter Ambulance to transport Waterford 3 personnel to support medical facilities, should air helicopter transport be determined advisable for medically unstable patients or if ground transportation is impractical. The Waterford 3 Shift Manager/Emergency Director in consultation with members of the First Aid Team will determine the priorities for the mode of emergency medical transportation based on the need for immediate medical intervention, the comfort of the patient, and the vehicles available. Support hospitals receive prior notification of patients with radiological complications being transported to their emergency departments for emergency medical care. Procedures for notification and content are specified in Emergency Plan Implementing Procedures and Appendix I, Emergency Medical Assistance Plan. Following the transportation to and admission of a contaminated patient(s) to the support hospital Radiation Emergency Area, the ambulance vehicle, associated equipment and emergency medical personnel are surveyed by the Waterford 3 Radiation Protection personnel assisting the hospital Radiation Management Team. If contamination is detected, the ambulance is returned to Waterford 3 for decontamination, as necessary. 6.7.5 Medical Treatment Arrangements for medical treatment of personnel from Waterford 3 are predetermined through written agreements with offsite medical facilities. 6-21 Rev.048
WATERFORD 3 SES EMERGENCY PLAN Ochsner Clinic Foundation, New Orleans, Louisiana, a 532-bed acute-care medical facility, designated as the regional medical resource hospital and regional trauma center agrees to accept and provide treatment to Waterford 3 personnel experiencing injury/illness, provide long-term treatment or evaluation of radiation-associated injuries or overexposure, and provide medical ' consultation or onsite physician assistance to the Emergency Plant Manager/First Aid Team. ( 6.7.5 (Cont'd) West Jefferson Medical Center, Marrero, Louisiana, a 462-bed acute-care medical facility, designated as an area-wide trauma center, agrees to accept and provide treatment to Waterford 3 personnel experiencing injury/illness and to provide long-term treatment or evaluation of radiation associated injuries or overexposure, and provide medical consultation or onsite assistance to the Emergency Plant Manager/First Aid Team. St. Charles Parish Hospital, Luling, Louisiana, a 50-bed acute-care general hospital, agrees to accept and treat personnel from Waterford 3 having experienced injuries or illness uncomplicated by radiation contamination or overexposure. All three support hospital facilities further agree to participate to the fullest extent possible in training programs and emergency medical drills intended to maintain emergency preparedness. The admission of injured/ill patients to the supporting hospital will be governed by standard admissions procedures. However, in the event that the injured/ill patient is radioactively contaminated, normal admissions procedures will be superseded by the appropriate procedures for medical emergencies involving radiation contained within the supporting hospital's Emergency Management Plan. For extreme radiation accident cases, the Department of Energy provides patient referral facilities to Ochsner Clinic Foundation and West Jefferson Medical Center through the Radiation Emergency Assistance Center/Training Site. 6.8 Public Alert/Notification and Public Information 6.8.1 Public Alert/Notification The means for the alert/notification of the public in the event of an accident at W3SES have been established upon the direction of the emergency preparedness/civil defense department of the risk parishes. Once local and State authorities have been notified of the accident and the decision to take protective actions has been made, the alert/notification cif the public will be accomplished. Back-up means of notifying the public include the use of route alerting as outlined in the WF3 ANS FEMA Design Report. 6.8.2 Public Information St. Charles Parish, St. John the Baptist Parish, LDEQ, GOHSEP and Entergy Operations, Inc., coordinate the dissemination of printed material to the public 6-22 Rev.048
WATERFORD 3 SES EMERGENCY PLAN within the 10-mile EPZ. This printed material informs the public as to how they will be notified and what their actions should be in an emergency. This printed material contains information on radiation, protective measures, special needs of the handicapped, and points of contact for obtaining further information. 6-23 Rev.048
W3 SES EMERGENCY PLAN FIGURE 6-1 WATERFORD 3 EMERGENCY ORGANIZATION ACTIVATION SCHEME I SHIFT M.A.NAGER I I I NUCLEAR AUXillARY EMERGENCY OPERATOR EMERGENCY PiANi COMMUNICATOR MANAGER I I '- ACTlVATION OF COMPANY EMERGENCY ONSlTE SPOKESPERSON ERF DIRECTOR ORGANIZATION I I I I I I I I I TSC RADIOLOGICAL REACTOR Electricalll&C CHEMISTRY ENTERGY DUTY COMMUNICATOR COORDINATOR ENGINEER ENGINEER TECHNICIAN OPERATIONS EMERGENCY CORPORATE JIC STAFF PLANNER
- COMMUNICATiONS I
EOFSTAFF ENGINEERING RP ,_ MECHANICAL OPERATIONS rsc TECHNlCIANS ENGINEER COORDINATOR COORDINATOR MANAGER ENS osc osc EOC
""' COMMUNICATOR STAFF - TSC SIAFf' MANAGER .__ UAISONS
*ACTIVATED WITH ONSITE EMERGENCY ORGANIZATION. PART OF EOF STAFF A-6-1 Rev.048
WATERFORD 3 SES EMERGENCY PLAN FIGURE 6-2 NOTIFICATION MESSAGE FORM (Typical)
- 1. THIS IS WATERFORD 3 WITH MESSAGE NUMBER F-_ _ __
(OHL CODE NO.) _ _ _ __
- 2. A. ----~-------B. COMM: - - - - - - - - - - - - C. TEL N O . - - - - - -
(TIME/DATE) (NAME)
- 3. EMERGENCY CLASSIFICATION:
A. D NOTIFICATION OF UNUSUAL EVENT C. D SITE AREA EMERGENCY E. D TERMINATED B. DALERT D. D GENERAL EMERGENCY
- 4. CURRENT EMERGENCY CLASSIFICATION DECLARATION/TERMINATION Time/Date:_ _ _ _ _._ _ _ __
- 5. RECOMMENDED PROTECTIVE ACTIONS:
A. D No Protective Actions Recommended At This Time (Go to Item 6). B.DEVACUATE _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ D MONITOR AND PREPARE _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ DSHELTER - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
- 6. INCIDENT DESCRIPTION/UPDATE/COMMENTS:
- 7. REACTOR SHUT DOWN? D NO DYES Time/Date: -----~*/_ _ _ _ __
- 8. METEOROLOGICAL DATA:
A. Wind Direction FROM-----...,-------- Degrees at _ _ _ _ _ _~ MPH B. Sectors Affected (A-R): - - - - - - - - - - - - - - - - - - - - - - C. Stability Class (A-G): - - - - - - - - - - - - - - - - - - - - - D. Precipitation: D None D Rain D Sleet D Snow D Hail D Other _ _ _ _ __
- 9. RELEASE INFORMATION:
A. D No RELEASE (Go to Item 13) B. D A RELEASE is occurring BELOW federally approved operating limits C. D A RELEASE is occurring ABOVE federally approved operating limits D. D A RELEASE OCCURRED BUT STOPPED E. Release started at _ _ _ _ _ _ (time) Release stopped at _ _ _ _ _ _ (time) Release duration hrs. (actual or expected)
- 10. TYPE OF RELEASE:
A. D Radioactive Gases B. D Radioactive Airborne Particulates C. D Radioactive Liquids
- 11. RELEASE RATE:
A. NOBLE GASES Ci/s B. IODINES _ _ _ _ _ _ _ _ _ _ _ Ci/s
- 12. ESTIMATE OF PROJECTED OFFSITE DOSE:
A. Projections for hours based on: D Field Data D Plant Data D Default Data B. (TEDE) WB DOSE COMMITMENT (mRem) C. (COE) THYROID DOSE COMMITMENT (mRem)
. Site Boundary____ 5 miles _ _ __ Site Boundary____ 5 miles _ _ __
2 miles 1O miles _ _ __ 2 miles 10 miles _ _ __
- 13. MESSAGE APPROVED BY: _ _ _ _ _ _ _ _ _ _ _ _ _ TITLE: - - - - - - - - - - - -
A-6-2 Rev. 048
W3 SES EMERGENCY PLAN FIGURE 6-3 INITIAL NOTIFICATION PERSONNEL SCHEME Organization Primary Alternate Waterford 3 Emergency Communicator Emergency Director Louisiana Department of Administrator LDEQ Duty Officer Environmental Quality St. Charles Parish Emergency Preparedness Emergency Coordinator Director St. John the Baptist Parish Civil Defense Director Public Safety Dispatcher Governor's Office of Assistant Deputy Director GOHSEP Duty Officer Homeland Security & Emergency Emergency Management Preparedness A-6-3 Rev.048
W3 SES EMERGENCY PLAN FIGURE 6-4 EFFECTIVENESS OF SHELTERS REPRESENTATIVE CLOUD-GAMMA ATTENUATION FACTORS Structure Attenuation Factor Wood frame house, no basement 0.9 Masonry house, no basement 0.6 Basement of wood house 0.6 Basement of masonry house 0.4 Large office or industrial building 0.2 or less AIR CHANGES TAKING PLACE UNDER AV,ERAGE CONDITIONS IN RESIDENCES, EXCLUSIVE OF AIR PROVIDED FOR VENTILATION Kind of Room of Building Number of Air Changes Taking Place per Hour* Rooms with no windows or exterior doors 1/2 Rooms with windows or exterior doors on one side Rooms with windows or exterior doors 1-1/2 on two sides Rooms with windows or exterior doors 2 on three sides Entrance halls 2
- For rooms with weather-stripped windows or with storm sash, use two-thirds of these values.
A-6-4 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN 7.0 EMERGENCY RESPONSE FACILITIES AND EQUIPMENT The emergency equipment and facilities described in this section operate as an integrated system to support the Control Room in the mitigation of the'consequences of an accident and act to enhance Entergy Operations, lnc.'s capability to respond to abnormal plant conditions. The equipment and facilities function during an emergency to provide the following services:
- a. Aid reactor operators in the determination of plant safety status.
- b. Relieve the Control Room of those duties and responsibilities not directly related to reactor systems manipulation.
- c. Eliminate unnecessary Control Room traffic.
- d. Provide technical assistance to Control Room personnel through the use of technical personnel and comprehensive plant data.
- e. Provide a coordinated response by both technical and management personnel.
- f. Provide reliable communications between onsite and nearsite emergency response personnel.
- g. Provide a focal point for the development of recommendations for offsite actions.
- h. Provide to the NRC, for its analysis, relevant plant data.
- i. Support accident mitigation operations.
- j. Activate the resources required to mitigate the consequences of an accident.
- k. Provide protection to station personnel.
I. Provide immediate care for injured personnel.
- m. Effect damage control measures.
A diagram identifying the emergency facilities and their general location relative to each other is attached as Figure 7-1, 7-2 and 7-3. Many of the Waterford 3 facilities and much of the equipment is employed in the daily operation of the station .. Other facilities and equipment are reserved for use only on an emergency "as needed" basis. 7 .1 Waterford 3 On site Emergency Facilities 7 .1.1 Control Room The Control R,oom is located on the 46.0 ft. MSL elevation of the Reactor Auxiliary Building and is designed to be habitable under accident conditions. The ven'tilation system has redundant fans and chillers and is provided with radiation, chemical and smoke detectors with appropriate alarms and interlocks. The emergency lighting, power air-filtration-ventilation system, cascade air system and shield walls enable operators and other emergency support personnel to remain in these areas with adequate protection. The physical arrangement of the Control Room is shown in Figure 7-5. Permanent radiation monitoring is installed in the Control Room. These systems continuously monitor radiation dose rates and airborne radioactivity concentrations. These monitoring systems include local alarms set to provide early warning to personnel of adverse conditions that could affect habitability. 7-1 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN 7.1.1 (Cont'd.) The Operations Group supplies continuous shift coverage and staffs the main Control Room at all times. The operator(s) keep the Shift Manager informed of abnormal and accident situations or conditions. The communications, procedures, controls and instrumentation required for safe plant operation and for accident assessment are located in this area. Emergency equipment and supplies needed to support Emergency Actions by shift personnel are also located in close proximity to the Control Room. 7.1.2 Technical Support Center The Technical Support Center (TSC) is located on the 46.0 ft. MSL elevation in the Reactor Auxiliary Building. It is contained entirely within the Control Room emergency ventilation system envelope but separate from the Control Room. Fixture installations within the various areas of the TSC prevent the TSC from being seismic Category I qualified. The physical arrangement of the TSC is shown in Figure 7-6. In the event that access to the Control Room envelope is limited and response procedures require TSC activation, a Backup TSC will be established in the EOF. The primary function of the TSC will be performed in cohabitation with EOF personnel. In its location, the TSC is in the closest possible proximity to'the Control Room and readily allows face-to-face interaction between TSC and Control Room personnel. The size of the TSC provides sufficient storage space and access to data displays, plant records and historical data. Located in the Control Room envelope, the TSC has the same heating, ventilation, air conditioning and radiological habitability as the Control Room for postulated accident conditions. Personnel are protected from radiological hazards, including direct radiation and airborne contaminants, under accident conditions, within the guideline criteria of General Design Criterion 19 and Standard Review Plan Section 6.4. Particulate (HEPA) and charcoal filters are an integral part of the ventilation system. The ventilation system is designed to seismic Category I design criteria and is automatically activated as a part of the Control Room ventilation systems. Personnel in the center will not receive doses in excess of 5 rem to the whole body or 30 rem to the thyroid for the duration of the accident. The TSC has facilities to support the plant management and tech~ical personnel who are assigned there during an emergency and is the primary onsite communications center for the plant during the emergency. TSC personnel use the TSC data system (see Section 7.4.11) to analyze the plant steady state and dynamic behavior prior to and throughout the course of an accident. This information is transmitted to the TSC via the plant computer to four Satellite Display System (SOS) units. Emergency power supply to the plant computer is provided from the computer SUPS and emergency diesel generators. The results of this analysis are used to provide guidance to the Control Room operating personnel in the management of abnormal conditions and in accident mitigation. TSC personnel use the environmental and radiological information available from the TSC data system to perform the necessary functions. The TSC also is used to provide technical support during the recovery operations following an emergency. 7-2 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN 7.1.2 (Cont'd) The TSC acts as a complete and up-to-date repository of plant records and procedures and is at the disposal of TSC personnel to* aid in their technical analysis and evaluation of emergency conditions. In particular, up-to-date as-built drawings of the plant systems are available to diagnose sensor data, evaluate data inconsistencies, and identify and counteract faulty plant system elements .
. To ensure that TSC personnel can remain self-sufficient, emergency equipment and supplies are stored in the Technical Support Center (see Section 7.4.8).
7.1.3 Operational Support Center The primary location for the Operational Support Center (OSC) is in the Maintenance Support Building (MSB). An area of .the first floor (+18.5 MSL) is designated as the OSC Command Room (Figure 7-7). The OSC is an assembly area where the operations support personnel and members of the emergency teams report in an emergency situation. The OSC can accommodate at least 100 people. Communications is provided with the Control Room, the Technical Support Center and the Emergency Operations Facility. An inventory of emergency supplies including respiratory protection, protective clothing, portable lighting and communications equipment is stored in the OSC for use by emergency response personnel assigned to the facility. Although it is physically separate from the MSB, an instrumentation laboratory can be used for radiation protection purposes. The laboratory is located in the -4 RAB and is considered part of the OSC. Access control to the Radiologically Controlled Area (RCA) may be through the Westside Facility or the -4 elevation of the Reactor Auxiliary Building. Other control points are established as necessary. Associated with the -4 access control point are lockers, toilets, showers and change room facilities. Separate facilities are provided for men and women. Space is provided in the Westside Access for Radiation Protection personnel. Associated with the Westside Access is space for Whole Body Counting, access and exit control terminals, personnel and tool contamination monitors. Space is reserved for personnel at the -4 elevation control point for Radiation Protection/Chemistry personnel. It is provided for equipment, records and supply storage. Space for instrumentation issue and storage may be provided near the Westside Access or the -4 Control Point. The counting room located in the -4 elevation RAB control point area provides facilities for analysis of samples. Portable sample counting instrumentation will be utilized at other control points as necessary. Limited personnel decontaminations may be performed in the Westside Access. The -4 control point decon facility will be used on a case by case basis, for example in the event personnel showering is needed. Contaminated equipment will normally be decontaminated in the decontamination facility located on the
+21.00 ft. west wing area. Other equipment decon locations may be approved by Radiation Protection.
Personnel contamination monitors, tool and personnel contamination friskers are located at the -4 and Westside Access control points. All personnel exiting the Radiologically Controlled Area will be monitored. Respiratory protection equipment is issued and stored near the access control points. Portal monitors are also located at the Primary Access Point in the administration building. 7-3 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN 7.1.3 (Cont'd.) Other in-plant control points may be established as applicable to ensure positive radiation control, and provide protective equipment and supplies. The Maintenance Support Building does not provide habitability comparable to the Control Room and TSC, thus a backup location is provided. The backup OSC is located in the Generation Support Building Executive Conference Room and is capable of functioning in the same manner as the primary OSC. 7.2 Waterford 3 Nearsite and Offsite Emergency Facilities 7.2.1 Emergency Operations Facility The Emergency Operations Facility (EOF is located within the James M. Cain Energy Education Center (see figure 7-4). The James M. Cain Energy Education Center is located approximately one mile southwest of the Waterford 3 plant site and is accessed from Louisiana State Road 3127. ,(See Figure 7-3) r The James M. Cain Energy Education Center also serves as an Alternative Facility and is a staging area for TSC and OSC personnel and is equipped with offsite and onsite communications. Engineering assessment activities, including damage control team planning and preparation may* be performed by augmented emergency response staff if the site is not accessible. The Emergency Operations Facility has been designed for a protection factor of 5 as provided for by NUREG-0696, Section 4.2 and Supplement 1 to NUREG-0737. The Emergency Operations Facility ventilation system's air intake and return air is continuously monitored for radiation. The ventilation system is equipped with zero leakage' dampers and is provided with a recirculation fan with both High Efficiency Particulate (HEPA) and charcoal filter systems. The facility is provided with an emergency diesel generator backup power system. The EOF provides facilities for:
- a. Management of overall licensee emergency response.
- b. '
Coordination of radiological. and environmental assessment.
- c. Determination of recommended public protective actions.
- d. Coordination of emergency response activities with Federal, State and local agencies.
- e. Communication between the EOF and the TSC, Control Room, NRC and State/local agencies.
Facilities are provided in the EOF for_Jhe acquisition, display and evaluation of all radiological, meteorological, and plant system data pertinent to determine offsite protective measures (see Subsection 7.4.11 ). These facilities are used to evaluate the magnitude and effects of actual or potential radioactive releases from the plant and to determine offsite dose projections as well as offsite protective measures. The EOF is not only used for coordination of offsite radiological monitoring during an emergency, but also is used to coordinate emergency response activities with those of Federal, State and local organizations. Personnel in the EOF use the evaluations of offsite effects to make protective action recommendations for-the public to State and local emergency response agencies. There ~re no provisions for accommodating news media personnel in the EOF. 7-4 Rev.048
WATERFORD 3 SES EMERGENCY PLAN 7.2.1 (Cont'd.) The State Liaison Team will locate in the EOF to facilitate coordination of activities between State representatives and EOF personnel. The EOF is used for coordination of the receipt and analysis of sample media from State and utility monitoring teams. After initial analysis in the field, samples are returned for further analysis onsite, at the Baton Rouge LDEQ facilities, or at backup analysis facilities identified in the Implementing Procedures. To ensure adequate radiological protection of EOF personnel, dedicated portable monitoring equipment is provided. This equipment is used to monitor radiological conditions inside the EOF. The dedicated portable equipment is used when the permanently installed monitoring system gives an indication of increasing airborne or direct radiation activity. The EOF technical data system acts to receive, store, process, and display information sufficient to perform assessments of the actual and potential onsite and offsite environmental consequences of an emergency condition. Data providing information on the general condition of the plant also is available for display in the EOF.
- The EOF data set includes radiological, meteorological and other environmental data as needed to:
- a. Assess environmental conditions,
- b. Coordinate radiological monitoring activities, and
- c. Recommend implementation of offsite emergency plans.
Up-to-date plant records, procedures and emergency plans needed to exercise overall management of licensee emergency response resources are available on line via the Entergy intranet. There are hard copies of select emergency plan implementing documents in the EOF to support EOF functions in the event this system is not available. In the event that the EOF should be uninhabitable, an alternate EOF Facility is located at 4809 Jefferson Highway Jefferson, Louisiana. This facility is equipped to provide the same operational capabilities as outlined for the nearsite EOF. i 7.2.2 Joint Information Center The Joint Information Center is located in the Governor's Office of Homeland Security and Emergency Preparedness building at 7667 Independence Blvd, Baton Rouge, Louisiana. The Joint Information Center acts as the control location for information dissemination to the public via the news media. News conferences and press briefings will be conducted at this location. 7-5 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN 7.3 State, Parish and Other Emergency Facilities r 7.3.1 Parish Emergency Operations Center The St. Charles Parish direction and control of emergency operations during an accident associated with Waterford 3 is maintained from the St. Charles Parish Emergency Operations Center (EOC) located in the basement of the St. Charles Courthouse, Hahnville, Louisiana. This facility is capable of operating on a 24-hour-per-day basis for an extended period of time. Figure 7-1 shows the relative location of the Parish EOC. The St. John the Baptist Parish direction and control of emergency operations during an accident associated with Waterford 3 is maintained from the St. John the Baptist Parish Emergency Operations Center (EOC) located in the Percy Hebert Office Building, Airline Highway, LaPlace, Louisiana. This facility is capable of operating on a 24-hour-per-day basis for an extended period of time. Figure 7-1 shows the relative location of the Parish EOC. 7 .3.2 State Emergency Operations Center Actions taken by the State during an emergency are coordinated by the State Emergency Operations Center (EOC), which is located at 7667 Independence Boulevard, Baton Rouge, Louisiana. This EOC is staffed by response agencies as indicated in the State of Louisiana Peacetime Radiological Response Plan. Figure 7-1 shows the relative location of the State EOC. 7.3.3 Louisiana Department of Environmental Quality The Louisiana Department of Environmental Quality (LDEQ) maintains an Operational Headquarters located at 602 North 5th Street, Baton Rouge, Louisiana. This facility is staffed during an emergency to aid the State and parish EOC's in conducting emergency operations. Figure 7-1 shows the relative location of the LDEQ Operational Headquarters. LDEQ establishes liaison at the EOF during an emergency for coordination of activities with EOF personnel and for direction of LDEQ Field Monitoring Team (FMT) activities. The FMT conducts monitoring and sampling activities at predesignated sites in the plume exposure pathway EPZ at the time of the accident. Location of the Field Response Team is established at the time of the accident to facilitate the coordination of monitoring and sample collection activities. After initial field analysis, further analyses will be performed at the LDEQ Laboratory in Baton Rouge. In the event that the number of samples is too large to allow processing in an expedient manner, provisions have been made for assistance from the Southern Mutual Radiological Assistance Plan and the U.S. Department of Energy. 7-6 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN 7 .3.4 Other Response Facilities In conjunction with the emergency facilities previously discussed, there are several organizations that are capable of providing support to Entergy Operations, Inc. in an emergency. Westinghouse Electric Company LLC and the Institute of Nuclear Power Operations provide facilities at their business locations that are staffed upon notification and serve to provide assistance as discussed in Section 5.2. The NRC maintains Incident Response Centers and Regional Office facilities, as does the Department of Energy, which is capable of supporting Entergy Operations, Inc. in an emergency. Locations for these supporting facilities are shown in Figure 7-8. 7.4 Assessment Facilities and Equipment 7.4.1 Control Room Instrumentation Control Room instrumentation provides for the measurement of appropriate plant parameters that are indicative of the status of various plant systems and the reactor itself. Tables 7.5-1 and 7.5-3 of the Waterfora' 3 FSAR describe the plant systems instrumentation that is used to initiate emergency conditions and assess plant status. These systems, including their installed monitoring instrumentation, are designed to be operational under post-accident conditions. In addition, the operability of these systems in post-accident conditions allows the operators to assess the magnitude and potential consequences of the accident. Various protective and engineered safety features (ESF) instrumentation systems provide continuous monitoring of the reactor and ensure that the associated ESF action and/or reactor trip will be initiated when the parameter monitored by each channel or combination thereof exceeds specified setpoints. 7.4.2 Fixed and Portable Radiation Monitoring Systems The Waterford 3 plant has an installed radiation monitoring system. The purpose of the system is to ensure that radiation levels throughout the plant and in process systems are continuously monitored. In addition, the system provides alarms and interlocks. The system consists of area monitors located throughout the plant and process monitors located in systems where the potential for accidental or excessive release of radioactive material to the environment exists. The operation of selected monitors in this system is described in the FSAR. Data obtained from selected monitors are used in estimating potential doses to the public as a result of routine or accidental releases of radioactive materials to the environment. 7.4.2.1 Process and Effluent Radiological Monitoring Systems monitor and furnish information to operators concerning activity levels in selected plant process systems and plant effluents. These systems consist of permanently installed continuous type monitoring devices together with provisions for specific routine sample collections and laboratory analyses. The overall systems are designed to assist the operator in providing information for evaluating and controlling the radiological consequences of normal plant operation, anticipated operational occurrences, and postulated accidents such that resultant radiation exposures and releases of radioactive materials in effluents to unrestricted areas are maintained as low as reasonably achievable. 7-7 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN 7.4.2.1 (Cont'd) Table 7-2 is a tabulation of basic information describing each of the continuous process and effluent radiological monitors and samplers, including type of monitor and measurement made, sampler and/or detector type, range of activity concentrations to be monitored, provision for power supplies, and automatic actions initiated. Table 4-4, provided in Section 4 of this plan, references the applicable radiological process, effluent and accident monitors to accidents analyzed in the FSAR. This table may be referred to for further information.
- 7.4.2.2 The Area Radiation Monitoring channels are located at selected places inside the plant to provide information on the radiation levels and annunciate any abnormal radiation conditions. Table 12.3-2 of the Waterford 3 FSAR indicates locations and range for these alarms.
7.4.2.3 The Airborne Radiation Monitoring System consists of monitors for the containment, the main Control Room, as well as certain areas in the Reactor Auxiliary Building. Table 12.3-3 of the Waterford 3 FSAR lists the Airborne Radiation Monitoring System monitors including the locations, number of channels and ranges. 7.4.2.4 The High Range Effluent Monitors/Containment High Range Monitors provide instrumentation that enables plant operators to better follow the course of a major accident and thereby assist them in making decisions with reference to mitigating the effects of a major accident. The instrumentation consists of the following monitors (For additional information see Table 1.9-4 of the FSAR).
- 1. One Plant Vent Stack Monitor
- 2. One Condenser Vacuum Pump Effluent Monitor
- 3. One Fuel Handling Building Emergency Exhaust Effluent Monitor
- 4. Two Main Steam Line Monitors
- 5. Two High Range Containment Monitors Readout of all monitored items for all of the accident radiation monitors are available from the Radiation Monitoring System Computer Remote Console display (CP-6) and from separate readouts found in the Control Room (CP-52) and the Radiochemistry Count Room (CP-51 B).
Additionally, the two High Range Containment Monitors have separate readouts via safety-related remote display/control devices. These remote display/control devices are mounted on the existing safety-related radiation monitoring cabinet (CP-14) located in the Control Room. A functional description of the High Range Effluent Monitors is provided in Subsection 7.4.11. 7-8 Rev.048
WATERFORD 3 SES EMERGENCY PLAN 7.4.2.4 (Cont'd} The High-Range Containment Radiation Monitor consists of a gamma detector and cable for use in a containment environment, and support electronics that includes a readout located in the Control Room and Radiochemistry Count Room. The detector is encased in stainless steel to protect it from containment sprays and high temperatures. The monitor is a safety monitor (Class 1E) and is qualified un,r LOCA conditions to IEEE 323-1974. Radiation levels of up to 10 R/hr are displayed in the Control Room on a front panel meter. Two level trips are provided for alert and high radiation levels and are independently adjustable over the full range. A failure trip is provided to actuate upon loss of power, high voltage, or signal from the detector. Automatic self-testing is provided to continuously verify detector operation. Outputs are provided for recorders, remote alarm relays and meters. A separate local display of radiation levels and alarm conditions exists. Energy response is uniform (+/-20 percent) for photons in the range of 80 Kev to 3 M~v. 7.4.2.5 Monitoring of overall Reactor Auxiliary Building radioactive particulate, iodine and gas concentrations is provided for via the In-Plant Airborne Radiation Monitoring System (IPARMS). Using these monitors, the presence of potentially unacceptable high airborne activity levels can be detected in the RAB. If the existence of a potential problem area is shown by the IPARMS, portable high volume samplers are used by Radiation Protection personnel to establish initial occupancy constraints for personnel who shall be working in a given area. Analysis of the samples taken via the portable high volume samplers is performed by the existing gamma spectroscopy system located in the counting room. Finally, if plant personnel need to work in an area that was previously cleared by Radiation Protection personnel for occupancy for any length of time, Portable Continuous Air Monitors (PCAM) may be placed in the area to continuously monitor airborne activity levels, if conditions warrant. If unusually high activity levels were to be detected, the personnel occupying the area would be warned by the PCAM alarms. 7.4.2.6 Portable radiation detection equipment consists of low and high range instruments to measure gamma radiation levels from a fraction of an mR/hr to 10,000 R/hr. Instruments for alpha, beta, and neutron radiation measurements are available. Sampling equipment is also available to collect samples for analysis of particulate and radioiodine concentrations. Emergency radioiodine sampling is done with silver zeolite cartridges that have extremely low retention efficiency for noble gas. With minimal interference from noble gases, radioiodine concentrations as low as 1 x 10-7 uCi/cc can be measured. Portable radiation survey instruments are listed in Table 12.5-2 of the Waterford 3 FSAR. 7-9 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN 7.4.2.7 Personnel monitoring is provided by use of Dosimeter of Legal Record (DLRs), direct reading pocket dosimeters, direct reading electronic dosimeters and survey instrumentation. The dose measuring devices used consist of devices that can be q'uickly and accurately evaluated by EOI Dosimetry Process Facility personnel (DLRs) and devices that can be easily read by the individual (direct reading dosimeters). During an emergency/accident condition, all personnel entering the Controlled Access Area will be issued DLR badges which will be used to measure exposure to beta-gamma and neutron radiation, and to provide the official personnel exposure records. 7.4.2.8 Personnel survey instrumentation consists of G-M countrate meters (contamination friskers), PC~s. portal monitors, and whole body counting capability. The criteria for selection of external contamination measuring equipment were to have devices available at checkpoints and other areas that could be used to determine the location of contamination (friskers and tool monitor), and to have devices at all normal exits from the controlled area that do not require any action by personnel being checked (portal monitors and PCMs). These instruments are calibrated in accordance with Radiation Protection procedures. The criteria for selection of the whole body counting system were to have a system readily available to quickly supply information concerning internal contamination levels. The whole body counting system calibration and source checks are performed in accordance with Radiation Protection procedures. Personnel* monitoring instrumentation is listed in Table 12.5-3 of the Waterford 3 FSAR. 7.4.3 Laboratory Facilities The Radiochemistry counting rooms are near the -4 elevation access control point. The counting rooms provide the necessary laboratory instruments for personnel to process radioactive material survey samples, post-accident chemistry samples, or samples collected by radiological field monitoring teams. Portable sample counting instrumentation is utilized at other control points as necessary. Analysis of Radiation Protection and field samples will normally be performed in the Radiochemistry counting rooms or using the Onsite Monitoring Kit equipment in the OSC. The counting rooms are equipped with High Purity Germanium (HPGE) detectors for gamma spectral analysis in addition to gas flow proportional and liquid scintillation counters. These detectors are shielded to reduce background radiation to an acceptable level. In an emergency, this equipment is available for use in the analysis of samples. A list of equipment maintained in the counting rooms is included in Table 12.5 of the Waterford 3 FSAR. Instrumentation located in the counting rooms allows plant personnel to ascertain the radioactive material present in survey samples. Typical samples would be contamination survey smears, airborne survey filters, and charcoal or silver zeolite cartridges; tritium and other samples may be processed also. The criteria for selection of these various counters were to obtain instrumentation that could reliably and quickly count samples; provide necessary low backgrounds and sensitivities; and to some extent, analyze counting data to provide information in a form more easily used in radiological assessment. 7-10 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN 7.4.3 (Cont'd.) Each laboratory counting system is checked and calibrated at regular intervals with standard radioactive sources traceable to a National Institute of Standards and Technology (NIST) source. Counting efficiency, background count rates, and high voltage settings are checked by plant personnel in accordance with plant procedures. Additional laboratory facilities may be utilized at Louisiana Department of Environmental Quality (LDEQ), Riverbend, Arkansas Nuclear One, and Grand Gulf Nuclear Stations. Laboratory facilities for the analysis of State field team samples are provided at the Baton Rouge LDEQ headquarters. Shipment of samples to these facilities is handled in accordance with emergency implementing procedures, chemistry procedures, Radiation Protection procedures and agreements regarding offsite laboratory facilities in Appendix C. Samples may also be analyzed using the Onsite Monitoring Kit equipment in the OSC. 7.4.4 Environmental and Offsite Monitoring Equipment and Facilities The Waterford 3 plant has a Radiological Environmental Monitoring Program (REMP) which provides environmental data for the Waterford 3 site and the surrounding area. Detailed information concerning this program can be found in the Waterford 3 Environmental Report Technical Requirements Manual (TRM) and in the Offsite Dose Calculation Manual (ODCM). There are presently 31 external radiation monitoring locations in the REMP. However, the number of monitoring locations may vary from year to year in accordance with Plant Procedures. Each external radiation monitoring device consists of two Panasonic UD814 TLDs. Each unit contains one lithium borate element and three calcium sulfate elements. There are additional sample locations for milk, water, river sediment, fish, broad leafy vegetation, and airborne (iodine and particulate) samples. Many ,of these sample locations correspond to external radiation points. More than one sample type may be collected at specific sample locations. The sample station identification numbers for all external radiation and environmental sampling locations are designated with respect to the 16 directional sections demonstrated in the ODCM/TRM and the distance from the plant. The REMP monitoring sample locations are shown in the ODCM. All REMP stations serve the dual function of environmental fixed monitoring sample locations and emergency fixed monitoring/sample locations. In addition, predetermined points for monitoring and environmental sampling in an emergency have been identified and are shown in Figure 7-9d. 7-11 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN 7.4.4.1 The objectives of the (REMP) are:
- a. To determine any statistically significant increase in the concentration of radionuclides in critical pathways.
- b. To detect any build-up of long-lived radionuclides in the environment.
- c. To detect any change in ambient gamma radiation levels.
- d. To verify that radioactive releases are within allowable limits and that plant operations have no detrimental effects on the health and safety of the public or on the environment.
The Waterford 3 REMP satisfies the NRC Radiological Assessment Branch technical position. Additionally, in response to an offsite release, the Louisiana Department of Environmental Quality will'request State agencies to assist with environmental sampling as follows:
- a. Department of Wildlife and Fisheries (1) Fish sampling (2) Wildlife sampling
- b. Department of Health and Hospitals (1) Drinking water sampling (2) Processed (consumer ready) milk, fruit, vegetables, poultry and egg sampling
- c. Department of Agriculture and Forestry (1) Animal food sampling (2) Raw milk sampling (3) Unprocessed fruit, vegetables, poultry and egg sampling The type of emergency sampling employed is indicated in Table 7-8.
7.4.5 Meteorological Detection The Waterford 3 plant has an onsite meteorological monitoring system. The purpose of this system is to ensure that sufficient meteorological data are available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere. The operational meteorological monitoring program is designed to comply with the requirements of USNRC Regulatory Guide 1.23 and Appendix 2 NUREG-0654. The location.of the two independent meteorological towers.(primary and back-up) are such that the data from the towers are representative of the Waterford 3 site. 7-12 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN 7.4.5 (Cont'd.) Both monitoring locations were selected to "minimize the effects of wake interference from surrounding obstacles and to decrease the probability that a natural event, such as a lightning strike, will disable both systems. Each location is fenced and contains an equipment shelter, a meteorological tower, a complete lightning protection system (i.e., lightning dissipation array system, lightning rods, surge arrestors, buried grid, etc.), and adequate night illumination. Signals from both the primary and back-up stations are transmitted to the plant via communication cables to the plant monitoring computer for processing (quality assurance check). These weather-resistant cables are placed in trenches approximately six feet deep that are covered with concrete slabs and adequately protected against transient electrical fields from lightning strikes. Signals from the back-up station are sent through a different multiplexer site than those from the primary station and each multiplexer passes the signal on to the online plant monitoring computer. All signals may be switched to the redundant computer system if required. Meteorological information coming into the computer is available for use by the MARMOND display described in Section 7.4.11 for prediction of effluent transport and diffusion. It is also available for display on several remote terminals connected to the plant monitoring computers. Additionally, local displays and data loggers operate at each tower location for the purpose of contjnually monitoring and recording meteorological data necessary to perform diffusion calculations. The operation of this*system is specified in the technical requirements manual. The 60-meter ( 199 ft) primary tower monitors the following meteorological parameters at the specified levels: Parameters Level (m) Wind Speed 10 Wind Speed 60 Wind Direction 10 Wind Direction 60 Sigma Theta 10 Sigma Theta 60 Temperature Difference "A" 10-60 Temperature Difference "B" 10-60 Ambient Temperature "A" 10 Ambient Temperature "B" 10 Ambient Temperature "A" 60 Ambient Temperature "B" 60 Precipitation Ground The 60-m (199 ft) back-up tower monitors the following meteorological parameters at the specified levels: Parameters Level (m) Wind Speed 10 Wind Direction 10 Sigma Theta 10 Ambient Temperature 10' Ambient Temperature 601 Temperature Difference 10-60 7-13 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN 7.4.5 (Cont'd.) Since the two meteorological monitoring systems have totally independent power
. supply, cables, back-up line power, signal transmission cables, and signal handling for the plant monitoring computer input, it is highly unlikely that meteorological data will be unavailable from either the primary or back-up stations at any time. Rigorous quality assurance procedures and semi-annual calibration of the equipment ensure the reliability and proper operation of both stations.
The National Weather Service (NWS) provides additional minimal back-up meteorological information (i.e., wind speed, direction and probability of upper air inversion) in the vicinity of the Waterford 3 plant from the NWS Office at Slidell. 7.4.6 Fire Protection and Detection A comprehensive Fire Protection Program is provided at Waterford Steam Electric Station Unit 3 (W3) to maintain the ability to perform the safe reactor shutdown function, maintain the reactor in a safe shutdown condition, and to minimize radioactive releases to the environment in the event of a lire, as well as to prevent/minimize economic loss due to property damage and operating interruption. The overall objective of the Fire Protection Program is to minimize both the probability and consequence of postulated fires. The design bases of these goals are directed toward:
- a. Prevention of fires through the control and separation of ignition sources.
- b. Prompt detection and suppression of fires in areas containing safety-related equipment or high combustible loadings;
- c. Confinement of fires to their areas of initiation by provision of fire barriers, spatial separation, administrative procedures, and segregation of combustibles; and
- d. Protection of redundant safe shutdown equipment and associated cabling to ensure post-fire shutdown capability.
At Waterford 3, structures, systems and components important to safety are designed and located to minimize, consistent with other safety requirements, the probability and effect of fires and explosions. Noncombustible and heat-resistant materials are used wherever practical throughout the unit, particularly in locations such as Containment and the Control Room. Fire detection and suppression systems of appropriate capacity and capability are provided and designed to minimize the adverse effects of fires ori structures, systems and components important to safety. Fire suppression systems have been bounded by general plant flooding analyses to provide assurance that their rupture or inadvertent operation does not significantly impair the safety capability of these structures, systems and components. Equipment and facilities for fire protection, including detection, alarm and extinguishment, are provided to protect both plant and personnel from fire or explosion. Both wet and preaction type fire suppression equipment are provided. Normal fire protection is provided by sprinkler systems, hose lines and portable extinguishers. 7-14 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN 7.4.6 (Cont'd.) The Fire Protection System is designed to protect systems/components such that a failure of any component of the system will not impair the ability of redundant , equipment to achieve and maintain safe shutdown or limit the release of radioactivity to the environment in the event of a postulated accident. Total reliance is not placed on any single fire suppression system, automatic or manual. A full complement of appropriate portable fire extinguishers are installed throughout the plant to provide either initial fire fighting capacity or back~up to automatic or manual suppression system. As a back-up to portable fire extinguishers and/or automatic suppression systems, a system of 1-1/2 inch hose stations is installed, throughout the plant, so that all areas within each building can be reached with an effective hose stream. As a final back-up to all of , the protection outlined above, outside yard hydrants and hose houses are also provided. A single failure in the water-supplied fire suppression system will not impair both the primary and back-up fire suppression capability. Three fire pumps, one electric motor and two diesel engine driven, provided with independent suction and discharge lines, supply water to the underground yard loop. The Fire Protection System at Waterford 3 is designed and installed using guidance provided by the National Fire Protection Association (NFPA) and applicable regulatory guides. 7.4.7 Seismographic and Hydrologic Equipment The Waterford 3 Station employs an active seismic monitoring system which serves to alert station personnel that a seismic event has occurred and records/displays the seismic data to allow evaluation upon which response actions will be initiated. The system consists of triaxial time history accelerographs, located at various locations within the plant, which detect vibratory ground motion and input data to a recording unit. In addition to the seismic instrumentation onsite, the following stations maintain seismographs in the vicinity of the site. Recorded seismic data from these stations is available to corroborate onsite data or as a back-up source of information in the unlikely event that onsite instrumentation does not function properly. University of St. Louis, Department of Earth & Atmospheric Sciences, St. Louis, Missouri Center for Earthquake Research and Information, Memphis, Tennessee National Earthquake Information Center, Denver, Colorado California State Institute of.Technology, Pasadena, California U.S. Geological/Albuquerque Seismological Lab, Albuquerque, New Mexico Alabama Geological Survey/Georgia Institute of Technology 7-15 Rev. 048 J
WATERFORD 3 SES EMERGENCY PLAN 7.4.7 (Cont'd) Hydrological equipment used in monitoring the Mississippi River level consists of a gage station installed adjacent to the intake structures. The U.S. Army Corps of Engineers maintains a system of river gage stations upstream and downstream of the plant. The river level is monitored and, under conditions conducive to higher than normal levels, the Corps of Engineers will provide estimates of the crest level and time. The hydrology of the Mississippi Valley is such that ample warning, on the order of days, will be available prior to reaching the flood stage. 7.4.8 Protective Facilities and Equipment Offsite evacuation assembly points provide a predesignated location where evacuating personnel can assemble during an emergency. These areas provide locations to allow the flexibility to select an area upwind from any release or potential release. Figure 7-9 shows the location of these areas. Communications between the assembly points and the Operational Support Center are provided by radio. Facilities for decontaminating personnel are available at Waterford 3 in the -4.0 ft. Control Point Access Area. Decontamination showers, sinks and specialized equipment are located in this area, as is the normal inventory of Radiation Protection equipment. This area also acts as a storage area for emergency equipment and supplies. Should this area become uninhabitable, facilities are available on the +7 ft. MSL to carry out decontamination activities. Limited personnel decontamination may be performed in the Westside Access. The Waterford 3 Station maintains an extensive complement of protective equipment to provide emergency response personnel with adequate protection to carry out their roles in an emergency. This equipment is located in the following facilities:
- a. Control Room/Technical Support Center
- b. Operational Support Center
- c. Control Point Area (-4 RAB and Westside Access point)
- d. Emergency Operations Facility
- e. Main Security Office An adequate inventory of protective clothing is m.aintained on hand at the access control point or other control points as necessary to support emergency operations and maintenance activities. This clothing includes lab coats, overalls, hoods, caps, plastic oversuits, gloves (plastic, rubber, cloth), shoe covers, boots and rubbers. Tape is provided for sealing. A listing of Radiation Protection equipment is shown in Table 12.5-4 of the Waterford 3 FSAR.
Additional contamination control supplies are available. These include vacuum cleaners, mops, absorbent paper, plastic sheets and bags, barricade ropes, signs and labels. To minimize exposure to non-emergency personnel, protective actions will be implemented. 7-16 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN Typical equipment listings for each facility are contained in Appendix G. Instructions for their dissemination and us'e are provided for in the Implementing Procedures. 7.4.9 Damage Control Equipment The Waterford 3 Station is extensively equipped to conduct preventive maintenance and repairs on mechanical, structural, electrical, and instrumentation and control equipment found in the station. Maintenanc.e personnel are trained to perform the tasks associated with their craft in the working environment of a nuclear plant. In addition to the equipment and materials required for normal maintenance, other items are available to handle extraordinary maintenance jobs that might arise in damage control.
- 7.4.10 First Aid and Medical Facilities Facilities for first aid/emergency medical care and related decontamination of .
injured/ill personnel are available in the Radiation Protection Area on the -4.0 ft. MSL elevation of the Reactor Auxiliary Building. Basic emergency medical equipment and supplies are contained within this area. In addition, first aid lockers are provided in strategic locations onsite, as des?ribed in station procedures. The first aid and emergency care supplies available at all locations are designated appropriate to the training level of the First Aid Team. Decontamination equipment/supplies, to support a first aid effort, are located in the Radiological Controlled Area and include showers, sinks, eyewash supplies, cleaning agents and materials, contamination monitoring equipment, and materials to control the spread of contamination. Specific decontamination procedures/supplies are detailed in the Emergency Plan Implementing Procedures. 7.4.11 Assessment Capabilities
- a. The capability to make rapid assessment of the actual or potential magnitude and location of any radiological hazards through gaseous release pathways is provided by computerized and manual dose assessment procedures described in the Emergency Plan Implementing Procedures.
The first item which must be determined in evaluating an accidental release of radioactive materials is the amount of activity released. This information is available since those systems, which contain or may contain radioactive materials, and their potential release paths, are monitored by the installed Radiation Monitoring System described in Subsection 7.4.2. In addition, these systems are routinely sampled and analyzed. Radiation surveys, contamination surveys and air samples are performed as necessary to provide supporting information. If actual data is not immediately available, the magnitude and duration of the release may be estimated by station personnel from plant conditions or from knowledge of the type of incident that occurred. 7-17 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN 7.4.11a (Cont'd.) All radiation monitors at the Waterford 3 plant, including process, effluent, area and airborne monitors, include local microprocessors with inputs to the Radiation Monitoring Computer. Data coming into the Radiation Monitoring Computer is available for interrogation by plant personnel. The plant stack is the common release point for normal exhaust from the Reactor Auxiliary Building as well as emergency exhaust from the Shield Building Ventilation System and the Controlled Ventilation Area System. These release points are provided with radiation monitors which function to confirm that releases of radioactivity do not exceed the limits of 10CFR20. Additional high-range monitors are provided for accident situations in which the range sensitivity of the normal monitors may be exceeded. The normal stack and FHB monitors are listed in Table 7-2. The normal plant stack radiation monitor is a three-stage isokinetic monitor that monitors the plant stack for particulates, iodine and noble gases. During an accident the concentration of radioactive effluents monitored by each channel is input into the plant monitoring computer. The release rate is determined by multiplying the concentration by the stack flow rate, which is also measured by the monitor and polled by the plant computer. The release rate from the normal Fuel Handling Building Exhaust is determined in the same manner as for stack releases. Concentration of particulates, iodines and noble gases, and exhaust flow rates in Exhausts A and B are obtained from two three-stage isokinetic monitors whose design and operation is the same as the plant stack monitor. The concentration in each channel is multiplied by the volumetric flow rate to obtain the release rate. The source term from the Condenser Vacuum Pumps exhaust is determined in a similar manner to the above source terms. The exhaust is monitored by a three-stage isokinetic monitor whose design and operation is the same as the plant stack monitor. Following an accidental release of radioactivity, dose assessment personnel can perform dose projections based on the best release and atmospheric dispersion data available. The primary sources of the data are the effluent monitors and the primary and backup meteorological towers. If release data from effluent monitors is unavailable, or if the releases bypass the monitor, the operator is able to explicitly specify the source term based on an assessment of inventory available for release. If the type and magnitude of the source term cannot be estimated, dose assessment personnel can classify the accident according to one of the accident types in Chapter 15 of the FSAR. Similarly, if data from the meteorological monitors (i.e., wind speed and direction and atmospheric stability category) is unavailable or suspect, dose assessment personnel can explicitly specify the necessary meteorological parameters from offsite sources. 7-18 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN 7.4.11a (Cont'd.) In addition to normal effluent monitors, high range monitors are provided on the plant stack, exhaust from the Fuel Handling Building, and the Condenser Vacuum Pump and main steam lines. These monitors are used to measure effluent concentration at levels above the normal monitor alarm levels. The monitors are discussed in Subsection 7.4.2 and described in detail in FSAR Subsection 1.9.29. Radiation monitor readings and other information useful in performing offsite dose calculations can be found on PMC mimic display "MARMOND 2." Meteorological data and summaries can be found on PMC mimic display "MARMOND 1." The MARMOND program acquires meteorological parameters from the meteorological monitors described in Subsection 7.4.5 and provides information that allows for the calculation of atmospheric dispersion estimates at various locations. Other sources of meteorological data are described in the Emergency Plan Implementing Procedures. Data acquired from MARMOND displays is used as input to the Dose Assessment computer or as input to one of the manual methods of Dose Assessment. The calculation procedures that are employed to predict the transport and diffusion of airborne effluents are derived from regulatory guidance and other industry reference documents, and documented in accordance with accepted Entergy Operations, Inc. practices. The exact procedures and formulations are described in the Emergency Plan Implementing Procedures. If the situation warrants, additional information on meteorology, radiation levels and the environment is gathered and evaluated to determine exposure rates as well as confirming and/or updating previous assessments. Air samples and dose rate readings are taken, as appropriate, at offsite locations based on present meteorological data. The projected dose is confirmed by analyzing air samples or by comparing dose rate readings to doses projected by Dose Assessment or a combination of both. As indicated in Subsection 7.4.2, main steam line monitors are installed in order to estimate releases that may occur from secondary relief valves and atmospheric steam dump valves. One collimated GM tube is installed to view the activity and is recorded by the microprocessor at 10-minute, 24-hour and 28-day averages. Two conversion factors have been developed for the main steam line monitors in terms of mR/hr per uCi/cc of pressurized steam. These factors-are based on isotopic functions arising from gross fuel failure and 1.0% cladding failure, respectively. The conversion factors take into account the thickness of the main steam line. Plant personnel can calculate the flow in cubic feet per minute of steam through secondary relief valves or atmospheric dump valves. Using the above information they are able to estimate the activity release rate at any time during the accident or, after the valves have closed, estimate the integrated releases which had occurred during the accident. 7-19 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN 7.4.11a (Cont'd.) An indication of the source term of radioactive material within, and potentially available for release from, the containment is provided by the two high range containment monitors described in Subsection 7.4.2. To facilitate assessment of accident severity and the potential for radioactivity release, plots have been prepared showing the containment radiation monitor readings vs. time following an accident for incidents involving 100 percent release of coolant activity, 100 percent release of gap activity, one percent release of fuel inventory, and 10 percent release of fuel inventory. These plots are shown in Figure 7-10. A projected dose from a liquid release, whether it is within normal limits or assumed to be an incident, is determined through normal procedural methods. The concentrations of radioactivity being released are determined from installed radiation monitors, samples, release records or estimated if necessary. The release rate and flow path are determined as well. The appropriate dilution factors are applied to the concentration in the effluent at the point of measurement to allow for the additional dilution by circulating water.
- b. In the event an accident results in a release of radioactive materials to the environment, an emergency radiological survey team is assembled. This team is composed of sufficient Radiation Protection and other trained personnel to provide for offsite emergency monitoring within the 10-mile EPZ.
The offsite monitoring teams assemble at predetermined locations and are given instructions as defined in the Emergency Plan Implementing Procedures as to location and types of samples that are required within the plume exposure pathway. These teams have the capability of communicating with the Emergency Operations Facility when that location becomes operational. The EOF will then be the central point for coordinating the receipt and analysis of field monitoring data. Transportation for offsite monitoring is provided by company vehicles assigned to the station. The teams maintain contact with the EOF when in the field. Portable radiation detection equipment consists of instruments to measure gamma and beta radiation levels. Sampling equipment is also available for the collection of air samples. Battery-operated air samplers are used to collect low volume air samples for analysis of radioiodine concentrations. These air samples are initially analyzed in the field using a GM Survey Meter with pancake probe. Emergency radioiodine sampling is done with silver zeolite cartridges that have extremely low retention efficiency for noble gases. Radioiodine concentrations as low as 1 x 10-7 uCi/cc can be measured. The exact types and quantity of equipment for emergency radiological monitoring is specified in the Emergency Plan Implementing Procedures. 7-20 Rev.048
WATERFORD 3 SES EMERGENCY PLAN 7.4.11 (Cont'd.)
- c. The Waterford 3 Safety Parameter Display System (SPDS) consists of a plant computer-driven SOS display in the Control Room on the Plant Operator's desk providing the operators with a continuous indication of a set of parameters defining the safety status of the plant. While the main purpose of the SPDS is to aid the operator in the detection of abnormal operating conditions, duplication of the SPDS displays in the Technical Support Center (TSC) and the Emergency Operations Facility (EOF) enhances the exchange of information between these facilities and the Control Room; it also assists management in the decision-making process.
The data base of the plant monitoring computer includes many of the variables required to provide significant information to the operator on the status of important plant functions, such as: Reactivity Control Reactor Core Cooling and Reactor Coolant System Heat Removal Reactor Coolant System Integrity Radioactivity inside the Containment Radiation monitor readings Meteorological data and summaries Other equipment and plant functions important to plant safety The use of the plant computer as a data acquisition system for the SPDS offers the following advantages: (1) Most, if not all, of the specified parameters required for the SPDS are already available in the extensive plant computer database, as required by other monitoring activities or specific application programs. (2) Additional inputs from plant instrumentation or from other monitoring systems (e.g., radiation monitoring system) are provided. (3) Derived variables required for the display are obtained through software information processing. (4) The display formats are designed according to human factor principles. A routinely displayed, readily interpretable presentation of the safety status for all modes of operation is always available to the operator. This is obtained by grouping a limited number of parameters, derived variables, and their trends in dedicated primary display formats. 7-21 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN 7.4.11c (Cont'd.) (5) The displays used for the safety parameter displays in the Control Room, as well as their corresponding keyboards, were physically and functionally integrated in the Control Room. Availability of similar displays in the Technical Support Center (TSC) and the Emergency Operations Facility (EOF) is obtained through additional displays arid keyboard consoles linked to the plant computer. The advantages listed above are complemented by the optimum flexibility allowed by a computer-driven display system. This flexibility is available at different levels: (a) Flexibility in changing the display formats. (b) Flexibility allowing for interaction by the operator in the choice and grouping of displays. (c) Flexibility for future incorporation of advanced diagnostic concepts and evaluation techniques. 7.4.12 Post Accident Liquid Effluent Sampling Various sampling sinks are located on the -35 elevation RAB near the tank rooms. These sinks are used for both normal and post accident sampling. 7.4.13 Post Accident Stack Gas Sampling A post accident stack effluent sample can be obtained off the wide range gas monitor located on the +46 elevation near the plant stack. 7.5 Communications Systems A comprehensive communications system is provided to assure reliable intra-plant communication, offsite commercial telephone service and offsite emergency communication capabilities. The communications system is designed to ensure a reliable, timely flow of information and action directives between personnel and agencies having response or supporting roles in the mitigation of emergencies at Waterford 3. 7.5.1 Normal Communications Systems at Waterford 3 The communication facilities at Waterford 3 are as follows: a) . lntraplant voice communication is provided by a Private Automatic Branch Exchange (PABX) telephone system which will also interconnect with the central office of the AT&T Telephone System. ) b) lntraplant voice paging is provided by a system of high-level audio amplifiers and speakers. c) A sound-powered headset intercom system provides communication for maintenance and operational purposes. The refueling operation intercom is a dedicated circuit in this system. It provides communication between the Fuel Handling Building operating levels and the main Control Room. 7-22 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN 7.5.1 .(Cont'd.) d) Five radio communication systems are provided, two for intraplant operation and maintenance (O&M), a third system for intraplant security, a fourth system for offsite communications (Civil Defense) and a fifth system for communications with field monitoring teams during emergencies. e) The main Control Room is provided with a PABX dial telephone, PA paging, radio and sound-powered headset communication facilities. f) Plant working stations located throughout the plant site are provided with communication facilities so that personnel can communicate with other working stations, and/or the main Control Room, and/or the remote shutdown room. g) Telecommunications support is provided to the plant security system by the telephone and paging systems. h) The Emergency Operations Facility, in the James M. Cain Energy Education Center, is connected to the plant telephone system via the building switch. To ensure reliable telephone communications, the telephone system automatically re-routes calls to switches located at the plant site upon failure of the James M. Cain Energy Education Center switch. In addition, the EOF has a building page system separate from the Plant Page system. This building page system is accessed through the EOF phone system. 7.5.1.1 The Private Automatic Branch Exchange (PABX) telephone system supports at least 30 simultaneous conversations on a dial-up basis between extension stations located strategically throughout the plant areas. The telephone switching equipment is a modern electronic-type with built-in safeguards and annunciation signals. Its design is modular and utilizes plug-in-type components. The telephone operator or technician can check the status of the system through the consoles. Any malfunction can be easily detected and usually corrected by replacing the affected module. If a line is severed or shorted, it will be automatically isolated by the switch until it is repaired and the rest of the system will continue to function normally. In case of power failure, the telephone switch sends an annunciation alarm signal to the Control Room. Desk, wall and weatherproof-type telephone instruments are installed as required and connected to the main switching unit with shielded cable. Telephone instruments are the pushbutton type. A PABX extension station has access to all telephones in the plant. Designated PABX extension stations have access to the loudspeaker-paging network. Telephone calls from the plant into the AT&T System can be made from designated unrestricted service phones. The central switching unit is located in a limited access, air conditioned communications equipment room in the Reactor Auxiliary Building (elevation +7 ft. MSL}. The PABX is supplied 120 Vac power from independent circuits of the plant static uninterruptible power system (SUPS). 7-23 Rev. 048
I WATERFORD 3 SES EMERGENCY PLAN 7.5.1.2 The Public Address (PA) System allows intraplant paging. It is used to supply general information and emergency information to station personnel. It can be accessed by using the PABX telephone and dialing a four-digit access code. The paging system consists of two precompressor amplifiers and five power amplifiers (one is a spare) feeding four 70-volt independent audio and signal transmission lines. The preamps and power amplifiers are monitored by a supervisory signal. The active tone generator is also supervised. Failure of any of these components is detected and annunciated in the main Control Room. The output of the power amplifiers is distributed to the loudspeakers via four independent transmission lines (channels). To improve system reliability, the speaker load is divided into nine zones. Each zone is covered by two channels. These two channels are connected to different precompressor amplifiers and are run in the same conduit system; diversification is carried further by connecting speakers on alternate channels. Failure of the precompressor amplifier will mute half of the speaker system; malfunction of a power amplifier will only affect 25% of the speakers, but in no case will an area or building lose total coverage. However the standby unit can be switched on immediately to restore the system to 100% capability. The paging system is provided with a spare power amplifier that is manually switched into operation should an active amplifier fail. The paging system is powered from a 120 Vac source from the plant static uninterruptible power system (SUPS). Flashing lights are provided in high noise areas to alert personnel of a plant alarm. Personnel are trained to proceed to an area in which they can hear the announcement when the light begins to flash. 7.5.1.3 The Sound-Powered System is a communications network between the Control Room and various in-plant locations. The Sound-Powered System is located in the Waterford 3 SES emergency facilities. During normal operations, the Sound-Powered System is used to coordinate various tests and maintenance tasks. During emergencies, it is used as a backup communications method to pass plant status and operational information. There are 11 dedicated sound-powered headset intercom circuits installed. By segmenting this system, it is possible to have several teams working simultaneously. These 11 circuits are terminated in the patchboard terminal panels, which are located in the main Control Room. Plug-in patches allow temporary circuit interconnections at these panels whenever there is a need for it. Each circuit consists of a two-conductor shielded line interconnecting two or more remote rstations. A jack is provided at each remote station into which the portable headset equipment can be plugged. This arrangement allows for handsfree operation and requires no amplifiers or power source. The Sound-Powered System is a simple system, it does not require a power supply and component failure is minimal. A damaged headset is easily replaced and there is very little to go wrong with the jack stations and the patchboard terminal panels. 7-24 Rev.048 I
WATERFORD 3 SES EMERGENCY PLAN 7.5.1.3 (Cont'd) A separate independent sound powered phone system is provided between the Control Room, TSC, OSC, EOF and Backup OSC. This
. sound powered phone circuit exists primarily to provide plant status and operational information between emergency facilities.
These systems also serve as back-up to the normal communications system (PABX). 7.5.1.4 Station Radio System
- a. The Operation and Maintenance Radio System (O&M) is the primary radio communications network for normal onsite communication for Operations and Maintenance personnel.
When an emergency is declared (Unusual Event, Alert, Site Area Emergency or General Emergency), the maintenance radio frequency is dedicated to emergency communications. The O&M Radio System includes the following features: One-way (paging) and two-way operation. A base station is used as a repeater for portable-to-portable and portable-to-base station communications. The O&M Radio System operates in the FM band. The O&M Radio system is powered from a 120 Vac source from the static uninterruptible power system.
- b. The Security Radio System is the primary radio communications network for security personnel during normal and emergency conditions. Further details of the Security Radio System are contained in the Waterford 3 SES Security Plan.
- c. The State Civil Defense Radio Network is a communications network primarily used by offsite agencies during any type of emergency. It can provide communications.links with the local parishes and State agencies. The State Civil Defense Radio Network operates on the 700 MHz band. The State Civil Defense Radio Network is powered from a 120 Vac source from the static uninterruptible power system.
- d. During emergencies, the Radiological Field Monitoring Radio Network is utilized by Waterford 3 SES personnel to transmit offsite radiological data. The Radiological Field Monitoring Radio Network operates in the FM band. The Radiological Field Monitoring Radio Network is powered from a 120 Vac source from the uninterruptible power system.
7-25 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN 7.5.1.4d (Cont'd) The radio remote stations are provided in locations inside and outside the protected area. The transmitter and antenna are located in the Information Technology Building. Component failure probability is quite small and the system requires minimum wiring. Should the control or transmission lines be faulted, depending on the fault's location, a portion of the subsystem will be operable. A repeater system is provided throughout the Metro New Orleans area and a talk-around feature is available with a coverage of 2 miles if a repeater failure occurs. A summary of onsite communications system capabilities versus work station noise considerations during transients and/or accidents is shown in Table 9.5-6 of the Waterford 3 FSAR. Besides the reliability provided with each subsystem, the strength of the onsite communications system lies in the overlapping coverage given by the subsystems, where the likelihood of simultaneous failure is minimal. During normal operations, offsite telephone service is provided to the plant by the AT&T central office. In the event that commercial telephone service is lost, an emergency communications link will be set up from the main Control Room, the central alarm station, and/or the secondary alarm station via the two-way radio system and/or Entergy Louisiana's fiber optic system, which are both available to the plant. Communications system protective measures are in some cases built into the equipment, in other instances they are provided in the design of the subsystems. Each of the subsystems is provided with a dedicated conduit system. The wiring is sectionalized by areas, floors, and/or building to facilitate troubleshooting. Further, the basic systems (PABX and loudspeaker paging) are monitored by Control Room annunciators. 7.5.2 Emergency Communications Systems In the event of an emergency, the communications system discussed in Section 7 .5.1 is employed by emergency response personnel to initiate corrective and protective actions. The reliability of emergency communications is ensured through: (1) extensive redundance, (2) alternate communication methods and (3) routine testing of the communications system. Timeliness of the flow of information is achieved through: (1) prompt notification, (2) predetermined lines of communication, (3) predetermined emergency action levels, and (4) predetermined levels of authority and responsibility as discussed in other sections of this plan. ' In addition to the communications systems discussed in Section 7.5.1, the following systems are provided for emergency use: 7-26 Rev. 048
WATERFORD 3 SES EMERGE~CY PLAN 7.5.2.1 Operational Hotline - The Operational Hotline is a communications network between Waterford 3 SES and the following agencies*: GOHSEP, LDEQ, St. Charles 'Parish, St. John the Baptist Parish and Waterford 1&2. In the event of an emergency, the Operational Hotline in conjunction with a computerized notification system, serve as the primary method of notification. It is used to transmit plant status, classification of emergency, radiological considerations, and protective action recommendations. The Operational Hotline System includes the following features: 24-hour monitoring by St. Charles Parish, St. John the Baptist Parish and GOHSEP (GOHSEP notifies LDEQ of emergencies after normal working hours), dedicated cable and switching facilities. The PABX and the Civil Defense Radio network are Backups to the
*Operational Hotline. The Industrial Hotline may also be used as a backup means of notification of St. Charles Parish. The Entergy Telecommunications Network is a backup for Waterford 1&2.
7.5.2.2 Industrial Hotline - The Industrial Hotline is a communications network between the St. Charles Parish EOC and industries in St. Charles Parish. Waterford 3 SES is a member of this network. In the event of an emergency, the affected industry member notifies the St. Charles EOC via the Industrial Hotline. The class of emergency, type of incident and recommended actions are reported. The St. Charles EOC then notifies the affected neighboring industry members. The Industrial Hotline System includes the following features: Voluntary participation by member industries, 24-hour monitoring by St. Charles Parish EOC, dedicated cable and switching facilities, and automatic ring. The Industrial Hotline is normally used only for communication between a member industry and St. Charles Parish. If* needed, the St. Charles Parish EOC can patch individual members together. 7.5.2.3 NRC Emergency Notification System (ENS) and Emergency Response Data System (EROS) - The ENS is a dedicated communications system between the NRC Operations Center in, Bethesda, Maryland and Waterford 3 SES. Additionally, the NRC Operations Center has the ability to patch in the NRC regional office. In the event of an emergency, the ENS is the primary method of notification to the NRC. It is used to transmit plant status, classification of emergency, radiological considerations, and other operational information, as requested. The backup to the ENS is commercial telephone lines. The EROS supplements the existing voice transmission over the ENS by providing the NRC Operations Center with timely and accurate updates of a limited set of parameters from Waterford 3's installed onsite computer system in the event of an emergency. 7-27 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN 7.5.2.4 Health Physics Network (HPN) - The HPN is a telephone line supplied by the NRC. It is routed to the Emergency Facilities separate from the normal plant PABX lines and, therefore, would not-be affected by a malfunction of the plant telephone system. The HPN telephones are appropriately labeled and are designed for communications with the NRC Operations Center, Bethesda, Maryland and the Regional NRC Offices. In the event of an emergency, the HPN is primarily used to supply Radiation Protection support to the affected site. 7;.5.2.5 Control Room Intercom - The Control Room Intercom is the primary method of communicating plant status and operational information between the Control Room, TSC, OSC and EOF. The backup to the Control Room Intercom is the Sound Powered System. 7.5.2.6 Hotline Circuits - The Hotline Circuits provide direct communications between positions in the EOF, TSC, OSC, and Joint Information Center (JIG) and the State and Parish Agency Technical Representatives. Hotlines are used to enhance the senior management decision-making process. A hotline is used by the Emergency Director in the EOF and Emergency Plant Manager. Additionally hotlines are used to transmit plant status and information to various members of the emergency organization. Backup communications are provided by PABX. 7.5.2.7 Health Physics (HP) Telecom is used to enhance the onsite Radiation Protection decision-making process. It is used by the Radiological Coordinator and Rad Chem Coordinator. Additionally, it can be used to transmit Radiation Prote~tion and radiological information to various members of the emergency organization. The backup to the HP Telecom is the Sound Powered System. 7.5.2.8 Facsimile transmission capabilities are available to provide rapid transmission of printed material between Waterford 3 emergency facilities and offsite agencies. 7.5.2.9 Entergy's Telecommunications Network - The Entergy Telecommunications Network interconnects Waterford 3 SES to Entergy Business Units and Entergy Power Plants throughout Arkansas, Louisiana, Mississippi and Texas. The system uses a combination of fiber optics and microwave for transmission, therefore totally bypassing all public telephone systems. It is used to transmit emergency information to the Entergy Louisiana, LLC. organization. 7.5.2.10 Pine Bluff Network - The Pine Bluff Network is the primary communications network between Transmission System Security Complex and Waterford 3 SES. Pine Bluff is the central dispatch of electrical power for Entergy Corporation. The system uses a combination of fiber optics and microwaves for transmission. 7-28 Rev. 048 .J
WATERFORD 3 SES EMERGENCY PLAN 7 .5.2.11 Southern Control Network - The Southern Control Network is the primary communications network between the Gretna Transmission Operations Center and Waterford 3 SES. Gretna Transmission Operations Center is the central dispatch for Entergy Louisiana's Transmission and Distribution System. The system uses a combination of fiber optics and microwave for transmission. 7.5.2.12 Satellite Phones - Waterford 3 maintains satellite phones onsite for use by onsite and nearsite Emergency Response Facilities. There are at minimum 5 satellite phones available on the Waterford-3 site. Table 7-10 outlines the communication systems provided in each of the emergency response facilities. 7.5.3 Onsite Emergency Notification System To ensure notification to all site personnel that an emergency condition exists, Waterford 3 provides the following systems: 7.5.3.1 Waterford 3 has two alarms with distinctive sounds that all plant personnel and contractors are trained to recognize, namely, the Fire Alarm and the Station Alarm. There are also radiation alarms at the local radiation monitors and in the Control Room. The paging system is used in conjunction with the Fire Alarm and the Station Alarm. The Fire Alarm and Station Alarm can be manually activated from the Control Room, remote shutdown room, or the TSC. In addition, the paging system has a spare alarm tone capability built in. The alarm signals are generated by one of two tone generators. The tone generators are arranged such that one generator is active and the ' other is standby. If the active generator fails, the standby generator will be automatically connected and an annunciation signal will be sent to the Control Room. The tone generator signals are fed to the paging amplifiers and broadcast through the loudspeaker system covering the entire site. 7.5.4 Offsite Emergency Notification System A summary of the Offsite Emergency Notification System is contained in Appendix K. Details of the System are provided as a separate document. 7-29 Rev. 048
*___ _J
W3 SES EMERGENCY PLAN FIGURE 7-1 EMERGENCY RESPONSE FACILITIES LOCATIONS
*-***** Loutl&ANAa'Tl\TlfOC 8.l1'0Htlt0Uot.U A-7-1 Rev. 048
W3 SES EMERGENCY PLAN FIGURE 7-2 ONSITE EMERGENCY FACILITIES LOCATIONS
- 1. Reactor Shield Bldg.
------, \
- 2. Fuel Handling Bldg.
- 3. Reactor Auxiliary Bldg,
\
\ 4. Turbine Bldg.
\
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- 5. Maintenance Support Bldg.
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- 6. Administration Bldg.
\ 7. Protected Area
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\ 8. Parking Area
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- 9. River Road (LA 18)
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(GSB)
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I I 1~ Operalfonal Support
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\ ~- - Center Technical Support Center A-7-2 Rev . 048
W3 SES EMERGENCY PLAN FIGURE 7-3 WATERFORD 3 ENERGY EDUCATION CENTER A-7-3 Rev. 048
I W3 SES EMERGENCY-PLAN FIGURE 7-4 EMERGENCY OPERATIONS FACILITY (EOF) A-7-4 Rev.048
W3 SES EMERGENCY PLAN FIGURE7-5 CONTROL ROOM LAYOUT 2 6 6 7
-\
1- Shift Manager's Office Operation Administrative Area-3- RO Desk 4- Control Desk 5- Operation Control Area 6- Restroom 7- Kitchen 8- Communication Desk A-7-5 Rev. 048
W3 SES EMERGENCY PL.AN FIGURE 7-6 TECHNICAL SUPPORT CENTER LAYOUT
-* ' s:;/A: -~ . . .. . . . . . .*1"
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- -~,)"'. TSC
, Command 'i ,,:~' Room :
1:%_, A-7-6 Rev. 048
W3 SES EMERGENCY PLAN FIGURE 7-7 OSC FLOOR PLAN MAINTENANCE SUPPORT BUILDING FIRST FLOOR osc STORAGE ROOM OSC MANPOWER AREA OSC COMMAND ROOM A-7-7 Rev. 048
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- a CD
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W3 SES EMERG~NCY PLAl\I; FIGURe-7;;9,:, OF.FSltE EVACUA;t1¢:N AS$EMBL¥4\R~As's A-7-9 Rev. 048
W3 SES EMERGENCY PLAN FIGURE 7-9A REMP SAMPLE LOCATIONS WITHIN 2 MILES OF WATERFORD 3 The map showing REMP sample locations within 2 miles of Waterford 3 which under earlier revisions resided in this figure, has been deleted . This information is provided in the Waterford 3 Offsite Dose Calculation Manual (ODCM). A-7-10 Rev. 048
W3 SES EMERGENCY PLAN FIGURE 7-98 REMP SAMPLE LOCATIONS WITHIN 10 MILES OF WATERFORD 3
\
The map showing REMP sample locations within 10 miles of Waterford 3 which under earlier revisions resided in this figure, has been deleted. This information is provided in the Waterford 3 Offsite Dose Calculation Manual (ODCM). A-7-11 Rev. 048
W3 SES EMERGENCY PLAN FIGURE 7-9C REMP SAMPLE LOCATIONS WITHIN 50 MILES OF WATERFORD 3 The map showing REMP sample locations within 50 miles of Waterford 3 which under earlier revisions resided in this figure, has been deleted. This information is provided in the Waterford 3 Offsite Dose Calculation Manual (ODCM). A-7-12 Rev. 048
W3 SES EMERGENCY PLAN FIGURE 7-C!O . EMERGENCY ENVIRONMENTAL MONITORING POINTS NORTH A WEST
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LEGEND M._ CJ
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e I 2 J 4 NII.£$ B J !i g il<ILINTUS A-7-13 Rev. 048
w3* SES EMERGENCY PLAN FIGURE 7-10 CONTAINMENT RADIATION PLOT 2 10 6 8 6 fT'=Ol
- 10 J
!!; 6 ....Lii a: 6 4 lal "'00 2 10 2 8 6
-4 100% COOL.ANT 2
CT*OI 10 2 4 a e 10 2 4 a e 100 2 4 8 II 1000 I DAY 4 DAYS 30 DAYS TIME AFTER REL.EASE IHOURlll A-7-14 Rev.048
WATERFORD 3 SES EMERGENCY PLAN TABLE 7-1 CONTROL ROOM PLANT SYSTEMS INSTRUMENTATION Information which resided here in earlier revisions has been deleted. This information is located in Tables 7.5-1 and 7.5-3 of the Waterford 3 FSAR. Rev.048 A-7-15 (1 of 1)
WATERFORD 3 SES EMERGENCY PLAN TABLE 7-2
- PROCESS AND EFFLUENT RADIOLOGICAL MONITORS/SAMPLERS MONITORS QUANTITY TYPE FUNCTION POWER SUPPLY RANGE& ALARM JUSTIFICATION LOCATION
(µci)/cm3*
- 1. CONDENSER 1 Off-Line Beta Alarm Instrumentation ac bus 10-7 -10+5 Main Control VACUUM Scint. & Table 11.3-5 Room PUMPS Cadmium (PRM-IR-0002) Telluride
- 2. CCW MONITOR A/B 1 Off-Line Alarm Instrumentation ac bus 10-8 2 Main Control (PRM-IR-5700) Gamma Scint. Table 11.1-3 Room and Locally
- 3. CCW MONITOR A Off-Line Alarm Safety-related ac bus 10 10-2 Main Control (PRM-IR-7050AS) Gamma Scint. Table 11.1-3 Room and Locally
- 4. CCW MONITOR B 1 Off-Line Alarm Safety-related ac bus 10 10-2 Main Control (PRM-IR-7050BS) Gamma Scint. Table 11.1-3 Room and Locally
- 5. SGB MONITOR Off-Line Alarm Instrumentation ac bus 10 10-,l Main Control (PRM-IR-01 OOX) Gamma Scint. Table 11.2-11 Room and Locally
- 6. LIQUID WASTE 1 Off-Line Alarm and automatic Instrumentation ac bus 10 10-1 Main Control MANAGEMENT Gamma Scint. termination of flow See Table 12.2-11# Room (PRM-IR-0647)
- 7. GASEOUS WASTE 1 Off-Line Beta Alarm and automatic Instrumentation ac bus 4x1 o 4x1 o+2 Main Control MANAGEMENT Scint. termination of flow Table 12.2-11 #delayed Room (PRM-1 R-0648) 90 days
- 8. BORON Off-Line Alarm and automatic Instrumentation ac bus 10 10-1 Main Control MANAGEMENT Gamma Scint. termination of flow Table 12.2-8# Room (PRM-IR-0627)
- 9. DRY COOLING Off-Line Alarm and automatic Instrumentation ac bus 4.2x1 o 4.2x1 o-2 Main Control TOWER SUMP #1 Gamma Scint. Sump Pump Isolation Table 11.1-3 Room and Locally PRM-IR-6775
- Values of this table should be divided by approximately 10 for average condition.
- The tables listed in this column are located in the FSAR.
Rev.048 A-7-16 (1 of 2)
WATERFORD 3 SES EMERGENCY PLAN TABLE 7-2 (Continued) PROCESS AND EFFLUENT RADIOLOGICAL MONITORS/SAMPLERS MONITORS QUANTITY TYPE FUNCTION POWER SUPPLY RANGE& ALARM JUSTIFICATION LOCATION {gci}/cm3* 10: REACTOR 1 Off-Line Alarm Instrumentation ac bus 10~8 2 Main Control BUILDING SUMP Gamma Scint. Isotopic Cone. is Room and Locally {PRM-1 R-6777} unknown
- 11. DRY COOLING 1 Off-Line Alarm and automatic Instrumentation ac bus 4.2x1 o 4.2x1 o-2 Main Control TOWER SUMP #2 Gamma Scint. Sump Pump Isolation Table 11.1-3 Room and Locally (PRM-1 R-6776)
- 12. INDUSTRIAL 1 Off-Line Alarm. Upon high Instrumentation ac bus 10 10-2 Main Control WASTE SUMP- Gamma Scint. radiation signal closes Room and Locally TURBINE BUILDING valve 7WM-V186 and (PRM-IR-6778) opens valve 7WM-V650. Upon emptying the sumps, operator to re-establish normal flow to oil separator manual.
- 13. CIRCULATING 1 Off-Line Alarm and initiate Instrumentation ac bus 4.2x1 o 4.2x1 o-2 Main Control WATER Gamma Scint. Automatic Closure of Table 11.2-13 Room and Locally DISCHARGE Slowdown Flow (PRM-1 R-1900}
- 14. FHB EXHAUST A 1 Off-Line Alarm Instrumentation ac bus Part. 10 10-5 Main Control (PRM-IR-5107A) Particu- Iodine 1o 1o-3 Room and Locally late Iodine Gas 10 10-1 Gas
- 15. FHB EXHAUST B Off-Line Alarm Instrumentation ac bus Part. 10 1o-5 Main Control (PRM-IR-51078) Particu- Iodine 1o 1o-3 Room and Locally late Iodine Gas 10 10-1 Gas
- 16. PLANT STACK 1 Off-Line Alarm and automatic Instrumentation ac bus Part. 10 10-5 Main Control (PRM-IR-0100.1 S) Particu- Terminate Iodine 1o 1o-3 Room and Locally (PRM-IR-0100.2S) late Iodine Containment Purge Gas 10 10-1 Gas
- The tables listed in this column are located in the FSAR.
Rev. 048 A-7-17 (2 of 2) I
WATERFORD 3 SES EMERGENCY PLAN TABLE 7-3 AREA RADIATION MONITORS Information which resided here in earlier revisions has been deleted. This information is located in Table 12.3-2 of the Waterford 3 FSAR.
~
Rev.048 A-7-18 (1 of 1)
WATERFORD 3 SES EMERGENCY PLAN TABLE 7-4 AIRBORNE RADIATION MONITORS Information which resided here in earlier revisions has been deleted. This information is located in Table 12.3-3 of the Waterford 3 FSAR. Rev.048 A-7-19 (1 of 1)
WATERFORD 3 SES EMERGENCY PLAN TABLE 7-5 RADIATION SURVEY/MONITORING INSTRUMENTATION Information which resided here in earlier revisions has been deleted. This information is located in Tables 12.5-2 and 12.5-3 of the Waterford 3 FSAR.
\
Rev.048 A-7-20 (1 of 1)
WATERFORD 3 SES EMERGENCY PLAN TABLE 7-6 LABORATORY FACILITY EQUIPMENT LIST (Typical) EQUIPMENT DESCRIPTION
- 1. Argon Plasma Spectrometer
- 2. Gamma Spectrometer
- 3. Liquid Scintillation Counter
- 4. Manual Gas Flow Proportional Counter
- 5. Ion Chromatograph COUNTING ROOM INSTRUMENTATION Information which resided here in earlier revisions has been deleted. This information is located i!'"l Table 12.5-1 of the Waterford 3 FSAR. i Rev.048 A-7-21 (1 of 1)
WATERFORD 3 SES EMERGENCY PLAN. TABLE 7-7 HEALTH PHYSICS EQUIPMENT Information which resided here in earlier revisions has been deleted. This information is located in Table 12.5-4 of the Waterford 3 FSAR. Rev.048 A-7-22 (1 of 1)
WATERFORD 3 SES EMERGENCY PLAN TABLE 7-8 EMERGENCY ENVIRONMENTAL SAMPLING In responding to an emergency or accident at a fixed nuclear facility, the following guidelines will be used for environmental sampling priorities: AIR SAMPLES As soon as possible after a reported accident at a fixed nuclear facility, remove and change all routine air particulate and charcoal filters in the affected area. Place air sampler on full duty cycle. Be prepared to change air samples daily. Portable air samplers will be used on an as-needed basis. SURFACE WATER SAMPLES As soon as possible after a reported accident at a fixed nuclear facility, collect at least a one-gallon surface water sample from at least two downstream locations. Samples may have to be taken every 2-4 hours for the first 24 hours following a release. Collect surface water samples from at least one upstream location. Prepare for large-volume sampling and composites. POTABLE WATER SAMPLES As soon as possible after a reported accident at a nuclear facility, collect at least a one-gallon drinking water sample from the potable water sample stations. Sample raw water intake points or raw water at the treatment plant. RAW MILK SAMPLING As soon as possible, collect at least a one-gallon sample of raw milk at each potentially affected dairy. Sample the dairy every two days. Sample water from source used to water livestock. Sample pasture grass and/or feed. VEGETATION AND CROPS Obtain samples of critical food crops and other vegetation as soon as possible. *
- Rev.048 A-7-23 (1 of 1)
WATERFORD 3 SES EMERGENCY PLAN TABLE 7-9
SUMMARY
OF ONSITE COMMUNICATION SYSTEM CAPABILITIES AND NOISE CONSIDERATION DURING TRANSIENTS AND/OR ACCIDENTS Information which resided here in earlier revisions has been deleted. This information is located in Table 9.5-6 of the Waterford 3 FSAR. Rev.048 A-7-24
WATERFORD 3 SES EMERGENCY PLAN TABLE 7-10 EMERGENCY RESPONSE FACILITIES COMMUNICATIONS COMMUNICATION PLAN OFFSITE AGENCIES INFORMATION TRANSMITTED BACKUP/ALTERNATE CIRCUIT REFERENCE LOCATION COMMUNICATOR LOCATION CIRCUIT TYPE CIRCUITS Operational Hotline 7.5.2.1 Control Room Emergency Comunicator St. Charles EOC Emergency Notification, Plant Conditions, Dedicated Circuit with PABX or Civil Defense TSC St. Charles 911 Protective Action Recommendation Two Digit Dial Access Radio Network EOF Offsite Communicator Center Backup EOF St. John EOC Remote S/D Panel St. John E-911 Center LDEQ GOH SEP Waterford 1 & 2 Industrial Hotline 7.5.2.2 SM Office Emergency Comunicator St. Charles EOC Industrial Emergency - type, location and severity Dedicated Circuit - PABX Control Room-CRS St. Charles 911 Automatic Ring Control Room-Comm. Center EOF Offsite Communicator Member Industries Remote S/D Panel Operator TSC Control Room Intercom 7.5.2.5 Control Room (Floor) TSC Operations Coordinator None Plant Status and Operational Information Intercom Circuit Sound Powered System TSC Operations Communicator osc EOF Technical Advisor Backup OSC OSC Operations personnel EOF Backup EOF Health Physics Telecom 7.5:2.7 TSC Radiological CoordinatorRad None Onsite Health Physics and Radiological Speed Dial - one-digit Sound Powered System osc Chem Coordinator Information dial access EOF Radiological Assessment Coordinator Dose Assessor Sound-Powered System 7.5.1.3 TSC RO None Plant Status and Operational !~formation Sound-Powered jack N/A (Emergency Ck!) Control Room NAO connected. (Administrative Area) Operations Comunicator Control Room (Floor) OSC Communicator osc Backup OSC EOF Pine Bluff Network 7.5.2.10 SM Office Emergency Comunicator Transmission System Dedicated Circuit - PABX Control Room-CRS TSC Communicator Security Complex Automatic Ring TSC Operator Waterford SES 1 & 2 Remote S/D Panel Little Gypsy Southern Control Network 7.5.2.11 SM Office Emergency Comunicator Gretna Transmission Dedicated Circuit - PABX Control Room-CRS TSC Communicat,or Operations Center Automatic Ring TSC Operator Waterford SES 1 & 2 Remote SID Panel Little Gyp~y Rev.048 A-7-25 (1 of 3)
WATERFORD 3 SES EMERGENCY PLAN TABLE 7-10 (Continued) EMERGENCY RESPONSE FACILITIES COMMUNICATIONS COMMUNICATION PLAN OFFSITE AGENCIES INFORMATION BACKUP/ALTERNATE CIRCUIT REFERENCE LOCATION COMMUNICATOR LOCATION TRANSMITIED CIRCUIT TYPE CIRCUITS NRC Emergency 7.5.2.3 Control Room-Comm. Emergency Communicator NRC Operations Center Emergency Dial Telephone Commercial Telephone Notification Network TSC ENS Communicator Notification/Plant (ENS) EOF Condition NRC Health Physics 7.5.2.4 TSC Radiological Coordinator NRC Operations Center Radiological Information Dial Telephone Commercial Telephone Network (HPN) -4RAB RAC All NRC Offices EOF All Nuclear Power Stations osc Public Address 7.5.1.2 Select PABX Locations Station Personnel None General Information, Two-digit Dial Access None System Emergency Information State Civil Defense 7.5.1.4c Control Room-Comm. Emergency Communicator St. Charles EOC Emergency Information N/A N/A Radio Network EOF St. John EOC Backup EOF Offsite Communicator GOH SEP CAS SAS PAP Radiological Field 7.5.1.4d Control Room Emergency Communicator None Emergency Offsite 800 MHz Radio PABX/ Low Band Radio Monitoring Radio EOF Communicators with Frequency Frequency I Network Backup EOF Offsite Team Coordinator Station Personnel Mobile Phones osc Field Teams Portable Vehicles Waterford 3 7.5.1.4a SM Office SM None Normal Operations N/A N/A Operations Radio Control Room-CRS Operations Department Information Network TSC osc CAS SAS PAP Remote S/D Panel Portable Waterford 3 7.5.1.4a Control Room-CRS SM None Normal Maintenance NIA N/A Maintenance Radio Control Room TSC Communicator Information and Network TSC Maintenance Department Emergency Onsite osc Emergency Teams Communications CAS Operations Department SAS PAP Remote. SID Panel Portable Waterford 3 Security 7.5.1.4b CAS Security Personnel None Normal and Emergency NIA N/A Radio Network SAS Security traffic PAP Portable Rev.048 A-7-26 (2 of 3)
WATERFORD 3 SES EMERGENCY PLAN TABLE 7-10 (Continued) EMERGENCY RESPONSE FACILITIES COMMUNICATIONS COMMUNICATION PLAN OFFSITE AGENCIES INFORMATION BACKUP/ALTERNATE CIRCUIT REFERENCE LOCATION COMMUNICATOR LOCATION TRANSMITTED CIRCUIT TYPE CIRCUITS Waterford 3 PABX 7.5.1.1 All Facilities Station Personnel None lntraplant Communication Dial Telephone Sound-Powered System Information EOF/Energy Education 7.5.1h EOF EOF Communicator None lntraplant Telephone Dial Waterford 3 SES PABX Center Control Room SM Communication Information PABX TSC TSC Communicator osc Emergency Director OSC Supervisor Emergency 7.5.2.6 EOF Emergency Director None Emergency Management Dedicated Circuit - PABX Coordinator/EOF ~ TSC Emergency Plant Mgr Decision making Information Auto Ring Director Hotline RAC/RC Hotline 7.5.2.6 EOF RAC None Health Physics Decision Dedicated Circuit - PABX TSC Rad Coordinator making Information Auto Ring Technical Advisor 7.5.2.6 EOF Offsite Liaison St. Charles Parish EOC Emergency News Release Dedicated PABX Conference Bridge BU/EOF JIC Tech Asst St. John Parish EOC Information Conference Bridge JIC GOH SEP line Ops/Engineering 7.5.2.6 EOF Lead Engineer None Engineering Dedicated Circuit - PABX Coordinator/Lead TSC Information Auto Ring Engineer Hotline EOF/Energy Education 7.5.1h EOF Emergency Director None Emergency Status Briefing Dial Access N/A Center Page System Information SM/TSC OPS 7.5.2.6 SM Office SM None Plant Status and Operational Dedicated Circuit - PABX Coordinator Hotline TSC Operations Coordinator Information Auto Ring OSC Work Control 7.5.2.6 TSC TSC Maintenance Coordinator None Emergency Status and Dedicated Circuit - PABX Coordinator/TSC osc OSC Work Control Coordinator Repair Team Information Auto Ring Maintenance Coordinator Hotline Satellite Telephones 7.5.2.12 Various Station Personnel None Emergency Information Satellite Telephone N/A Rev. 048 A-7-27 (3 of 3)
WATERFORD 3 SES EMERGENCY PLAN 8.0 MAINTENANCE OF EMERGENCY PREPAREDNESS Entergy Operations, Inc. maintains, as separate _documents, this Emergency Plan and the Implementing Document. Efforts are made to assure continuous emergency preparedness and operational readiness among Entergy Operations, Inc. personnel and the offsite response agencies and organizations. The Vice President, Operations, Waterford 3 has the overall authority and responsibility for emergency response planning as related to the W3SES. This responsibility includes not only the W3SES Emergency Plan and Implementing Procedures, but also includes its interrelationships with State, Federal and parish plans; agreement letters; and other related plans, programs, and procedures. The Emergency Planning Manager, within the Nuclear Safety Assurance Department, is delegated the responsibility and authority as the Emergency Planning Coordinator to ensure the overall requirements of emergency response planning are achieved. The Emergency Planning 1 Manager will carry out this responsibility through the efforts of the Emergency Planning Department and by coordination with other organizations within Entergy Operations, Inc. and Entergy, offsite agencies and non-utility organizations. 8.1 Organizational Preparedness In order to establish and maintain a high degree of preparedness at all levels of the W3SES Emergency Organization, Entergy Operations, Inc., has established an Emergency Planning Training Program. This program consists of periodic training and supplemental reading as delineated by Waterford 3 Training procedures, and participation in drills and exercises. 8.1.1 Training All personnel at the W3SES shall take part in a formal training program under the direction of the Manager, Training. In general, this training program provides for the indoctrination of Entergy Operations, Inc. employees and contractors in addition to providing specialized training for licensed operators, chemists and Radiation Prot~Qtion personnel, and personnel assigned specific responsibilities in the emergency organization. The Manager, Training, is responsible for ensuring that personnel in each onsite department receive the appropriate training and is responsible for offsite and non-utility training. To carry out this responsibility, a dedicated Emergency Planning Trainer has been assigned to the Waterford-3 Training Department. The training program for the W3SES Emergency Plan includes the following~ 8.1.1.1 All personnel in the W3SES Protected Area who require unescorted access shall successfully complete the appropriate General Employee Training indoctrination course prior to being granted unescorted access and at least annually thereafter. This course provides instruction on station alarms and the expected responses of those individuals not assigned to the emergency response organization during emergencies, including evacuation routes, assembly points, and accountability procedures. 8.1.1.2 All Waterford 1 & 2 personnel who will coordinate actions in relation to an emergency condition at Waterford 3 will be required to attend, per calendar year, a training session on emergency response actions for Waterford 1 & 2, due to an emergency condition at Waterford 3. 8-1 Rev.048
WATERFORD 3 SES EMERGENCY PLAN 8.1.1.3 ;Personnel assigned to the W3SES emergency organization With specific Emergency Plan duties and responsibilities receive specialized training for their respective assignments. The Emergency Plan Training Program delineates which personnel shall' receive specialized training, and the type of training to be received. The minimum required frequency of this training shall be at least per calendar year. Specialized initial training and periodic retraining to be provided to each of the following categories of emergency personnel:
- a. Emergency Directors;
- b. Emergency Plant Managers;
- c. Accident assessment personnel, including Control Room shift
' personnel; *
- d. Radiological monitoring teams;
- e. Fire Brigades;
- f. Repair teams;
- g. First aid and rescue teams;
- h. Security personnel 8.1.1.4 The Louisiana Department of Environmental Quality (LDEQ), assisted by the Governor's Office of Homeland Security & Emergency Preparedness (GOHSEP), develops, conducts, coordinates and promotes_ a training program throughout the State of Louisiana and assists the parishes in developing training policy for parish radiological response readiness. The parishes are responsible for planning and conducting preparedness training of respective emergency response personnel. Entergy Operations, Inc. works closely with the LDEQ, parish Emergency Directors, and local authorities in the conduct and coordination of the training programs.
In addition, orientation and training of State and parish agencies and personnel involved in the W3SES emergency planning effort is made available by Entergy Operations, Inc. The offsite organizations listed below shall be invited, on at least a per calendar year basis, to participate in a training program.
- 1. Louisiana Department of Environmental Quality
- 2. Governor's Office of Homeland Security & Emergency Preparedness
- 3. St. Charles Parish Office of Emergency Preparedness
- 4. St. John the Baptist Parish Civil Defense Organization
- 5. Louisiana State Police
- 6. St. Charles Parish Sheriff's Department
- 7. Media personnel from television, radio or newspaper.
8-2 Rev.048
WATERFORD 3 SES EMERGENCY PLAN 8.1.1.4 (Cont'd) The following additional organizations will receive training based on their role in an emergency at the W3SES. This training will occur per calendar year.
- 1. Hahnville Volunteer Fire Department
- 2. Ochsner Clinic Foundation
- 3. West Jefferson Medical Center
- 4. St. Charles Hospital Ambulance Service
- 5. Ochsner Flight Care Medical/Flight Crew The LDEQ program relates the importance of effective planning for emergency organizations and the offsite (State, parish and local) emergency organizations. The Entergy Operations, Inc., Emergency Plan Training Program includes training on interfacing with W3SES personnel, site access and security procedures, plant layout, dosimetry issuance and use, firefighting systems location and use, basic radiation protection, and protective action guide decision making. The training provided to each offsite organization is based upon the organization's function under the Emergency Plan.
In addition to this training, Entergy Operations, Inc., shall also provide orientation and training to the above support organizations as specified in respective letters of agreement and as required to ensure a high state of emergency preparedness and response capability between these organizations and the W3SES organization. The local services support organizations and personnel who may provide onsite emergency assistance shall be encouraged to become familiar with the W3SES facility (including the physical plant layout and key station personnel). 8.1.1.5 The Emergency Planning Coordinator is responsible for ensuring that personnel assigned to the Emergency Planning Department maintain an adequate degree of training and qualification through their participation in training courses, seminars, industry meetings and conferences as necessary. 8-3 Rev.048
WATERFORD 3 SES EMERGENCY PLAN 8.1.2 Drills and Exercises Drills and exercises are conducted in order to test the state of emergency preparedness. The prime objective of this form of training is to verify the emergency preparedness of all participating personnel, organizations and agencies. Each drill or exercise is conducted to meet the following objectives:
- 1. Ensure that the participants are familiar with their respective duties and responsibilities; *
- 2. Verify the adequacy of the W3SES Emergency Plan and the methods used in the Emergency Plan Implementing Procedures;
- 3. Test communications networks and systems;
- 4. Check the availability of emergency supplies and equipment; and
- 5. Verify the operability of emergency equipment.
8.1.2.1 The Emergency Planning Coordinator is responsible for the overall planning, scheduling, and coordination of all Emergency Planning related drills and exercises. Some of the drills will be performed under the direction of other organizations as defined in the Implementing Document.. 8.1.2.2 Scheduled drills and exercises shall be held involving appropriate offsite as well as onsite emergency personnel, organizations, and agencies. These drills and exercises shall be conducted, simulating as closely as possible actual emergency conditions. Drill scenarios can and shall be prepared that involve participation of several emergency teams and all or specific parts of the onsite, nearsite and offsite emergency organizations including varying degrees of participation of parish, State, and Federal organizations and agencies, and local service support personnel and organizations. The Emergency Planning Coordinator shall notify the offsite emergency response organizations and agencies at least thirty (30) days in advance of the scheduled date of the drill or exercise. Collection and analysis of all sample media as appropriate (e.g., water, grass, soil and air) shall be included in the drills. 8.1.2.3 During practice drills, on-the-spot correction of erroneous performance shall be made and a demonstration of the proper performance offered by the instructor. 8.1.2.4 Recommendations for revisions to the W3SES Emergency Plan and/or the Emergency Plan Implementing Procedures and/or the upgrading of emergency equipment and supplies as a result of a drill or exercise shall be forwarded to the Emergency Planning Coordinator by observers or participants. Recommended changes that are approved by the Emergency Planning Manager shall be incorporated into the Emergency Preparedness Program. Records shall be maintained on each drill and exercise, which shall be conducted as described below: 8-4 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN (1) Emergency Exercise A major exercise simulating a Site Area Emergency or General Emergency shall be held every two years. This exercise shall include mobilization of State and local personnel and resources sufficient to show the capability to respond to an accident. Involvement by offsite response organizations will be consistent with Federal regulations. Actions shall be taken to ensure that adequate emergency response capabilities are maintained during the interval between biennial exercises by conducting periodic drills, including at least orie drill involving a combination of some of the principal functional areas of the Waterford 3 Emergency Planning Program. The scenario shall be varied from exercise to exercise such that all major elements of the plans and preparedness organizations are tested within an eight-year period. Provisions shall be made to start an exercise between 6:00 p.m. and 4:00 a.m., once every eight years. Some exercises will be unannounced. The unannounced and offhours objectives may be satisfied as part of a separate drill. Scheduled exercises will not be postponed due to inclement weather unless unusual weather conditions exist that could pose undue risk to personnel or demand the full attention of the plant staff and/or support personnel. Critique of this biennial exercise shall be provided by Federal and State observers/evaluators and Entergy Operations, Inc. qualified observers. Remedial exercises may be required if it is determined that elements of the Emergency Plan are not satisfactorily tested during an exercise such that agencies of the Federal government cannot find reasonable assurance that adequate protective measures can be taken in the event of a radiological emergency. In the event that State or local governments refuse to participate in Emergency Planning activities, an exercise can be conducted with Waterford-3 and other governmental entities that elect to participate in the Emergency Planning process. Biennial exercise scenarios are submitted to the NRC at least 60 days in advance of the exercise date in accordance 10 CFR 50 Appendix E.IV.F(2) requirements. (2) Communication Drills and Tests A. Communication Drills - Communications with State and local governments within the plume exposure pathway Emergency Planning Zone shall be tested monthly. Communications with Federal emergency response organizations and states within the ingestion pathway shall be tested quarterly. 8-5 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN Communications between the nuclear facility, State and local emergency operations centers, and field assessment teams shall be tested annually and may be performed as part of an exercise or other scheduled drill. Communication 8.1.2.4 (2) (Cont'd) drills will be designed to test the understanding of messages and the operability of equipment. B. Communication Tests - Provisions for Communications with NRC Headquarters and the Region IV Office Operations Center from the Control Room, TSC and EOF shall be tested monthly. (3) Fire Drills Fire drills shall be conducted in accordance with the Waterford 3 Fire Protection Program. (4) Medical Emergency Drills A medical emergency drill, involving a simulated contaminated individual, which contains provisions for participation by the local support services agencies (i.e., ambulance and offsite medical treatment facility), shall be conducted annually. The offsite portions of the medical drill may be performed as part of an exercise or other scheduled drills. (5) Radiological Monitoring Drills
/:\t least one drill per calendar year shall involve radiological monitoring both onsite and offsite and the collection and analysis of sample media (e.g., water, grass, soil and air), and provisions for communications and record keeping. This drill may be performed as part of an exercise or other scheduled drills.
(6) Health Physics Drills A semi-annual drill shall involve response to, and analysis of, simulated elevated airborne and liquid samples and direct radiation measurements in the environment. This drill may be performed as part of an exercise or other scheduled drills. (7) Control Room Protective Response Drill A semi-annual drill shall involve the use of air-supplied , respiratory equipment by Control Room personnel in order to assess their capability to don the equipment within two minutes. 8.1.2.5 Scenarios for each of the exercises and selected site drills will include, as a minimum, the following:
- 1. The basic objective(s) and appropriate evaluation criteria.
8-6 Rev.048
\
WATERFORD 3 SES EMERGENCY PLAN
- 2. The date(s), time period, place(s) and participating organizations an\d agencies.
- 3. The simulated events.
- 4. A time schedule of real and simulated initiating events.
8.1.2.5 (Cont'd)
- 5. A narrative summary describing the conduct of the exercise or drills to include such things as simulated casualties, offsite fire department assistance, rescue of personnel, use of protective clothing, employment of radiological monitoring teams, and public information activities.
8.1.2.6 Observers from the Federal, State and local governments will be invited to observe and critique the required exercises for the purpose of evaluating the ability of the organizations to respond as called for in the Plan. The exercise objectives will be established by the involved organizations and provided to official observers as requested (normally approximately 90 days before the exercise). Advance copies of the exercise package, including cue cards, will be provided to the official observers as requested (normally approximately 60 days before the exercise). The critique shall be conducted as soon as practicable after the exercise, and a formal evaluation should result from the critique. The LDEQ Administrator will be responsible for reviewing and evaluating offsite observer comments. The Vice President, Operations, Waterford 3 will ensure that action is taken to make needed improvements including Emergency Plan procedural changes. The Emergency Planning Coordinator is given the responsibility for implementing corrective actions with the concurrence of the General Manager Plant Operations, the results of which will be reported to the Vice President, Operations, Waterford 3. 8.1.2. 7 Ingestion Pathway exercises are conducted with the State of Louisiana on a periodic basis. The frequency of these exercises is determined by a schedule established by the Federal government. 8-7 Rev.048
WATERFORD 3 SES EMERGENCY PLAN 8.2 Educational Information to the Public For those members of the public residing within the 10-mile Emergency Planning Zone and for the transient population, Entergy Operations, Inc., will provide written information on the following topics:
- 1. Basic radiological health.
- 2. W3SES Emergency Planning Program.
- 3. Actions that would be taken to protect the public.
- 4. The method that will be used to warn the public of a real or potential emergency condition at W3SES and the action expected of the public.
Methods of providing this information may include direct mail or information brochures. At least annually Entergy Operations, Inc., will update the information where required for members of the public within the 10-mile Emergency Planning Zone. 8.3 Review and Updating of the Emergency Plan and Implementing Documents The Waterford 3 Emergency Plan, together with the appended letters of agreement and the Emergency Plan Implementing Procedures, Emergency Plan Implementing Instructions and Emergency Plan Supporting Procedures, will be reviewed at least annually and updated as necessary. Personnel performing reviews of the Emergency Plan and/or Implementing Document shall take into account corporate policy, State policy and plans, parish plans, training, drills and exercises and the various agreements and understanding with Federal, State and local support agencies and organizations. 8.3.1 The Emergency Planning Coordinator is responsible for coordinating the annual reviews of the Waterford 3 Emergency Plan and Implementing Document. The On-Site Safety Review Committee will review changes to the Emergency Plan. Appointed Qualified Reviewers will review changes to the Emergency Plan Implementing Instructions, Emergency Plan Implementing Procedures and Emergency Plan Supporting Procedures in accordance with the Waterford 3 site Qualified Reviewer Program requirements. 8.3.2 In addition, the Emergency Planning Coordinator shall, through letters, meetings, seminars, or other means available, ensure that all elements of the total emergency organization (e.g., Entergy Operations, Inc., State, Federal, parish, etc.) are informed of the Waterford 3 Emergency Plan, the Implementing Document and revisions thereto. 8.3.3 The Waterford 3 Emergency Plan Implementing Procedures, Instructions and Supporting Procedures are incorporated into the Waterford 3 Nuclear Station procedures program. As such, these documents will be prepared, reviewed, approved, controlled, distributed and revised, including the performance of appropriate 10CFR50.54(q) reviews, in accordance with Waterford 3 SES administrative procedures. Document holders (e.g., Entergy Operations, Inc., State, parish and Federal agencies, etc.) will receive revisions to these documents, according to established methods, as they are issued. 8.3.4 Telephone numbers included in the Emergency Plan call list are updated at least quarterly. 8-8 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN 8.3.5 A review of Emergency Action Levels (EALs) shall be conducted by Entergy Operations, Inc. with State and local agencies on an annual basis. State and local agency review and concurrence is obtained prior to the approval and implementation of EAL changes. 8.3.6 Results of each annual review and update will be reported to the General \_ Manager Plant Operations and Vice President, Operations, Waterford 3 as necessary. 8.4 Maintenance and Inventory of Emergency Equipment and Supplies I The Emergency Planning Coordinator is responsible for planning and scheduling the inventory and inspection of designated emergency equipment and supplies. Individuals are assigned to perform these activities at least once each calendar quarter and after M~U~. . Designated emergency equipment and supplies and their locations are listed in the Implementing Document. Portable radiation monitoring equipment included in these inventories is calibrated'i.n accordance with approved procedures. To the extent practicable, emergency equipment is sele.cted on a rotational basis from normal station *. equipment to assure proper operational status and familiarity with its use. Instruments/equipment removed from the emergency equipment inventory for calibration or repair will be replaced with normal station equipment such that the emergency equipment is aiways at its full complement. Normal station equipment is available in sufficient*quantity such that this does not hinder normal operations. Equipment, supplies and parts having shelf-lives are checked and replaced as necessary. Any deficiencies found during the inventory and inspection will be either cleared or documented for corrective action. A report of each inventory and inspection, including documented deficiencies, will be prepared and submitted to the Emergency Planning Manager or his designee. The Emergency Planning Coordinator is responsible for ensuring deficiencies are corrected. 8.5 Review/Audit of Emergency Preparedness Program I A review/audit of emergency preparedness is conducted by persons who have no direct responsibility for the implementation of the emergency preparedness program. A review will be performed as necessary, based on an assessment by the licensee against performance indicators, and as soon as reasonably practicable after a change occurs in personnel, procedures, equipment, or facilities that potentially could adversely affect emergency preparedness, but no longer than 12 months after the change. In any case, all elements of the emergency preparedness program must be reviewed at least once every 24 months. 8.5.1 The Review is to be scheduled and coordinated with the Emergency Planning Coordinator. 8.5.2 Results of the review shall be submitted to the General Manager Plant Operations, the Vice President, Operations, Waterford 3, and the Safety Review Committee within 30 days after it is completed. Deficiencies will be resolved in accordance with the Corrective Action program. 8.5.3 That part of the review involving State and parish plans shall be submitted to the Louisiana Department of Environmental Quality, the Governor's Office of 8-9 Rev. 048
)
WATERFORD 3 SES EMERGENCY PLAN Homeland Security & Emergency Preparedness, St. Charles Parish, and St. John the Baptist Parish for their evaluation. 8-10 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN 9.0 RECOVERY In any emergency situation, the immediate action is directed to limiting the consequences of the incident in a manner that shall afford maximum protection to the general public, to plant personnel and to equipment. Once the immediate corrective and-protective actions have been established and effective control over the incident exists, the emergency actions shift to a recovery phase. The recovery actions are directed toward restoring the plant, as nearly as possible, to its pre-emergency condition. This section provides criteria and guidance for entering the recovery phase and the responsibilities for establishing a Recovery Organization. 9.1 Transition from Emergency Organization to Recovery Organization The transition to a recovery organization can only be effected after the plant conditions are stable and the probability of any adverse effect on the general public or damage to the plant has been substantially reduced. The Emergency Director has the responsibility to determine when the emergency situation is stable and entry into the recovery phase can be affected. Guidelines for determining when the emergency situation can be considered stable and a Recovery Organization can be established (if necessary) are as follows:
- a. The plant is in a stable configuration with adequate core cooling capability,
- b. In-plant radiation levels are stable or decreasing with time,
- c. The release of radioactive material to the environment is controlled and there is no significant potential for additional uncontrolled releases,
- d. Fire, flooding or similar emergencies are under control,
- e. The final conditions as described in the Emergency Plan Implementing Procedures are met, or specific responsibilities have been assigned so as to follow those procedures to completion.
Following a determination that the emergency situation is stable or that the emergency conditions no longer exist, the Emergency Plant Manager will notify and obtain the concurrence of the Emergency Director prior to disbanding the emergency organization. The Emergency Director is responsible for ensuring that all emergency procedures are complete and closed out or that the Recovery Organization is available with adequate staffing and definition of responsibilities to continue the performance of those procedures. All emergency response and support organizations, including the NRC, LDEQ, GOHSEP, St. Charles EOC, St. John the Baptist EOC, etc., if activated, shall be notified as described in Section 6.2.1 of the termination of the emergency and/or the initiation of the Recovery Organization. In the event that, upon termination of the emergency condition, the plant is in its pre-emergency condition and capable of routine operation within its Technical Specifications, the Emergency Director may effect the transition to the normal operating organization in the manner previously described. 9-1 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN 9.2 Recoverv Organization In those cases where post-accident conditions indicate the recovery operations will be complicated or will extend over a relatively long period of time {after bringing the plant to a stable condition), Entergy Operations, Inc., will shift from Emergency Response Organizations (i.e., onsite and nearsite support) to a long-term Recovery organization.
- Its basic structure will be dependent on the nature of the accident, the post-accident conditions, and the nature and magnitude of the effort needed to maintain the plant in a safe.condition and to restore the plant to pre-accident conditions. This organization will be established from the combined resources of the Waterford 3 Emergency Response
- Organizations.
9.2.1 Responsibility for Establishing Recovery Organization 9.2.1.1 Site Recovery Director Upon the EOF7 becoming operational and responsibility transferred, the Emergency Director will assume overall responsibility for recovery until relieved by the Site Recovery Director. The Site Recovery Director is responsible to develop the Recovery Organization, including specific responsibilities of individuals, and a chain of command to meet the objectives of Section 9.2.2. The Site Recovery Director will coordinate with the Emergency Director and Emergency Plant Manager as necessary to develop both the Recovery Organization and administrative activities necessary for a smooth transition from the Emergency Organizations to the Recovery Organization. The Site Recovery Director is responsible for the activities of the Recovery Organization. The Waterford 3 Safety Review Committee (SRC) shall be responsible for the review of the nuclear safety aspects of the significant activities of the Recovery Organization to verify that the activities did not constitute an unresolved safety question. 9.2.1.2 Emergency Plant Manager During emergency conditions where activation of the Emergency Operations Facility is not required, the Emergency Plant Manager is then responsible for the development of a Recovery Organization as necessary to meet the objectives of Section 9.2.2. For events of a minor nature, the normal plant organization may be adequate to fulfill these objectives. 9.2.2 Objectives of Recovery Organization 9.2.2.1 Short-Term Objectives **
- The initial recovery organization must be established to meet the following objectives on a 24-hour-per-day basis:
- a. Maintain the plant in a stable condition.
(
- b. Establish additional assurance of plant stability by providing additional safety system capability.
I
- 9-2 Rev.048 I
(
WATERFORD 3 SES EMERGENCY PLAN 9.2.2.1 (Cont'd.)
- c. '-- Maintain control of the release of radioactive material to the environment.
- d. Maintain control of personnel exposures.
- e. Maintain adequate communication with Federal, State and local agencies.
- f. Maintain adequate capabilities for release of factual and timely information to the general public.
9.2.2.2 Long-Term Objectives The long-term objectives of the recovery organization are:
- a. Restore the plant to pre-emergency conditions.
- b. Dispose of all waste material generated during the emergency and recovery phases.
- c. Evaluate the cause of the emergency, the response to the emergency, and any potential effects of the emergency on future plant operations.
9.3 Mode of Operations The objective basis for the mode of operations of assigned recovery activities is to maintain compliance with applicable federal regulations, State permits and plant Technical Specifications. Specifically, the radiation exposure limits of 10CFR20 shall apply and any discharges shall be controlled in accordance with the National Pollution Discharge Elimination System permit and the radiological limits as defined in the plant Technical Specifications. In addition, to the extent practical, based on equipment availability, accessibility, and the safety aspects of the post-emergency plant conditions, applicable limiting conditions for operations (LCOs) and surveillance requirements of the plant Technical Specifications will be complied with. For those LCOs and surveillance in which compliance is impractical, the NRC will be informed and consulted regarding the safety implications of continued operation in that mode. To the extent practical, the administrative controls imposed on normal operation will be maintained during the recovery phase. Procedures shall be generated for each specific operation and maintenance evolution and will be reviewed for potential nuclear safety, personnel safety or environmental impact by a technically competent review group. As necessary, the review group will be identified in the development of the Recovery Organization, as will the individual(s) having final signature authority on all procedures. Normal plant administrative procedures will be modified to acc:::ommodate the Recovery Organization. 9-3 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN 9.3.1 Recovery Organization The Recovery Organization would vary depending on the nature of the preceding emergency conditions. The functional requirements of the Recovery Organization would however closely resemble the normal Nuclear Operations Department responsibilities. As such, the normal organization may be sufficient to handle recovery operations. Key roles that would generally be required for a major recovery operation are identified below and shown in Figure 9-1. Assignment of these roles/functions is addressed in the Emergency Plan Implementing Procedures. 9.3.1.1 Site Recovery Director The Site Recovery Director will be responsible for overall recovery activities. The position would report to the Chief Operating Officer of Entergy Operations, Inc. 9.3.1.2 Onsite Recovery Manager The Onsite Recovery Manager would report to the Site Recovery Director and be responsible for directing recovery activities to restore the plant to pre-incident conditions. 9.3.1.3 Offsite Recovery Manager The Offsite Recovery Manager would report to the Site Recovery Director and be responsible for directing the interface with Federal, State and local agencies during the recovery process. 9.3.1.4 Recovery Project Manager The Recovery Project Manager would report to the Onsite Recovery
- Manager and be responsible for overall engineering, construction and procurement activities.
9.3.1.5 Recovery Project Engineer The Recovery Project Engineer would report to the Recovery Project Manager and be responsible for engineering activities in support of the recovery operation. 9.3.1.6 Recovery Construction Manager The Recovery Construction Manager would report to the Recovery Project Manager and be. responsible for construction or plant modification in support of the recovery operations. 9.3.1. 7 Recovery Administration Manager The Recovery Administration Manager would report to the Recovery Project Manager and be responsible for overall administration, and logistics activities in support of the recovery operations. r 9.3.1.8 Recovery Licensing Manager The Recovery Licensing Manager would report to the Offsite Recovery Manager and be responsible for overall regulatory coordination and compliance. 9-4 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN 9.3.1.9 Recovery Radiological Manager The Recovery Radiological Manager would report to the Onsite Recovery Manager and be responsible for health physics and radwaste activities in support of the recovery operation. 9.3.1.10 Recovery Operations Manager The Recovery Operations Manager would report to the Onsite Recovery Manager and be responsible for coordination of plant operations in support of the recovery operation. 9.3.1.11 Recovery Public Relations Manager The Recovery Public Relations Manager would report to the Site Recovery Director and be responsible for directing the Entergy Public Information program during the recovery process. The Recovery Organization must be defined based on the initiating accident conditions. The Organization would expand or contract accordingly. 9.3.2 Reentry The recovery program as defined herein includes activities associated with initial reentry into affected station areas. Detailed instructions for conducting reentry are given in the Emergency Plan Implementing Procedures; however, the basic goals for reentry activities include:
- a. A comprehensive radiation surveillance of plant facilities such that radiological problem areas are defined .
. b. Visual observation of hazards or potential hazards is made and evaluated.
- c. Appropriate warning signs and rope barriers are established to isolate the identified reentry problem areas.
9.3.3 Restoration The last element of the recovery program is restoration of operations. The overall purpose of restoration is to prepare for resumption of full power operations. This program shall include a detailed investigation of the accident causes and consequences both to the plant and the environment. Determinations shall be made as to the repair work required to perform necessary modifications to plant equipment and/or qperating procedures. Repair work and approved modifications shall be carried out as authorized. Test programs to confirm fitness and acceptability to return to service shall be developed and executed. 9-5 Rev.048
W3 EMERGENCY PLAN FIGURE 9-1 LONG - TERM RECOVERY ORGANIZATION ONSltE nttoVERY
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A-9-1 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN APPENDIX A MUTUAL ASSISTANCE PLAN Rev. 048
WATERFORD 3 SES EMERGENCY PLAN APPENDIX A The Mutual Assistance Plan which under earlier revisions resided in this appendix has been deleted. The Mutual Assistance Plan has been superceded by the INPO Emergency Resources Mani:Jal which is provided by INPO as a separate document. A-1 Rev.048
l WATERFORD 3 SES EMERGENCY PLAN APPENDIX B EVACUATION TIME STUDY Rev. 048
WATERFORD 3 SES EMERGENCY PLAN
)
APPENDIX B The Waterford Steam Electric Station Unit No. 3 Evacuation Time Estimate is provided as a separate document. The Evacuation Time Estimate is provided to offsite agencies when it is updated. B-1 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN APPENDIX C LETTERS OF AGREEMENT Rev.048
WATERFORD 3 SES EMERGENCY PLAN APPENDIXC The Annual Confirmation Letters and the current Letters of Agreement with each of the agencies, which under earlier revisions resided in this appendix, have been removed. These documents are now maintained in the Emergency Planning Department files. Entergy Operations, Inc. maintains agreements and/or contracts with the following organizations in support of Waterford 3 emergency response. United States Coast Guard
. Provides personnel and equipment for the control of marine traffic as well as the safety and security of maritime interests in navigable waters including the Mississippi River adjacent to Waterford 3 as directed through communications with the Duty Command Officer and implemented through the incident command system (ICS).
Louisiana Department of Public Safety Provide personnel and equipment from the Louisiana State Police for control of traffic on LA 18, control of public access to Waterford and maintaining law and order in the area around the plant as directed via notification of the St. Charles Parish Sheriff's Office and implemented using the incident command system (ICS). Office of the Sheriff, St Charles Parish Provides equipment and personnel for control of traffic on Highway 18 during a security event, maintains law and order, preventing unauthorized access to the site and provision for a trained Bomb Specialist as requested by Waterford 3 to the St. Charles Parish 91 operator and implemented using the incident command system (ICS). Hahnville Volunteer Fire Department Provision of firefighting services and equipment including use of the department's available equipment such as snorkel trucks and aerial trucks through existing mutual aid agreements as requested by the Waterford 3 control room and implemented using the incident command system (ICS). Union Pacific Railroad Company Will arrange for stoppage of Union Pacific Railroad traffic within the area of Waterford 3 upon notification via the Response Management Communications Center (RMCC). Southland Fire & Safety Provision of services related to SCBA bottle refills upon request from Waterford 3 via the Southland emergency number. Westinghouse Electric Company LLC Provision of support personnel and equipment as requested by Waterford 3 in areas of scientific, engineering or technical services related to inspection or direct labor. Bristow U.S. LLC Provides emergency related helicopter response upon the request of Waterford 3 and implemented as part of the incident command system (ICS). C-1 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN Entergy Services - Transmission System Provides transmission engineering support as well as substation maintenance and repairs as requested by Waterford 3. Entergy Services - Fossil Implementation of protective actions for fossil plants within the 10 mile EPZ as provided by Waterford 3. MYU Helicopters Services and equipment to include helicopters and pilots, establishing flight routes and the operation of notification equipment as provided by Waterford 3 to St. Charles Parish and St. John the Baptist Parish, implemented through notification of the afore mentioned parish's via incident command system {ICS). Panther Helicopters 1 Provision of services and equipment to include helicopters and pilots, establishing flight routes and the operation of notification equipment as provided by Waterford 3 to St. Charles Parish and St. John the Baptist Parish, implemented through notification of the afore mentioned parish's via incidents command system (ICS). NOTE: The Letters of Agreement associated with the Emergency Medical Assistance
, Program (EMAP) are located in Appendix I as part of the EMAP.
C-2 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN APPENDIXD LOUISIANA PEACETIME RADIOLOGICAL RESPONSE PLAN Rev.048
WATERFORD 3 SES EMERGENCY PLAN APPENDIXD The Louisiana Peacetime Radiological Response Plan is provided as a separate document. D-1 Rev. 048
.WATERFORD 3 SES EMERGENCY PLAN APPENDIXE LOUISIANA PEACETIME RADIOLOGICAL RESPONSE PLAN -ATTACHMENT 1 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN APPENDIX E The Louisiana Peacetime Radiological Response Plan Attachment 1 is provided as a separate document. E-1 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN APPENDIX F MEMORANDUM OF UNDERSTANDING WITH THE LOUISIANA DEPARTMENT OF ENVIRONMENTAL QUALITY Rev. 048
WATERFORD 3 SES EMERGENCY PLAN APPENDIXF The Memorandum of Understanding with the Louisiana Department of Environmental Quality which under earlier revisions resided in this appendix has been deleted. The Memorandum of Understanding with the Louisiana Department of Environmental Quality has been superseded by State Law. F-1 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN APPENDIXG TYPICAL EMERGENCY RESPONSE EQUIPMENT LISTS Rev. 048
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WATERFORD 3 SES EMERGENCY PLAN APPENDIXG TYPICAL EMERGENCY RESPONSE EQUIPMENT LISTS Equipment listings in this Appendix are typical of the type of equipment located at each facility listed. Exact equipment inventories can be found in the implementing Document under Section Ill, Supporting Procedures, EP-003-040, Emergency Equipment Inventory. G-1 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN APPENDIXG OSC STORAGE ROOM Ludlum 177 (or equivalent) with Pancake Probe Ludlum 12 (or equivalent) with Pancake Probe RS0-50 (or equivalent) Teletector (or equivalent) R02 (or equivalent) R02A (or equivalent) CS-137 Check Source Air Sampler (High Volume) Air Filters Silver Zeolite Cartridges Smears Protective Clothing - full sets SC BA'S SCBA Spare Cylinders Batteries Dosimeter 0-200 mR Dosimeter 0-1.5 R Dosimeter 0-10 R DLR's Dosimeter Charger Electronic Dosimeters Barricade Ribbon Tape 2-inch Radiation Postings w/lnserts Radioactive Material Bags Stopwatch / Plastic Suits Clipboard Survey Forms Stepoff Pads Sample Bags Potassium Iodide Handheld Radio Handheld Radio Charger Air Purifying Respirator w/Canister Flashlight Constant Air Monitor Constant Air Monitor Check Source Regulated Air Sampler Frisking Station Equipment G-2 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN APPENDIXG TSC EMERGENCY KIT LOCKER Ludlum 177 (or equivalent) w/Pancake Probe RS0-5 (or equivalent) Air Sampler (High Volume) SCBA's SCBA Spare Cylinders Dosimeter 0-200 mR Dosimeter 0-1.5R DLR's Dosimeter Charger Stopwatch 6V Lanterns Batteries Tape, 2-inch Clipboard Potassium Iodide Air Filter Paper Sample Envelopes Silver Zeolite Cartridges Protective Clothing - full sets CS-137 Check Source Frisking Station Equipment
)
G-3 Rev. 048
WATERFORD3 SES EMERGENCY PLAN
.APPENDIXG FIELD MONITORING KITS EP-002-060 EP-002-061 R02 (or equivalent)
CS-137 Check Source Air Sampler (Battery Powered) Spare Air Sampler Fuses Sample Holder Air Sample Filters Potassium Iodide Silver Zeolite Cartridges Screwdriver Smears Shovel Stopwatch Liquid Sample Containers Clipboard Writing Tablets Pens Mark-a-lot Flashlight Scissors Batteries Roll of Quarters Paper Coveralls Sample Bags Sample Labels Cotton Insert Gloves Rubber Gloves Air Purifying Respirator w/Canister Shoe Covers Survey Location Maps Tape 2-inch Ludlum 177 or Ludlum 12 (or equivalent) w/Pancake Probe 0-200 mR Dosimeters 0-1.5 R Dosimeters 0-10 R Dosimeters Dosimeter Charger Handheld Radios Handheld Radio Chargers G-4 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN APPENDIXG EOFEMERGENCYLOCKER Ludlum 177 (or equivalent) w/Pancake Probe RS0-50 (or equivalent) ,, CS-137 Check Source Tape, 2-inch Potassium Iodide Protective Clothing - full sets 6V Lanterns Flashlight Batteries Stopwatch Clipboard Dosimeter 0-200 mR DLR's Respirators - full face Combination Particulate and Charcoal Cartridge Air Sampler (Hi - Vol) Silver Zeolite Cartridges Air Sampling Filters Radioactive Material Bags Sample Bags Dosimeter Charger Pens Smears Spare Air Sampler Fuses G-5 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN APPENDIX G PERSONNEL DEGON KITS EP-002-032 HP-002-704 Plastic Bags (Assorted) Towels, Cloth - Washing and Drying Paper Towels Soft Brush Shaving Cream Razors Hand Soap Gloves, Disposable Ludlum 12 or Ludlum 177 (or equivalent) w/Pancake Probe CS-137 Check Source .Flashlight Batteries Masselin Cloth Smears Tweezers Scissors Q-Tips G-6 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN APPENDIXG HEALTH PHYSICS HOSPITAL LOCKER E-520 Beta/Gamma Meter (or equivalent) Ludlum 12 or Ludlum 177 (or equivalent) w/Pancake Probe Dosimeter 0-200 mR Dosimeter Charger CS-137 Check Source Tape, 2-inch Absorbent Paper (or Herculite) Radiation Rope/Ribbon Radiation Postings w/lnserts 15-Gallon Poly Bottle Plastic Liners Stepoff Pads Scissors Radioactive Material Stickers Yellow and Magenta Tape Stanchion Clipboard w/Dosimeter ID Number Pens/Pencils Notebook Writing Tablets Smears Decontamination Table Top Hose with Hand Shower Connection Potassium Iodide Batteries Decon Soap DLR's Masselin Mop Masselin Cloth Waste Containers (Yellow) G-7 Rev. 048 __ J'
l WATERFORD 3 SES EMERGENCY PLAN APPENDIXG HEALTH PHYSICS AMBULANCE KIT Ludlum 12 (or equivalent) w/Pancake Probe Rubber Overshoes Rubber Gloves Tape Absorbent Material Pens Survey Forms Clipboard Smears DLR's Plastic Booties Pre-Cut Herculite Batteries Barricade Tape Paper Coveralls Radioactive Material Bags CS-137 Check Source Dosimeters 0-200 mR G-8 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN APPENDIXG ASSEMBLY AREA SUPERVISOR KIT Bull Horn Air Horn Flashlight Cellular Phone Handheld Radio G-9 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN APPENDIX H PROCEDURE CROSS REFERENCE BETWEEN THE EMERGENCY PLAN IMPLEMENTING PROCEDURES . AND THE EMERGENCY PLAN Rev.048
WATERFORD 3 SES EMERGENCY PLAN APPENDIX H PROCEDURE CROSS REFERENCE Document Section I Implementing Instructions Emergency Plan Sections EP-001-001 Recognition and Classification of 1.1.16, 1.1.17, 1.1.19, 4.0, 4.1, Emergency Conditions 4.2, 4.3, 5.1.2.1, 5.1.2.2a 1, 6.1 EP-001-010 Unusual Event 1.1.83, 4.1.1, 4.3, 5.1.2.1, 5.1.2.2a1, 6.1.3 EP-001-020 Alert 1.1.4, 4.1.2, 4.3, 5.1.2.2a1, 6.1.3 EP-001-030 Site Area Emergency 1.1.77, 4.1.3, 4.3, 5.1.2.2a1 I 6.1.3 EP-001-040 General Emergency 1.1.36, 4.1.4, 4.3, 5.1.2.2a 5.1.2.2a1, 6.1.3 Document Section II Implementing Procedures Emergency Plan Sections EP-002-010 Notifications and Communications 5.1.2.1, 5.1.2.2c, 5.1.2.2d, 5.1.2.3a4, 5.1.2.3g, 5.3, 6.1.3c, 6.2.1, 6.2.2.2, 6.2.2.4, 6.2.2.5, 6.2.2.6, 6.2.2.7, 7.5 EP-002-015 Emergency Responder Activation 5.1.2, 6.2.1.1, 6.2.2, 6.2.2.3 EP-002-030 Emergency Radiation Exposure 3.1.2.1 c, 5.1.2.2a8, 5.1.2.2g, Guidelines and Controls 5.1.2.2r, 6.6.2, 6.6.3, 6. 7 .1, 7.4.8, 9.2.2.1, ~.3 EP-002-031 *in-Plant Radiological Controls and 5.1.2.2g, 5.1.2.2r, 6.6.2, 6.6.3.1, Surveys During Emergencies 7.1.3, 7.4.2, 7.4.3, 7.4.8 EP-002-032 Monitoring and Decontamination 5.1.2.2g, 5.1.2.2r, 5.1.2.2t, 6.6.1.1, 6.7.3, 6.7.4, 7.1.3, 7.4.2.7, 7.4.2.8, 7.4.8, 7.4.10 EP-002-033 Administration of Iodine Blocking 5.1.2.2a, 5.1.2.2g, 5.1.2.2r, Agents 5.1.2.3a, 5.1.2.3c, 6.6.2, 6. 7.2 H-1 Rev.048
WATERFORD 3 SES EMERGENCY PLAN APPENDIX H PROCEDURE CROSS REFERENCE Document Section II Implementing Procedures Emergency Plan Sections EP-002-034 Onsite Surveys Duririg Emergencies 5.1.2.2g, 5.1.2.2r, 6.6.3.1, 7.1.3, 7.4.2.6, 7.4.2.7, 7.4.3, 7.4.8 EP-002-050 Offsite Dose Assessment 1.1.5, 5.1.2.1, 5.1.2.3c, 5.1.2.3k, 6.3.2.4, 6.3.3.3, 6.4.2, 6.4.3, 7.4.11a EP-002-052 Protective Action Guidelines 1.1.67, 1.1.68, 4.0, 5.1.2.1a, 5.1.2.3a, 5.1.2.3c, 6.6.1.2, 7 .1.1, 7.1.2, 7.2.1 EP-002-060 Radiological Field Monitoring 5.1.2.1 g, 5.1.2.21, 5.1.2.2w6, 5.1.2.3k, 6.3.2.3, 6.3.3.2, 6.4.1, 6.4.2, 7.1.3, 7.2.1, 7.4.2.6, 7.4.3, 7.4.4, 7.4.11 b EP-002-061 Emergency Environmental 6.3.2.3, 6.3.3.2, 6.4.1, 6.4.2, Monitoring 7.4.2.6, 7.4.4, 7.4.11b EP-002-071 Site Protective Measures 1.1.77, 3.1.2.1c, 6.6.1.1, 7.4.8 EP-002-081 Search and Rescue } ( 5.1.2.2s, 5.1.2.2u3, 6.6.1.1 b EP-002-090 Core Damage. Assessment 1 1.1.5, 3.1.2.1a, 5.1.2.1c, 5:1.2.2h, 5.1.2.2k, 5.1.2.2g, 5.1.2.3c, 5.1.2.3d, 6.1.2, 6.3, 7.4.1, 7.4.2, 7.4.11c EP-002-091 Emergency Chemistry 5.1.2.1h, 5.1.2.2g, 7.4.3, 7.4.12, 7.4.13 EP-002-100 Technical Support Cente~ (TSC) 1.1.80, 5.1.2.2, 7.1.2 Activation, Operation, and Deactivation H-2 Rev.048
WATERFORD 3 SES EMERGENCY PLAN APPENDIX H PROCEDURE CROSS REFERENCE Document Section II Implementing Procedures Emergency Plan Sections EP-002-101 Operational Support Center (OSC) 1.1.59, 5.1.2.2, 7.1.3 Activation, Operation, and Deactivation EP-002-102 Emergency Operations Facility 1.1.23, 5.1.2.3, 7.2.1 (EOF) Activation, Operation, and Deactivation EP-002-130 Emergency Team Assignments 5.1.2.1.1, 5.1.2.2a, 5.1.2.2e, 5.1.2.2p, 5.1.2.2u EP-002-140 Reentry 9.3.2 EP-002-150 Emergency Plan Implementing 5.1.2.1 a, 5.1.2.2b, 5.1.2.2m, Records 5.1.2.3e, 5.1.2.4c EP-002-190 Personnel Accountability 5.1.2.1 b, 5.1.2.2b, 5.1.2.2m, 5.1.2.2p, 5.1.2.2q, 5.1.2.2s, 5.1.2.2t, 6.6.1.1 b Document Section Ill Supporting Procedures Emergency Plan Sections EP-003-020 Emergency Preparedness Drills and 3.4, 8.1.2 Exercises EP-003-030 Emergency Program Review, 3.4, 8.3, 8.4, 8.5 Updating and Modification EP-003-040 Emergency Equipment Inventory 8.4, App. G EP-003-050 Emergency Organization 5.0, 6.2.1.1, 8.3 Documentation and Control
,~,
EP-003-060 , Emergency Communications 6.2.1.2 Guidelines EP-003-070 Emergency Communications 3.4, 8.1.2.4(2) Systems Routine Testing H-3 Rev.048
WATERFORD 3 SES EMERGENCY PLAN APPENDIX H PROCEDURE CROSS REFERENCE Document Section IV Implementing Procedures Emergency Plan Sections EP-004-010 Toxic Chemical Contingency 4.3.3, 6.6.1 Procedure EP-004-015 Offsite Personnel Staging During a 6.6.1.1 Toxic Chemical Emergency EP-004-020 Backup EOF Activation, Operation 7.2.1 and Deactivation During a Toxic Chemical Emergency Document Section V Supporting Procedures Emergency Plan Sections UNT-007-018 First Aid and Medical Care 5.1.2.1.1 b, 5.1.2.2u2, 5.3.4.1, 5.3.4.2, 5.3.4.3, 5.3.4.4, 6.2.1.2a, 6.7.3, 6.7.4, 6.7.5, 7.4.10, App. G, App. I Document Section VI Training Procedures Emergency Plan Sections EN-TQ-110 Emergency Response Organization 8.1.1.3 Training EN-TQ-110-01 Fleet EPlan Training Course 8.1.1.3 Summary Document Section VII Implementing Procedures (Fleet) Emergency Plan Sections EN-EP-609 Emergency Operations Facility 1.1.23, 5.1.2.3, 7.2.1 (EOF) Operations EN-EP-610 Technical Support Center (TSC) 1.1.80, 5.1.2.2, 7.1.2 Operations EN-EP-611 Operations Support Center (OSC) 1.1.59, 5.1.2.2, 7.1.3 Operations EN-EP-613 Recovery from a Declared 1.1.72, 3.3, 9.0 Emergency H-4 Rev.048
WATERFORD 3 SES EMERGENCY PLAN APPENDIX I EMERGENCY MEDICAL ASSISTANCE PROGRAM (EMAP) Rev. 048
WATERFORD 3 SES EMERGENCY PLAN APPENDIX I EMERGENCY MEDICf.L ASSISTANGE PROGRAM TABLE OF CONTENTS Section Title Page 1.0 Scope and Applicability 1-1 2.0 References 1-1 3.0 Responsibilities 1-2 4.0 Precautions 1-4 5.0 Management of Medical Emergencies 1-4 6.0 Medical Emergency Training 1-11 7.0 Medical Emergency Drills 1-11 8.0 Letters of Agreement Listing 1-12 NOTE: The Annual Confirmation Letters and Letters of Agreement, which under earlier revisions were included in the Attachments portion of this appendix, have been removed. These letters are now maintained in the Emergency Planning Department files. Rev. 048
WATERFORD 3 SES EMERGENCY PLAN APPENDIX I 1.0 SCOPE AND APPLICABILITY The Waterford 3 Emergency Medical Assistance Program (EMAP) provides the basis for handling onsite medical emergencies, including injured/ill persons that are radioactively contaminated or have received exposures to ionizing radiation above limits, requiring action by offsite medical personnel/services. EMAP assigns general responsibilities to Entergy Operations, Inc. and to support hospitals. EMAP describes the essential elements for provision of emergency medical services. Thus, EMAP provides the overall plans, specific requirements, and commitments required for the development of a detailed implementing document for managing medical emergencies. Waterford 3 procedures provide the detailed information and protocols for management of onsite medical emergencies. The implementing document is distributed to those individuals, facilities, or organizations involved in response to medical emergencies.
2.0 REFERENCES
2.1 Waterford 3 Emergency Plan Section 6.0, Emergency Response Measures Section 7.0, Emergency Response Facilities and Equipment Section 8.0, Maintenance of Emergency Preparedness 2.2 Waterford 3 Emergency Plan Implementing Documents EP-003-020, Emergency Preparedness Drills and Exercises EP-003-040, Emergency Equipment Inventory EP-002-032, Monitoring and Decontamination UNT-007-018, First Aid and Medical Care 2.3 St. Charles Parish Emergency Operations Plan, Annex J, Health and Medical 2.4 Ochsner Clinic Foundation ~adiation Accident Plan 2.5 West Jefferson Medical Center Procedures for the Decontamination and Treatment of the Radioactively Contaminated Patient 2.6 State of Louisiana Peacetime Radiological Response Plan, Attachment 1
- Waterford 3 Steam Electric Station
- 2. 7 State of Louisiana Peacetime Radiological Response Plan, Chapter 10, Medical and Public Health Services 2.8 Facilities and Medical Care for Onsite Nuclear Power Plant Radiological Emergencies, ANSI/ANS - 3.7.1 -1979 2.9 Public Health Service Guide for Developing Health Disaster Plans, DHEW, 1974 1-1 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN APPENDIX I 2.10 Emergency Medical Services System Act of 1973 (P.L. 93-154 as amended) 3.0 RESPONSIBILITIES 3.1 Entergy Operations, Inc. and Entergy Louisiana, LLC. 3.1.1 Initiate all appropriate provisions of EMAP in the event of an onsite medical emergency. 3.1.2 Coordinate all aspects of providing onsite emergency medical services. 3.1.3 Provide initial first aid via designated, trained shift personnel. 3.1.4 Provide technical guidance and assistance to protect emergency medical personnel involved in the treatment/ transportation of the radiation accident patient and to minimize the spread of radionuclide contamination. 3.1.5 Provide a Health Physics technician to assist support hospital
- emergency departments with monitoring and decontamination of the radiation accident patient.
3.1.6 Provide personnel, equipment and facilities for the radiological monitoring and decontamination of any and all ambulance vehicles and equipment used for transport of the radiation accident patient and involved hospital facilities/equipment. 3.1. 7 Provide initial and training per calendar year to support hospital personnel in decontamination procedures, use of radiation emergency equipment and supplies, basic health physics indoctrination, radiological aspects of emergency medical treatment, and procedural elements of EMAP and associated Emergency Plan Implementing Procedures. 3.1.8 Coordinate emergency medical drills per calendar year, involving a simulated contaminated patient, which will require participation by local (offsite) emergency medical services/agencies. 3.1.9 Provide to the support hospitals a Radiation Emergency Kit containing equipment/supplies necessary for personnel protection; Radiation Emergency Area set-up; patient monitoring, decontamination and sample taking; and waste handling. 3.1.10 Provide for quarterly inspection, inventory, operational checking, and maintenance/calibration of all Health Physics and emergency medical equipment/supplies stored for emergency use. 3.1.11 Coordinate release of information to news media.regarding emergency occurrences at Waterford 3. 3.2 Ochsner Clinic Foundation (hereinafter Ochsner) 3.2.1 Accept and treat injured/ill personnel from Waterford 3, including personnel that are radioactively contaminated or have been exposed to ionizing radiation. 1-2 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN APPENDIX I
- 3.2.2 Maintain the capability and facilities to provide emergency medical treatment, monitoring and decontamination to injured/ill personnel from Waterford 3 for 24 hours per day.
3.2.3 Provide, upon Entergy Operations, Inc., request, qualified medical personnel for consultation and/or onsite assistance in managing medical emergencies with associated radiation contamination/overexposure, and/or administration of radioprotective drugs to affected persons. 3.2.4 Provide storage space for the Radiation Emergency Kit provided by Entergy Operations; Inc. 3.2.5 Participate to the fullest extent possible in training programs and emergency medical drills intended to maintain emergency preparedness. 3.2.6 Accept and transport, via Flight Care helicopter, injured or ill personnel from Waterford 3, whether or not they are radioactively contaminated or overexposed to the support hospital designated by Entergy Operations, Inc. 3.3 West Jefferson Medical Center 3.3.1 Accept and treat injured/ill personnel from Waterford 3, including personnel that are radioactively contaminated or have been exposed to ionizing radiation. 3.3.2 Maintain the capability and facilities to provide emergency medical treatment, monitoring and decontamination to injured/ill personnel from Waterford 3 for 24 hours per day. 3.3.3 Provide storage space for the Radiation Emergency Kit provided by Entergy Operations, Inc. ' 3.3.4 Accept and transport, via the Flight Care helicopter ambulance service, injured/ill personnel from Waterford 3 (including personnel that are radioactively contaminated or have been exposed to ionizing radiation) to the support hospital designated by Entergy Operations, Inc. 3.3.5 Participate to the fullest extent possible in training programs and emergency medical drills intended to maintain emergency preparedness. 3.4 St. Charles Parish Hospital 3.4.1 Accept and treat personnel from Waterford 3, having experienced an injury or illness that are not radioactively contaminated or overexposed to ionizing radiation. 3.4.2 Provide 24-hour primary (first-due) emergency medical transportation (ambulance) to accept and transport, via the St. Charles Parish Hospital Ambulance Service, injured/ill personnel from Waterford 3 (including personnel that are radioactively contaminated or have been exposed to ionizing radiation) to the support hospital designated by Entergy Operations, Inc. I 1-3 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN APPENDIX I 3.4.3 Participate to the fullest extent possible in training programs and emergency medical drills intended to maintain emergency preparedness. 1-4 Rev. 048 /
WATERFORD 3 SES EMERGENCY PLAN. APPENDIX I 3.5 U.S. Department of Energy 3.5.1 Provide radiation medicine and health physics consultation through the Radiation Emergency Assistance Centerffraining Site (REACffS) operated by Oak Ridge Associated Universities. 3.5.2 Provide patient referral facilities of Ochsner and West Jefferson . Medical Center through the Radiation Emergency Assistance Centerffraining Site operated by Oak Ridge Associated Universities in conjunction with Oak Ridge Hospital of the United Methodist Church. 4.0 PRECAUTIONS 4.1 Emergency medical treatment ' takes precedence over decontamination. Life-support procedures must be instituted prior to decontamination (i.e., bleeding must be stopped and breathing restored). 4.2 Treatment and transfer of contaminated injured/ill personnel to support hospital facilities must include appropriate actions to minimize spread of contamination to uncontaminated areas and emergency medical personnel. 5.0 MANAGEMENT OF MEDICAL EMERGENCIES 5.1 Entergy Operations, Inc. Emergency Medical Services 5.1.1 Decontamination and First Aid Facilities Facilities for monitoring, decontaminating and/or providing first aid/emergency care treatment of personnel are located in the Health Physics Area on the -4.0 ft. Mean Sea Level (MSL) elevation of the Waterford 3 Reactor Auxiliary Building. Decontamination showers, sinks, eyewash supplies, personnel monitoring equipment, as well as basic emergency medical equipment and supplies are contained within this area. In addition, first aid lockers are provided in strategic locations onsite as described in station procedures. 5.1.2 Emergency Teams Emergency teams including the First Aid Team and the Search and Rescue Team (as described in Section 5.0 of the Waterford 3 Emergency Plan) can be assembled to render necessary assistance. Shift personnel maintaining first aid/emergency care certification are available on a 24-hour per day basis to assist injured/ill personnel either at the accident scene or in the First Aid Area. Health Physics personnel will be available on a 24-
,hour per day basis to process personnel radiation dosimetry, monitor for radiation contamination and decontaminate affected personnel.
1-5 Rev.048
WATERFORD 3 SES EMERGENCY PLAN APPENDIX I 5.1.3 Emergency Medical Transportation St. Charles Parish Hospital Emergency Medical Service, Advanced Life Support, staffed/equipped, provides primary (first-due) emergency medical services to transport injured/ill personnel to offsite support hospitals (reference Attachment 8.3). The vehicle(s) operated to provide this care and transportation are designed to meet U.S. D.O.T. Federal specifications for "Star of Life Ambulance" (KKKA-1822A) and carry the patient care, security, access, and miscellaneous equipment recommended by the American College of Surgeons. The vehicle(s) have two-way radio communications capability to the St. Charles Parish Sheriff's Office for dispatch and coordination and to the support hospitals (Ochsner and West Jefferson Medical Center) and St. Charles Parish Hospital for appropriate medical control, consultation and notification. Personnel protective equipment, monitoring devices and patient contaminant control materials are provided by Entergy Operations, Inc., upon ambulance vehicle entrance to the Waterford 3 plant site. Ochsner provides Flight Care helicopter ambulance service (advanced life support staffed/equipped) for patient care and transportation should circumstances require air evacuation to support hospitals and/or immediate medical intervention in cases of life-threatening trauma/cardio-respiratory ( arrest. 5.2 Medical Support Facilities 5.2.1 Ochsner Ochsner, 1514 Jefferson Highway, New Orleans, Louisiana 70121 (located approximately 20 miles from Waterford 3) is a 532-bed acute care medical facility designated as the regional trauma center (ACS Level I) and Medical Resource Hospital. As a professional partnership providing 31 medical and surgical specialists, including the Department of Radiation Oncology (which coordinates the medical care and treatment of radiation-associated injuries) and the Departments of Nuclear Medicine, Radiology, Hematology and Emergency Medical Service-Industrial Medicine, Ochsner provides the capability to accept and provide treatment to patients experiencing radiation-associated injury/illness. Ochsner arrangements for managing medical emergencies involving radiation include configuration of an isolated radiation emergency area adjacent to the emergency department and utilization of a designated radiation management team for patient treatment/decontamination. 1-6 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN / APPENDIX I 5.2.2 West Jefferson Medical Center West Jefferson Medical Center, 1101 Medical Center Boulevard, Marrero, Louisiana 70072 (located approximately 20 miles from Waterford 3) is a 462-bed acute care medical facility designated as an area-wide trauma center (ACS Level II). West Jefferson Medical Center arrangements for managing medical emergencies inv.olving radiation include configuration of an isolated radiation emergency area adjacent to the emergency department and utilization of a designated radiation management team for patient treatqient/decontamination. 5.2.3 Nearest Available Medical Facility - St. Charles Parish Hospital St. Charles Parish Hospital, Post Office Box 87, 1057 Paul Maillard Road, Luling, Louisiana 70070 (located approximately 8 miles from W3SES) is a 99-bed acute care general hospital \ providing 24-hour emergency room services with an on-duty physician. Fifty (50) acute care beds are located in the main building and 49 psychiatric beds are located within the two back wings of St. Charles Manor. Entrance to the Psychiatric Unit is on Angus Drive. As a parish general hospital, St. Charles Parish Hospital is capable of managing medical and surgical emergencies that do not involve radiation exposure or radioactive contamination. 5.3 Patient Handling and Treatment 5.3.1 First Aid/Emergency Care (Onsite) c Emergency medical care to injured/ill personnel is initiated regardless of whether the injury/illness is radiation or non-radiation associated. Shift personnel, certified in first aid/emergency care techniques, are available onsite on a 24-hour per day basis to render assistance to injured/ill personnel at the accident scene. 5.3.2 Radiation Monitoring arid Decontamination Injured/ill personnel exiting controlled access areas or found to be contaminated are monitored and decontaminated prior to being transported to support medical facilities, provided such decontamination does not adversely affect the health and safety of the patient. In cases of life-threatening trauma/illness or persistent contamination, where patients must be transported to support medical facilities prior to complete decontamination, measures are taken to minimize the spread of contamination. A Waterford 3 Health Physics technician shall accompany contaminated patient(s) to the support hospital to supervise control of contamination and to serve in an advisory capacity to the hospital Radiation Management Team for monitoring and decontamination of the radiation accident patient and involved hospital facilities/equipment. - 1-7 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN APPENDIX I 5.3.3 Physician Consultation/Onsite Assistance For managing life-threatening medical emergencies, wound decontamination, and/or treatment requiring administration of radioprotective drugs, medical consultation, and/or onsite physician assistance is available through qualified medical personnel of Ochsner. Consultation for managing persistent or difficult cases of radiation contamination/overexposure is available through qualified medical/Health Physics personnel of the Radiation Emergency Assistance Center/Training Site (REAC/TS). 5.3.4 Notifications Transportation of a contaminated or overexposed injured/ill patient from Waterford 3 to a support hospital requires advanced notification of support hospitals (reference Section 5.3.6.2). 5.3.5 Emergency Medical Transportation 5.3.5.1 Transportation Modalities The primary means of emergency medical transportation is the St. Charles Parish Hospital Ambulance Service. Air transportation via Ochsner's Flight Care helicopter ambulance service supplements ground transportation in situations where the injured/ill patient is determined to be medically unstable or when ground transportation would be inadvisable. The Waterford 3 Emergency Coordinator, in consultation with members of the First Aid Team, will determine the priorities for the mode of emergency medical transportation based on the need for immediate medical intervention, the comfort of the patient, and the vehicles available. 5.3.5.2 Ambulance Monitoring/ Decontamination Following admission of the contaminated patient(s) to the support hospital Radiation Emergency Area, the ambulance vehicle, associated equipment and emergency medical personnel are surveyed by the Waterford 3 Health Physics technician assisting the hospital Radiation Management Team. If contamination is determined, the ambulance is returned to Waterford 3 for decontamination prior to release to active duty. An exception can be made should the vehicle in question be the only emergency ambulance available to answer an emergency call and the area of contamination can be adequately contained or sealed against further spreading. 1-8 Rev. 048 L __ _
WATERFORD 3 SES EMERGENCY PLAN APPENDIX I 5.3.5.3 Medical Communications Emergency medical communications between the support hospitals (Ochsner and West Jefferson Medical Center) and the ambulance services (St. Charles Parish Hospital Emergency Medical Service and/or Ochsner's Flight Care helicopter) utilize the HEAR network radio system (regional hospital disaster Channel). 5.3.6 Support Hospital 5.3'.6.1 Selection of Support Hospital Depending upon the severity of injury/illness, the number of affected individuals, and the presence and degree of radiation contamination/ overexposure, the Waterford 3 Emergency Coordinator determines patient(s) destination. 5.3.6.2 Hospital Notifications Support hospitals receive prior notification of patients being transported to their emergency departments for emergency medical care. Notification includes:
- a. Number of patients;
- b. Number of radioactively contaminated/injured patients;
- c. Type/degree of radioactive contamination or overexposure;
- d. Assessment of injury/illness type and severity;
- e. Method of emergency medical transportation to be utilized; and
. f. Estimated time of arrival.
5.3.6.3 Emergency Department Admission Support hospital emergency department admission and treatment of injured/ill patient(s) is governed by standard operating procedures. However, in the event that the injured/ill patient is radioactively contaminated, normal admissions procedures are superseded by the appropriate procedures for managing medical emergencies involving radiation contained within the support hospital's Emergency Management Plan. 1-9 Rev.048
WATERFORD 3 SES EMERGENCY PLAN APPENDIX I 5.3.6.4 Inter-Hospital Patient Transfer For extreme radiation accident cases requiring long-term treatment, the Department of Energy provides patient referral facilities to Ochsner and West Jefferson Medical Center through the Radiation Emergercy Assistance CenterfTraining Site operated by Oak Ridge Associated Universities in conjunction with Oak Ridge Hospital of the United Methodist Church. 5.4 Public Information Entergy is responsible for release of information to news media regarding circumstances related to emergency occurrences at Waterford 3, including nature and extent of the occurrence; time and date it occurred; number of persons (believed to be) injured; and medical destination of those injured. Release of information on the medical* condition of injured persons is the responsibility of the treating medical facility, after notifying the Duty Entergy Spokesperson or the Emergency News Center Director as to what information is to be released. Support hospitals will release information, initially and periodically, on persons injured in Waterford 3 emergency occurrences, although not on the occurrences themselves. Support hospitals will release no information on DOA victims or Waterford 3 emergencies until next of kin and the Duty Entergy Spokesperson or the Emergency News Center Director have been notified. 5.5 Synopsis As indicated, medical support for Waterford 3 is based on a three-tier approach involving;
- a. Onsite first aid/emergency care and triage;
- b. Offsite emergency medical treatment at support hospitals; and, where necessary,
- c. Definitive radiological evaluation and/or treatment from the Radiation Emergency Assistance CenterfTraining Site (REACfTS).
To understand the EMAP response to medical emergencies, the following scenario is provided. 1-10 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN APPENDIX I 5.5.1 Scenario Initially, the Control Room operators are notified of a medical emergency occurrence through contact with personnel at the emergency scene. Control Room operators in turn alert the First Aid Team to respond and render immediate medical attention. The First Aid Team makes a determination as to whether the medical emergency will require offsite medical assistance and whether the involved individual is radioactively contaminated or overexposed. In the event that the injured/ill individual(s) requires offsite medical attention, emergency medical transportation, provided by the St. Charles Parish Hospital Ambulance Service or the Ochsner Flight Care helicopter is dispatched through the St. Charles Parish Sheriff's Office for St. Charles Parish Hospital and by telephone for Ochsner via request from the Shift Manager. Patients requiring offsite medical care are transported fo the selected support hospital for medical treatment. Injured/ill personnel exiting a controlled access area and i requiring offsite medical attention are monitored and decontaminated prior to being transported to support.medical facilities, provided such decontamination does not adversely affect the health and safety of the patient. In cases of life-threatening trauma/illness or persistent contamination, measures are taken to minimize the spread of contamination during transport to the support hospital.
- A Waterford 3 Health Physics technician accompanies the contaminated patient to the support hospital to serve in an advisory capacity to the hospital Radiation Management Team.
This individual assists in the monitoring and decontamination of the involved ambulance vehicle or helicopter. Support hospitals are primarily responsible for patient resuscitation and stabilization, decontamination, and providing . initial treatment of radiation injuries, if such treatment is indicated. In the event that the patient has incurred excessive radiation exposure and/or internal contamination, the services of the Radiation Emergency Assistance Center/Training Site (REAC/TS) may be called upon. This assistance may include direct consultation with REAC/TS physicians and/or transfer of the patient to REAC/TS for specialized treatment (radiosurgical decontamination, reverse isolation, bone marrow transplantation, and/or while blood cell transfusion) as determined necessary by the patient's conditions. Following treatment and transfer of the radiation accident patient (to direct hospital admission status or another facility for specialized care), all involved facilities, equipment, and personnel are monitored and decontaminated (as necessary) prior to release by the Waterford 3 Health Physics technician. 1-11 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN APPENDIX I 6.0 MEDICAL EMERGENCY TRAINING 6.1 Onsite Emergency Response Personnel Waterford 3 personnel assigned to Emergency Teams (reference Section 5.1.2) receive general Emergency Plan instruction/training and, dependent upon team assignments, instruction/training in specific subjects. 6.2 Offsite Emergency Response Personnel and Support Organization Personnel Entergy Operations, Inc. provides support hospital (Ochsner and West Jefferson Medical Center) emergency departments and Radiation Management Team members, St. Charles Parish Hospital Ambulance Service and Ochsner's Flight Care helicopter flight/medical crew with initial and instruction/training per calendar year in decontamination procedures, use of radiological emergency equipment and supplies, basic health physics indoctrination, radiological aspects of emergency medical treatment, and procedural elements of the EMAP and associated Emergency Plan Implementing Procedures. 7.0 MEDICAL EMERGENCY DRILLS A medical emergency drill (supervised instruction period intended to test, develop and maintain skills in emergency operations) involving a simulated contaminated individual, and containing provisions for support hospital and ground or air ambulance services participation, is conducted at least annually. The offsite portions of the medical emergency drill may be performed as part of an exercise or other scheduled drills (emergency simulation of offsite radiological
- release requiring response by offsite organizations, including mobilization of state and parish emergency personnel/resources, adequate to verify the capability to respond to accident scenarios requiring response).
Qualified individuals observe and critique the drills for the purpose of evaluating the ability of participating organizations to respond as called for in EMAP. Any inadequacies found as a result of the drill critique are documented, with necessary improvements incorporated in EMAP and/or supporting Emergency Plan Implementing Procedures. 1-12' Rev. 048
WATERFORD 3 SES EMERGENCY PLAN APPENDIX I 8.0 LETIERS OF AGREEMENT LISTING I The current Letters of Agreement maintained with the hospitals listed . below, which under earlier revisions resided in this appendix, have been removed. These documents are now maintained in the Emergency Planning Department files. Entergy OperatiOns, Inc. maintains agreements with the following hospitals in support of Waterford 3 emergency response. Ochsner Clinic Foundation St. Charles Parish Hospital West Jefferson Medial Center Rev.048
WATERFORD 3 SES EMERGENCY PLAN APPENDIXJ NUREG 0654 CROSS REFERENCE Rev. 048
WATERFORD 3 SES EMERGENCY PLAN APPENDIXJ NUREG 0654 CROSS REFERENCE A. Assignment of Responsibility NUREG 0654 W3SES E-PLAN REFERENCE GUIDELINES Section Figures Tables 1a 5.2, 5.3, APP. I 5-6 5-2 1b 5.1, 5.2, 5.3, APP. I 5-2 1c 5-1A, 5-1C, 5-2, 5-2, 5-3 5-3, 5-4, 5-6 1d 5.1.2.1 a, 5.1.2.2a, 5.1.2.3a 1e 5.1.2.1 3 APP. A, C, D, E, F, I 4 5.1.1.1 B. Onsite Emergency Organization NUREG 0654 W3SES E-PLAN REFERENCE GUIDELINES Section Fi~ures Tables 1 5.1.1.1, 5.1.2.1, 5.1.2.2 5-2 2 5.1.2.1a 3 5.1.2.1 a, 5.1.2.1 b, 5.1.2.2a I 4 5.1.2.2a, 5.1.2.3.1 a 5 5.1.2, 5.4 5-1 6 5-6 7a 5.1.2.3 5-3 7b 5.1.2.3 5-3 7c 5.1.2.3 5-6 7d 5.1.2.4 5-4 8 5.2, APP. A, C, F 9 5.3.1, 5.3.2, 5.3.4, 5-6 5-2 APP.C, I J-1 Rev. 048
WATERFORD3 SES EMERGENCY PLAN APPENDIXJ NUREG 0654 CROSS REFERENCE C. Emergency Response Support and Resources NUREG 0654 W3SES E-PLAN REFERENCE GUIDELINES Section Figures Tables 1a 5.1.2.2a, 5.1.2.3a 1b 5.3.3.1, 5.3.3.2 1c 5.3.3.2 2b 5.1.2.3q 5-3 3 7.4.3 4 5.2, 7.4.3, 7.4.4, 7.4.5, 7.4.7, APP. A, C, F D. Emergency Classification System NUREG 0654 W3SES E-PLAN REFERENCE GUIDELINES* Section I Figures Tables 1 4.0 4-4, 4-5 2 4-1, 4-2, 4-3, 4-4 E. Notification Methods and Procedures NUREG 0654 W3SES E-PLAN REFERENCE GUIDELINES Section Figures Tables 1 6.2 2 6.2.2 3 6-2 4a 6-2 4b 6-2 4c 6-2 4d 6-2 4e ' 6-2 4f 6-2 4g 6-2
- Waterford 3's Emergency Classification System is based on NEI 99-01 Methodology of Development of Emergency Action Levels J-2 . Rev. 048
WATERFORD 3 SES EMERGENCY PLAN APPENDIXJ NUREG 0654 CROSS REFERENCE . E. Notification Methods and Procedures (Cont'd.) NUREG 0654 W3SES E-PLAN REFERENCE GUIDELINES Section Figures Tables 4h 6-2 4i 6-2 4j 6-2 4k 6-2 41 6-2 4m 6-2 4n 6-2 6 6.2.2.4, 6.2.2.5, 6.2.2.6, 6.2.2. 7' 6.6.1.3, 6.8, APP.K 7 6.8.1, App. K
'c.
F. Emergency Communications NUREG 0654 W3SES E-PLAN REFERENCE GUIDELINES Section FiQures Tables 1a 6.2.1.2, 7.5.2 6-3 7-10 1b 7.5.2 7-10 1c 7.5.2 7-10 1d 7.5.1, 7.5.2 7-10 1e 6.2.1.1, 6.2.2 1f 7.5.2 7-10 2 6.7.4 3 8.1.2.4(2) J-3 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN APPENDIXJ NUREG 0654 CROSS REFERENCE G. Public Education and Information NUREG 0654 W3SES E-PLAN REFERENCE GUIDELINES Section Figures Tables 1 6.8.2, 8.2 2 6.8.2, 8.2 3a 7.2.2 I 3b 7.2.1, 7.2.2 4a 5.1.2.3s, 5.1.2.4a 4b 5.1.2.4a 4c 5.1.2.4a7, 5.1.2.4f, 5.1.2.4g 5 8.1.1.4 H. Emergency Facilities and Equipment NUREG 0654 W3SES E-PLAN REFERENCE GUIDELINES Section Figures Tables 1 7.1.2, 7.1.3 7-2, 7-6, 7-7 2 7.2.1 7-1, 7-3, 7-4 4 5.1.2, 5.4, 6.2.1.1, 6.2.2 5-1C, 5-2, 5-1 5-3, 5-4 5 7.4 5a 7.4.5, 7.4. 7 5b 7.4.2, 7.4.11 4-4, 7-2,7-3, 7-4, 7-5, 7-7 5c 7.4.1, 7.4.11, 4.3.2 4-3, 4-4' 5d 7.4.6 6a 7.4.5, 7.4.7 6b 7.4.2 7-2 ) 6c 7.4.4, 7.4.3 7 7.4.4 J-4 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN APPENDIXJ NUREG 0654 CROSS REFERENCE H. Emergency Facilities and Equipment (Cont'd.) NUREG 0654 W3SES E-PLAN REFERENCE GUIDELINES Section Fiaures Tables 8 7.4.5 9 7.1.3 7-2, 7-7 10 8.4 11 APP.G 12 7.2.1 I. Accident Assessment NUREG 0654 W3SES E-PLAN REFERENCE GUIDELINES* Section Fiaures Tables 1 4-1, 4-3, 4-4 2 7.4 7-2 3a 7.4.11, 6.3 3b 7.4.11 4 7.4.11a 5 7.4.5, 7.2.1, 7.4.11 6 7.4.11a 7 6.4.1, 7.4.4, 7.4.11 8 7.4, 6.3, 6.4 9 7.4.11b 10 7.4.11 J. Protective Response NUREG 0654 W3SES E-PLAN REFERENCE GUIDELINES Section Fiaures Tables 1a 7.5.3, 6.6 1b 7.5.3, 6.6 1c 7.5.3, 6.6
- Waterford 3's Emergency Classification System is based on NEI 99-01 Methodology of Development of i
' Emergency Action Levels J-5 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN APPENDIXJ NUREG 0654 CROSS REFERENCE J. Protective Response (Confd.) NUREG 0654 W3SES E-PLAN REFERENCE GUIDELINES Section Fi!::iures Tables 1d 7.5.3, 6.6 2 6.6, 7.4.8 7-9 3 6.6.1.1 4 6.6.1.1 5 6.6.1.1 6a 6.6.2.1, 7.4.8, APP. G 6b 6.6.2.1, 7.4.8, App. G . 6c 6.6.2.2, APP. G 7 6.3, 6.6.1.2, 6.4, 4.2 8 APP. B 10a APP. E 7-9, 7-9a, 7-9b, 7-9c, 7-9d 10b APP.E 2-4, 2-5 10c 6.8, 7.5.4, APP. K 10m 6.6.1.2, APP. B 6-4 K. Radiological Exposure Control NUREG 0654 W3SES E-PLAN REFERENCE GUIDELINES Section Figures Tables 1a 6.7 1b 6.7 1c 6.7 1d 6.7 1e 6.7
'1f 6.7 1g 6.7 J-6 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN APPENDIXJ NUREG 0654 CROSS REFERENCE K. Radiological Exposure Control (Cont'd.) NUREG 0654 W3SES E-PLAN REFERENCE GUIDELINES Section FiQures Tables 2 6.7 J 3a 7.4.2.7 3b 7.4.2.7 5a 6.6.3 5b 6.7.3, 7.4.8, 7.4.10, 7.1.3 6a 6.6.3 6b 6.6.3 6c 6.6.3 7 6.6 ..1, 6.6.2, 7.4.8, 7.4.10 L. Medical and Public Health Support NUREG 0654 W3SES E-PLAN REFERENCE GUIDELINES Section Figures Tables 1 6.7.3, 6.7.4, 6.7.5, 5.3.4, APP. I 2 6.7.3, 7.4.10 4 5.3.4, 6.7.4, APP. I M. Recovery and Reentry Planning and Post-accident Operations NUREG 0654 W3SES E-PLAN REFERENCE GUIDELINES Section Figures Tables 1 9.3.2 2 9.2 9-1 3 9.1 4 7.4.11 a J-7 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN APPENDIXJ NUREG 0654 CROSS REFERENCE N. Exercises and Drills NUREG 0654 W3SES E-PLAN REFERENCE GUIDELINES Section Figures Tables 1a 8.1.2.4(1) 1b 8.1.2.4(1) 2a 8.1.2.4(2) 2b 8.1.2.4(3) 2c 8.1.2.4(4) 2d 8.1.2.4(5) 2e 8.1.2.4(6) 3a 8.1.2 3b 8.1.2 3c 8.1.2 3d 8.1.2 3e 8.1.2 ' 3f 8.1.2 4 8.1.2.6 5 8.1.2.6
- 0. Radiological Emergency Response Training NUREG 0654 W3SES E-PLAN REFERENCE GUIDELINES . Section Figures Tables 1a 8.1.1 2 8.1.2 3 5.1.2.1.1 b, 5.1.2.2aa2 4a 8.1.1 4b 8.1.1 4c 8.1.1 4d 8.1.1 J-8 Rev. 048
WATERFORD 3 SES EMERGENCY PLAN APPENDIXJ NUREG 0654 CROSS REFERENCE
- 0. Radiological Emergency Response Training (Cont'd.}
NUREG 0654 W3SES E-PLAN REFERENCE GUIDELINES Section Figures Tables 4e 8.1.1 4f 8.1.1 4g 8.1.1 4h 8.1.1 4i 8.1.1 4j 8.1.1 5 8.1.1 P. Responsibility for the Planning Effort NUREG 0654 W3SES E-PLAN REFERENCE GUIDELINES Section Figures Tables 1 8.1.1.5 2 8.0 3 8.3.1 4 8.3
)
5 8.3 6 Appendices 7 APP.H I 8 Table of Contents 9 8.5 10 8.3.4 J-9 Rev. 048
APPENDIX K WATERFORD 3 STEAM ELECTRIC STATION ALERT/NOTIFICATION SYSTEM REPORT (
SUMMARY
) Rev. 048
WATERFORD 3 SES EMERGENCY PLAN APPENDIX K The Alert Notification System Report provides a description of the systems used by St. Charles and St. John the Baptist Parishes to alert and notify the public in the event of an accident at Waterford 3. This report provides information on the authorities for the activation of the system and a description of the primary and back-up systems for alert and notification. The primary alert system is composed of 73 fixed sirens, helicopters equipped with alerting devices, the St. Charles Industrial Hot-Line, the St. John Industrial Mutual Aid Radio System, automatic dialing devices as well as special provisions for the hearing impaired, river traffic and special facilities. The back-up alert system utilizes route alerting in populated and wetland areas and alert confirmation done by the Local Parishes. The primary notification system uses both local and State release of notification messages, through the Emergency Alert System. Local Parishes also use cable TV override as part of the notification system. System maintenance and testing activities are also covered in the report. Appended to the report is a technical report which provides specific information on the analysis,
\
verification and testing of the siren system and the helicopter alerting system. The Alert/Notification System Report is provided as a separate document. K-1 Rev.048
WF3 ON-SHIFT STAFFING ANALYIS REPORT ENTERGY WATERFORD 3 STATION ON-SHIFT STAFFING ANALYSIS FINAL REPORT Revision 1 April 4, 2017
WF3 ON-SHIFT STAFFING ANALYIS REPORT TABLE OF CONTENTS I. INTRODUCTION ............................................................................................................................ 4 II. ANALYSIS
SUMMARY
.................................................................................................................. 4 A. Emergency Plan Minimum Staffing .................................................................................. s B. Other Commitments to Shift Staffing: ............................................................................... 7 C. Staffing Exceptions and Time Motion Studies (TMS) ..................................................... 6 D. Emergency Plan Tasks Not Analyzed .............................................................................. 7 Ill. ANALYSIS PROCESS ........... ~ ....................................................-................................................... 8 IV. ACCIDENT SCENARIOS .............................................................................;.................. ~ ............. 9 A. Accident Selection ............................................................................................................. 9 B. Accident Scenarios included in the Analysis ................................................................... 9 C. Accident Scenarios Not Included in the Analysis .......................................................... 11 V. GENERAL ASSUMPTIONS AND LIMITATIONS ...................................................................... 12 A. Notes and Assumptions Applicable to All WF3 OSA ........................ ,........................... 12 B. NEI 10-05 Rev 0 Assumptions ........................................................................................ 12 VI. APPENDIX A - ANALYZED EVENTS AND ACCIDENTS ........................................................ 15 VII. APPENDIX B - ON-SHIFT STAFFING ANALYSIS .................................................................. 17 A. Accident Analysis #1 - Design Basis Threat (DBT)...................................................... 17 B. Design Basis Accident Analysis #2 -Steam Line Break Inside Containment with Loss of Offsite Power (LOP) .................................................................................................... 22
- c. Design Basis Accident Analysis #3 - Feedwater Line Break with Loss of Offsite Power (LOP) ..................................................................................................................... 28
- p. Design Basis Accident Analysis #4 - Single RCP Shaft Seizure/Sheared Shaft with LOP ................................................................................................................................... 33 E. Design Basis Accident Analysis #5 - Control Element Assembly Ejection ................ 39 F. Design Basis Accident Analysis 00 :. Letdown Line Break Outside Containment ...... 44 G. Design Basis Accident Analysis #7 - Steam Generator Tube Rupture ...................... 49 H. Design Basis Accident Analysis #8 - Loss of Coolant Accident (LOCA) .................... 54 WF3 Page 2
WF3 ON-SHIFT STAFFING ANALYIS REPORT I. Design Basis Accident Analysis #9 - Fuel Handling Accident... .................................. 59 J. Accident Analysis #10 - Control Room Evacuation and Remote Shutdown ............... 64 K. Accident Analysis #11 - Aircraft Probable Threat... ...................................................... 69 L. Accident Analysis #12- LOCA/General Emergency with Release and PAR. ............ 75 M. Accident Analysis #14 - Station Blackout... ................................................................... 81 VIII. APPENDIX C- TIME MOTION STUDIES SUPPORTING THE STAFFING ANALYSIS ...... 86 A. None......................: ..................................................*........................................................ 86 IX. OVERLAP OF TASKS ACTIVITIES OR OTHER CONFLICTS IDENTIFIED ......................... 86 A. _overlap Requiring Compensatory Measures ................................................................ 86 X. REFERENCES ............................................................................................................................. 86 XI. STAFFING ANALYIS TEAM .......................................................:................................................ 86 WF3 Page 3
WF3 ON-SHIFT STAFFING ANALYIS REPORT I. INTRODUCTION 1 This document is revision 1 to the final report for the On-shift Staffing Analysis (OSA) for the Waterford Station (WF3). This OSA satisfies the requirement of 10 CFR 50 Appendix E Section IV.A9, which states that nuclear power licensees shall perform "a detailed analysis demonstrating that on-shift personnel assigned emergency plan implementation functions are not assigned responsibilities that would prevent the timely performance of their assigned functions as specified in the emergency plan." A structured approach was utilized to perform this analysis using the guidance found in NEI 10-05, Rev. 0, Assessment of On-Shift Emergency Response Organization Staffing and Capabilities. This analysis examined the capability of the minimum staff listed in Table 5-1 of the WF3 Emergency Plan (E-Plan) to perform the actions for the key functional areas of events described in NSIR/DPR-ISG-01, Interim Staff Guidance - Emergency Planning for Nuclear Power Plants, until augmenting Emergency Response Organization (ERO) staff arrives in accordance with the E-Plan. Changes made in revision 1 include: (1) elimination of the Remote Shutdown Operator #2 position in the tables supporting accident analyses throughout the report and the reassignment of these responsibilities; (2) reduction of the on-shift personnel requirement from 17 to 16 to reflect the elimination of the Remote Shutdown Operator #2 position; (3) correction of information appearing Revision 0, Table 5 to Analysis 4 to account for the Emergency Communicator filling the Offsite Radiological Assessment function; (4) correction of information appearing Revision 0, Table 1 to Analysis 11 to add the Personnel Accountability role to Auxiliary Operator #5. II. ANALYSIS
SUMMARY
The OSA team determined that an on-shift staff of sixteen (16) is required to respond to the most limiting accident scenario reviewed, Main Control Room fire and shutdown at the Remote Shutdown Panel. The on-shift staff consists of individuals necessary to support each of the emergency plan functional areas or tasks:
- Emergency Direction and Control
- Plant Operations and Safe Shutdown (SSD)
- Fire Fighting (FB)
- Accident Assessment
- Radiation Protection and Chemistry
- Notification/Communication
- Technical Support
- Access Control and Accountability NEI 10-05 states it is acceptable for certain functions to be assigned to personnel already assigned other functions/tasks. These include Repair and Corrective Action, Rescue Operations and First Aid.
WF3 Page4
WF3 ON-SHIFT STAFFING ANALYIS REPORT A. Emergency Plan Minimum Staffing Per 10 CFR 50.54 (q)(1 )(iii), Emergency planning function means a capability or resource necessary to prepare for and respond to a radiological emergency, as set forth in the elements of section IV of Appendix E and, for nuclear power reactor licensees, the planning standards of§ 50.47(b). The following table indicates the result of the NEI 10-05 staffing analysis of on-shift personnel to perform the required emergency planning functions and the licensing basis requirement for each on-shift position. On-Shift Staffing Position E-Plan Requirement E-Plan Functional Area Analysis Results Emergency Direction and Shift Manager (SM) E-Plan Table 5-1 1 Control Control Room Supervisor E-Plan Table 5-1 SSD 1 (CRS) Shift Technical Advisor/FSS E-Plan Table 5-1 Technical Support 1 (STA) Reactor Operator (RO #1 ) E-Plan Table 5-1 SSD 1 Reactor Operator (RO #2) E-Plan Table 5-1 SSD 1 Remote Shutdown Operator E-Plan Table 5-1 SSD 12 I N/A N/A N/A N/A I Nuclear Auxiliary Operator E-Plan Table 5-1 FB 1 tAO #1) Nuclear Auxiliary Operator ,-- E-Plan Table 5-1 FB 1 (AO #2)) Nuclear Auxiliary Operator E-Plan Table 5-1 FB 1 (AO #3) Nuclear Auxiliary Operator E-Plan Table 5-1 FB 1 (AO #4) Nuclear Auxiliary Operator E-Plan Tabl~ 5-1 FB 1 (AO #5) Communicator I Notifications Nuclear Auxiliary Operator E-Plan Table 5-1 Accident Analysis 1 (AO #6) (Dose Assessment) Chemistry #1 E-Plan Table 5-1 Chemistry 1 Radiation Protection #1 E-Plan Table 5-1 Radiation Protection 1 Radiation Protection #2 E-Plan Table 5-1 Radiation Protection 1 Maintenance Tech #1 E-Plan Table 5-1 Repair & Corrective Action 11 Per Security Security Contingency Access Control and Security Contingency Plan IE-Plan Table 5-1 Accountability Plan TOTAL I 16 I Maintenance Tech - May be mechanical, electrical, or l&C WF3 Page 5
WF3 ON-SHIFT STAFFING ANALYIS REPORT 2 Remote Shutdown Operator - position required to fulfill position specific responsibilities per station operating procedures to support Control Room Evacuation due to fire. The on-shift member is available to support the Shift Manager, where qualified, in events not requiring a Control Room Evacuation due to fire. This position may be operations or other on-shift qualified individuals. None B. Staffing Exceptions and Time Motion Studies (TMS)
- 1. The primary responsibility for the on-shift Chemistry Technician is chemistry/radiochemistry sampling; however no chemistry job tasks were noted as being required within the first 90 minutes of any of the analyzed events.
- 2. The Shift Manager is assigned the responsibility to make some notifications per 01-035-000, Notification Matrix, such as the Duty Plant Manager, Operations Manager, and Resident Inspector. These notifications by phone are considered communications that are approximately one minute in length and are acceptable tasks for the Shift Manager. No further analysis or TMS is required.
- 3. Station staff is required to maintain continuous communications with the notification source during an aircraft threat in accordance with 10CFR50.54(hh) and Reg. Guide 1.214. There are no specific qualifications required to perform this task and the function is not required to be assigned in advance. The analysis of this event identified there are suffi.cient personnel on-shift to perform this task during the event. Specifically, an auxiliary operator, the radiation protection
( technicians, and a chemistry technician were all available to fill this function. No further analysis or TMS is required.
- 4. The dose assessment process used in the Control Room prior to the arrival of the augmented ERO at W3 is automated and designed to provide a radiological dose assessment value and Protective Action Recommendation in conjunction with the off-site emergency notification form. This dose assessment process is an automatic function of the emergency classification. The information for th~
notification and classification is provided to the emergency communicator by the Shift Manager and that information is input into a program that determines dose assessment criteria and develops the emergency notification form. The task of on-shift dose assessment is identified within the report as a concurrent task for the on-shift Communicator but because this is a combined and automated
\ process, the performance of dose assessment was evaluated as not requiring a separate time motion study or further evaluation to justify the task performance by the on-shift staff.
WF3 Page6 _)
WF3 ON-SHIFT STAFFING ANALYIS REPORT C. Emergency Plan Tasks Not Analyzed
- 1. Repair and Corrective Action - Per the guidance of NUREG-0654, Table B-1, repair and corrective action tasks may be performed by dedicated shift personnel or qualified shift personnel assigned other functions/tasks. Repair and corrective action is defined as:
- An action that can be performed promptly to restore a non-functional component to functional status (e.g., resetting a breaker), or to place a component in a desired configuration (e.g., open a valve), and which does not require work planning or implementation of lockout/tagout controls to complete.
In accordance with NEI 10-05 section 2.5, the analysis included a review of repair and corrective action tasks. For the purpose of this analysis, the tasks were considered to fall into two broad categories:
- Unplanned/unexpected actions that address equipment failures. These actions are contingent in nature and cannot be specified in advance.
- Planned/expected actions performed in support of operating procedure implementation, including severe accident management guidelines.
At WF3, a maintenance technician is on shift and available to perform repair and corrective actions a's needed. Nuclear Auxiliary Operators are also trained to perform the actions associated with this functional area. Repair and Corrective Action is an acceptable collateral duty per the guidance of NEI 10-05 and was not analyzed
- 2. Rescue Operations and First Aid: In accordance with NEI 10-05 section 2.6, the analysis also included a review of rescue operations and first aid response. Per the guidance of NUREG-0654, Table B-1, rescue operations and first aid may be performed by shift personnel assigned other functions. WF3 Fire brigade members are trained to perform rescue operations and are assigned the task should the need arise. Rescue operations were not required in any of the accident scenarios reviewed. Additionally, RP and Chemistry members on shift are trained to Red Cross First Aid standards and meet the basic requirements to render first aid and CPR. Rescue operations and first aid response are acceptable collateral duties per the guidance of NEI 10-05 and were not analyzed.
WF3 Page 7
WF3 ON-SHIFT STAFFING ANALYIS REPORT Ill. ANALYSIS PROCESS I This analysis was conducted by a joint team of corporate Emergency Preparedness (EP) personnel and station personnel from the Operations, Operations Training, Radiation Protection,
~
EP Training and Emergency Preparedness (EP) departments. The team members are identified in Section XI of this report. The emergency response to each event was determined by conducting a tabletop of the event using the emergency plan and procedures and the applicable department procedures such as Operations emergency and abnormal operating procedures. Each scenario was reviewed by the cross disciplinary team to determine what plant actio-ns and emergency plan implementation actions were required based on plant procedures prior to staff augmentation. These actions were then compared to the minimum staffing for Emergency Plan implementation as described in the Emergency Plan Table 5~1, ensuring that no actions were assigned to staff members that conflicted with either their dedicated emergency plan role or their dedicated operational role as appropriate. In cases where multiple tasks were assigned to an individual in their role, the team evaluated timin~ of the tasks to ensure that they could be performed by the individual in series within any specified time requirements. The results of the analysis for each of the scenarios are included in Section VII, APPENDIX B - ON-SHIFT STAFFING ANALYSIS. Note that NSIR DPR-ISG-01 states that only DBA accidents "which would result in an emergency declaration" should be evaluated in the staffing assessment. Each of WF3 DBA's were evaluated and classified according to its FSAR Chapter 15 description. If the accident description alone did not result in a classification, the projected accident Exclusion Area Boundary (EAB) dose found in the FSAR was utilized to determine if an EAL threshold would be exceeded within the first 90 minutes* using the Abnormal Rad Level EAL thresholds. In cases where several projected dose rates were provided or release data was not detailed significantly to determine an EAL, the assessment used the radiological consequences associated with the realistic case in accordance with NEI 10-05. WF3 Page 8
WF3 ON-SHIFT STAFFING ANALYIS REPORT IV. ACCIDENT SCENARIOS A. Accident Selection
- 1. The OSA scenarios were chosen using the guidance of NEI 10-05 and NSIR/DPR-ISG-01, "Interim Staff Guidance - Emergency Planning for Nuclear Power Plants." The evaluation considered the station Design Basis Accidents (OBA) described in the FSAR along with. additional scenarios specified by the guidance documents. The scenarios considered were:
- Design Basis Threat (DBT) ground assault
- OBA Steam Line Break Accident
- OBA Feedwater System Pipe Break
- OBA Single Reactor Coolant Pump Shaft Seizure/Sheared Shaft
- OBA Control Element Ejection Accident
- OBA Primary Sample or Instrument Line Break (Letdown Line)
- OBA Steam Generator Tube Rupture with Loss of Offsite Power
- OBA Loss of Coolant Accident
- OBA Fuel Handling Accident
- Fire requiring evacuation of the Control Room and plant shutdown from remote location, (Appendix R Fire)
- Aircraft Probable Threat /
- Station Blackout, (SBO)
- LOCA/General Emergency with release and PAR
- LOCA with entry into Severe Accident Management
- Appendix R Fire (Fire that results in reactor trip)
B. Accident Scenarios included. in the Analysis
- 1. Design Basis Threat (DBT) as described in NEI 10-05
- Land and/or waterborne Hostile Action directed against the Protected Area by a Hostile Force. This event assumes the threat is neutralized immediately when inside the protected area fence, no significant damage to equipment or systems that require corrective actions before the ERO is staffed, no radiological release, and no fire that requires firefighting response before the ERO is staffed.
- 2. Main Steam Line Break (MSLB) as described in FSAR 15.1.3.1 and 15.1.3.3
- Main steam line break inside containment with loss of offsite power.
Break assumes 2% fuel failure and 540 gal/day primary to secondary leak. Leakage path is reactor coolant system to steam generator to atmospheric dump valve to the atmosphere.
- 3. Feedwater Line Break as described in FSAR 15.2.3.1
- Break of main Feedwater line with loss of offsite power.
WF3 Page 9
WF3 ON-SHIFT STAFFING ANALYIS REPORT
- 4. Single Reactor Coolant Pump Shaft Seizure/Sheared Shaft as described in FSAR 15.3.3
- Reactor coolant pump shaft seizure/sheared shaft with loss of offsite power when turbine/generator trips. 15% fuel rods experience DNB.
- 5. Control Element Assembly Ejection as described in FSAR 15.4.3.2
- A CEA ejection that results in fuel damage and coolant leak. EAL is based on event.
- 6. Letdown Line Break Outside Containment as described in FSAR 15.6.3.1
- Letdown line break outside containment into the reactor auxiliary building. EAL is based on the event.
- 7. Steam Generator Tube Rupture as described in FSAR 15.6.3.2
- Double ended rupture of a single U-tube that results in exceeding charging pump capacity. No fuel failure is postulated. The EAL is based on the event.
- 8. Loss of Coolant Accident as described in USAR 15.6.3.3
- Double ended guillotine break of a recirculation line concurrent with a safe shutdown earthquake and a loss of offsite power with single diesel generator failure. No fuel damage. EAL based on event.
- 9. Fuel Handling Accident as described in 15. 7.3.4
- The accident involves a dropped fuel bundle on top of the core. Initial EAL is based on the event.
- 10. Control Room Fire and Remote Shutdown
- A fire occurs in the main control room requiring the evacuation and the procedure implemented to shutdown from the remote shutdown panels.
EAL is based on the event.
- 11. Aircraft Probable Threat (50.54hh)
- Notification is received from the NRC that a probable aircraft threat exists
(>5 minutes, <30 minutes). EAL is based on the event.
- 12. Station Blackout
- A loss of all offsite AC power occurs arid the failure of the emergency diesel generators to start.
.13. General Emergency with release and PAR
- Assumed SAE condition when dose projection indicates an upgrade to GE and a PAR based on release is needed.
WF3 Page 10
WF3 ON-SHIFT STAFFING ANALYIS REPORT C. Accident Scenarios Not Included in the Analysis
- 1. Implement Severe Accident Management Guidelines (SAMG)
- A review of the SAMGs associated with the initial site-specific Candidate High Level Actions concluded that no actions would require on-shift personnel other than licensed and non-licensed operators. No analysis required.
- 2. Appendix R Fire
- The team concluded the Control Room fire to be the most limiting for resources and therefore a staffing analysis for an additional fire scenario is not required. The emergency plan and fire brigade responsibilities are the same for both events. No analysis required.
WF3 Page 11 ...
WF3 ON-SHIFT STAFFING ANALYIS REPORT V. GENERAL ASSUMPTIONS AND LIMITATIONS A. Notes and Assumptions Applicable to All WF3 OSA
- 1. The RP and Chemistry tasks reviewed were those directed by the Shift Manager to support actions in Off Normal Procedures (OP), Emergency Operating Procedures (OP), and Emergency Plan Implementing Procedures (EP). Any additional tasks directed by the Technical Support Center (TSC), Operations Support Center (OSC), or Emergency Operations Facility (EOF) procedures were not reviewed.
- 2. WF3 has 75 minute and 90 minute emergency responders when augmented while the ERO is offsite. This analysis was conducted assuming a 90 minute response of the augmented ERO since this.is the time the emergency response facilities are required to be operational. No credit was taken for the 75 minute responders. No specific emergency response tasks requiring the augmented ERO were identified prior to the 90 minutes following the emergency declaration.
- 3. The OSA team determined there are no time critical RP and Chemistry tasks and that task performance is directed and prioritized by the Shift Manager. The time RP or Chemistry is directed to perform a task and the amount of time taken to complete tasks are estimated. No Chemistry samples are required by Tech Specs within the 90 minute period after a declaration. Since the Shift Manager directs when the tasks are performed, there are no overlapping RP or chemistry tasks.
- 4. All crews have one individual filling the SM and one individual filling the STA roles therefore the analysis did not consider using a dual-role individual.
B. NEI 10-05 Rev 0 Assumptions*
- 1. Response time used for thi.s analysis was the maximum adceptable number of minutes elapsed between emergency declaration and the augmented ERO position holder at a location necess9ry to relieve an on-shift position of the emergency response task. (90 min.)
- 2. On-shift personnel complement was limited to the minimum required number and composition as described in the site emergency plan. If the plan commitments allow for different minimum staffing levels (e.g., a variance between a nprmal dayshift and a backshift), the staffing with the smallest total number of personnel was used for the analysis.
- 3. Although the temporary absence of a position may be allowed by Tech Specs, the analysis was performed assuming that all required on-shift positions are filled.
- 4. Event occurred during off-normal work hours where ERO was offsite and all required minimum on-shift positions were filled.
WF3 Page 12
WF3 ON-SHIFT STAFFING ANALYIS REPORT
- 5. On-shift personnel reported to their assigned response locations within timeframes sufficient to allow for performance of assigned actions.
- 6. On-shift staff had necessary Radiation Worker qualification to obtain normal dosimetry and enter the radiological control area (RCA) (but not locked high or very high radiation areas) without the aid of a RP technician.
- 7. Personnel assigned plant operations and SSD met the requirements and guidance (analyzed through other programs such as operator training) and were not evaluated as part of this assessment unless a role/function/task from another major response area was assigned as a collateral duty.
- 8. In-plant (manual) safety related operator actions to manipulate components and equipment from locations outside the control room to achieve and maintain safe shutdown was done by a member of the on-shift staff as defined in the unit's Tech Specs.
- 9. Fire brigade (FB) staff performance is analyzed through other station programs (e.g., fire drills) and was not evaluated as part of this assessment unless a role/function/task from another major response area was assigned as a collateral duty.
- 10. Individuals holding the position of RP technician or Chemistry technician are qualified to perform the range of tasks expected of their position.
\
- 11. Security was not evaluated unless a role or function from another major response area was assigned as a collateral duty.
- 12. Communications, briefings, and peer checks are acceptable collateral duties.
- 13. All on-shift staff positions were evaluated, even if they had no known collateral duties, to ensure they can perform the tasks assigned to them. [Ref NSIR/DPR-ISG-01]
- 14. The Staffing Analysis specified the resources available to perform "Repair and Corrective Actions" and "Rescue Operations and First Aid" but these may be assigned as collateral duty to a designated on-shift responder.
- 15. For assessment purposes, NRC notifications were treated as a continuous action per 10CFR50.72(c)(3) and 73.71(b)(1). This means once the initial NRC communications are established, the NRC will request an open line be maintained with the NRC Operations Center.
- 16. DBA (postul~ted accident, Condition IV event, or limiting fault) is considered as "Unanticipated occurrences that are postulated for accident analysis purposes but not expected to occur during the life of the plant. A postulated accident could result in sufficient damage to preclude resumption of plant operation. As a result, a greater number and variety of actions would need to be implemented by plant personnel."
WF3 Page 13
WF3 ON-SHIFT STAFFING ANALYIS REPORT
- 17. Unless otherwise specified in NSIR/DPR-ISG-01, Interim Staff Guidance-Emergency Planning for Nuclear Power Plants, or by the USAR initial conditions of a DBA analysis, it was assumed that the unit was in Mode 1, Power.
- 18. DBT assumed a hostile force breached the protected area fence but was neutralized with no adverse consequences to plant safety. Damage inflicted on
-* plant systems, structures and components was not sufficient to prevent safe shutdown or cause a radiological release. There was no fire significant enough to warrant firefighting efforts prior to arrival of offsite resources and/or the augmented ERO.
- 19. The Staffing Analysis used OBA analysis assumptions, inputs, timing of events, plant protective response, and specified manual operator actions and their timing, as documented in the USAR.
- 20. In cases where a OBA analysis included a radiological release, and the starting point of the release was not clearly defined, the staffing analysis assumed that the release began 15-minutes after the initiating event.
- 21. Severe Accident Management Guideline (SAMG) - It is sufficient to simply assume that the accident progressed to conditions requiring a severe accident
- response; it did not include determining specific failures and the accident sequence.
- 22. SAMG - The actions analyzed included those that implement the initial site-specific actions assuming the core is not ex-vessel (i.e., no reactor vessel failure), and there is no actual or imminent challenge to containment integrity.
WF3 Page 14
WF3 ON-SHIFT STAFFING ANALYIS REPORT VI. APPENDIX A - ANALYZED EVENTS AND ACCIDENTS Event Event Summary Description Plant Reference Analysis Event ECL
# Type of Event Mode 1 Document(s) Required?
Land and/or 1 waterborne HOSTILE ACTION directed NEI 10-05 Site Area 1 DBT YES against the Protected ISGIV.C Emergency I Area by a HOSTILE FORCE. Steam Line Break 1 inside containment with FSAR 15.1.3.1 & 2 OBA LOP (bounding for Alert YES 15.1.3.3 steam system piping failures) Feedwater System 1 Unusual 3 OBA FSAR 15.2.3.1 YES Pipe Break Event Single Reactor Coolant 1 Unusual 4 OBA Pump Shaft FSAR 15.3.3.1 YES J Event Seizure/Sheared Shaft CEA Ejection 1 Site Area 5 OBA FSAR 15.4.3.2 YES Emergency Primary Sample or 1 Instrument Line Break . 6 OBA FSAR 15.6.3.1 Alert YES (Letdown Line Break Outside Containment) Steam Generator Tube 1 7 OBA Rupture with FSAR 15.6.3.2 Alert YES concurrent LOP Loss Of Coolant 1 8 OBA FSAR 15.6.3.3 Alert YES Accident Design Basis Fuel 6 9 OBA FSAR 15.7.3.4 Alert YES Handling Accident Assumed Control Room 1 10CFR50 for Evacuation and Appendix R 10 Alert YES Analysis Remote Shutdown (fire Procedure Purpose in main control room) OP-901-502 Assumed Aircraft Probable 1 for Threat. 10CFR50.54hh(1) 11 Alert YES Analysis RG 1.214 Purpose Assumed LOCA - General 1 for Emergency with 12 ISGIV.C GE YES Analysis radiological release Purpose and PAR ' WF3 Page 15
WF3 ON-SHIFT STAFFING ANALYIS REPORT Event Event Summary Descriptio~ Plant Reference Analysis 1 Event EGL
# Type of Event Mode Document(s) Required?
Assumed LOCA with entry into 1
\
for severe accident 13 ISGIV.C GE No2 Analysis procedures. Purpose I Assumed Station Blackout Event 1 for 14 ISGIV.C SAE YES Analysis Purpose Assumed Appendix R Fire with 1 for Reactor Trip 3 15 ISGIV.C Alert No Analysis Purpose 1 Plant mode per USAR or assumed for analysis purpose 2 WF3 does not meet the NEI 10-05 intent for the analysis of implementing SAMG. NEI 10-05 Section 2.11 states that the analysis of the ability to implement SAMG focuses on the reasonably expected initial mitigation action that would be performed by on-shift personnel other than licensed and non-licensed operators. The actions assessed by NEI 10-05 are those which implement the initial site-specific Candidate High Level Action assuming the core is not ex-vessel (i.e., no reactor vessel failure}, and there is no actual or imminent challenge to containment integrity. SAMG is implemented by the TSC. The CR implements OP-902-008, Functional Recovery. All success paths' actions are performed by on-shift licensed and non-licensed operators. 3 Appendix R Fire is bound by the Control Room Fire and Remote Shutdown. WF3 Page 16
WF3 ON-SHIFT STAFFING ANALYIS REPORT VII. APPENDIX B - ON-SHIFT STAFFING ANALYSIS A. J Accident Analysis #1 - Design Basis Threat (DBT)
- 1. Accident Summary
- Land and/or waterborne HOSTILE ACTION directed against the Protected Area by a HOSTILE FORCE. Assume adversary characteristics defined by the Design Basis Threat.
- Security Code Red condition
- 2. Accident Specific Assumptions Made
- This event assumes the threat is neutralized immediately when inside the protected area fence, no significant damage to equipment or systems that require corrective actions before the ERO is staffed, no radiological release, and no fire that requires firefighting response before the ERO is staffed.
- Assume at power in Mode 1
- Assume Security notifies the Shift Manager of condition Security Code RED.
- Assume all non-security staff is located inside the protected area at their normal work station when the event occurs.
- Assume all systems function and the core remains covered. No fuel damage and no release.
- 3. Procedures for Accident Response
- OP-901-523, Security Threat
- EP-001-001, Recognition & Classification of Emergency Conditions
- EP-002-015, Emergency Responder Activation
- EP-002-190, Personnel Accountability
- EP-001-030, Site Area Emergency
- EP-002-010, Notifications and Communications
- OP-902-000, Standard Post Trip Actions WF3 Page 17
WF3 ON-SHIFT STAFFING ANALYIS REPORT
- 4. Tables T2/L1 T5/L1 E-Plan Table 5-1 T5/L3 1 Shift Manager (SM) 90 No Yes T5/L5 T5/L6 T5/L 14 Control Room Supervisor E-Plan Table 5-1 2 N/A T2/L2 No No (CRS)
E-Plan Table 5-1 T2/L3 Shift Technical 3 90 T5L7 No No Advisor/FSS (STA) 4 Reactor Operator (RO #1) E-Plan Table 5-1 N/A T2/L4 No No 5 Reactor Operator (RO #2) E-Plan Table 5-1 N/A T2/L5 No No Nuclear Auxiliary Operator E-Plan Table 5-1 T2/L6 6 N/A No No (AO #1) Nuclear Auxiliary Operator E-Plan Table 5-1 T2/L7 7 N/A No No (AO #2)) Nuclear Auxiliary Operator E-Plan Table 5-1 N/A N/A 8 No No (AO #3) Nuclear Auxiliary Operator E-Plan Table 5-1 N/A N/A 9 No No (AO #4) Nuclear Auxiliary Operator E-Plan Table 5-1 N/A N/A 10 ' No No (AO #5) E-Plan Table 5-1 90 T5/L8 T5/L9 11 Communicator T5/L 10 No No T5/L 11 T5/L 13 E-Plan Table 5-1 N/A N/A 12 Chemistry #1 No No 13 Radiation Protection #1 E-Plan Table 5-1 90 N/A No No E-Plan Table 5-1 N/A 14 Radiation Protection #2 90 No No E-Plan Table 5-1 N/A 15 Maintenance Tech #1 . 90 No No Remote Shutdown E-Plan Table 5-1 16 N/A N/A No No Operator 17 N/A N/A N/A N/A N/A N/A Security Contingency Plan 18 Security I E-Plan Table 5-1 N/A T5/L15 No No WF3 Page 18
WF3 ON-SHIFT STAFFING ANALYIS REPORT
**.. .' :' . ~* *' : *~*,'. -.-'*
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" ,WF~TABLE:2-PLANT'OPERAJ"IONS'&SAFESHu'i:oOWN: >' ' '
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- OneUnit'-OneControl,Room* ,.,.,,." ,_.,,
** * **.. *""Analysis #'1 DBT Security Threat. : . .. **
Minimum Operations-Crew Necessary* to Implement AOPs and*EOPs or SAMGs ifAoolicable*~ * * ** ** Line.~ Generic. Title/Role< * * , on-Shift Positior:i: * * * ' *' . . . . Task Analysis Controlling.
** * * * ' " . Method. '. * :. * '
Shift Manager Licensed Operator Training 1 Shift Manager Program Control Room Supervisor Licensed Operator Training 2 Unit Supervisor Program Shift Technical Advisor Licensed Operator Training 3 Shift Technical Advisor Program Reactor Operator #1 Licensed Operator Training 4 Reactor Operator #1 Program Reactor Operator #2 Licensed Operator Training , 5 Reactor Operator #2 Program Non-Licensed Operator 6 ~uxiliary Operator #1 Nuclear Auxiliary Operator (AO #1) Training Program Non-Licensed Operator 7 ~uxiliary Operator #2 Nuclear Auxiliary Operator (AO #2) Training Program Other needed for Safe N/A N/A 8 Shutdown Other needed for Safe N/A N/A 9 Shutdown Other needed for Safe N/A N/A 10 Shutdown Other (non-Operations) Personnel Necessary to Implement AOPs and EOPs or SAMGs if Applicable
*** .. *: Task.Analysis~.< .
Line#': ' GenericTitie/RolEi*;: * * (*. Q~;.Shift.Positiow:
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11 Mechanic N/A N/A 12 Electrician N/A N/A 13 l&C Technician N/A N/A 14 Other N/A N/A 15 Other N/A N/A WF3 Page 19
WF3 ON-SHIFT STAFFING ANALYIS REPORT Fire Brigade
* *.,, ... "<. WF3'..TABLE*3
..:...FIREFIGHTING*
**' .";*: ; * ~' *.* ;*,> '* ."... ::'.;:*,*~~,l~~i~.~:*\~~i':~~~.UI.'.~.'~~-~e~~tf: .:.;-,*'.
- Line 1
N/A N/A 2 N/A N/A 3 N/A N/A 4 N/A N/A 5 N/A N/A Note: This accident does not include the need for firefighting, first aid or search & rescue. In-Plant Survey: N/A 2 On-site Survey: N/A 3 Personnel Monitoring: N/A 4 Uob Coverage: N/A 5 Offsite Rad
~ssessment:
N/A 6 Other site specific RP (describe): N/A 7 Chemistry Function ask #1 (describe) N/A 8 Chemistry Function task #2 {describe) N/A Note: No chemistry or RP job function tasks for the conditions described in the DBT assumptions. RP and Chemistry take cover as directed. WF3 Page 20
WF3 ON-SHIFT STAFFING ANALYIS REPORT
, . '.*:~3}A.B,LE5..:. E~ERGENC::PlA~*IMPLEMENT~~l()~f***;'.-::*::}.'.:'.*::: ~*:"*** >.*
. :* .:"*""* .. *. Analys1s 1#,.1 DBT Security.Threat, -,.. * , :" .. :.... *; , . * .
,* **.:-**:, '*"' :.*~':;~~-;.-,**i::.* . .~* .. ,-*:*::*;1~ .. *;,*.* .- . ~/_*:-;,1:~ . :.:**,'_:<"*,: ::>:~:.,::,*' . :
Lineti 1: Declare the emergency classification l~vel Emergency Planning Training 1 Shift Manager (ECL) Program I EP Drills I
/
Approve Offsite Protective Action 2 N/A N/A Recommenqations '
, I Emergency Planning Training 3 ~pprove content of State/local notifications Shift Manager Program 4 ~pprove extension to allowable dose N/A N/A Licensed Operator Training Program Notification and direction to on-shift st~ff 1 5 Shift Manager Emergency Planning Training (e.g., to assemble, evacuate, etc.) 'I Program
' Emergency Planning Training 6 ERO notification Shift Manager /
I Program 7 Abbreviated NRC notification for DBT ~vent STA Licensed Operator Training Program 8 Complete State/local notification form ; Communicator Emergency Planning Training Program *,, 9 Perform State/local notifications I Communicator Emergency Planning Training Program 10 Complete NRC event notification form'I Communicator Emergency Planning Training Program 11 ~ctivate EROS I Communicator Emergency Planning Training I Program 12 Offsite radiological assessment N/A N/A i 13 Perform NRC notifications I Communicator Emergency Planning Training
' Program Perform other site-specific event notifications Sh"ft M 14 (e.g., Duty Plant Manager, INPO, ANl,;etc.) 1 Licensed Operator Training Program anager Security Training Program I EP 15 Personnel Accountability Security Drills WF3 Page 21
WF3 ON-SHIFT STAFFING ANALYIS REPORT B. Design Basis Accident Analysis #2 -Steam Line Break Inside Containment with Loss of Offsite Power(LOP)
- 1. Accident Summary
- A double ended inside containment guillotine break of a steam li.ne upstream of the MSIVs causing an un-isolable condition in the affected steam generator (SG). A concurrent loss of offsite power followed by the failure of a diesel generator and a HPSI pump occurs.
- The releases occur due to primary-to-secondary leakage from the RCS to the steam generator. Activity is then released to the environment through the use of atmospheric dump valves. The EAB worst 2 hour dose was noted in the FSAR as being within acceptable criteria but specific EAB dose was not provided to determine if a radiation based EAL condition was met in the first 90 minutes of the event. The event declaration was therefore made based on the loss of off-site power.
- The resultant radioactive material release is maintained far below the guideline values of 10CFR50.67.
- 2. Accident Specific Assumptions Made
- EAL is based on the loss of offsite power.
- 3. Procedures for Accident Response
- EP~001-010, Unusual Event
- OP-902-004, Excess Steam Demand Recovery Procedure
- OP-902-003, Loss of Offsite Power/Loss of Forced Circulation Recovery
- OP-902-000, Standard Post Trip Actions (if shutdown due to the event)
- EP-001-001, Recognition & Classification of Emergency Conditions
- EP-002-010, Notifications and Communications
- EP-002-190, Personnel Accountability
- 01-035-000, Notification Matrix (other notifications)
) \
WF3- Page 22
WF3 ON-SHIFT STAFFING ANALYIS REPORT
- 4. Tables
-, ; '*
Line _ ; . :*. :,* ::: : . : .*. ;.. _ *. -~ .~:.* , . Aug!llentation* Role:in.. Unanalyzed . n,, .: ::* pn~shiftP9sition;::_ Basis:~ocument:/ __ * * ** Elapsed-Time- :;.Table',#.I ** .....* , , *...,,. 1 5 .':***
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T2/L 1 T5/L 1 E-Plan Table 5-1 1 Shift Manager (SM) 90 T5/L3 No No T5/L5 T5/L 14 Control Room 2 E-Plan Table 5-1 N/A T2/L2 No No Supervisor (CRS) Shift Technical 3 E-Plan Table 5-1 90 T2/L3 No No Advisor/FSS (STA) Reactor Operator N/A 4 E-Plan Table 5-1 T2/L4 No No (RO #1) Reactor Operator N/A 5 E-Plan Table 5-1 T2/L5 No No (RO #2) Nuclear Auxiliary N/A T2/L6 6 E-Plan Table 5-1 No No Operator (AO #1) Nuclear Auxiliary T2/L7 7 E-Plan Table 5-1 N/A No No Operator (AO #2)) Nuclear Auxiliary N/A N/A 8 E-Plan Table 5-1 No No Operator (AO #3) Nuclear Auxiliary N/A N/A 9 E-Plan Table 5-1 No No Operator (AO #4) Nuclear Auxiliary N/A T5/L 15 10 E-Plan Table 5-1 No No Operator (AO #5) T5/L6 T5/L8 T5/L9 11 Communicator E-Plan Table 5-1 90 No Yes T5/L 10 T5/L 12 T5/L 13 90 N/A 12 Chemistry #1 E-Plan Table 5-1 No No Radiation Protection 13 E-Plan Table 5-1 90 T4/L6 No No
#1 Radiation Protection 14 E-Plan Table 5-1 90 N/A No No
#2 Maintenance Tech 15 E-Plan Table 5-1 90 N/A No* No
#1 Remote Shutdown N/A 16 E-Plan Table 5-1 N/A No No Operator N/A 17 N/A N/A N/A N/A N/A Security Contingency 18 Security N/A N/A No No Plan IE-Plan Table 5-1 WF3 Page 23
WF3 ON-SHIFT STAFFING ANALYIS REPORT .
* .. .' : i . + .* yYF3.TABL;E:Z-PtAN~ O~ERATIO~S &'.SAfE:SHUTDOWN*~. *<*>:,(;;.*. : '*J ,'
.. ' *' ,,_ ,... \ *. ** , _; . <;>,ne: ljmt::-One,c;ontrol, Room>: * , .*. : ;';;
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~.J/\. *. '**Analysis# 2 Stearfrline.Break w/LOP~>'.'**:,,:~ * .
Minimum *Operatio~s. t~e~* ~etess~~-~;'1*~*hi~~~~~*~bJ~*':~~:~~~~,~~.:~A*~'.~.~~'.;~:~ppiibab1~. ", ...*. Line # Generic Title/Role On-Shift Position Jask Analysis Controlling Method Shift Manager Licensed Operator 1 Shift Manager lrraining Program Control Room Supervisor Licensed Operator 2 Unit Supervisor rrraining Program Shift Technical Advisor Licensed Operator 3 Shift Techni.cal Advisor rrraining Program Reactor Operator #1 Licensed Operator 4 Reactor Operator #1 rrraining Program Reactor Operator #2 Licensed Operator 5 Reactor Operator #2 rrraining Program Nuclear Auxiliary Operator Non-Licensed Operator 6 Auxiliary Operator #1 (A0#1) rrraining Program Nuclear Auxiliary Operator Non-Licensed Operator 7 Auxiliary Operator #2 (AO #2) rrraining Program 8 Other needed for Safe Shutdown N/A N/A 9 Other needed for Safe Shutdown N/A N/A 10 Other needed for Safe Shutdown N/A N/A Other (non-Operations) Personnel Necessary to Implement AOPs and EOPs or SAMGs if Applicable L.i~}:~~T, G:;~,;i;Ti!!.~':7~.'t'.*.* .* * **. ',/:; . *.. ,;:Xi}( >,*;'. : !~*:s;i~}~~r::i!.iP?'.'~,~~L;*.'. ~!~~r:~~~~MsJih~~;>..:i(. 11 Mechanic N/A N/A N/A N/A 12 Electrician N/A N/A 13 l&C Technician N/A N/A 14 Other 15 Other N/A N/A WF3 Page 24
WF3 ON-SHIFT STAFFING ANALYIS REPORT Fire Brigade
*\ ~. ~ ~:.. '.;WF3.:~~ABLE:i3*~;,FlR~FIGHTl~G:-_. _*:(_*:._
* :Analysis #: 2' StearfrLine: Break w/LOP;* '* .
Line
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1 N/A N/A 2 N/A N/A 3 N/A N/A 4 N/A N/A 5 N/A N/A This accident does not include the need for firefighting, first aid or search & rescue. WF3 Page 25
WF3 ON-SHIFT STAFFING ANALYIS REPORT
- '.: . . . . . . *-.Wf~,TABLE:4:.:.~DIATION.PR~TECTION__AND,CHEIVllS[RY,:*. * : *i *: ... *. ;: ;.
'* * "* . * , *.
- Analysis'# 2 Steam* Lme Break w/LOP ., ". * . .... * * "*< '. ,z
~ ~?.siti?n* ~;r!'q~~i,ng,:.: t*, .* ": .: :..'P.~rfo~m~ncefrime P.~rio~fAft~r E~erg~r{~y Declar~u6~*(miniies)~.:~, *:,1:: **, * *;
- ~n,c1~1t;:.'.~:~*">.l:{ :* , . : .* *. ,,,,' , :**... ,.,... ; " ,.. ** *. ". :: **:"' * : .* *.? *...
N .. * .: : <,,:.<<< ;* :;: {*l:'. 0.::5 , p- *10.,. ~5- ,2p,. ?5~ ,;30:- 35~ .4q~ *:45: 50~ ~5.!;i,:- .60,. ,El~,. 70::- JfJ,. 89~ 85:-1 E 1* .* * * . * *. *... ,_,:\;. * ::- *..* 1'0. :15: *20* :25 *30 ,35 40' *.45' :50. **55: ;50* '65. 10. *75; *80 "85: :901 1
- In-Plant Survey: N/A 2 On-site Survey:
N/A 3 Personnel Monitoring:
. N/A 4 Uob Coverage: N/A 5 Offsite Rad
~ssessment:
flncluded in Table 5 6 Other site specific RP: RP #1 Monitor x x x x x x x x x x x x x x x x x RMS 7 Chemistry Function task #1 (describe) N/A 8 Chemistry Function task #2 (describe) N/A
*Times are estimated Chemistry will sample Steam Generators if directed by the Shift Manager within the first 90 minutes~ Per procedure, sample if SG sample path is available but path is isolated on SIAS signal. Otherwise, sample is not required until 2 - 6 hours after the event.
WF3 Page 26
WF3 ON-SHIFT STAFFING ANALYIS REPORT
*. !i:J,~s'~:f1i~+*);rp~;~~~~~~~~:!S!~E~~;r~~~1t19~i~~:~~~'11~:~f~l~1 L~.r:.* iN*:::,f~\;:~(~~*i~!j:/:.~~"~~i,~::!e~~.~i'.}~if:'.:D~f:~ :* :;~:;.;:; ~~~*.ff,1-~i:~~;~,~tim~.::I~~, ~i::~~~~rrr~~.;~~a.~:!~~~~~r~:
Emergency Planning Declare the emergency classification level Shift Manager n-raining Program I EP (ECL) Drills Approve Offsite Protective Action N/A 2 N/A Recommendations Emergency Planning 3 Approve content of State/local notifications Shift Manager rrraining Program 4 Approve extension to allowable dose N/A N/A Licensed Operator Notification and direction to on-shift staff n-raining Program I 5 Shift Manager (e.g., to assemble, evacuate, etc.) Emergency Planning n-raining Program Emergency Planning 6 ERO notification Communicator n-raining Program 7 Abbreviated NRC notification for DBT event N/A N/A Emergency Planning 8 Complete State/local notification form Communicator n-raining Program Emergency Planning 9 Perform State/local notifications Communicator rrraining Program Emergency Planning 10 Complete NRC event notification form Communicator n-raining Program 11 Activate EROS N/A N/A Emergency Planning 12 Offsite radiological assessment Communicator [Training Program Emergency Planning 13 Perform NRC notifications Communicator [Training Program Perform other site-specific event Licensed Operator 14 notifications (e.g., Duty Plant Manager, Shift Manager [Training Program INPO, ANI, etc.) Emergency Planning 15 Personnel Accountability A0#5 rT"raining Program WF3 Page 27
WF3 ON-SHIFT STAFFING ANALYIS REPORT C. Design Basis Accident Analysis #3 - Feedwater Line Break with Loss of Offsite Power (LOP)
- 1. Accident Summary
- This event involves the break of the main feedwater line and complete loss of feedwater flow. A loss of offsite power occurs when the turbine/generator trips. No fuel failure occurs.
- 2. Accident Specific Assumptions Made
- Emergency Classification is not required based on the break of the feedwater line but on the loss of offsite power.
- 3. Procedures for Accident Response
- EP-001-010, Unusual Event
- OP-902-004, Excess Steam Demand Recovery Procedure
- OP-902-000, Standard Post Trip Actions (if shutdown due to the event)
- EP-001-001, Recognition & Classification of Emergency Conditions
- EP-002-010, Notifications and Communications
- EP-002-190, Personnel Accountability
- 01-035-000, Notification Matrix (other notifications)
\ WF3 Page 28
\
WF3 ON-SHIFT STAFFING ANALYIS REPORT
- 4. Tables T2/L 1 T5/L 1 E-Plan Table 5-1 Shift Manager (SM) 90 T5/L3 No No T5/L5 T5/L 14 Control Room Supervisor 2 E-Plan Table 5-1 N/A T2/L2 No No (CRS)
Shift Technical 3 E-Plan Table 5-1 90 T2/L3 No No Advisor/FSS (STA) 4 Reactor Operator (RO #1) E-Plan Table 5-1 N/A T2/L4 No No 5 Reactor Operator (RO #2) E-Plan Table 5-1 N/A T2/L5 No No Nuclear Auxiliary Operator T2/L6 6 E-Plan Table 5-1 N/A No No (AO #1) T2/L7 Nuclear Auxiliary Operator 7 E-Plan Table 5-1 N/A No No (AO #2)) Nuclear Auxiliary Operator 8 E-Plan Table 5-1 N/A N/A No No (AO #3) Nuclear Auxiliary Operator 9 E-Plan Table 5-1 N/A N/A No No (AO #4) Nuclear Auxiliary Operator 10 E-Plan Table 5-1 N/A T5/L 15 No No (AO #5) T5/L6 ) T5/L8 \ 11 Communicator E-Plan Table 5-1 90 T5/L9 No No T5/L 10 T5/L13 12 Chemist#1 E-Plan Table 5-1 90 N/A No No 13 Radiation Protection #1 E-Plan Table 5-1 90 T4/L6 No No 14 Radiation Protection #2 E-Plan Table 5-1 90 N/A No No 15 Maintenance Tech #1 E-Plan Table 5-1 90 N/A No No Remote Shutdown N/A 16 E-Plan Table 5-1 N/A No N6 Operator N/A 17 N/A N/A N/A N/A N/A Security Contingency 18 Security Plan I E-Plan Table 5- N/A N/A No No 1 WF3 Page 29
WF3 ON-SHIFT STAFFING ANALYIS REPORT
,; .*/ ,\ .***:"* ..
- WF3'TABLE:2,;- PLANT'OPERATIONS & SAFE' SHUTDOWN-*:* .;..* *:. : ***.
'** .. : . . .*.* ;>>" One*Un_it.,,...One"Control-R,oom* **: :..: .'.:*<. ::: ,:-~'." ., ,:~, .
* ..... * :* . . ": "'. .Analysis#:3Feedwater:uneBreak\vith top*'\>"".; :>.,.::~ .._ ,
- u,ne # ?e~~~ic ~itl~/~ole/'._, . *- "\:_ , , _. );*: ~t~jni~~:~~;!l,i~'.~:-'.f',;.. . .* 6:~~r:~~~~~:~*~od*.* ,' ,
Shift Manager Licensed Operator 1 Shift Manager rrraining Program Control Room Supervisor Licensed Operator 2 Unit Supervisor
!Training Program Shift Technical Advisor Licensed Operator 3 Shift Technical Advisor rrraining Program Reactor Operator #1 Licensed Operator 4 Reactor Operator #1 rrraining Program Reactor Operator #2 Licensed Operator 5 Reactor Operator #2 rrraining Program Nuclear Auxiliary Operator Non-Licensed Operator 6 ~uxiliary Operator #1 (AO #1) rrraining Program Nuclear Auxiliary Operator Non-Licensed Operator 7 ~uxiliary Operator #2 (AO #2) rrraining Program 8 Other needed for Safe Shutdown N/A N/A 9 Other needed for Safe Shutdown N/A N/A 10 Other needed for Safe Shutdown N/A N/A Other (non-Operations) Personnel Necessary to Implement AOPs and EOPs or SAMGs if Applicable li!le:;#.~: G~nerig'.Ti~lefR~le. *~: ' '... '.~~~ "'.<~~*. : .: ** . . O!i~SJli~ F;'osition:/:': ; "ry-~~k-An.~lysis,:,.,' ,:*_,.: *:;<_
~::/~/'*i* : ,\..,.:_:;;,.:.:/ .-_'*;.: .y;:., , :~~ <-: ~~.1; . ~t:i\,*:: . * ':;.** ~* ;>,:::;:;:.\:/S'*~:;;;:t*'"' .:r:*"' . Cpritrollipg;li/le~hoCli:t;.)';;
N/A N/A 11 Mechanic N/A N/A 12 Electrician N/A N/A 13 l&C Technician N/A N/A 14 Other N/A N/A 15 Other WF3 Page 30
WF3 ON-SHIFT STAFFING ANALYIS REPORT Fire Brigade WF3 TABLE; 3...:. FIREFIGHTING' , , * . ~ { '
- Analysis # 3 Feedwater*Line Break with* LOP~ * **
Line,
#:* ;***
' 1.* : :
NIA NIA 2 NIA NIA 3 NIA NIA 4 NIA NIA 5 NIA NIA This accident does not include the need for firefighting, first aid or search & rescue .
. * . . *.*. '*.*<:: :.* .. c: Wff3'TABLE.4'- RADIATION~.PROTECTION'AND (;t:IEMISTRY".' . :'::. '._ . "':*,_-~_-/'.~
*.; *... ::: .. *.. <*:_,:.:* . *Analysis #:3*Feedwater.'LineBreak with*LOP;:**: :r*:" .* ., }*:";*'~\:, ., '* ..
L: Position.Performing:.* *:
- _-. .. P.e.rf_b_rm~nce_.,Time,Perihd:~ft:Eir-E.m_ e_ rg*.-~---~*cy-De. clar_atio_ri:(rn_.. ih~tes).**.**_.. :.: 1* .. *,
I FUrlctihi'il-T8sk:~* *...... , ;.~* . , * - . , .* *.-- .. *' .... *. .. ~ ._ . . , *." * , j NE*.* __.*_ .. *.~_* :._:**:;__;~:_._'_._"_*_:_:_*.*.._ :_._'; _* .* _.~-_*.*.*:*.*_. _:.* ()~ 5 5 15~ 20- 25.:. 30.:. 35"." 40,, 45: .. 50:: 55_;; *50;,; 65-. ,70: .75~ 80~ . 85~
.. _ . . .. 10 :.15 20 *2°5. *30: 35 Ao.: A.5': 50 "5ff -60' *55, 70 f5. 80" BS *gm In-Plant Survey:_
NIA 2 On-site Survey: _ NIA 3 Personnel Monitoring:
~NIA _ _
4 Job Coverage: __ NIA 5 Offsite Rad Assessment: _LTable5)_ 6 Other site specific RP (Monitor RMS): RP x x x x x x x x x x x x x x x x x x
#1 7 Chemistry Function ask #1 (describe)
NIA
*Times are estimated WF3 Page 31
WF3 ON-SHIFT STAFFING ANALYIS REPORT
*"' WF3;TABLE 5.- EMERGENCY PLAN IMPLEMENTATION-*, '*'*; ,,
.*r: " .: .
\
*
- Analysis*# 3'Feedwater Line Break*witii"1::.op*** *' .** . ' '** .
_Function./ Task'. ::-'.: *. on.,.Shift Position;,, :*. ,
- Task,Analysis:: ._'.;_.
Line# '. :'-"'( *,n * .: ,,~ \' :--:,*. ~,,:; . .. '. *:L,. ..
\: *:,
- Controlling* Method;,;
Emergency Planning Declare the emergency classification level 1 Shift Manager Training Program I EP (ECL) Drills
~pprove Offsite Protective Action N/A 2 N/A Recommendations Emergency Planning 3 ~pprove content of State/local notifications Shift Manager Traininq Program 4 ~pprove extension to allowable dose N/A N/A Licensed Operator Notification and direction to on-shift staff Training Program I 5 Shift Manager (e.g., to assemble, evacuate, etc.) Emergency Planning Training Program Emergency Planning 6 ERO notification Communicator Training Program 7 ~bbreviated NRC notification for DBT event N/A N/A Emergency Planning 8 Complete State/local notification form Communicator Traininq Proqram Emergency Planning 9 Perform State/local notifications Communicator Traininq Proqram Emergency Planning 10 Complete NRC event notification form Communicator Traininq Proqram 11 Activate EROS N/A N/A 12 Offsite radiological assessment N/A N/A Emergency Planning 13 Perform NRC notifications Communicator Training Program Perform other site-specific event Licensed Operator 14 notifications (e.g., Duty Plant Manager, Shift Manager Training Program INPO, ANI, etc.)
Emergency Planning 15 Personnel Accountability A0#5 rrraining Program WF3 Page 32
WF3 ON-SHIFT STAFFING ANALYIS REPORT D. Design Basis Accident Analysis #4 - Single RCP Shaft Seizure/Sheared Shaft with LOP
- 1. Accident Summary
- Single RCP Shaft Seizure/Sheared Shaft with loss of offsite power when the turbine/generator trips. Other 3 RCP pumps coast down after loss of power.
- 15% fuel rods experience DNB. Primary to secondary leakage (150 gpd) and secondary steaming using dump valves (ADV) to atmosphere.
- 2. Accident Specific Assumptions Made
- EAL is based on plant event. FSAR does not provide an EAL dose to determine if an EAL would be met based on the radiological analysis.
- 3. Procedures for Accident Response
- EP-001-010, Unusual Event
- OP-901-202, Steam Generator Tube Leak
- OP-902-003, Loss of Offsite Power/Loss of Forced Circulation Recovery
- OP-902-000, Standard Post Trip Actions
- EP-001-001, Recognition & Classification of Emergency Conditions
/
- EP-002~010, Notifications and Communications
- EP-002-015, Emergency Responder Activation
- 01-035-000, Notification Matrix (other notifications)
- EP-002-031, lnplant Radiological Controls and Surveys During an Emergency WF3 Page 33
WF3 ON-SHIFT STAFFING ANALYIS REPORT
- 4. Tables
- _,*;.;* ' '!';:::*,,,_.* )' *WFl'TABLE':1'~0N~SHIF.:TPOSITIONS,~:>? *;, .;:,?;-* :,j(: ):':> .
- * * * * *, . ** ;,,,, : Analysis t14<-,sing!eRcP.*st1*attSeizure/Sfieared stiattwithJ.OP,: :;, ..; ;.'.,/ '/ .. :<., *:
L~e ?"~~j~~~l~o~~" ~,~1*~;~~~Jt: ,~~:11'~~ l~j,~f~*:*:~ l;~t~~'C ,~~~; T2/L 1 T5/L 1 Shift Mana~er (SM) E-Plan Table 5-1 90 T5/L3 No No T5/L5 T5/L 14 Control Room E-Plan Table 5-1 2 N/A T2/L2 No No Supervisor (CRS) E-Plan Table 5-1 Shift Technical 3 90 T2/L3 No No Advisor/FSS (STA) Reactor Operator (RO E-Plan Table 5-1 4 N/A T2/L4 No No
#1) {
Reactor Operator (RO E-Plan Table 5-1 5 N/A T2/L5 No No
#2)
Nuclear Auxiliary E-Plan Table 5-1 T2/L6 6 N/A No No Operator (AO #1) E-Plan Table 5-1 T2/L7 Nuclear Auxiliary 7 N/A No No Operator (AO #2)) Nuclear Auxiliary E-Plan Table 5-1 8 N/A N/A No No Operator (AO #3) Nuclear Auxiliary E-Plan Table 5-1 9 N/A N/A No No Operator (AO #4) Nuclear Auxiliary E-Plan Table 5-1 T5/L 15 No No 10 N/A Operator (AO #5) E-Plan Table 5-1 T5/L6 T5/L8 T5/L9 11 Communicator 90 No Yes T5/L10 T5/L12 T5/L13 12 Chemist#1 E-Plan\Table 5-1 90 N/A No No 13 Radiation Protection #1 E-Plan Table 5-1 90 T4/L2 No No 14 Radiation Protection #2 E-Plan Table 5-1 90 T4/L6 No No 15 Maintenance Tech #1 E-Plan Table 5-1 90 N/A No No Remote Shutdown N/A 16 E-Plan Table 5-1 N/A No No Operator N/A 17 N/A N/A N/A N/A N/A
~
Security Contingency 18 Security Plan IE-Plan Table N/A N/A No No 5-1 WF3 Page 34
WF3 ON-SHIFT STAFFING ANALYIS REPORT
* .-* . ::*'.\,: WF3'TABLE*2-PLANT.QPERATIONS.&SAFE.SHUTDOWN' ,. *::, :,, ** :*;
**. ' . * ' ' * : ... :. "c OneUnit-OneCon.trolRoom.*. :**.*. **.~ .,. . ,,:* *
... '* Analysis #4..'.:. Single RCP Shaft SeizureiSheared ShaffWith top:~;:*:,. " **
Minimum Operations Grew Necessary to lrilplementAOPs andd;OPs,or ~AM~s:if Appliq:ible * *<: .*,
. ; : *.. ." : . ' :* : ' . : ' : . . ':.'.: :., . *' ~ ' *: ;.;f . ; *.. ~ * *.: ' . >:' ' ; *' ' .
LinEt:# Gener:ic/f.itle/~ole; -*~*. .., * *. : o_n,.~hi~,P()sition** * "; Task.Analysis;1, .*.
. .. * * .. .. . c: .. ** ". . . ~- * . , .' cbrltrolling Methock. ,:
Shift Manager Licensed Operator 1 Shift Manager Training Program Control Room Supervisor Licensed Operator 2 Unit Supervisor Training Program Shift Technical Advisor Licensed Operator 3 Shift Technical Advisor Training Program Reactor Operator #1 Licensed Operator 4 Reactor Operator #1 Training Program Reactor Operator #2 Licensed Operator 5 Reactor Operator #2 Training Program Nuclear Auxiliary Operator Non-Licensed Operator 6 ~uxiliaiy Operator #1 (AO #1) Training Program Nuclear Auxiliary Operator Non-Licensed Operator 7 ~uxiliary Operator #2 (AO #2) Training Program 8 Other needed for Safe Shutdown N/A N/A 9 Other needed for Safe Shutdown N/A N/A 10 Other needed for Safe Shutdown N/A N/A Other (non-Operations) Personnel Necessary to Implement AOPs and EOPs or SAMGs if Applicable Line#;; Generic:Title/Role;;i
- ask:Analysis-:: * \ *.*.,.'
*~ .....
; -
** ce>ntroll)ng. Method.. * :* .
11 Mechanic N/A N/A 12 Electrician N/A N/A 13 * . l&C Technician N/A N/A 14 Other N/A N/A WF3 Page 35
WF3 ON-SHIFT STAFFING ANALYIS REPORT Fire Brigade
." , , . , WF3 TABLE 3..:. FIREFIGHTING. : - . , -** '- '
,*-;,
* *** ., Anal 'sis#4*:_*Single*RCP*SnaftSeizure/Sheare*d-Shaft.with LOP-< : ..
Line 1 N/A 2 N/A 3 N/A _. 4 N/A 5 N/A This accident does not include the need for firefighting, first aid or search & rescue. WF3 Page 36
WF3 ON-SH~FT STAFFING ANALYIS REPORT
;
.: :.'_/{ : -,':* .... ''*' . WF3ffABLE~:-t*~ ~l)IATIO~f PROTECTION ~ND:CHEMl.~T,RY\:ir ; ;:*: ; : ;<<:/:, ?' . ;!:;*
* .. *:: . * * '.:;( "'*Analy,sis #4*~ Single* RCP ShaftSeizure/Sheared. Shaft With LOP* <<.: , '* * : . ; i .* ' ,,' *'.'
L Position. Performing . ' , * ..," 1:.:*;t : . Rerform~n.ce.;Tl~.~ Perio.ciA~eriJ::me~gen~y Declaration,~~inui~s)*'.;j* I Flil"!ction'./. Tasl(' ., N' *-r.; 5- .10:- 1.5.:. :20:.. 29~ .;30f :35;. 40:::. .45-* *50:.: 55... ao:.. 65~ *10- 75,. ao,. *a5:.., 0~5 E* ,.: *'.* '.; ,, '
. ' '~* ; *10 ~1'5i 20' J25. *;30* '35'.* ;'46'* \~5'. ,50* *55: ".acl< *a5. *70* .'i5 mo 85 *go<
1 In-Plant Survey: N/A 2 On-site Survey: RP#1 x x x x x x x x x 3 Personnel Monitoring: ~
._N/A 4 Wob Coverage: N/A 5 Offsite Rad
!Assessment:
f/ncluded in Table 5 6 Other site specific RP (describe): RP#2 x x x x x x x x x x x x x x x x x x Monitor RMS 7 Chemistry Function ask#1 (describe) N/A 8 Chemistry Function task #2 (describe) N/A
*Times are estimated RP#1 performs survey onsite after ADV opened RP#2 monitors RMS and is available for job support Chemistry does not have a task.
WF3 Page 37
WF3 ON-SHIFT STAFFING ANALYIS REPORT
*' ., .... ,: :: .., .. ".
- WF3*TABl:..E~5- _ERf1ERG~NCY PL:AN _IMP,LEMENT,6.TION;; -.;, * * . -~- * * ';c, :;* *
. ; " .* *~{.
,:>Analysis'#4~Sirig!e:R~P:shaftSeizur.e/Sheared.*Shaftwith:Lop* .ff-. .* ,., ..* ..
Line. Task Analysis C~>ntrolling
#:. *.*. ;,::: :/)~'lett:iod:~: ~-- '
Emergency Planning Declare the emergency classification level 1 Shift Manager Training Program I EP (ECL} Drills Approve Offsite Protective Action N/A 2 N/A Recommendations Emergency Planning 3 Approve content of State/local notifications Shift Manager Training. Program 4 Approve extension to allowable dose N/A N/A Licensed Operator Training Notification and direction to on-shift staff (e.g., 5 ,. Shift Manager Program I Emergency to assemble, evacuate, etc.) Planning Training Program Emergency Planning 6 ERO notification Communicator Training Program 7 Abbreviated NRC notification for DBT event N/A N/A Emergency Planning 8 ' Complete State/local notification form Communicator Training Program Emergency Planning 9 Perform State/local notifications Communicator Training Program Emergency Planning 10 Complete NRC event notification form Communicator Training Program 11 . Activate EROS N/A N/A Emergency Planning 12 Offsite radiological assessment Communicator Training Program Emergency Planning 13 Perform NRC notifications Communicator Training Program Perform other site-specific event notifications Licensed Operator Training 14 Shift Manager (e.g., Duty Plant Manager, INPO, ANI, etc.) Program Emergency Planning 15 Personnel Accountability A0#5 Training Program WF3 Page 38
WF3 ON-SHIFT STAFFING ANALYIS REPORT E. Design Basis Accident Analysis #5 - Control Element Assembly Ejection
- 1. Accident Summary
- Control element assembly (CEA) ejection. Per Emergency Plan Table 4-3.2a the Containment High Range Accident Monitors indicate 1 E5 R/hr at monitor location.
- 2. Accident Specific Assumptions Made
- N/A
- 3. Procedures for Accident Response
- OP-902-004, Excess Steam Demand Recovery Procedure
- EP-001-030, Site Area Emergency
- OP-902-002, Loss of Coolant Accident Recovery
- OP-902-000, Standard Post Trip Actions
- EP-001-001, Recognition & Classification of Emergency Conditions
- EP-002-010, Notifications and Communications
- EP-002-034, Onsite Surveys During Emergencies
- EP-002-190, Personnel Accountability
- EP-002-031, In-plant Radiological Controls & Surveys During Emergencies
- EP-002-015, Emergency Responder Activation WF3 Page 39
WF3 ON-SHIFT STAFFING ANALYIS REPORT
- 4. Tables
' ..... '* . . ,. . WF3 TABLEt*.::;. ON~SHIFTPOSITIONS'.. i: , ' '
~ "
*.-
- Analysis #5:..,.. Controi ElementAssembly. Ejection** '. ..
Line* . * *
* * *1 * . ~ugmentation Role in Table U. "
- 1 . d ; . r'Ms*
# O_n,;shift'P°.s~tion*. E~Plan R~terepce~
- Elapsedcffime * .~_#I Line.#;* . ntna :~~. R:* . .. ci?
-- . .!" " ' -~ . ; ' " : '~\ : . ,. , ,\ (iniil) *; . , ; .. '*.... , . _ ~~-. ~~'.: '>: equ1r.e *.
E-Plan Table 5-1 T2/L1 T5/L1 Shift Manager (SM) 90 T5/L3 No No T5/L5 T5/L14 E-Plan Table 5-1 Control Room 2 N/A T2/L2 No No Supervisor (CRS) Shift Technical E-Plan Table 5-1 3 90 T2/L3 No No Advisor/FSS (STA) Reactor Operator E-Plan Table 5-1 4 N/A T2/L4 No No (RO #1) Reactor Operator E-Plan Table 5-1 5 N/A T2/L5 No No (RO #2) Nuclear Auxiliary E-Plan Table 5-1 T2/L6 6 N/A No No Operator (AO #1) Nuclear Auxiliary E-Plan Table 5-1 T2/L7 7 N/A No No Operator (AO #2)) Nuclear Auxiliary E-Plan Table .5-1 8 N/A N/A No No Operator (AO #3) Nuclear Auxiliary E-Plan Table 5-1 9 N/A N/A No No Operator (AO #4) Nuclear Auxiliary E-Plan Table 5-1 10 N/A T5/L15 No No Operator (AO #5) E-Plan Table 5-1 T5/L6 T5/L8 T5/L9 11 Communicator 90 T5/L10 No Yes T5/L 11 T5/L12 T5/L13 12 Chemist #1 E-Plan Table 5-1 90 N/A No No Radiation Protection E-Plan Table 5-1 T4/L6 13 90 No No
#1 Radiation Protection E-Plan Table 5-1 N/A 14 90' No No
#2 15 Maintenance Tech #1 E-Plan Table 5-1 90 N/A No No Remote Shutdown N/A 16 E-Plan Table 5-1 N/A No No Operator N/A 17 N/A N/A N/A N/A N/A Security Contingency 18 Security N/A N/A No No Plan IE-Plan Table 5-1 WF3 Page 40
WF3 ON-SHIFT STAFFING ANALYIS REPORT l ,,
~*
, WF3TABLE2',.-PLANTOPERATIONS'&*SAFESHUTDOWN --*** '
* * * ** * * * * * . One Unit - One. Control* Room'. . * ** . .'. .., "
* * . Analysis #5 ~ Controi: Element Assembly EJection. , , ' ** ' ... . . * ..
Line #. Generic,;Titl~/Role. Task; Analysis .... -' * .. *
* ; * ~ *' = I ,.
Controlling Meth~d; ** Shift Manager Licensed Operator Shift Manager Training Program Control Room Supervisor Licensed Operator 2 Unit Supervisor Training Program Shift Technical Advisor Licensed Operator 3 Shift Technical Advisor Training Program Reactor Operator #1 Licensed Operator 4 Reactor Operator #1 Training Program Reactor Operator #2 Licensed Operator 5 Reactor Operator #2 Training Program Nuclear Auxiliary Operator Non-Licensed Operator 6 Auxiliary Operator #1 (AO #1) Training Program Nuclear Auxiliary Operator Non-Licensed Operator 7 !Auxiliary Operator #2 (AO #2) Training Program 8 Other needed for Safe Shutdown N/A N/A 9 Other needed for Safe Shutdown N/A N/A 10 Other needed for Safe Shutdown N/A N/A Other (non-Operations) Personnel Necessary to Implement AOPs and EOPs or SAMGs if Applicable Line#;: Gei1eri~:Title/Role*" "'.: **.,'. :. *. "'... 011:-Shi~. Position:;<,
- Task;Analysis} *'. .'. * ' **
' *~ ' ' ,J . : :* '.4'. '.: **.' *
. ' " '. .. ' /i: ' .. t ; >: .<:. (' : ' *; ; Co.~troilihg:M~tijt>d.:;:
- 11 Mechanic N/A N/A N/A N/A 12 Electrician N/A N/A 13 l&C Technician N/A N/A 14 Other 15 Other N/A N/A Fire Brigade
\
WF3 Page 41
WF3 ON-SHIFT STAFFING ANALYIS REPORT
. ,-* - *WF3 TABLE0.a*;:;..:.,flREFIGHTING'.'.'"- "'* **: .: ..., ....
_ A~alysis #5',~ 'control Element*As!;embiy Ej~ctio~*L 1 N/A N/A 2 N/A N/A 3 N/A N/A 4 N/A N/A 5 N/A N/A This accident does not include the need for firefighting, first aid or search & rescue.
- . ~;. '.ir.' *'.:*~.:i **;.':*';: .*-~F~_TA~LE:4'.;.;, RApl~"IJQN:.~~PJ:ECT!~N-ANP;,gtt.~111!1;>/RY:ir~::~~'.'.'.::t/s;:* *::: /;'
.. -*** . :* <: ~'/;:. _.*** .,, * *<*_,Analysis #s:~:control ElementAssembly:E1~ct1or'l:i ': !' :"'/:*~*"- :/ :.;**::,;.--*:. ,* :, .-, * */:
L: PF. ~s.~tti?n:P,, eT*rj'qrkTi9~~' 1~,>- _ : *:,,~:_._;-i:>~riorril~ri~~i.Tihl~;*Peribct.Aft~ii,i:fuk'r~~ricy* oe~i~r~ti6~'*cn:lih~tes)t< ::;:~,;:>:*: :;-
- 1. ..unc ion, * *as . ,,**:. - '*.. . * *** ' . * - * * * -' , :** - **- * '*~ * -- **. * ,., .** . " .:. - , ' *. - *, - .. _.. -* **. ,- - ....... *-:**,_ * ' '"*
N' (~- * "*:**: '* - < +,: '* '.':; fr' *10** '15 20. 25-- -30 35' 40' ~5* 50. 55" 50** 65' 10
- 7f>> ao: 85'"
E* ii'~:::~;~t:~;*,:::::;:~:,:.2lCi1::,: :~~~ :18: .+~ :21f ;25-: :3o::* :;35-'.: i4cF :4i:f: ;::5cf, T55} *6o:b *65: >ro: "1-1~ ~.ao~ **a5~-; g~: In-Plant Survey: 1--N/A_ 2 On-site Survey: N/A 3 Personnel Monitoring: N/A 4 Job Coverage: _N/A 5 Offsite Rad
~ssessment:
(Included in Table 5 6 Other site specific RP RP#1 monitor RMS x x x x x x x x x x x x x x x x x x 7 Chemistry Function task #1 (describe) NIA 8 Chemistry Function task #2 (describe) N/A
*Times are estimated RP#2 is available for surveys and job support as needed.
WF3 Page 42
WF3 ON-SHIFT STAFFING ANALYIS REPORT
. .. , . WF3'TABlE.5:'-- EMERGENCY. Pl.AN* IMPLEMEN"FATION:.', .,; . ** . * , . *.
., ,, * * * ,, .* * ' :' : Arialysis.#5 .:.:coritrol Elerrient:Assemi:>ly Ejection*-.':.' ::. .. ,. . o ,~~ . , *
- Declare the emergency classification level Emergency Planning 1 Shift Manager (ECL) !Training Program I EP Drills Approve Offsite Protective Action N/A 2 N/A Recommendations Emergency Planning 3 Approve content of State/local notifications Shift Manager Training Program 4 Approve extension to allowable dose N/A N/A Licensed Operator Training Notification* and direction to on-shift staff (e.g.,
5 Shift Manager Program I Emergency
~o assemble, evacuate, etc.)
Planning Training Program Emergency Planning 6 ERO notification Communicator Training Program 7 ~bbreviated NRC notification for DBT event N/A N/A Emergency Planning 8 Complete State/local notification form Communicator Training Program
'* Emergency Planning 9 Perform State/local notifications Communicator Training Program Emergency Planning 10 Complete NRC event notification form Communicator Training Program J
Emergency Planning 11 ~ctivate EROS Communicator Training Program Emergency Planning 12 Offsite radiological assessment Communicator Training Program I Emergency Planning 13 Perform NRC notifications Communicator Training Program Perform other site-specific event notifications Licensed Operator Training 14 Shift Manager (e.g., Duty Plant Manager, INPO, ANI, etc.) Program Emergency Planning 15 Personnel Accountability ~0#5 Training Program WF3 Page 43
WF3 ON-SHIFT STAFFING ANALYIS REPORT F. Design Basis Accident Analysis #6 - Letdown Line Break Outside Containment
- 1. Accident Summary
- A letdown line break outside containment resulted in a reactor coolant spill in the reactor auxiliary building. '
- 2. Accident Specific Assumptions Made
- Assume leak is isolated after 1800 seconds.
- 3. Procedures for Accident Response
- EP-001-020, Alert
- OP-901-111, Reactor Coolant System Leak
- OP-902-002, Loss of Coolant Accident Recovery
- EP-001-001, Recognition & Classification of Emergency Conditions
- EP-002-010, Notifications and Communications
- EP-002-015, Emergency Responder Activation
- EP-002-190, Personnel Accountability
- 01-035-000, Notification Matrix (other notifications)
- EP-002-031, lnplant Radiological Controls and Surveys During Emergencies WF3 Page 44
WF3 ON-SHIFT STAFFING ANALYIS REPORT
- 4. Tables
- .***... . '.* 1 .-;., .,
*': :_,p;'.~. :'.WF3TABLE1::;:.oN~SHIFTPOSITIONS'.;*;: *_!': :.;:,: * ) '._.:~. *:*.;' "
** * ** ' ._,. , ~. *'Arialysis*#a:;; Letdow11*Line Breal(:outside,contafnm.ent:**:;:;.:t: ** ,' '<<*
- ,,.. _-,: ; .
E-Plan Table 5-1 T2/L 1 T5/L 1 Shift Manager (SM) 90 T5/L3 No No T5/L5 T5/L 14 E-Plan Table 5-1 Control Room 2 N/A T2/L2 No No Supervisor (CRS) Shift Technical E-Plan Table 5-1 3 90 T2/L3 No No Advisor/FSS (STA) Reactor Operator (RO E-Plan Table 5-1 4 N/A T2/L4 No No
#1)
Reactor Operator (RO E-Plan Table 5-1 5 N/A T2/L5 No No
#2)
Nuclear Auxiliary E-Plan Table 5-1 T2/L6 , 6 N/A No No Operator (AO #1) Nuclear Auxiliary
- E-Plan Table 5-1 T2/L7 7 N/A No No Operator (AO #2))
Nuclear Auxiliary E-Plan Table 5-1 8 N/A N/A No No Operator (AO #3) Nuclear Auxiliary E-Plan Table 5-1 9 N/A N/A No No Operator (AO #4) Nuclear Auxiliary E-Plan Table 5-1 10 N/A T5/L 15 No No Operator (AO #5) E-Plan Table 5-1 T5/L6 T5/L8 T5/L9 11 Communicator 90 T5/L 10 No Yes T5/L 11 T5/L 12 T5/L 13 12 Chemist#1 E-Plan Table 5-1 90 N/A No No Radiation Protection E-Plan Table 5-1 13 90 T4/L 1 No No
#1 Radiation Protection E-Plan Table 5-1 T4/L6 14 90 No No
#2 15 Maintenance Tech #1 E-Plan Table 5-1 90 N/A No No Remote Shutdown N/A 16 E-Plan Table 5-1 No Operator N/A No I
N/A 17 N/A N/A N/A N/A N/A Security Contingency 18 Security N/A N/A No No Plan IE-Plan Table 5-1 WF3 Page 45
WF3 ON-SHIFT STAFFING ANALYIS REPORT
' * : . *... * :wF.3'.TABLE':2*-PLANTOPERATIONS:&.SAFE'SHUTDOWN ...;* .. ; ..
.,'* ,.. * *.. : * ":**." One.Unit"'.-.One*C!JntrolRoom':.. *: ' . . ,'.. ** ;.:.*
, ... _... . . Analysis #Si- Letdowntline:Break:'Outside C6ntainmeiit~ *.*. **
Minimum. Qperations GrewNecessaryto1 lmplementAOP~ and:EOPs *or; SAMGs;if'Applicable;*: 1..* : *, .-~*
.: ;.- ...... ~:,/ *':.*:' .*.,:;*_: ,. '"~ {*::*~*i'.. <*~ '*~:-~' ;"*,*, *.: .1~~* ::: ** ~.~'. ~'.*1: .. ;' *: :***,~:"> .* .. ;
Line#. Generic'.Title/Rolec *,,*
- -.*.:_*,, ._,. OptShi~-~~~-*i_t_,io___ n,:,':.- ,'" Task Analysis: * , i <
..-:* '.J . '*
- .. . -... * .. contromn 9 Method*' '* '
Shift Manager Licensed Operator 1 Shift Manager Training Program Control Room Supervisor Licensed Operator 2 Unit Supervisor Training Program Shift Technical Advisor . Licensed Operator 3 Shift Technical Advisor Training Program Reactor Operator #1 Licensed Operator 4 Reactor Operator #1 Training Program Reactor Operator #2 Licensed Operator 5 Reactor Operator #2 Jraining Program Nuclear Auxiliary Operator Non-Licensed Operator 6 ~uxiliary Operator #1 (AO #1)
- Ifraining Program Nuclear Auxiliary Operator Non-Licensed Operator 7 ~uxiliary Operator #2 (AO #2) Training Program 8 Other needed for Safe Shutdown N/A N/A 9 Other needed for Safe Shutdown N/A 'N/A 10 Other needed for Safe Shutdown N/A N/A Other (non-Operations) Personnel Necessary to Implement AOPs and EOPs or SAMGs if Applicable
~ *. * ... Q!)~~-~iff~ositior:a\ . "". rr~s~;Ar:aaiysJs*:.>,;O':'.i, ., r*,
,, * .* - .*:: * * -; ~ * *; ... * , corl'tro'1nri9 Ni~tJiod.C ,,
11 Mechanic N/A N/A 12 Electrician N/A N/A 13 l&C Technician N/A N/A 14 Other N/A N/A 15 Other N/A N/A WF3 Page 46
~--------------------------- --------
WF3 ON-SHIFT STAFFING ANALYIS REPORT Fire Brigade
,'. * * , :*::* .* .. WF,.3:JABLE:3':-.FIREFIGHTINGi ." '<, '.....;.. ;- :'", J r* , *Ana.lys'iS #6:-_.Letdowrl: L.irl-&!B[eakrOUtSide Coritainrilent<::_***)~.:~. ~,.:-
N/A N/A 2 N/A N/A 3 N/A N/A 4 N/A N/A 5 N/A . N/A This accident does not include the need for firefighting, first aid or search & rescue.
" , ,,,. ""
- Wf3,TABL:.E.4.*- RADIATION:l?ROTECTION AND CHEMISTRY-*.*" ....: * -" ' .. , '.!.
*:* ", *: : * -* Analysis #6*--Letdown lihe:Break:. ciutsicte'containmenf.,,.-:'. '.'
- _':'.*.. ; '-'-.'.~.,;- ,*;*
L. Positibn*Peifcirming*, * * .::'.*.::'.' . *.'.. *...,,' : : .:.;1:* - + : .. * " .\' . " *: .. />' ** :.. <:*,*:-:ir; ,. < t:+*-::*;~:r:*,,:'.-.:\:: :>~-~-' r.: Ft:iricuo'riw*.:task;':; :{.,. *:. : .. ,, ..~ P~rl'qrr:na.~.G~*1T1rn~!?.eri.o.9f\~~rc:E~ergr,ncypecl.i:ir~~!9n\.(~.!~Y.t~s} :\1* -~n~:.1~ N: * ,\ :*:*<*** q, '*
- _*: ~~-- .: . ** " *:.s.- JO- . ,15:.:. -20:. 2s~ .30- ,35;,. 40;.. fl-5.,. so::. 55:. ao::., 55:.* zo~ .75; ao;; 85<
E L:-_:_.,:~--~_,,_;,~: .., *. :;,,,_ * o-5 '-'.fer '"15* 20:* :25-. 30:. :35', 40' :145: '56 'S5: 60. :;65; i*?CX 15i ao: :85 '.-90£ In-Plant Survey: RP#1 x x x x x x 2 On-site Survey: N/A 3 Personnel Monitoring: N/A_ 4 Job Coverage: N/A 5 Offsite Rad Assessment: Oncluded in Table 5 6 Other site specific RP (describe): RP#2 x x x x x x x x x x x x x x x x x monitor RMS 7 Chemistry Function
~ask #1 (describe)
N/A 8 Chemistry Function ask #2 (describe) N/A
*Times are estimated WF3 Page 47
WF3 ON-SHIFT STAFFING ANALYIS REPORT
*,; WF3.TABlE 5;--.;...EMERGENCY PLAN IMPLEMENTATION"' * .':' * * * * * .. *
*Analysis #6*~. Letdown*Line 1Break Outside Containment.*.* .* * ;. : ** ; . '.. .*.
<*. * ::rask*Analysis;),;-,;.:;
**'coiitrolling:l\ilethoCI*::*
Declare the emergency classification level Emergency Planning 1 Shift Manager Training Program I EP (ECL) Drills
~pprove Offsite Protective Action N/A 2 N/A Recommendations 3 ~pprove content of State/local notifications Emergency Planning Shift Manager Training Program 4 ~pprove extension to allowable dose N/A N/A Licensed Operator Notification and direction to on-shift staff Training Program I 5 Shift Manager (e.g., to assemble, evacuate, etc.) Emergency Planning Training Program 6 ERO notification Emergency Planning Communicator Training Program 7 ~bbreviated NRC notification for DBT event N/A N/A Emergency Planning 8 Complete State/local notification form Communicator Training Program Emergency Planning 9 Perform State/local notifications Communicator Training Program 10 Complete NRC event notification form Emergency Planning Communicator Training Program 11 ~ctivate EROS Emergency Planning Communicator Training Program Emergency Planning 12 Offsite radiological assessment Communicator Training Program Emergency Planning 13 Perform NRC notifications Communicator Training Program Perform other site-specific event notifications Sh"ft M Licensed Operator 14 1 (e.g., Duty Plant Manager, INPO, ANI, etc.) anager Training Program Emergency Planning 15 Personnel Accountability A0#5 Training Program WF3 Page 48
WF3 ON-SHIFT STAFFING ANALYIS REPORT G. . Design Basis Accident Analysis #7 - Steam Generator Tube Rupture
- 1. Accident Summary
- Double-ended rupture of a single U-tube resulted in exceeding charging pump capacity. No fuel failure is postulated.
- 2. Accident Specific Assumptions Made
- EAL is based on accident event.
- 3. Procedures for Accident Response
- OP-902-007, Steam Generator Tube Rupture Recovery
- EP-001-020, Alert
- OP-902-002, Loss of Coolant Accident Recovery
- OP-902-000, Standard Post Trip Actions (if shutdown due to the event)
- EP-001-001, Recognition & Classification of Emergency Conditions
- EP-002-010, Notifications and Communications
- EP-002-015, Emergency Responder Activation
- EP-002-190, Personnel Accountability
- 01-035-000, Notification Matrix (other notifications)
- EP-002-034, Onsite Surveys During Emergencies
- EP-002-031, lnplant Radiological Controls and Surveys During an Emergency WF3 Page 49
WF3 ON-SHIFT STAFFING ANALYIS REPORT
.,*'.** ,.'** ..... :;:*:. :*1:* Wi=3:TABLE'1:~0N~SHIFT'.POSITIONSt:,~*:.,,,:*;, *:*: ";(::\~;*>; ;;:,',.* .*** * * *L . * .;:* * . , : 'Analysis#7:::...steam Generator*Tube.Ru~ture':;*:;. ::~ 3;\'~;:: ., , <-.~ 1 * ,<
- T2/L1 T5/L1 E-Plan Table 5-1 1 Shift Manager (SM) 90 T5/L3 No No T5/L5 T5/L14 2 Control Room Supervisor E-Plan Table 5_1 N/A T2/L2 No No (CRS)
Shift Technical 3 E-Plan Table 5-1 90 T2/L3 No No Advisor/FSS (STA) Reactor Operator 4 E-Plan Table 5-1 N/A T2/L4 No No (RO #1) Reactor Operator 5 E-Plan Table 5-1 N/A T2/L5 No No (RO #2) Nuclear Auxiliary T2/L6 6 E-Plan Table 5-1 N/A No No Operator (AO #1) Nuclear Auxiliary T2/L7 7 E-Plan Table 5-1 N/A No No Operator (AO #2)) Nuclear Auxiliary 8 E-Plan Table 5-1 N/A N/A No No Operator (AO #3) Nuclear Auxiliary 9 E-Plan Table 5-1 N/A N/A No No Operator (AO #4) Nuclear Auxiliary 10 E-Plan Table 5-1 N/A T5/L15 No No Operator (AO #5) T5/L6 T5/L8 T5/L9 11 Commqnicator E-Plan Table 5-1 90 T5/L10 No Yes T5/L 11 T5/L12 T5/L 13 12 Chemist #1 E-Plan Table 5-1 90 N/A No No 13 Radiation Protection #1 E-Plan Table 5-1 90 T4/L6 No No N/A 14 Radiation Protection #2 E-Plan Table 5-1 90 No No 15 Maintenance Tech #1 E-Plan Table 5-1 90 T2/L 13 No No Remote Shutdown N/A 16 E-Plan Table 5-1 N/A No No Operator N/A 17 N/A N/A N/A N/A N/A Security 18 Security Contingency Plan N/A N/A No No IE-Plan Table 5-1 WF3 Page 50
WF3 ON-SHIFT STAFFING ANALYIS REPORT
.. ~ " .WF3 .TABLE*2.:.. PL:ANrOPERATIONS & SAFE SHl)TDOWNi:
.*.* *' . ... pne Unit-:- One. Control. Room" * *. :. *. . ,.. * ** * *,
(\:,'*
. ' " Analysis #7'.:: Steam GeneratorTube: Rupture. " ** , "
Minimum OperationSiCrewNecessaryto lmplementAOPs:and.EOps:orSAMGs:ifApplicable '.. * '*. :
. ;: : ' . . ' i*: ~* . ;:. , ' ',
Line # Generip~Title/Role:. *. On~Shift Position:. *....: :. Jask Analy~i~,; " ; r*
* **: ' .: ** * * **: * ** Controlling)Jlethod' . ..
- Shift Manager Licensed Operator Shift Manager lrraining Program Control Room Supervisor Licensed Operator 2 Unit Supervisor rTraining Program Shift Technical Advisor Licensed Operator 3 Shift Technical Advisor rTraining Program Reactor Operator #1 Licensed Operator 4 Reactor Operator #1 rT"raining Program Reactor Operator #2 Licensed Operator 5 Reactor Operator #2 rTraining Program Nuclear Auxiliary Operator Non-Licensed Operator 6 Auxilia~ Operator #1 (AO #1) rTraining Program Nuclear Auxiliary Operator Non-Licensed Operator 7 Auxiliary Operator #2 (AO #2) rT"raining Program 8 Other needed for Safe Shutdown N/A N/A 9 Other needed for Safe Shutdown N/A N/A 10 Other needed for Safe Shutdown N/A N/A Other (non-Operations) Personnel Necessary to Implement AOPs and EOPs or SAMGs if Applicable Line # .. Generic.Title/Role > 1'> TaskcAnalysis.: *- .* * *. *.
'- ~ ., .. . conf~o11fo 9 *11i1ett,ocr :>:*;
11 Mechanic N/A N/A N/A N/A 12 Electrician Maintenance #1 N/A 13 l&C Technician N/A N/A 14 Other 15 Other N/A N/A WF3 Page 51
WF3 ON-SHIFT STAFFING ANALYIS REPORT Fire Brigade
,
- WF3:TABLE 3.-FIREFIGHTING< '* .,, . . ., ,: *
**: .. , * * .* * * * * * :* Ahalysis:#1':.... Steam Generator.Tube Rupture'.: ' ; -:*"
Line, . J>erformed by** !; . . *> :. . .Task Analysis Controlling.Method'; * *'*
# . . 1**,
t.:*, , :::* ..... ":":.~; . : ..,"<"*: *r'.' '* ';: :.: *:;'.: , :,{: >*~:_'/; :.. /~-:~ *... *: **:" .. :.. ;~*1/::'.: :,~:* :. . N/A N/A 2 N/A N/A 3 N/A N/A 4 N/A N/A 5 N/A N/A This accident does not include the need for firefighting, first aid or search & rescue. L Positi?n. '.er!orn,;ii?~:< .. '>~,:: *. : ~ertormari~e<:Tim~ F>erioa:~fier..Errierg~r\~y,Depiar~~iori::(~:in~t~.s}*: ** I Funct1or:i/Tas~.*:*.;:: .. 1* . . .. * . * .*, *' . . . , * * . * . .. . . * * , **.. N > . * *,, ". * * *5= 10- *15;, 20:. 25,. 30-: 35:_; 40 50:- 55.~ .60:. 65-* 70:: "Z.5'- .80"-' 85.f E *:: :. :.:.:*'.. ~"<".': ::<... 0-:: 10 .. 15*, *20*. *25 30 :35 ;40' *45:_ 5o *55~ :6b* "65: . .10. d5 5
.aff 85, go.
In-Plant Survey: N/A 2 On-site Survey: N/A 3 Personnel Monitoring: _N/A 4 Job Coverage: N/A 5 Offsite Rad
~ssessment:
(Included in Table 5 6 Other site specific RP (describe}: RP#1 x x x x x x x x x x x x x x x x x monitor RMS 7 Chemistry Function task #1 (describe) N/A 8 Chemistry Function task #2 (describe) N/A
*Times are estimated RP#2 is available for surveys and job support if directed by the Shift Manager.
WF3 Page 52
WF3 ON-SHIFT STAFFING ANALYIS REPORT
' ... -,: * :"(WF.3:TABLE'5..:.,;EMERGENCYPt.ANIMPLEMENTATION/,.* ... *.,.;;J:,.*"'
'* .,.., '*i.:,>~- ***.' Analysis:#r:.:: steam*G~*neiatol:iT.id)e. Ru"pture'.'.*"< ~:'.<>/\)Y-: * .
Line Declare the emergency classification level Emergency Planning 1 Shift Manager (EGL) rrraining Program I EP Drills
~pprove Offsite Protective Action N/A 2 N/A Recommendations Emergency Planning 3 ~pprove content of State/local notifications Shift Manager
[Training Program 4 ~pprove extension to allowable dose N/A N/A Licensed Operator Training Notification and direction to on-shift staff (e.g., 5 Shift Manager Program I Emergency
~o assemble, evacuate, etc.)
Planning Training Program Emergency Planning 6 ERO notification Communicator
!Training Program 7 ~bbreviated NRG notification for DBT event N/A N/A Emergency Planning 8 Complete State/local notification form Communicator rrraining Program Emergency Planning 9 Perform State/local notifications Communicator
[Training Program Emergency Planning 10 Complete NRG event notification form Communicator rrraining Program Emergency Planning 11 Activate EROS Communicator Training Program Emergency Planning 12 Offsite radiological assessment Communicator rrraining Program Emergency Planning 13 Perform NRG notifications Communicator Training Program Perform other site-specific event notifications Licensed Operator Training 14 Shift Manager (e.g., Duty Plant Manager, INPO, ANI, etc.) Program Emergency Planning 15 Personnel Accountability A0#5 Training Program WF3 Page 53
WF3 ON-SHIFT STAFFING ANALYIS REPORT H. Design Basis Accident Analysis #8 - Loss of Coolant Accident (LOCA)
- 1. Accident Summary
- Double-ended guillotine break of a recirculation line Concurrent safe shutdown eart,hquake and loss of offsite power. No fuel failure is postulated. Bounds all size leaks in containment.
- 2. Accident Specific Assumptions Made
- EAL is based on accident event.
- 3. Procedures for Accident Response
- OP-902-002, Loss of Coolant Accident Recovery
- OP-001-523, Seismic Event
- EP-001-001, Recognition & Classification of Emergency Conditions
- EP-001-020, Alert
- EP-002-010, Notifications and Communications
- EP-002-015, Emergency Responder Activation
- EP-002-190, Personnel, Accountability
- 01-035-000, Notification Matrix (other notifications)
- OP-902-000, Standard Post Trip Actions
- EP-002-034, Onsite Surveys During Emergencies
- EP-002-031, lnplant Radiological Control and Surveys During Emergency WF3 Page 54
WF3 ON-SHIFT STAFFING ANALYIS REPORT
>:.: *;":;. ': ;::* ' "wF3TABtE1' ON SHIFT POSITIONS'** ' . ,., *. *. ,* * .. *' .
,_ .,,.... *._ .... , __:.._:'*"::.,_;:,::. ';' An~l~~*is.#~:~LdcAc:/*";~:::: *-::'~:.*:. __ _,--c;,. :' ., ..... -~'; ...
T2/L1 T5/L1 E-Plan Table 5-1 Shift Manager (SM) 90 T5/L3 No No T5/L5 T5/L14 Control Room 2 E-Plan Table 5-1 N/A T2/L2 No No Supervisor (CRS) Shift Technical 3 Advisor/FSS (STA) E-Plan Table 5-1 90 T2/L3 No No Reactor Operator (RO 4 E-Plan Table 5-1 N/A T2/L4 No No
#1)
Reactor Operator (RO 5 E-Plan Table 5-1 N/A T2/L5 No No
#2)
Nuclear Auxiliary T2/L6 6 E-Plan Table 5-1 N/A No No Operator (AO #1) Nuclear Auxiliary T2/L7 7 E-Plan Table 5-1 N/A No No Operator (AO #2)) Nuclear Auxiliary 8 E-Plan Table 5-1 N/A N/A No No Operator (AO #3) Nuclear Auxiliary 9 E-Plan Table 5-1 N/A N/A No No Operator (AO #4) Nuclear Auxiliary 10 E-Plan Table 5-1 N/A T5/L 15 No No Operator (AO #5) T5/L6 T5/L8 T5/L9 11 Communicator E-Plan Table 5-1 90 T5/L10 No Yes T5/L 11 T5/L12 T5/L13 12 Chemist #1 E-Plan Table 5-1 90 N/A No No Radiation Protection 13
#1 E-Plan Table 5-1 90 T4/L6 No No Radiation Protection T4/L4
#2 E-Plan lable 5-1 90 No No 15 Maintenance Tech #1 E-Plan Table 5-1 90 N/A No No 16 Remote Shutdown E-Plan Table 5-1 N/A N/A No No Operator N/A 17 N/A N/A N/A N/A N/A Security Contingency 18 Security Plan IE-Plan Table 5-1 N/A N/A No No WF3 Page 55
WF3 ON-SHIFT STAFFING ANALYIS REPORT
<:
- WF3.TABLE:2;;...PtANT OPERATIONS:&.SAFE'.SHUl;D0WN.< **
- ,, .;p~~ Ur:iit.7 ~ne *c?ntrol. R,oom
'.:* Analys1s#8~LOCA*.*
- _:;
1 Line#,. Generic:,Title/Role.
*,:*.-,: . *;. *. ,.. _
;... -~: On7Shift.Positio11. Tas~ Analysis::.:-:.:* *i ..:
.. ' . .. ~-. :_:.* ...... . *.*
;*,
Controlling Method " ' Shift Manager Licensed Operator 1 Shift Manager Training Program Control Room Supervisor Licensed Operator 2 Unit Supervisor Training Program Shift Technical Advisor Licensed Operator 3 Shift Technical Advisor Training Program Reactor Operator #1 Licensed Operator 4 Reactor Operator #1 Training Program Reactor Operator #2 Licensed Operator 5 Reactor Operator #2 Training Program Nuclear Auxiliary Operator Non-Licensed Operator 6 Auxiliary Operator #1 (AO #1) rrraining Program Nuclear Auxiliary Operator Non-Licensed Operator 7 Auxiliary Operator #2 (AO #2) rrraining Program 8 Other needed for Safe Shutdown N/A N/A 9 Other needed for Safe Shutdown N/A N/A 10 Other needed for Safe Sh1,Jtdown N/A N/A Other (non-Operations) Personnel Necessary to Implement AOPs and EOPs or SAMGs if Applicable Line.#. Generic'Title/Role * *'.' :* * * * * , * *., On*Shift Position**' .\'.. :raskiAnalysis*, . *: .* ...,,,.,
* .. * . .* ~. ~- ::... ;. **. ~. ~ * : *. * ;.c}. "::: *. ~ :* ,. : .~* . . > >::.:,, ..* . *.: .~*. .. * *... F : ¢o~~ronirig!Metho&~:. ;. /
11 Mechanic N/A N/A 12 Electrician N/A N/A 13 l&C Technician
- N/A N/A 14
- Other N/A N/A 15 Other N/A N/A WF3 Page 56
\
WF3 ON-SHIFT STAFFING ANALYIS REPORT Fire Brigade I
. WF3. TABLE*3~:._ FIREFIGHTING : , '
. ':*: </ Analysis*#S.':0.:LOCA*,,,,:::*, : '*.
Line '.*.' P.~.rformed by, , >.: .*. *~ .' *Task Analysispontrol,ling .Method .. *. :~"";: ,
#: ... ' ' ;
' .... - . . ' .. : *. ; ~1. , ' '~ ,,
1 N/A N/A 2 N/A N/A 3 N/A N/A 4 N/A N/A ' 5 N/A N/A This accident does not include the need for firefighting, first aid or search & rescue.
**.
- WF3-.TABLE 4-..:. RADIATION PROTECTION* AND,CHEMISTRY; . * . . *':1
_ . " - .. - - 'Analysis-#8:..,.LOCA::*; :', " :*. -. - * *:. '::'- _ '- ,, -- L Positi?n Rerfor.l!li,ng: '. *
- J *
- Perform~nce *Time Period After Emergenty -Decla~~tion .(minutes)~' -
1-: Funct1off/ Task:~ .. _. _ **,. ** * * * - _ * . . -* . * . ' - .* * - _- .* - *. * * - NE.' :_ , ', , : 0""5 5:.~ .1,0;. *,15-- ::zo~ :~S:~ 30~ :;35:: '45'-, 5,o:: 5S:- qO, 65- ,;7_0~- 75 .. 80-- ~8_5~:
"'* - * ._ <~ :..-- . 10 **t5* *20. '25' 30 35, 40 :4fr- 50:- *55* *50 *65' 7o'- *75' :ao* '85 90 1 In-Plant Survey:
N/A 2 On-site Survey: N/A 3 Personnel Monitoring:
~N/A 4 Job Coverage:RP#2 Post Seismic x x x x x x x x x x Walkdowns 5 Offsite Rad Assessment: (Included in Table 5 6 Other site specific RP (describe): RP#1 x x x x x x x x x x x x x x x x x monitor RMS 7 Chemistry Function task #1 (describe)
N/A 8 Chemistry Function task #2 (describe) N/A
*Times are estimated WF3 Page 57
WF3 ON-SHIFT STAFFING ANALYIS REPORT WF3 TABLE. 5 - EMERGENCY P.LAN, IMPLEMENTATION:- * " * :~
- .. *. * , * ., . : .:. :Analysis #8'"-LOCA.; ~: * * .. * . ,:
line . , Fu11~~ion I Tas~t*: *; *' ..* *
- On-Shiff Po'sitiot(. Tj:isk Analysis:Controlling
#: .:\* .':~*;........ ,:.::,,>".::,.* .... ' :._.* ':~. ~;,>, : ' , < I.:*,'*~ ... '.':M~ttiod~* *. :~'::'
Declare the emergency classification level Emergency Planning Shift Manager (ECL) Training Program I EP Drills 2
~pprove Offsite Protective Action NIA NIA Recommendations Emergency Planning 3 ~pprove content of State/local notifications Shift Manager Training Program 4 ~pprove extension to allowable dose NIA NIA Licensed Operator Training Notification and direction to on-shift staff (e.g.,
5 Shift Manager Program I Emergency
~o assemble, evacuate, etc.)
Planning Training Program Emergency Planning 6 ERO notificatio_n Communicator Training Program 7 ~bbreviated NRC notification for DST event NIA NIA Emergency Planning 8 Complete State/local notification form Communicator Training Program Emergency Planning 9 Perform State/local notifications Communicator Training Program Emergency Planning 10 Complete NRC event notification form Communicator Training Program Emerg~ncy Planning 11 ~ctivate EROS Communicator Training Program Emergency Planning 12 Offsite radiological assessment Communicator Training Program Emergency Planning 13 Perform NRC notifications Communicator Training Program Perform other site-specific event notifications Licensed Operator Training 14 Shift Manager (e.g., Duty Plant Manager, INPO, ANI, etc.) Program Emergency Planning 15 Personnel Accountability A0#5 Training Program WF3 Page 58
WF3 ON-SHIFT STAFFING ANALYIS REPORT I. Design Basis Accident Analysis #9 - Fuel Handling Accident
- 1. Accident Summary
- A fuel assembly is dropped on the core during refueling operations.
- 2. Accident Specific Assumptions Made
- Additional SROs, ROs and NAOs on shift per 01-041-000, Operations Outage Support.
- The Outage Control Center and Refueling support staff is on shift.
- EAL is based on accident event.
- 3. Procedures for Accident Response
- OP-901-405, Fuel Handling Incident
- OP-901-131, Attachment 1 Containment Closure Checklist
- EP-001-001, Recognition & Classification of Emergency Conditions
- EP-002-020, Notifications and Communications
- EP-002-015, Emergency Responder Activation
- EP-002-190, Personnel Accountability
- EP-002-031, lnplant Radiological Controls and Surveys During an Emergency
- EP-002-034, Onsite Surveys During Emergencies
- EP-001-020 Alert
- 4. Tables WF3 Page 59
)
WF3 ON-SHIFT STAFFING ANALYIS REPORT T2/L1 T5/L1 E-Plan Table 5-1 1 Shift Manager (SM) '90 T5/L3 No No T5/L5 T5/L 14 Control Room 2 E-Plan Table 5-1 N/A T2/L2 No No Supervisor (CRS) Shift Technical 3 E-Plan Table 5-1 90 T2/L3 'No No Advisor/FSS (STA) Reactor Operator (RO 4 E-Plan Table 5-1 N/A T2/L4 No No
#1)
Reactor Operator (RO 5 E-Plan Table 5-1 N/A T2/L5 No No
#2)
Nuclear Auxiliary T2/L6 6 E-Plan Table 5-1 N/A No No
.* Operator (AO #1)
Nuclear Auxiliary T2/L7 7 E-Plan Table 5-1 N/A No No Operator (AO #2)) Nuclear Auxiliary 8 E-Plan Table 5-1 N/A N/A No No Operator (AO #3) Nuclear Auxiliary 9 E-Plan Table 5-1 N/A N/A No No Operator (AO #4) Nucle~r Auxiliary 10 E-Plan Table 5-1 N/A T5/L15 No No Operator (AO #5) T5/L6 T5/L8 T5/L9 11 Communicator E-Plan Table 5-1 90 T5/L10 No Yes
- T5/L 11 T5/L 12 T5/L13 12 Chemist#1 E-Plan Table 5-1 90 N/A No No Radiation Protection 13
#1 E-Plan Table 5-1 90 T4/L6 No No Radiation Protection T4/L3 14
#2 E-Plan Table 5-1 90 No No 15 Maintenance Tech #1 E-Plan Table 5-1 90 N/A No No Remote Shutdown N/A 16 E-Plan Table 5-1 N/A No No Operator N/A 17 N/A N/A N/A N/A N/A Security Contingency 18 Security N/A N/A No No Plan IE-Plan Table 5-1 WF3 Page 60
WF3 ON-SHIFT STAFFING ANALYIS REPORT
'WF3TABL:E'2~:-PLANT OPERATIONS'&,SAFE SHUTDOWN .. * ; *'~* ...*. : .*
** * * .-. " OneoUnit-One*Control Rooin:. *. , .' ,. * * :*' ,: .;
., -- ,*:. .- * */* .:'. Analysis#9::...FHA<*,;<: '... * . ,. , .. J Minimur~r Qperations Qte~ . - NeceS_s8rY:
to* Jmplement AOP,$~**arid
*EpPs.
or SAMGst-ifAppli.cabl~, l , . .;* ~'. Line.#.** Generic:Title/~ole, * .,, ... ,. :,. On-Shift Position * ** Task Anal~sis*: ..
.. _.:,* *) "'
- Control Ii rig_* Method~~*. *
- Shift Manager Licensed Operator Shift Manager Training Program Control Room Supervisor Licensed Operator 2 Unit Supervisor Training Program Shift Technical Advisor Licensed Operator 3 Shift Technical Advisor Training Program Reactor Operator #1 Licensed Operator 4 Reactor Operator #1 Training Program Reactor Operator #2 Licensed Operator 5 Reactor Operator #2 Training Program Nuclear Auxiliary Operator Non-Licensed Operator 6 Auxiliary Operator #1 (AO #1) Training Program Nuclear Auxiliary Operator Non-Licensed Operator 7 Auxiliary Operator #2 (AO #2) Training Program 8 Other needed for Safe Shutdown N/A N/A 9 Other needed for Safe Shutdown N/A N/A 10 Other needed for Safe Shutdown N/A N/A Other (non-Operations) Personnel Necessary to Implement AOPs and EOPs or SAMGs if Applicable on~Shift Position.::*.*,: !Task.Ar'!alys!s .: "* *:: . ;
**. ,: .*,* 'r*'; ;* .. , >1,*
.. *'* Controlling* Method** T 11 Mechanic N/A N/A 12 Electrician N/A N/A 13 l&C Technician NIK N/A 14 Other N/A N/A 15 Other N/A N/A WF3 Page 61
WF3 ON-SHIFT STAFFING ANALYIS REPORT Fire Brigade
.. ' WF3 TABLE3..:.. FIREFclGHTING . ..
** ; "..* ,,. :: * : *:';'. '."Analysis.'#9::....; FHA;<>' * .. '. ";: '** * *'
Line Perfo.~med by.*.* . _ _ Task.Analysis Controlling Meth.od . " .
#' ;,*, *.::,4*:( . . . . . ,,,_,.~,Ji" *'*'~;:,:;,.** ,*:!.* .,~.,.',* *".* *
'i*,' .
. i ' ' . .. . ":~,. . ,~, . . 4 ' ** ,* .;. * ". ' * ' ' ' ;.- * ,- '
- 1 N/A N/A 2 N/A N/A 3 N/A N/A 4 N/A N/A 5 N/A N/A This accident does not include the need for firefighting, first aid or search & rescue.
*. WF3 TABLE:.:4:- RADIATION.PROTECTIO~ AND:CHEMIST~Y*.' *>. ;*: :*, . ' .. _
* . ;~"-* *:.*.: 1 Analysis#9>-FHA. * * .. "" - .:._, -~.--'.*, .., **~. *:i::>.,..
- L Position:Performirig'; ** :*.::,.
I
- FUnction:/ Task>~ .. : , 4 Perform~nce.Tifne* Peribd: After *Eme~g~ncy Declarati~n. ('minutest . -.,. i N:~~ ** ~{*:~.=.~~=~~~=o=-~~=~~~?~=o~~F2=~~.=3=~~-=~=~~:=~=-*4=5=~~5=0=~~.5=5=~~s=o~~?6=5~:F:7=~~J=~~.=oo=:*r=M~~
E- L:."'::~:x_,,.* ..":. :c:: \" 9.:5 .10 :;15: 20' :25> :30' -:35' .4o .:45* 50: 5s:* :60.: 65> '::10 ';75; ::ac'r1 85:: - 90:' 1 In-Plant Survey: N/A 2 On-site Survey: N/A 3 Personnel Monitoring: RP#2 contamination monitoring of bldg. x x x x x x x x x evacuees 4 Job Coverage: N/A 5 Offsite Rad \ Assessment: (Included in Table 5 6 Other site specific RP (describe): RP#1 x x x x x x x x x x x x x x x x x monitor RMS 7 Chemistry Function'
~ask #1 (describe)
N/A 8 Chemistry Function task #2 (describe) N/A
*Times are estimated WF3 Page 62
~-------------------------
WF3 ON-SHIFT STAFFING ANALYIS REPORT
-. __ ** *:: ,_,.. * ;'Nf~:*T:~B~E*~.*~EMERGE~CY~LAN,l~~*TEME~~~~I~.~~:; >>.- ~; >>{. '.' ._-:*: * *:-* * :
- . *. : . . . .. ... :.:. Analys1s#9_.FHA,.. ,,._ \. ., .. ':-\ ... ~~: * . \
Line: " , . * . Functkm/Ta~k<<" ; _:.' ... '* . * * .On::-S.!Jift1 l;'ositio_ri T,ask,Analysis Controlling
#*- . _.,.,. .. *- *_.,. *;:' _ ;_, . - :~. f_'.':*.':;:-~_*Y<,** ':'-'*:*\ .. Metlloc(t::;: . :_
Declare the emergency classification level ' Emergency Planning 1 Shift Manager (ECL} Training Program I EP Drills lApprove Offsite Protective Action N/A N/A 2 Recommendations Emergency Planning 3 lApprove content of State/local notifications Shift Manager Training Program 4 !Approve extension to allowable dose N/A N/A Licensed Operator Training Notification and direction to on-shift staff (e.g., 5 Shift Manager Program I Emergency to assemble, evacuate, etc.) Planning Training Program Emergency Planning 6 ERO notification Communicator Training Program 7 !Abbreviated NRC notification for DBT event N/A N/A Emergency Planning 8 Complete State/local notification form Communicator Training Program Emergency Planning 9 Perform State/local notifications Communicator Training Program Emergency Planning 10 Complete NRC event notification form Communicator Training Program Emergency Planning 11 Activate EROS Communicator Training_ Program Emergency Planning 12 Offsite radiological assessment Communicator Training Program Emergency Planning 13 Perform NRC notifications Communicator Training Program Perform other site-specific event notifications Licensed Operator Training 14 Shift Manager (e.g., Duty Plant Manager, INPO, ANI, etc.) Program 15 Per~onnel Accountability A0#5 Emergency Planning Training Program WF3 Page 63
WF3 ON-SHIFT STAFFING ANALYIS REPORT J. Accident Analysis #10 - Control Room Evacuation and Remote Shutdown
- 1. Accident Summary
- A large fire in the control room occurred that included shorts and/or spurious signals producing potential LOCA pathways and/or incorrect system lineup for shutdown.
- Require~s control room evacuation and control from alternate shutdown panels.
- 2. Accident Specific Assumptions Made
- Operator immediate actions are completed prior to evacuation.
- Assume all systems required for remote shutdown function as designed and the core remains covered. No fuel damage and no release.
- 3. Procedures for Accident Response
- OP-901-502, Evacuation of Control Room and Subsequent Plant Shutdown
- FP-001-020, Fire Emergency Response
- EP-001-001, Recognition & Classification of Emergency Conditions
- EP-002-010, Notifications and Communications
- EP-002-190, Personnel Accountability
- EP-001-020, Alert
- OP-902-000, Standard Post Trip Actions (if shutdown due to the event)
- EP-002-015, Emergency Responder Activation WF3 Page 64
WF3 ON-SHIFT STAFFING ANALYIS REPORT
- 4. Tables T2/L 1, T5/L 1 Shift Manager (SM) E-Plan Table 5-1 90 T5/L3 No Yes1 T5/L5 T5/L 14 E-Plan Table 5-1 Control Room Supervisor 2 N/A T2/L2 No No (CRS)
Shift Technical E-Plan Table 5-1 3 90 T2/L3 No Yes1 Advisor/FSS {STA) 4 Reactor Operator (RO #1) E-Plan Table 5-1 N/A T2/L4 No No 5 Reactor Operator (RO #2) E-Plan Table 5- 1 N/A T2/L5 No No Nuclear Auxiliary Operator E-Plan Table 5-1 6 N/A T3/L 1 No No (AO #1) Nuclear Auxiliary Operator E-Plan Table 5-1 7 N/A T3/L2 No No (AO #2)) Nuclear Auxiliary Operator E-Plan Table 5-1 8 N/A T3/L3 No No (AO #3) Nuclear Auxiliary Operator E-Plan Table 5-1 9 N/A T3/L4 No No (AO #4) Nuclear Auxiliary Operator E-Plan Table 5-1 10 N/A T3/15 No Yes (AO #5) E-Plan Table 5-1 T5/L6 T5/L8 T5/L9 11 Communicator N/A No Yes1 T5/L10 T5/L 11 T5/L 13 12 Chemistry #1 E-Plan Table 5-1 90 N/A No No 13 Radiation Protection #1 E-Plan Table 5-1 90 N/A No No E-Plan Table 5-1 N/A 14 Radiation Protection #2 90 No No 15 Maintenance Tech #1 E-Plan Table 5-1 90 N/A No No Remote Shutdown 16 E-Plan Table 5-1 N/A T2/L6 No No Operator 17 N/A N/A N/A N/A N/A N/A Security 18 Security Contingency Plan N/A N/A No No IE-Plan Table 5-1 1 Assigned safe shutdown manipulations WF3 Page 65
WF3 ON-SHIFT STAFFING ANALYIS REPORT
, **.~*:';~ '.: ::~.:.. :_Y,'!;. . ;:::.:::~~.~1~~.~~,~*~'~'.P~~~u~it;~J~~~~~~o~:~~;.~~J~:~:V~;i";';:* >.;~*'. ~*-:,-::.:;:* *:.:
*.. c, * * :- * .:.;:::, -*:' Analysis #10.- CR; Evacuation& Remote.SD:>:'* -.. <': :*i * *,_, >>t .
Shift Manager Licensed Operator 1 Shift Manager rrraining Program Control Room Supervisor Licensed Operator 2 Unit Supervisor rrraining Program Shift Technical Advisor Licensed Operator 3 Shift Technical Advisor [rraining Program Reactor Operator #1 Licensed Operator 4 Reactor Operator #1 rrraining Program Reactor Operator #2 Licensed Operator 5 Reactor Operator #2 rrraining Program Remote Shutdown Non-Licensed Operator 6 Auxiliary Operator #1 Operator Training Program 7 N/A N/A N/A 8 Other needed for Safe Shutdown N/A N/A 9 Other needed for Safe Shutdown N/A N/A 10 Other needed for Safe Shutdown N/A N/A Other (non-Operations) Personnel Necessary to Implement AOPs and EOPs or SAMGs if Applicable Li.~~-~*~l ~*~:~~l~*i~.~~'~',~~~~.--*. ;~~-'.'.::::~-: )~:,; *.*-'.~-.:. :.*g-:* ~:~~-~~tt.;P,:~:7!;:!~.~L:;-::-~-: _.*: 6~t~~~h~~sri~f~~~~~f~'i:__i 11 Mech~nic N/A N/A 12 Electrician N/A N/A 13 l&C Technician N/A N/A 14 Other N/A N/A 15 Other N/A N/A WF3 Page 66
WF3 ON-SHIFT STAFFING ANALYIS REPORT Fire Brigade
*... * ** Wf3:TABLE 3- FIREFIGHTING:,.
- J". T
. :<'A~alysis.#~o;;:,:: CR Evacuation:&:Remc>te*Sci>
Line ~*:..
#.* *,_;.";,;I
~ '.\ *~* ~ :. .
A0#1 Fire Brigade Training 2 A0#2 Fire Brigade Training 3 A0#3 Fire Brigade Training 4 A0#4 Fire Brigade Training 5 A0#5 Fire Brigade Training
.**:: . ' * .. WF3*TABlE4'"-RADIATION*PROTECTION'AND.CHEMISTRY ::.,;. * ' -***t
. * ... , . *... *.<_:, ~;-.--*:.~* ~.-.*Analysis#10.:..cREvacuation&*Remote*,50,:-** *.*;.>*:...'./.>,:,*{ *.. :*.. _r,~: *'
.L_ P9~itiqn:Perforn.i.i~g ;: ::;1 *~~ *.* .. *p~[f6~rTia~ce*Tirrl.~;f>eribdAite~:E~~~g~hdy b~d~~~Hbni(~iii~te~)~~::*<. -:.,'iXi/.;
~** r:~f!~°,~.'~' *QiS. *fit *~~* .~i- ~~- ~ ~\ ~' hi 4td* ~~T *~~* *~~ *~; ~~* :1~*'~~ ~~i*;
1 In-Plant Survey: N/A _ __ 2 On-site Survey: N/A 3 Personnel Monitoring: N/A 4 Job Coverage: _ N/A 5 Offsite Rad Assessment: Included in Table t 6 Other site specific RP (describe}: N/A 7 Chemistry Function
~ask #1 (describe)
N/A 8 Chemistry Function
~ask #2 (describe) l N/A
*Times are estimated WF3 Page 67
WF3 ON-SHIFT STAFFING ANALYIS REPORT
". '.':*; - *::*:.', ,_ : WF3*TABLE5:::..EMERGENCYi-Pl:AN,IMPLEMENTATIQN.. 't>>; .. ', .,. ":~ ':.: *'.--.*.*, _.:;,: _ ,_
' :*.-* ," *: ->.::'*... :**'r< Analysis#10~::..-*cREvacuation&R:emoteso?: * ' *~.' . . *.* .
L~~- >.* ;". _~>- .-:.:~ ~u~F~i~~~-*1ras~r-**,.* :~*';i\:'~'.-::*. _:::r<>11~~~:i~~~~s~ti(j.r:* .. :*:*c:c>~::O~i~~a~:~~~~,a*~ Emergency Planning Declare the emergency classification level 1 Shift Manager Training Program I EP (ECL) Drills Approve Offsite Protective Action N/A 2 N/A Recommendations Emt:irgency Planning 3 Approve content of State/local notifications Shift Manager Training Program 4 Approve extension to allowable dose i N/A N/A
\ Licensed Operator Notification and direction to on-shift staff Training Program I 5 Shift Manager (e.g., to assemble, evacuate, etc.) Emergency Planning Traininq Proqram Emergency Planning 6 ERO notification Communicator Traininq Proqram 7 Abbreviated NRC notification for DBT event N/A N/A Emergency Planning 8 Complete State/local notification form Communicator
[Training Program Emergency Planning 9 Perform State/local notifications Communicator Training Program Emergency Planning 10 Complete NRC event notification form Communicator Training Program Emergency Planning 11 Activate EROS Communicator Training Program 12 Offsite radiological assessment N/A N/A Emergency Planning 13 Perform NRC notifications Communicator [Training Program Perform other site-specific event Licensed Operator 14 notifications (e.g., Duty Plant Manager, Shift Manager [Training Program INPO, ANI, etc.) 15 Personnel Accountability Note 1 Note 1: A0#5 is normally assigned the task of personnel accountability. For the CR Evacuation and remote S/D, A0#5 is on the fire brigade. The Shift Manager may direct another on-shift member who is not SSD or FB to perform the task. WF3 Page 68
WF3 ON-SHIFT STAFFING ANALYIS REPORT K. Accident Analysis #11 - Aircraft Probable Threat
- 1. Accident Summary
- The analysis includes all emergency response actions taken prior to an aircraft impact in accordance with RG 1.214 for an aircraft .threat that is greater than 5 minutes, but less than 30 minutes from the site, and considers the dispersal of the site fire brigade away from target areas for firefighting. '
- The analysis does not include a scenario or response actions taken during or after a crash.
- 2. Accident Specific Assumptions Made
- The Shift Manager receives the call from the NRC of probable aircraft threat.
- All non-security on-shift personnel are inside the protected area fence at their normal workstation.
- 3. Procedures for Accident Response
- OP-901-525, Aircraft Threat 1__
WF3 Page 69
WF3 ON-SHIFT STAFFING ANALYIS REPORT
- 4. Tables
- WF3 TABLE:1.- ON-SHIF.T POSITIONS*:,:. * ~.~
*.::.;; ,*i' :,~: : < ..
~.
.. Arialysis #tt- Aircraft: Probable, Threat "* * :-:: *. *'C ;_. :" '* . .*
*.' .*~'<. f",
.. Augmentation *. Role inTable.# ;,hna~alyz~d: *.. 'TM$
Line# On~shift Position/ .. "* E-Plan Refere..nce:. Elapsed Time,* -::,*,, I*'.Urie*# .
." . " (min)*._. *. :*
) . '
',Task?:* Required?
~
T2/L 1 T5/L 1 E-Plan Table 5-1 1 Shift Manager (SM) 90 T5/L3 No No T5/L5 T5/L 14 Control Room Supervisor 2 E-Plan Table 5-1 N/A T2/L2 No No (CRS)
\ Shift Technical 3 E-Plan Table 5-1 90 T2/L3 No No Advisor/FSS (STA) 4 Reactor Operator (RO #1) E-Plan Table 5-1 N/A T2/L4 No No 5 Reactor Operator (RO #2) E-Plan Table 5-1 N/A T2/L5 No No Nuclear Auxiliary Operator T2/L6 6 E-Plan Table 5-1 N/A No No (AO #1) .
Nuclear Auxiliary Operator T2/L7 7 E-Plan Table 5-1 N/A No No (AO #2)) . Nuclear Auxiliary Operator 8 E-Plan Table 5-1 N/A N/A No No (AO #3) Nuclear Auxiliary Operator 9 E-Plan Table 5-1 N/A N/A No No (AO #4) - Nuclear Auxiliary Operator 10 E-Plan Table 5-1 N/A T5/L 15 No No (AO #5) T5/L6 T5/L8 T5/L9 11 Communicator E-Plan Table 5-1 90 No No T5/L 10 T5/L 11 T5/L 13 12 Chemistry #1 E-Plan Table 5-1 90 N/A No No 13 Radiation Protection #1 E-Plan Table 5-1 90 N/A No No N/A 14 Radiation Protection #2 E-Plan Table 5-1 90 No No 15 Maintenance Tech #1 E-Plan Table 5-1 90 N/A No No Remote Shutdown 16 E-Plan Table 5-1 N/A N/A No No Operator 17 N/A N/A N/A N/A N/A N/A Security 18 Security Contingency Plan I N/A N/A No No E-Plan Table 5-1 WF3 Page 70
WF3 ON-SHIFT STAFFING ANALYIS REPORT
" *: *"; WF3:TABl.:.E'.*2'.-Pl!ANT'OPERATIONSi&.SAFE~SHUTDOWN:,_,i<.> *.:*, ., ,,, * '*
- >, : * ..... * * - :-*.*one,l:Jnit.;..One:control.RooniL.:,,. *:>:f'.. :,: * * *:
. *: ... *""'** Ana1ysi~#ff:...Ai~craff*Proilail1eJ'hreat * *, *,: _, : .:~;; .~ _ 1 : * <
Shift Manager Licensed Operator Shift Manager Training Program Control Room Supervisor Licensed Operator 2 Unit Supervisor Training Program Shift Technical Advisor Licensed Operator 3 Shift Technical Advisor ifraining Program Reactor Operator #1 Licensed Operator 4 Reactor Operator #1 Training Program Reactor Operator #2 Licensed Operator *, 5 Reactor Operator #2 Training Program Auxiliary Operator #1 Nuclear Auxiliary Operator Non-Licensed Operator 6 (AO #1) Training Program Nuclear Auxiliary Operator Non-Licensed Operator 7 Auxiliary Operator #2 (AO #2) Training Program 8 Other needed for Safe Shutdown N/A N/A 9 Other needed for Safe Shutdown N/A N/A 10 Other needed for Safe Shutdown N/A N/A Other (non-Operations) Personnel Necessary to Implement AOPs and EOPs or SAMGs if Applicable Li~e,~~.~ G-~2.~~Jt:T'~Jef.:~~J~:?~.*:*;*,c,(.~...*:.: .1.*~- _-.,_ ** "\;,:);.** -, ?:?:}~~ft,'.:~~itI~;"<;.)l;t.':-.: ci~~~t~~~~:r!,5~i~g~;J~;:'i*~~.;*: 11 Mechanic N/A N/A 12 Electrician N/A N/A 13 l&C Technician N/A N/A 14 Other N/A N/A 15 Other N/A N/A WF3 Page 71
WF3 ON-SHIFT STAFFING ANALYIS REPORT
- Fire Brigade
**.WF3~TABLE:3>-FIREF,IGHTING~,~,.;*'.,;<::~.*.*
* , Analys*i~: #-11::.:. *Airchitt Probable.Threat; **: .: '.
- N/A N/A 2 N/A N/A 3 N/A N/A 4 N/A N/A 5 N/A N/A FB stages in the In-Processing Building, no firefighting activities during the 30 mi~utes included in the analysis.
WF3 Page 72
WF3 ON-SHIFT STAFFING ANALYIS REPORT
.\"' WF3 TABLE 4'- RADIATION PROTECTIONiAND CHEMISTRY':". ,.; *1 : '.*_:,. . ;. '*
,*;
*, ... : .* \1'.*
' ** '<. ,~' *
':~. >..
- ***;--*'- '. Analysis #11 - Aircraft *Probable.Threat -* " : "
L Position.Performing l ;* Perform.anc.e Tim~ Period Nter Emergepcy.Declaratiorr(~iriut~s)*;:, " *::~ I Function'/oTask::* * ' - ' < ~- ' - *,* N "
" ,.' 5- 10,; .15~ 20:.. 25~ .30~ 35- :40::, 45~ .5Q.,.: 5ff.: 130: 65: 10:. 75- 80'- 95:.,*
0-5 10* *ao: E ,;,,
,**!\
' 1'5. 20 25 :30 35 ,40. 45* .50 '55* 60' 65 ;70 75 .*85* ;go;*
1 In-Plant Survey: N/A 2 On-site Survey: N/A 3 Personnel Monitoring: N/A 4 Job Coverage: N/A 5 Offsite Rad Assessment:
'Included in Table 5 6 Other site specific RP (describe):
N/A ) 7 Chemistry Function ask #1 (describe) N/A 8 Chemistry Function ask #2 (describe) N/A Note: No chemistry or RP job function tasks for the conditions described in the Aircraft Threat assumptions. RP relocates to the survey vehicle outside the protected area. Chemistry and maintenance go to their work area or the skills training building to take cover. WF3 Page 73
WF3 ON-SHIFT STAFFING ANALYIS REPORT
, Wf.3.TABLE*s-..:.EMERGENCYPLAN'IMP,tEMENTATION ":/* .,. . ~,;: *
*
- Analysis #1'1 '"'"Aircraft, Probable:Threat::':.. * ** *** * * . . , .. _ "
Line.,*. Declare the emergency classification level Emergency Planning 1 Shift Manager (ECL) Training Program I EP Drills
~pprove Offsite Protective Action N/A 2 N/A Recommendations Emergency Planning 3 ~pprove content of State/local notifications Shift Manager lfraining Program 4 ~pprove extension to allowable dose N/A N/A Licensed Operator Training Notification and direction to on-shift staff (e.g.,
5 Shift Manager Program I Emergency
~o assemble, evacuate, etc.)
Planning Training Program Emergency Planning
*6 ERO notification Communicator lfraining Program 7 ~bbreviated NRC notification for DBT event N/A N/A Emergency Planning 8 Complete State/local notification form Communicator rrraining Program Emergency Planning 9 Perform State/local notifications Communicator rrraining Program Emergency Planning 10 Complete NRC event notification form Communicator Ifraining Program Emergency Planning 11 ~ctivate EROS Communicator rrraining Program 12 Offsite radiological assessment N/A N/A Emergency Planning 13 Perform NRC notifications Communicator rrraining Program Perform other site-specific event notifications Licensed Operator Training 14 Shift Manager (e.g., Duty Plant Manager, INPO, ANI, etc.) Program Emergency Planning 15 Personnel Accountability ~0#5 rrraining Program A0#5 performs accountability of on-shift staff from the In-processing building or prior to relocating.
WF3 Page 74
WF3 ON-SHIFT STAFFING ANALYIS REPORT L. Accident Analysis #12- LOCA/General Emergency with Release and PAR
- 1. Accident Summary (Assumed for Staffing Analysis Purpose)
- The unit is in a Site Area Emergency AS1 when the Shift Manager is given a dose projection update and site boundary survey data that supports >1 Rem TEDE dose at the site boundary.
- 2. Accident Specific Assumptions Made
- All actions for SAE are complete.
- No transients other than LOCA are considered.
- The ERO would be activated at an Alert or SAE. For Staffing Analysis purpose, the T=O clock is used for the emergency plan actions to evaluate the capability to implement the GE classification, PAR and notification functions before the ERO arrives.
- 3. Procedures for Accident Response
- EP-001-040, General Emergency
- EP-002-052, PARs
- EP-002-010, Notifications
- EP-002-034, Onsite Surveys During Emergencies
- EP-002-050, Offsite Dose Assessment
- OP-902-008, Functional Recovery WF3 Page 75
WF3 ON-SHIFT STAFFING ANALYIS REPORT
- 4. Tables T21L 1 T51L 1 E-Plan Table 5-1 T51L2 Shift Manager (SM) 90 No No T51L3 T51L4 T51L5 Control Room Supervisor 2
(CRS) E-Plan Table 5-1 NIA T21L2 No No Shift Technical AdvisorlFSS 3 E-Plan Table 5-1 90 T21L3 No No (STA) 4 Reactor Operator (RO #1) E-Plan Table 5-1 NIA T21L4 No No 5 Reactor Operator (RO #2) E-Plan Table 5-1 NIA T21L5 No No Nuclear Auxiliary Operator T21L6 6 (AO #1) E-Plan Table 5-1 NIA No No Nuclear Auxiliary Operator T2/L7 7 (AO #2)) E-Plan Table 5-1 NIA No No Nuclear Auxiliary Operator 8 (AO #3) E-Plan Table 5-1 NIA NIA No No Nuclear Auxiliary Operator 9 (AO #4) E-Plan Table 5-1 NIA NIA No No Nuclear Auxiliary Operator 10 (AO #5) E-Plan Table 5-1 NIA NIA No No T51L8 T5/L9 11 Communicator E-Plan Table 5-1 90 T51L 10 No Yes T51L 12 T51L 13 12 Chemistry #1 E-Plan Table 5-1 90 NIA No No 13 Radiation Protection #1 E-Plan Table 5-1 90 T41L2 ,No No 14 Radiation Protection #2 E-Plan Table 5-1 90 NIA No No 15 Maintenance Tech #1 E-Plan Table 5-1 90 NIA No No 16 Remote Shutdown Operator E-Plan Table 5-1 NIA NIA No No 17 NIA NIA NIA NIA NIA NIA Security Contingency 18 Security Plan IE-Plan Table 5-1 NIA NIA No No WF3 Page 76
WF3 ON-SHIFT STAFFING ANALYIS REPORT
'* ,, WF3. TABLE~ 2 :'"'"PLANT OPERATIONS . . &.SAFE
. . SHUTDOWN,';
,*:. ,. ;>. *
{ OneUnit-OneCont~olRoom.:; ., . " Analysis #12 - LOCA/General Emergency'with Release and PAR** . Minimum:Operations Crew Necessary to Implement AOPs and EOPs or.SAMGs ifApplicable .. *
. ' ; 'r ' * * , '* <, * < * ' ' * :. '* * * '. ~ *
,--,..; . '::-
Lin~# Generic.Title/Role * . . '.. "' ( , On*Shift Position:' ., ~ rTask.Analysis.. ""I,.
. : \' ~. ~ . ' . ' '
. .. Controlling Method*.* ;,,'
; '"* .. '
Shift Manager Licensed Operator 1 Shift Manager Training Program Control Room Supervisor Licensed Operator 2 Unit Supervisor rrraining Program Shift Technical Advisor Licensed Operator 3 Shift Technical Advisor rrraining Program Reactor Operator #1 Licensed Operator 4 Reactor Operator #1 ifraining Program Reactor Operator #2 Licensed Operator 5 Reactor Operator #2 rrraining Program Nuclear Auxiliary Operator Non-Licensed Operator 6 Auxiliary Operator #1 (AO #1) rrraining Program Nuclear Auxiliary Operator Non-Licensed Operator 7 Auxiliary Operator #2 (AO #2) rrraining Program 8 Other needed for Safe Shutdown N/A N/A 9 Other needed for Safe Shutdown N/A N/A 10 Other needed for Safe Shutdown N/A N/A Other (non-Operations) Personnel Necessary to Implement AOPs and EOPs or SAMGs if Applicable Line#/- Generic Title/Role'
.;:*',,
On-Shift ~osition* Task Analysis. :. ., coritromng*Metho~+: *
' ~'
11 Mechanic N/A N/A 12 Electrician N/A N/A 13 l&C Technician N/A N/A 14 Other N/A N/A 15 Other N/A N/A WF3 Page 77
WF3 ON-SHIFT STAFFING ANALYIS REPORT
- Fire Brigade
\,
. . ** * ., . . WF3~JABLE:3:'"'.".FIREFIGHTINGi**; .*. , * . -'. ' ,; .':
' "<. 'Analysis*#12'~ LOCA!General Emergency* with R~lea~e anci' PAR') '; ' ~' : ,' *;,
N/A N/A 2 N/A N/A 3 N/A N/A 4 N/A N/A 5 N/A N/A No firefighting activities included in the analysis. WF3 Page 78
WF3 ON-SHIFT STAFFING ANALYIS REPORT
.. :: ~~) ... , . : . WF3:T~BLE;47""*~DIATIONPROTECTION~N[)1CHEMISTRY: **(>* .** .. ,. <<
, .. '* :Analysis#12.:...LOCAJGerieralEmergency.with Release*and:PAR: >.. *'*/ .;: .:. :-/',
L Positi?n Perf?rm.ing ... "'. Performahce,Time Period.After E'n1ergenty:6ecl~ratidn. (miriLtes)*' *** * * * '! I Furict1on 1/Task. *" " * ** * * , , * . . . . . *. * . * : , N *. ~. 5,. 10.,. t5- *20::, 25- *30~*, 35~ Ao- .45- 50..:. :55- .60- .65.. 10::.. 75~ 80- 85~, E 0 5
- 10*.. 15:
- 20 .25. : 30 ':35* *j:4o:, *45: *50. 55 ':50
- 65 * :70-. ".75 ao :85 go;.
1 In-Plant Survey: N/A 2 On-site Survey: RP#1 x x x x x x 3 Personnel Monitoring: N/A 4 Job Coverage: N/A 5 Offsite Rad Assessment:
'Included in Table 5 6 Other site specific RP (describe):
N/A ) 7 Chemistry Function task #1 (describe) N/A 8 Chemistry Function task #2 {describe) N/A Note: Time 0 is GE condition met. Times are estimated. WF3 Page 79
WF3 ON-SHIFT STAFFINGANALYIS REPORT
.
- WF3TABLE 5-EMERGENCY P~N IMPLEMENTATION: .* *. *.: *:.
Analysis #12'.*..,. LOCA/General Emergency with.Release and, PA~' Line *Function I Task* ;_: . : ,Ori*Shift,Po!iilion.:t .. Task Analysis Controlling
# .. . ,, *:* '*~<:: *. , ,:* <' .* :::> * .f .:'.'.*~.\>,* ,*.o . . * ** ">'.
*'~" ~::,,. ivi~thod ..*pi.:.t*,
Declare the emergency classification level Emergency Planning 1 Shift Manager (ECL) rTraining Program I EP Drills Approve Offsite Protective Action Emergency Planning 2 Shift Manager Recommendations !Training Program I EP Drills Emergency Planning 3 ~pprove content of State/local notifications Shift Manager rTraining Program Emergency Planning 4 ~pprove extension to allowable dose Shift Manager
!Training Program I EP Drills Licensed Operator Training Notification and direction to on-shift staff (e.g.,
5 Shift Manager Program I Emergency to assemble, evacuate, etc.) Planning Training Program 6 ERO notification N/A N/A 7 ~bbreviated NRC notification for DBT event N/A N/A Emergency Planning 8 Complete State/local notification form Communicator rTraining Program Emergency Planning 9 Perform State/local notifications Communicator rTraining Program Emergency Planning 10 Complete NRC event notification form Communicator
!Training Program 11 ~ctivate EROS N/A N/A Emergency Planning 12 Offsite radiological assessment Communicator
!Training Program Emergency Planning 13 Perform NRC notifications Communicator rTraining Program Perform other site-specific event notifications N/A 14 N/A (e.g., Duty Plant Manager, INPO, ANI, etc.)
15 Personnel Accountability N/A N/A WF3 Page 80
WF3 ON~SHIFT STAFFING ANALYIS REPORT M. Accident Analysis #14- Station Blackout
- 1. Accident Summary
- At power, normal lineups and no additional events
- Loss of all offsite and onsite AC power occurs
- 2.
- Accident Specific Assumptions Made
- Assume the Shift Manager recognizes power cannot be restored within 15 minutes after the loss before the 15 minute SBO EAL period has expired.
- 3. Procedures for Accident Response
- OP-902-005, Station Blackout Recovery I
- EP-001-030 SAE I
- EP-001-001, Recognition & Classification of Emergency Conditions
- EP-002-010, Notifications and Communications
~ EP-002-015, Emergency Responder Activation
- EP-002-190, Personnel Accountability
- 01-035-000, Notification Matrix (other notifications)
- EP-002-031 In-plant Radiological Controls and Surveys During an Emergency
- EP-002-034 Onsite Surveys During Emergencies WF3 Page 81
WF3 ON-SHIFT STAFFING ANALYIS REPORT
- 4. Tables
; *. ,, ,*: -,WF3.TABl:.E.1£:..:,.QN,SHIFTJ?OSITIONS1i/.:,;*. -*
' " *~ .. ">.* "
,'*.*,* ***. _-_ **' :Analysis #14 ~'station s1~ckouf :'. ;-,y:*/ ,-
T2/L 1 T5/L 1 E-Plan Table 5-1 Shift Manager (SM) 90 T5/L3 No No T5/L5 T5/L 14. Control Room 2 E-Plan Table 5-1 N/A T2/L2 No No Supervisor (CRS) Shift Technical 3 E-Plan Table 5-1 90 T2/L3 No No Advisor/FSS (STA) Reactor Operator (RO 4 E-Plan Table 5-1 N/A T2/L4 No No
#1)
Reactor Operator (RO 5 E-Plan Table 5-1 N/A T2/L5 No No
#2)
Nuclear Auxiliary T2/L6 6 E-Plan Table 5-1 N/A No No Operator (AO #1) Nuclear Auxiliary T2/L7 7 E-Plan Table 5-1 N/A No No Operator (AO #2)) Nuclear Auxiliary 8 E-Plan Table 5-1 N/A N/A No No Operator (AO #3) Nuclear Auxiliary 9 E-Plan Table 5-1 N/A N/A No No Operator (AO #4) Nuclear Auxiliary 10 E-Plan Table 5-1 N/A T5/L15 No No Operator (AO #5) T5/L6 T5/L8 T5/L9 11 Communicator E-Plan Table 5-1 90 No No T5/L 10 T5/L 11 T5/L 13 12 Chemist#1 E-Plan Table 5-1 90 N/A No No 13 Radiation Protection #1 E-Plan Table 5-1 90 T4/L3 No No N/A 14 Radiation Protection #2 E-Plan Table 5-1 90 No No 15 Maintenance Tech #1 E-Plan Table 5-1 90 N/A No No Remote Shutdown 16 E-Plan Table 5-1 N/A N/A No No Operator 17 N/A N/A N/A N/A N/A N/A Security Contingency 18 Security Plan I E-Plan Table N/A N/A No No 5-1 WF3 Page 82
WF3 ON-SHIFT STAFFING ANALYIS REPORT Shift Manager Licensed Operator Shift Manager J Training Program Control Room Supervisor Licensed Operator 2 Unit Supervisor lrraining Program Shift Technical Advisor Licensed Operator 3 Shift Technical Advisor rrraining Program Reactor Operator #1 Licensed Operator 4 Reactor Operator #1 Ifraining Program Licensed Operator 5 Reactor Operator #2 Reactor Operator #2 Ifraining Program 6 Auxiliary Operator #1 Nuclear Auxiliary Operator Non-Licensed Operator (AO #1) Training Program Nuclear Auxiliary Non-Licensed Operator 7 Auxiliary Operator #2 Operator (AO #2) Training Program 8 Other needed for Safe Shutdown N/A N/A 9 Other needed for Safe Shutdown N/A N/A 10 Other needed for Safe Shutdown N/A N/A 11 Mechanic N/A 12 Electrician N/A N/A 13 l&C Technician NIA N/A 14 Other N/A N/A 15 Other N/A N/A WF3 Page 83
WF3 ON-SHIFT STAFFING ANALYIS REPORT
'.;,' "/
r
., . ," .. \,;: .
1 N/A N/A 2 N/A N/A 3 N/A N/A 4 ,N/A N/A 5 N/A N/A This accident does not include the need for firefighting, first aid or search & rescue .
.. . ; <...)/, , . <.:.:*~ *.; :~f:3 _TA~LE. ~{..,. RADl~TION<<RR~~ETION AND -~H~IVll,STR¥:"* " . ' /'{{' * ,i~
* :.'*>. *:*;,'** .. :* ~ .."..,.*:" Analys1s.#14-Stat1onBlackout-::,,_ ;>- '~,\~:,{ . . _.r .*.. }'
* ~*** ~S~it~if~ ~~fi'it~~~~~~,{~~!;~~~;~~cy~ii"~i~i;i:i;,~i\~i 1
1 In-Plant Survey: N/A 2 On-site Survey: N/A 3 Personnel . Monitoring: RP#2 set up battery friskers at x x x x control point 4 Uob Coverage:_ N/A 5 Offsite Rad
~ssessment:
'Included in Table f 6 Other site specific RP (describe):
N/A 7 Chemistry Function ask #1 (describe) N/A 8 Chemistry Function task #2 (describe) N/A
*Times are estimated Chemistry does not have an assigned chemistry task for SBO.
WF3 Page 84
WF3 ON-SHIFT STAFFING ANALYIS REPORT
***.::f~'..iM*:F:.r*.~;;:,:r;:;i:;::':/y'r';~'*~~ ~:~f~t1~~:~r!~~~fi~~11:!~~j~~~.T~I~~~l't:~~;t1J"ffr:~!';;!j:;;,:~t*r:J.~1 t 8
Li;~ ~>:'.:*:.;;:)':.;'."~*t*~~R:\!.'.~~,/*~!~~ftt?~E\;::.:;'..: . 1:* ::~~;~1~*~~:~'~.ig~jf}J)~~;~~t*f'.i,': :;:~\~~~:~~;~~;~:{~~:J§;( Emergency Planning Declare the emergency classification level (ECL} Shift Manager Training Program I EP Drills Approve Offsite Protective Action *N/A 2 N/A Recommendations Emergency Planning 3 Approve content of State/local notifications Shift Manager Training Program 4 Approve extension to allowable dose N/A N/A Licensed Operator Notification and direction to on-shift staff !rraining Program I 5 Shift Manager (e.g., to assemble, evacuate, etc.) Emergency Planning Training Program Emergency Planning 6 ERO notification Communicator Training Program 7 Abbreviated NRC notification for DBT event N/A N/A Emergency Planning 8 Complete State/local notification form Communicator Training Program Emergency Planning 9 Perform State/local notifications Communicator Training Program Emergency Planning 10 Complete NRC event notification form Communicator Tr;:iining Program Emergency Planning 11 Activate EROS Communicator Training Program 12 Offsite radiological assessment N/A N/A Emergency Planning 13 Perform NRC notifications Communicator Training Program Perform other site-specific event Licensed Operator 14 notifications (e.g., Duty Plant Manager, Shift Manager Training Program INPO, ANI, etc.) Emergency Planning 15 Personnel Accountability A0#5 Training Program WF3 Page 85
WF3 ON-SHIFT STAFFING ANALYIS REPORT VIII. APPENDIX C - TIME MOTION STUDIES SUPPORTING THE STAFFING ANALYSIS A. None IX. OVERLAP OF TASKS ACTIVITIES OR OTHER CONFLICTS IDENTIFIED A. Overlap Requiring Compensatory Measures
- 1. The Shift Technical Advisor is assigned a collateral task to perform safe shutdown (SSD) manipulations during the control room fire and alternate shutdown per OP-901-502, Evacuation of Control Room and Subsequent Plant Shutdown.
- 2. The Shift Manager is assigned a collateral task to perform SSD manipulations during the control room fire and alternate shutdown per OP-901-502, Evacuation of Control Room and Subsequent Plant Shutdown.
- 3. The Emergency Communicator is assigned a collateral task to perform SSD manipulations for the first 30 minutes during a control room fire and alternate shutdown per OP-901-502, Evacuation of Control Room and Subsequent Plant Shutdown.
- 4. The Shift Technical Advisor is assigned the task of designated operator and relocates outside the control room per OP-901~523, Security Events, during the probable aircraft threat.
- 5. An Auxiliary Operator normally assigned the task to perform accountability is not able to perform the task when OP-901-502, Evacuation of Control Room and Subsequent Plant Shutdown, is implemented due to a collateral duty of fire brigade.
- 6. The Shift Manager is assigned the task to perform the ERO notification during the Design Basis Threat.
X. REFERENCES
- NEI 10-05, Rev 0, Assessment of On-Shift Emergency Response Organization Staffing and Capabilities
- NSIR DPR-ISG-01, Interim Staff Guidance - Emergency Planning for Nuclear Power Plants
- NUREG-0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and
. \
Preparedness m Support of Nuclear Power Plants.
- WF3 Emergency Plan, Rev 37 XI. STAFFING ANALVIS TEAM
- Fred Guynn, Entergy ECH Sr. Project Manager, EP
- Myra Jones, Contractor CMCG
- Bryan Pellegrin, WF3 Manager - EP
- John Jarrell, Assistant Operations Manager
- Paul Wood , WF3 Operations Shift Manager
- Mike Huskey, WF3 Sr. Emergency Planner
- Gerald Thompson, WF3 EP Training Instructor
- Leonard Dauzat, WF3 Radiation Protection Supervisor
- John Signorelli, WF3 Training Superintendent WF3 Page 86
ATTACHMENT 9.2 10 CFR 50.54(0)(3) SCREENING SHEET1OF3 Procedure/Document Number: NIA I Revision: 048 Equipment/Facility/Other: Waterford-3
Title:
Waterford-3 SES Emergency Plan Part I. Description of Activity Being Reviewed Revision 48 to the Waterford-3 SES Emergency Plan includes:
- 1. Added the Fleet TSC, OSC, EOF and Emergency Recovery procedures to Appendix H, Procedure Cross Reference and deleted reference to EP-002-170, Recovery.
- 2. Revised Section 9, Recovery, to conform to recovery organization titles and responsibilities found in fleet Emergency Recovery procedure.
Part II. Activity Previously Reviewed? DYES [81 NO Is this activity fully bounded by an NRC approved 10 CFR 50.90 submittal or 50.54(q)(3) Continue to Evaluation is next part Alert and Notification System Design Report? NOT required. Enter If YES, identify bounding source document number/approval reference and justification ensure the basis for concluding the source document fully bounds the below and complete Part proposed change is documented below: VI. Justification: 0 Bounding document attached (optional) Part Ill. Applicability of Other Regulatory Change Control Processes Check if any other regulatory change processes control the proposed activity.(Refer to EN-Ll-100) APPLICABILITY CONCLUSION 0 If there are no other controlling change processes, continue the 50.54(q)(3) Screening. [81 One or more controlling change processes are selected, however, some portion of the activity involves the emergency plan or affects the implementation of the emergency plan; continue the 50.54(q)(3) Screening for that portion of the activity. Identify the applicable controlling change processes below. 0 One or more controlling change processes are selected and fully bounds all aspects of the activity. 50.54(q)(3) Evaluation is NOT required. Identify controllinq chanqe processes below and complete Part VI. CONTROLLING CHANGE PROCESSES 10 CFR 50.54 (q) 10 CFR 50.59 Part IV. Editorial Change 0YES [81 NO 50.54(q)(3) Continue to next Is this activity an editorial.or typographical change such as formatting, paragraph Evaluation is patt numbering, spelling, or punctuation that does not change intent? NOT required. Enter Justification: justification and continue to next part or complete Part VI as applicable. EN-EP-305 REV 4
ATTACHMENT 9.2 10 CFR 50.54(a)(3) SCREENING SHEET20F 3 Procedure/Document Number: N/A IRevision: 048 Equipment/Facility/Other: Waterford-3
Title:
Waterford-3 SES Emergency Plan Part V. Emergency Planning Element/Function Screen (Associated 10 CFR 50.47(b) planning standard function identified in brackets) Does this activity affect any of the following, including program elements from NU REG-0654/FEMA REP-1 Section II?
- 1. Responsibility for emergency response is assigned. [1] D
- 2. The response organization has the staff to respond and to augment staff on a continuing basis (24/7 D staffing) in accordance with the emergency plan. [1]
- 3. The process ensures that on shift emergency response responsibilities are staffed and assigned. [2] D
- 4. The process for timely augmentation of onshift staff is established and maintained. [2] D
- 5. Arrangements for requesting and using off site assistance have been made. [3] D
- 6. State and local staff can be accommodated at the EOF in accordance with the emergency plan. [3] D
- 7. A standard scheme of emergency classification and action levels is in use. [4] D
- 8. Procedures for notification of State and local governmental agencies are capable of alerting them of D the declared emergency within 15 minutes after declaration of an emergency and providing follow-up notifications. [5]
- 9. Administrative and physical means have been established for alerting and providing prompt D instructions to the public within the plume exposure pathway. [5]
- 10. The public ANS meets the design requirements of FEMA-REP-10, Guide for Evaluation of Alert and D Notification Systems for Nuclear Power Plants, or complies with the licensee's FEMA-approved ANS design report and supporting FEMA approval letter. [5]
- 11. Systems are established for prompt communication among principal emergency response D organizations. [6]
- 12. Systems are established for prompt communication to emergency response personnel. [6] D
- 13. Emergency preparedness information is made available to the public on a periodic basis within the 0 plume exposure pathway emergency planning zone (EPZ). [7]
- 14. Coordinated dissemination of public information during emergencies is established. [7] D
- 15. Adequate facilities are maintained to support emergency response. [8] 0
- 16. Adequate equipment is maintained to support emergency response. [8] D I
- 17. Methods, systems, and equipment for assessment of radioactive releases are in use. [9] 0
- 18. A range of public PARs is available for implementation during emergencies. [10] D
- 19. Evacuation time estimates for the population located in the plume exposure pathway EPZ are D available to support the formulation of PARs and have been provided to State and local governmental authorities. [10]
- 20. A range of protective actions is available for plant emergency workers during emergencies, including D those for hostile action events.[10]
- 21. The resources for controlling radiological exposures for emergency workers are established. [11] D
- 22. Arrangements are made for medical services for contaminated, injured individuals. [12] D
- 23. Plans for recovery and reentry are developed. [13] ~
- 24. A drill and exercise program (including radiological, medical, health physics and other program D areas) is established. [14]
EN-EP-305 REV 4
ATTACHMENT 9.2 10 CFR 50.54(a)(3) SCREENING SHEET30F 3 Procedure/Document Number: N/A I Revision: 048 Equipment/Facility/Other: W aterford-3
Title:
Waterford-3 SES Emergency Plan
- 25. Drills, exercises, and training evolutions that provide performance opportunities to develop, D maintain, and demonstrate key skills are assessed via a formal critique process in order to identify weaknesses. [14]
- 26. Identified weaknesses are corrected. [14] D
- 27. Training is provided to emergency responders. [15] D
- 28. Responsibility for emergency plan development and review is established. [16] D
- 29. Planners responsible for emergency plan development and maintenance are properly trained. [16] D APPLICABILITY CONCLUSION 0 If no Part V criteria are checked, a 50.54(q)(3) Evaluation is NOT required; document the basis for conclusion below and complete Part VI.
00 If any Part V criteria are checked, complete Part VI and perform a 50.54(q)(3) Evaluation. BASIS FOR CONCLUSION Change 1: Appendix H, Procedure Cross Reference, has been revised to include reference to the fleet TSC, OSC, EOF and Emergency Recovery procedures to the list of procedures used to implement the Emergency Plan. The fleet facility procedures will now be used in conjunction with the site facility procedures to direct operations from the site emergency facilities under emergency conditions. The Fleet Emergency Recovery procedure will be used in place of the site recovery procedure and the site recovery procedure, EP-002-170, is being deleted and removed from Appendix H in favor of the fleet Emergency Recovery procedure. The inclusion of these procedures in the cross reference is an enhancement. The meaning or intent of a description in the emergency plan, facilities or equipment described in the emergency plan or a process described in the emergency plan is not affected by this change. No further evaluation is required for this change. Change 2: 10 CFR 50.47 (b) Emergency Planning standard 13 identified in Part V of this form is affected by change 2. A 10CFR50.54(q}(3) evaluation will be performed to determine if the effectiveness of the emergency plan is reduced and prior NRC approval is required. Part VI. Signatures: Preparer Name (Print) Date: Aaron Ertel 1-2 J- 17 Date: (Optional) Reviewer N~lJ Reviewer Signature Reviewer Name (Print) Date: Jack Lewis Nuclear EP Project Manager ?-d-lf-17 Approver Name (Print) Date: John Signorelli Manager, Emergency Planning or designee EN-EP-305 REV 4
ATTACHMENT 9.3 10 CFR 50.54(0)(3) EVALUATION 5HEET1OF6 Procedure/Document Number: N/A I Revision: 048 Equipment/Facility/Other: Waterford-3
Title:
Waterford-3 SES Emergency Plan Part I. Description of Proposed Change:
- 2. Revised Section 9, Recovery, to conform to recovery organization titles and responsibilities found in fleet Emergency Recovery procedure.
1 J Part II. Description and Review of Licensing Basis Affected by the Proposed Change: An Autonomy search using search criteria: Emergency Plan, and "50.59 I 72.48" and was performed using keywords: "Recovery" (114 hits/3 relevant); Recovery Manager (4 hits/3 relevant); Site Recovery Director (0 hits); "Onsite Recovery Manager" (0 hits); "Offsite Recovery Manager" (0 hits); "Recovery Public Relations Manager" (1 hit/1 relevant); "Company Spokesperson" (1 hit/1 relevant) LRS Commitment Search
- (_ The Waterford 3 Licensing Research System search was performed using the Emergency Plan Query (EMPL) for all 376 Emergency Plan related commitments. The following relevant results were found:
P-7 418 states that the Emergency Coordinator is responsible for ensuring that emergency procedures are completed or that the recovery organization is available to continue performance of procedures. P-7 419 states that the offsite organizations are notified of the termination of the emergency and the initiation of recovery. P-7420 states that the EOF Director is responsible for recovery until relieved by the Recovery Manager. P-7421 enumerates the responsibilities of the Recovery Manager. P-7423 states that the Emergency Coordinator is responsible for the recovery organization when the EOF is not activated. P-7424 lists maintaining the plant in a stable condition as a short-term recovery objective. P-7425 lists providing additional safety system capability as a short-ter~ recovery objective. P-7426 lists maintaining control of the release of radioactive material as a short-term recovery objective. P-7428 lists maintaining communications with federal, state and local agencies as a short-term recovery objective. P-7429 lists maintaining the capability for release of public information as a short-term recovery objective. P-7430 lists returning the plant to pre-emergency conditions as a long-term recovery objective. P-7431 lists disposing of waste generated during the emergency as a long-term recovery objective. P-7432 lists evaluating the cause; response and effects of the emergency conditions as a long-term recovery objective. P-7433 states that 10CFR20 limits shall apply during recovery operations. P-7434 states that limiting conditions for operations shall be complied with during recovery operations. P-7435 states that administrative controls for normal operations shall be complied with during recovery operations. EN-EP-305 REV 4
ATTACHMENT 9.3 10 CFR 50.54(0)(3) EVALUATION 5HEET2 OF6 Procedure/Document Number: N/A Revision: 048 Equipment/Facility/Other: Waterford-3
Title:
Waterford-3 SES Emergency Plan Part II. Description and Review of Licensing Basis Affected by the Proposed Change (Condt): P-7436 states that procedures developed during the recovery phase will be reviewed by a technically competent review group. P-7437 states that the recovery Manager will report to the Entergy Operations COO. P-7438 specifies the responsibility and reporting requirements for the Recovery Project Manager. P-7439 specifies the responsibility and reporting requirements for the Recovery Project Engineer. P-7440 specifies the responsibility and reporting requirements for the Recovery Construction Manager. P-7441 specifies the responsibility and reporting requirements for the Recovery Administration Manager. P-7442 specifies the responsibility and reporting requirements for the Recovery Licensing Manager. P-7443 specifies the responsibility and reporting requirements for the Recovery Radiological Manager. P-7444 specifies the responsibility and reporting requirements for the Recovery Operations Manager. P-7445 specifies the *responsibility and reporting requirements for the Recovery Public Relations Manager. P-7446 specifies that reentry activities be included in the recovery program. P-7447 details elements of the restoration program related to recovery. Historical Document Search Previous revisions of the Emergency Plan were reviewed to determine whether relevance to Revision 48 with revision 6 used as a baseline. Revision 6 is the earliest fully intact Emergency Plan revision that can be accessed and this revision received prior NRC approval. It should be noted that Emergency Plan revision 29 also received prior NRC approval for those sections specifically related to ERO response time requirements and is not applicable to this review because the revision is not related to response times. The following is an assessment of the historical review related to revisions to section 9: (1) Basic recovery organization titles, long and short term objectives, mode of operations, reentry and restoration activities were established in revision 6 and remain fundamentally in place up to revision 47 which is the most recent revision to the plan. (2) The Entergy Standard Emergency Response Organization was implemented with revision 40. The recovery section was revised in this revision to make changes to the titles of persons filling normal emergency response organization roles related to recovery. EN-EP-305 REV 4
ATIACHMENT 9.3 10 CFR 50.54(a)(3) EVALUATION 5HEET3 OF6 Procedure/Document Number: N/A J Revision: 048 Equipment/Facility/Other: Waterford-3
Title:
Waterford-3 SES Emergency Plan Part Ill. Descril;>e How the Proposed Change Complies with Relevant Emergency Preparedness Regulation(s) and Previous Commitment(s) Made to the NRC: 10 CFR 50.47(b)(13)- Recovery and Reentry Planning
- Plans for recovery and reentry are developed.
Description of Item 2: Section 9 of the Emergency Plan, Recovery, has been revised to conform to recovery organization titles and responsibilities found in the fleet Emergency Recovery procedure. Site Compliance for item 2: Through implementation of this revision, plans for recovery from an emergency event continue to meet the regulatory requirements. In some cases, Recovery organization titles and responsibilities have been changed to align with those titles and responsibilities found in the recently established fleet recovery procedure. Otherwise, all regulatory requirements related to recovery continue to be met. Previous NRC Commitments: The Licensing Research System and NRC commitment system were reviewed for potential NRC commitment changes as a result of this revision. There were no identified conflicts with this emergency plan revision and the current listing of NRC commitments associated with the emergency plan except that in some cases titles have been changed. All current NRC commitments that relate to recovery continue to.be maintained and fulfilled under this plan revision. Part IV. Description of Emergency Plan Planning Standards, Functions and Program Elements Affected by the Proposed Change: 10 CFR 50.47(b)(13) - Recovery and Reentrv Planning
- Plans for recovery and reentry are developed.
Appendix E to 10 CFR 50 does not contain any supporting requirements. Informing criteria appear in Section \ , 11.M of NUREG-0654 and the licensee's emergency plan. EN-EP-305 REV 4
ATTACHMENT 9.3 10 CFR 50.54(a)(3) EVALUATION SHEET40F 6 Procedure/Document Number: N/A I Revision: 048 Equipment/Facility/Other: W aterford-3
Title:
Waterford-3 SES Emergency Plan Part V. Description of Impact of the Proposed Change on the Effectiveness of Emergency Plan Functions: Evaluation of Item 2: Section 9 of the Emergency Plan was revised to align with the position titles and responsibilities found in the newly established fleet Emergency Recovery procedure. The following is an itemized listing of the revisions to section 9 and a discussion of the effect of these revisions on the Emergency Plan: (1) Changed the title of "Recovery Manager" to "Site Recovery Director" throughout section 9. The capability for directing the overall recovery effort remains in place and is unaffected by the revision. It is concluded that the capability of maintaining the emergency plan function is sustained. (2) Changed the titles of "EOF Director" and "Emergency Coordinator" to "Emergency Director and "Emergency Plant Manager" respectively in section 9.2.1.1 to correct title changes for the Emergency Response Organization that were changed with the implementation of the Entergy Standard ERO. This corrects the Plan and conforms to titles found in Emergency Plan sections 5.1.2.2 and 5.1.2.3. It is concluded that the capability of maintaining the emergency plan function is sustained. (3) Added the position of Onsite Recovery Manager to section 9.3.1 and included responsibilities for directing activities related to the restoration of the plant to pre-incident conditions. This addition places specific responsibility for plant restoration in a defined senior management position and generally conforms to the normal reporting structure for plant operations. This change is considered to be a Recovery organization enhancement. It is concluded that the capability of maintaining the emergency plan function is sustained. (4) Added the position of Offsite Recovery Manager to section 9.3.1 and included responsibilities for interface with Federal, State and local agencies during the recovery process. This addition places specific responsibility for governmental liaison with a defined senior management position and provides a method for addressing governmental agency concerns during the recovery process. This change is considered to be a Recovery organization enhancement. It is concluded that the capability of maintaining the emergency plan function is sustained. (5) Changed the reporting responsibility for the Recovery Project Manager from the previous Recovery Manager to the Onsite Recovery Manager. This change properly aligns the reporting structure for this position to the individual responsible for overall restoration of the plant to pre-incident conditions. This change is considered to be a Recovery organization enhancement. It is concluded that the capability of maintaining the emergency plan function is sustained. (6) Changed the reporting responsibility for the Recovery Administration Manager from the previous Recovery Manager to the Recovery Project Manager. This change properly aligns the reporting structure for this position to the individual responsible for overall engineering, const~uction and procurement activities. This change is considered to be a Recovery organization enhancement. It is concluded that the capability of maintaining the emergency plan function is sustained. (7) Changed the reporting responsibility for the Recovery Licensing Manager from the previous Recovery Manager to the Offsite Recovery Manager. This change properly aligns the reporting structure for this position to the individual responsible for interface with Federal, State and local agencies during the recovery process. This change is considered to be a Recovery organization enhancement. It is concluded that the capability of maintaining the emergency plan function is sustained. (8) Changed the reporting responsibility for the Recovery Radiological Manager from the previous Recovery Manager to the Onsite Recovery Manager. This change properly aligns the reporting structure for this position to the individual responsible for overall restoration of the plant to pre-incident conditions. This change is considered to be a Recovery organization enhancement. It is concluded that the capability of maintaining the emergency plan function is sustained.
ATTACHMENT 9.3 10 CFR 50.54(0)(3) EVALUATION 5HEET50F 6 Procedure/Document Number: N/A I Revision: 048 Equipment/Facility/Other: Waterford-3
Title:
Waterford-3 SES Emergency Plan [Part V. Description of Impact of the Proposed Change on the Effectiveness of Emergency Plan Functions (Condt): * (9) Changed the reporting responsibility for the Recovery Operations Manager from the previous Recovery Manager to the Onsite Recovery Manager. This change properly aligns the reporting structure for this position to the individual responsible for overall restoration of the plant to pre-incident conditions. This change is considered to be a Recovery organization enhancement. It is concluded that the capability of maintaining the emergency plan function is sustained. (1 O) Changed the title of the "Company Spokesperson" to "Recovery Public Relations Manager" and changed the reporting requirement for this position to the Site Recovery Director. This changes the title and reporting requirements for this position but does not affect the recovery related functions performed by this position. It is concluded that the capability of maintaining the emergency plan recovery public information program is sustained. All other information previously found in section 9 of the Emergency Plan including short-term objectives, long-term objectives and re-entry considerations remain in place and are unaffected by this revision. The proposed changes to the Waterford-3 Emergency Plan continues to meet the planning standards outlined in 10 CFR 50.47(b)(13) - Recovery and Reentry Planning. The effectiveness of the Emergency Plan is not reduced. The changes can be incorporated without prior NRC approval. EN-EP-305 REV 1
ATTACHMENT 9.3 10 CFR 50.54(a)(3) EVALUATION 5HEET60F6 Procedure/Document Number: N/A I Revision: 048 Equipment/Facility/Other: Waterford-3
Title:
Waterford-3 SES Emergency Pl~m Part VI. Evaluation Conclusion Answer the following questions about the proposed change.
- 1. Does the proposed change comply with 10 CFR 50.47(b) and 10 CFR 50 Appendix E? ~YES0NO
- 2. Does the proposed change maintain the effectiveness of the emergency plan (i.e., no reduction in effectiveness)?
~YES D NO
- 3. Does the proposed change constitute an emergency action level scheme change? DYES [8J NO If questions 1 or 2 are answered NO, or question 3 answered YES, reject the proposed change, modify the proposed change and perform a new evaluation or obtain prior NRC approval under provisions of 10 CFR 50.90. If questions 1 and 2 are answered YES, and question 3 answered NO, implement applicable change process( es). Refer to step 5.8[8].
Part VII. Signatures Preparer Name (Print) Date: Aaron Ertel 7- 2? - I'""? (Optional) Reviewer Name (Print) Reviewer Signature Date:
~
Reviewer Name (Print) Date:
\
Jack Lewis Nuclear EP Proi,ect Manager Approver Name (Print) Date: EN-EP-305 REV 4
ATTACHMENT 9.2 10 CFR 50.54(Q){3) SCREENING SHEET 1OF3 Procedure/Document Number: N/A I Revision: 048 / 1 Equipment/Facility/Other: Waterford-3
Title:
Waterford-3 SES Emergency Plan I On-Shift Staffing Analysis Part I. Description of Activity Being Reviewed (This is generally changes to the emergency plan, EALs, EAL bases, etc. - refer to step 3.0(6]):
- 1. Reduced number of Remote Shutdown Operators in Section 5.1.2.1k, Table 5-1, and Table 5-4 of the Emergency Plan from two to one.
- 2. Reduced the number of Remote Shutdown Operators included in On-Shift Staffing Analysis from two to one.
- 3. Corrected information previously appearing in revision 0, Table 1 I Analysis #11 of the On-Shift Staffing Analysis to assign Auxiliary Operator with performing accountability actions.
- 4. Corrected information previously appearing in revision 0, Table 51 Analysis #4 of the On-Shift Staffing Analysis to assign Communicator with radiological assessment duties for RCP shaft seizure/shear accident.
Part II. Activity Previously Reviewed? DYES 181NO Is this activity fully bounded by an NRG approved 10 CFR 50.90 submittal or 50.54(q)(3) Continue to Evaluation is next part Alert and Notification System Design Report? NOT required. Enter If YES, identify bounding source document number/approval reference and justification ensure the basis for concluding the source document fully bounds the below and complete Part proposed change is documented below: VI. Justification: D Bounding document attached (optional) Part Ill. Applicability of Other Regulatory Change Control Processes Check if any other regulatory change processes control the proposed activity.(Refer to EN-Ll-100) APPLICABILITY CONCLUSION D If there are no other controlling change processes, continue the 50.54(q)(3) Screening. 181 One or more controlling change processes are selected, however, some portion of the activity involves the emergency plan or affects the implementation of the emergency plan; continue the 50.54(q)(3) Screening for that portion of the activity. Identify the applicable controlling change processes below. D One or more controlling change processes are selected and fully bounds all aspects of the activity. 50.54(q)(3) Evaluation is NOT required. ldentifv controllinq chanqe orocesses below and complete Part VI. CONTROLLING CHANGE PROCESSES I 10CFR50.54(q) 10 CFR 50.59 Part IV. Editorial Change DYES 181 NO 50.54(q)(3) Continue to next Is this activity an editorial or typographical change such as formatting, paragraph Evaluation is part numbering, spelling, or punctuation that does not change intent? NOT required. Enter Justification: justification and continue to next part or complete Part Vias applicable. EN-EP-305 REV 4
ATIACHMENT 9.2 10 CFR 50.54(Q)(3) SCREENING SHEET2 OF 3 Procedure/Document Number: N/A I Revision: 048 I 1 Equipment/Facility/Other: Waterford-3
Title:
Waterford-3 SES Emergency Plan I On-Shift Staffing Analysis Part V. Emergency Planning ElemenUFunction Screen (Associated 10 CFR 50.47(b) planning standard function identified in brackets) Does this activity affect any of the following, including program elements from NUREG-0654/FEMA REP-1 Section II?
- 1. Responsibility for emergency response is assigned. [1] D
- 2. The response organization has the staff to respond and to augment staff on a continuing basis (24/7 D staffing) in accordance with the emergency plan. [1]
- 3. The process ensures that on shift emergency response responsibilities are staffed and assigned. [2] ~
- 4. The process for timely augmentation of onshift staff is established and maintained. (2] D
- 5. Arrangements for requesting and using off site assistance have been made. [3] D
- 6. State and local staff can be accommodated at the EOF in accordance with the emergency plan. (3] D
- 7. A standard scheme of emergency classification and action levels is in use. [4] D
- 8. Procedures for notification of State and local governmental agencies are capable of alerting them of D the declared emergency within 15 minutes after declaration of an emergency and providing follow-up notifications. [5]
- 9. Administrative and physical means have been established for alerting and providing prompt D instructions to the public within the plume exposure pathway. [5)
- 10. The public ANS meets the design requirements of FEMA-REP-10, Guide for Evaluation of Alert and D Notification Systems for Nuclear Power Plants, or complies with the licensee's FEMA-approved ANS design report and supporting FEMA approval letter. [5]
- 11. Systems are established for prompt communication among principal emergency response D organizations. [6]
- 12. Systems are established for prompt communication*to emergency response personnel. [6] D
- 13. Emergency preparedness information is made available to the public on a periodic basis within the 0 plume exposure pathway emergency planning zone (EPZ). [7]
- 14. Coordinated dissemination of public information during emergencies is established. [7] 0
- 15. Adequate facilities are maintained to support emergency response. [8] 0
- 16. Adequate equipment is maintained to support emergency response. [8] D I 17. Methods, systems, and equipment for assessment of radioactive releases are in use. [9] D
- 18. A range of public PARs is available for implementation during emergencies. [1 OJ D
- 19. Evacuation time estimates for the population located in the plume exposure pathway EPZ are D available to support the formulation of PARs and have been provided to State and local governmental authorities. [10)
- 20. A range of protective actions is available for plant emergency workers during emergencies, including D those for hostile action events.(1 O]
EN-EP-305 REV 4
ATTACHMENT 9.2 10 CFR 50.54(0)(3) SCREENING SHEET30F 3 Procedure/Document Number: N/A Revision: 048/1 Equipment/Facility/Other: Waterford-3
Title:
Waterford-3 SES Emergency Plan I On-Shift Staffing Analysis 21.* The resources for controlling radiological exposures for emergency workers are established. [11] D 22, Arrangements are made for medical services for contaminated, injured individuals. [12] D
- 23. Plans for recovery and reentry are developed. [13] D
- 24. A drill and exercise program (including radiological, medical, health physics and other program D areas) is established. [14]
- 25. Drills, exercises, and training evolutions that provide performance opportunities to develop, D maintain, and demonstrate key skills are assessed via a formal critique process in order to identify weaknesses. [14] *
- 26. Identified weaknesses are corrected. [14] D
- 27. Training is provided to emergency responders. (15] D
- 28. Responsibility for emergency plan development and review is established. (16] D
- 29. Planners responsible for emergency plan development and maintenance are properly trained. [16] D APPLICABILITY CONCLUSION 0 If no Part V criteria are checked, a 50.54(q)(3) Evaluation is NOT required; document the basis for conclusion below and complete Part VI.
00 If any Part V criteria are checked, complete Part VI and perform a 50.54(q)(3) Evaluation. BASIS FOR CONCLUSION Items 1 & 2: 10CFR50.47 (b) Emergency Planning standard 2 identified in Part V of this form is affected. A 10CFR50.54(q)(3) evaluation will be performed to determine if the effectiveness of the emergency plan is reduced and prior NRC approval is required. Items 3 & 4: These items correct information appearing in revision 0 of the Onshift Staffing Analysis and do not require further evaluation. 1 Part VI. Signatures: Preparer Name (Prtnt) Date: Aaron Ertel 5-2-"?-(7 (Optional) Reviewer Name (Print) Reviewer Signature Date:
/rU -*-> -------*(____ ) _..
Approver Name (Print) /.~***/~~pp;:: ver .Signature Date: John Signorelli l_.,* (_... -:- // Manager, Emergency Planning or designee , . ~4
- EN-EP-305 REV 4
ATTACHMENT 9.2 10 CFR 50.54(a)(3) SCREENING SHEET1 OF4 Procedure/Document Number: N/A I Revision: 048 / 1 Equipment/Facility/Other: Waterford-3
Title:
Waterford-3 SES Emergency Plan I On-Shift Staffing Analysis Part I. Description of Activity Being Reviewed (This is generally changes to the emergency plan, EALs, EAL bases, etc. - refer to step 3.0[6]): This is a revision to an approved 10CFR50.54(q)(3) Screening for Revision 1 of the On-Shift Staffing Analysis (CR-WFJ-2017-2204).
- 1. Reduced number of Remote Shutdown Operators in Section 5.1.2.1k, Table 5-1, and Table 5-4 of the Emergency Plan from two to one.
- 2. Reduced the number of Remote Shutdown Operators included in On-Shift Staffing Analysis from two to one.
- 3. Corrected information previously appearing in revision 0, Table 1 I Analysis #11 of the On-Shift Staffing Analysis to assign Auxiliary Operator with performing accountability actions.
- 4. Corrected information previously appearing in revision 0, Table 5 /Analysis #4 of the On-Shift Staffing Analysis to assign Communicator with radiological assessment duties for RCP shaft seizure/shear accident.
Part II. Activity Previously Reviewed? . DYES t8:] NO Is this activity fully bounded by an NRC approved 10 CFR 50.90 submittal or 50.54(q)(3) Continue to Evaluation is next part Alert and Notification System Design Report? NOT required. I Enter If YES, identify bounding source document number/approval reference and justification ensure the basis for concluding the source document fully bounds the below and complete Part proposed change is documented below: VI. Justification: 0 Bounding document attached (optional) Part Ill. Applicability of Other Regulatory Change Control Processes Check if any other regulatory change processes control the proposed activity.(Refer to EN-Ll-100) APPLICABILITY CONCLUSION 0 If there are no other controlling change processes, continue the 50.54(q)(3) Screening. t8:] One or more controlling change processes are selected, however, some portion of the activity involves the emergency plan or affects the implementation of the emergency plan; continue the 50.54(q)(3) Screening for that portion of the activity. Identify the applicable controlling change processes below. D One or more controlling change processes are selected and fully bounds all aspects of the activity. 50.54(q)(3) Evaluation is NOT reauired. ldentifv controllino chanae processes below and complete Part VI. CONTROLLING CHANGE PROCESSES 10 CFR 50.54 (q) 10 CFR 50.59 Part IV. Editorial Change DYES t8:I NO 50.54(q)(3) Continue to next Is this activity an editorial or typographical change such as formatting, paragraph Evaluation is part numbering, spelling, or punctuation that does not change intent? NOT required. Enter Justification: justification and continue to next part or complete Part Vias applicable. EN-EP-305 REV 4
ATTACHMENT 9.2 10 CFR 50.54(0)(3) SCREENING SHEET20F 4 Procedure/Document Number: NIA I Revision: 048 I 1 Equipment/Facility/Other: Waterford-3
Title:
Waterford-3 SES Emergency Plan I On-Shift Staffing Analysis Part V. Emergency Planning Element/Function Screen (Associated 10 CFR 50.47(b) planning standard function identified in brackets) Does this activity affect any of the following, including program elements from NUREG-0654/FEMA REP-1 Section II? ',
- 1. Responsibility for emergency response is assigned. [1] 0
- 2. The response organization has the staff to respond and to augment staff on a continuing basis (24/7 0 staffing) in accordance with the emergency plan. [1]
- 3. The process ensures that on shift emergency response responsibilities are staffed and assigned. [2] ~
- 4. The process for timely augmentation of onshift staff is established and maintained. [2] 0
- 5. Arrangements for requesting and using off site assistance have been made. [3] 0
- 6. State and local staff can be accommodated at the EOF in accordance with the emergency plan. [3] 0
- 7. A standard scheme of emergency classification and action levels is in use. [4] 0
- 8. Procedures for notification of State and local governmental agencies are capable of alerting them of 0 the declared emergency within 15 minutes after declaration of an emergency and providing follow-up notifications. [5]
- 9. Administrative and physical means have been established for alerting and providing prompt 0 instructions to the public within the plume exposure pathway. [5]
- 10. The public ANS meets the design requirements of FEMA-REP-10, Guide for Evaluation of Alert and 0 Notjfication Systems for Nuclear Power Plants, or complies with the licensee's FEMA-approved ANS design report and supporting FEMA approval letter. [5]
- 11. Systems are established for prompt communication among principal emergency response 0 organizations. [6]
- 12. Systems are established for prompt communication to emergency response personnel. [6] 0
- 13. Emergency preparedness information is made available to the public on a periodic basis within the 0 plume exposure pathway emergency planning zone (EPZ). [7]
- 14. Coordinated dissemination of public information during emergencies is established. [7] 0
- 15. Adequate facilities are maintained to. support emergency response. [8] 0
- 16. Adequate equipment is maintained to support emergency response. [8] 0
- 17. Methods, systems, and equipment for assessment of radioactive releases are in use. [9] 0
- 18. A range of public PARs is available for implementation during emergencies. [1 O] 0
- 19. Evacuation time estimates for the population located in the plume exposure pathway EPZ are 0 available to support the formulation of PARs and have been provided to State and local governmental authorities. [1 OJ
- 20. A range of protective actions is available for plant emergency workers during emergencies, including 0 those for hostile action events.[1 O]
EN-EP-305 REV 4
ATTACHMENT 9.2 10 CFR 50.54(0)(3) SCREENING SHEET3 Of 4 Procedure/Document Number: N/A I Revision: 048 I 1 Equipment/Facility/Other: Waterford-3
Title:
Waterford-3 SES Emergency Plan I On-Shift Staffing Analysis
- 21. The resources for controlling radiological exposures for emergency workers are established. [11] DC.
- 22. Arrangements are made for medical services for contaminated, injured individuals. [12] D
- 23. Plans for recovery and reentry are developed. [13] D
- 24. A drill and exercise program (including radiological, medical, health physics and other program D areas) is established. [14]
- 25. Drills, exercises, and training evolutions that provide performance opportunities to develop, D maintain, and demonstrate key skills are assessed via a formal critique process in order to identify weaknesses. [14]
- 26. Identified weaknesses are corrected. [14] D
- 27. Training is provided to emergency responders. [15] D
- 28. Responsibility for emergency plan development and review is established. [16] D
- 29. Planners responsible for emergency plan development and maintenance are properly trained. [16] D APPLICABILITY CONCLUSION 0 If no Part V criteria are checked, a 50.54(q)(3) Evaluation is NOT required; document the basis for conclusion below and complete Part VI.
00 If any Part V criteria are checked, complete Part VI and perform a 50.54(q)(3) Evaluation. BASIS FOR CONCLUSION Items 1 & 2: 10 CFR 50.47 (b) Emergency Planning standard 2 identified in Part V of this form is affected. A 10CFR50.54( q)(3) evaluation will be performed to determine if the effectiveness of the emergency plan is reduced and prior NRC approval is required. Item 3: The role of AO (Auxiliary Operator) #5 was inadvertently left out of Table 1 I Analysis #11 (Aircraft Probable Threat) in revision 0 of the On-Shift Staffing Analysis (See Attachment 1-). The role of A0#5 in Table 5 of Analysis #11 clearly states A0#5 has responsibility for personnel accountability on line 15. Item 3 adds reference to the table and role (T5IL15) for A0#5 to Table 1 of Analysis #11 to correct this omission. No responsibility has been changed with this correction. Item 3 does not change any meaning or intent as described in the emergency plan. No process, facility or equipment is being affected with this change. No further evaluation is required. Item 4: Table 5 of Analysis #4 (Single RCP Shaft Seizure/Sheared Shaft with LOP) in revision 0 incorrectly omitted the on-shift position which is responsible for offsite radiological assessment (line 12) (See Attachment 2). Emergency Plan revision 47 section 5.1.2.1 states "Operations shift personnel are trained to perform offsite dose assessment calculations. The Shift Manager has primary responsibility for these calculations, but any member of the staff may perform them. Calculations will usually be performed by the Emergency Communicator (NAO)". Item 4 corrects the staffing analysis description of the Emergency Communicator's role in performing offsite radiological assessment for Analysis #4, as described in the emergency plan section 5.1.2.1. In fact, the Emergency Communicator performs this role in any declared emergency when offsite dose assessment calculations are necessary. No responsibility, as described in the emergency plan, has been changed or transferred. Item 4 does not change any meaning or intent as described in the emergency plan. No process, facility or equipment is being affected with this change. No further evaluation is required. EN-EP-305 REV 4
ATIACHMENT 9.2 10 CFR 50.54(a)(3) SCREENING REVISION 1 5HEET40F4 Procedure/Document Number: N/A I Revision: 048 / 1 Equipment/Facility/Other: W aterford-3
Title:
Waterford-3 SES Emergency Plan I On-Shift Staffing Analysis Part VI. Signatures: Preparer Name (Print) Date: Aaron Ertel 4111117 (Optional) Reviewer Name (Print) Reviewer Signature Date: NIA Reviewer Name (Print) Date: Jack Lewis Nuclear EP Project Manager Approver Name (Print) Date: John Signorelli Manager, Emergency Planning or designee EN-EP-305 REV 4
ATTACHMENT 1 Table 1 I Analysis #11 from Revision 0 T21L 1 T51L1 E-Plan Table 5-1 Shift Manager (SM) 90 TSIL3 No No T51L5 T51L 14 I Control Room Supervisor 2 E-Plan Table 5-1 NIA T21L2 No No (CRS) Shift Technical 3 E-Plan Table 5-1 90 T21L3 No No AdvisorlFSS (STA) 4 Reactor Operator (RO #1) E-Plan Table 5-1 NIA T21L4 No No 5 Reactor Operator (RO #2) E-Plan Table 5-1 NIA T21L5 No No Nuclear Auxiliary Operator 6 (AO #1) E-Plan Table 5-1 NIA NIA No No Nuclear Auxiliary Operator 7 E-Plan Table 5-1 NIA NIA No No (AO #2)) Nuclear Auxiliary Operator 8 E-Plan Table 5-1 NIA NIA No No (AO #3) 9 Nuclear Auxiliary Operator E-Plan Table 5-1 NIA NIA No No IAO #4) I 10 Nuclear Auxiliary Operator (AO #5) ' E-Plan Table 5-1 NIA NIA No No I 1 o/Lo TSIL8 T51L9 11 Communicator E-Plan Table 5-1 90 No No TSIL 10 T51L 11 T51L 13 12 Chemistry #1 E-Plan Table 5-1 90 N/A No No 13 Radiation Protection #1 E-Plan Table 5-1 90 NIA No No 14 Radiation Protection *#2 E-Plan Table 5-1 90 NIA No No 15 Maintenance Tech #1 E-Plan Table 5-1 90 N/A No No Remote Shutdown 16 E-Plan Table 5-1 NIA T2/L6 No No Operator #1 Remote Shutdown 17 E-Plan Table 5-1 N/A T2/L7 No No Operator#2 Security 18 Security Contingency Plan I N/A N/A No No E-Plan Table 5-1 1
ATTACHMENT, 1 Table 5 /Analysis #11 from Revision 0 Declare the emergency classification level Emergency Planning Shift Manager (ECL) Training Program I EP Drills [Approve Offsite Protective Action N/A 2 N/A Recommendations Emergency Planning 3 [Approve content of ~tate/local notifications Shift Manager
!Training Program 4 Approve extension to allowable dose N/A N/A I Licensed Operator Training Notification and direction to on-shift staff (e.g.,
5 Shift Manager Program I Emergency o assemble, evacuate, etc,) Planning Training Program Emergency Planning 6 ERO notification Communicator
!Training Program 7 Abbreviated NRC notification for DBT event N/A N/A Emergency Planning 8 Complete State/local notification form Communicator Training Program Emergency Planning 9 Perform State/local notifications Communicator training Program Emergency Planning 10 Complete NRC event notification form Communicator Training Program Emergency Planning 11 Activate EROS Communicator '
Training Program 12 Offsite radiological assessment N/A N/A Emergency Planning 13 Perform NRC notifications Communicator Training Program 14 Perform other site-specific event notifications Licensed Operator Training Shift Manager An n11h1 Pl::int '-A"'n"'"""r INPn ANI <>tr-) Proa ram Emergency Planning 15 Personnel Accountability 'A0#5 Training Program 2
ATTACHMENT 1 Table 1 /Analysis #11 from Revision 1 T2IL1 T5/L1 Shift Manager (SM) E-Plan Table 5-1 90 T51L3 No No T5/L5 T5/L 14 Control Room Supervisor 2 E-Plan Table 5-1 NIA T2/L2 No No (CRS) Shift Technical 3 E-Plan Table 5-1 90 T2/L3 No No AdvisorlFSS (STA) 4 Reactor Operator (RO #1) E-Plan Table 5-1 NIA T2/L4 No No 5 Reactor Operator (RO #2) E-Plan Table 5-1 NIA T2/L5 No No Nuclear Auxiliary Operator T2/L6 6 E-Plan Table 5-1 NIA No No (AO #1). Nuclear Auxiliary Operator T2/L7 7 E-Plan Table 5-1 NIA No No (AO #2)) Nuclear Auxiliary Operator 8 E-Plan Table 5-1 NIA N/A No No (A0#3) 9 Nuclear Auxiliary Operator {Ll.f"l'.lt4\ E-Plan Table 5-1 NIA N/A No No Nuclear Auxiliary Operator 10 E-Plan Table 5-1 NIA T5/L 15 No No (AO #5) 15/Lo T51L8 T51L9 11 Communicator E-Plan Table 5-1 90 No No T51L 10 T5/L11 T51L13 12 Chemistry #1 E-Plan Table 5-1 90 NIA No No 13 Radiation Protection #1 E-Plan,Table 5-1 90 NIA No No N/A 14 Radiation Protection #2 E-Plan Table 5-1 90 No No 15 Maintenance Tech #1 E-Plan Table 5-1 90 NIA No No Remote Shutdown 16 E-Plan Table 5-1 NIA N/A No No Operator 17 NIA NIA N/A N/A N/A N/A Security 18 Security Contingency Plan I N/A N/A No No E-Plan Table 5-1 3
ATTACHMENT 2 Table 5 I Analysis #4 from Revision 0 Emergency Planning Declare the emergency classification level 1 Shift Manager raining Program I EP (EGL} Drills pprove Offsite Protective Action N/A 2 N/A Recommendations Emergency Planning 3 pprove content of State/local notifications Shift Manager raining Program 4 pprove extension to allowable dose N/A N/A Licensed Operator Training Notification and direction to on-shift staff (e.g., 5 Shift Manager Program I Emergency o assemble, evacuate, etc.} Planning Training Program Emergency Planning 6 ERO notification Communicator raining Program 7 bbreviated NRC notification for DBT event N/A Emergency Planning 8 Complete State/local notification form Communicator raining Program Emergency Planning 9 Perform State/local notifications Communicator raining Program Emergency Planning 10 Complete NRG event notification form Communicator raining Program 11 ctivate EROS N/A Emergency Planning 12 Offsite radiological assessment N/A raining Program Emergency Planning 13 Perform NRG notifications Communicator raining Program Perform other site-specific event notifications Licensed Operator Training 14 Shift Manager (e.g., Duty Plant Manager, INPO, ANI, etc.) Program Emergency Planning 15 Personnel Accountability 0#5 raining Program 4
ATTACHMENT 2 Table 5 /Analysis #4 from Revision 1
'Line* rU.'i;,:\i*t;<:://\e;_Flj ti~*TtT~.s ....""'\,:L'i\(.:\\;0;*:. *{!>*.9ri~Shift:positio~;\::~t*:* l!'~~~Ar1alysis.::Cor1trollhig
#.***** r;*.:~c;;;*.***:**,*.::*.**}';_**.*.*';*;j*>;c;i';,; :**.:~u*:*.;g,*}:*:::'*i?'*+)*<~;c*:':.*:t.*'***. ~:f~lH:':y':(.:.;f.'*;:1:Diff.l<:;'::::::~~:\)2*:*;<:;:?:.*:*'i:* l*;1i;:>1~;i{'\'\cjff* Methbd4i~ju.ir.* *'.;:;@.**
Emergency Planning Declare the emergency classification level Shift Manager If raining Program I EP (ECL) Drills Approve Offsite Protective Action N/A 2 N/A Recommendations Emergency Planning 3 Approve content of State/local notifications Shift Manager rTraining Program 4 ~pprove extension to allowable dose NIA N/A Licensed Operator Training Notification and direction to on-shift staff (e.g., 5 Shift Manager Program I Emergency
~o assemble, evacuate, etc.)
Planning Training Program Emergency Planning 6 ERO notification Communicator Training Program 7 Abbreviated NRC notification for DBT event N/A N/A Emergency Planning 8 Complete State/local n'otification form Communicator Training Program i ,*~ ;' Emergency Planning 9 Perform State/local notifications Communicator Training Program Emergency Planning 10 Complete NRC event notification form Communicator Training Program 11 Activate EROS N/A N/A Emergency Planning 12 Offsite radiological assessment Communicator Training Program i Emergency Planning
\ 13 Perform NRC notifications Communicator I Training Program Perform other site-specific event notifications Licensed Operator Training 14 Shift Manager (e.g., Duty Plant Manager, INPO, ANI, etc.) Program Emergency Planning 15 Personnel Accountability ~0#5 Training Program 5
ATTACHMENT 9.3 10 CFR 50.54(0)(3) EVALUATION SHEET1 OF4 Procedure/Document Number: N/A I Revision: 048 I 1 Equipment/Facility/Other: Waterford-3
Title:
Waterford-3 SES Emergency Plan I On-Shift Staffing Analysis Part I.Description of Proposed Change:
- 1. Reduced number of Remote Shutdown Operators in Section 5.1.2.1k, Table 5-1, and Table 5-4 of the Emergency Plan from two to one.
- 2. Reduced the number of Remote Shutdown Operators included in On-Shift Staffing Analysis from two to one.
Part II. Description and Review of Licensing Basis Affected by the Proposed Change: An Autonomy search of the Emergency Plan and SERs and NRC correspondence was performed using keywords: "Remote Shutdown Operator" (3 hits/3 relevant); "On-Shift Staffing Analysis" (4 hits/2 relevant) LRS Commitment Search The Waterford 3 Licensing Research System search was performed using the Emergency Plan Query (EMPL) for all 376 Emergency Plan related commitments. No relevant results were found. Historical Document Search Previous revisions of the Emergency Plan were reviewed to determine relevance to Revision 48. The Remote Shutdown Operator position was first included in the Emergency Plan in revision 44 that went into effect on January 18, 2013. This position was included in response to the Waterf9rd-3 On-Shift Staffing Analysis Report. The Waterford-3 On-Shift Staffing Analysis Final Report, Revision 0 was placed into effect on December 19, 2012. It is this revision that is being revised at this time. Part Ill. Describe How the Proposed Change Complies with Relevant Emergency Preparedness Regulation(s) and Previous Commitment(s) Made to the NRC: 10 CFR 50.47(b)(2) - Onsite Emergency Organization
- The process ensures that onshift emergency response responsibilities are staffed and assigned.
- The process for timely augmentation of onshift staff is established and maintained.
Description of Item 1: The number of Remote Shutdown Operators described in section 5.1.2.1k, Table 5-1 and Table 5-4 of the Emergency Plan is being reduced from two to one. Compliance for Item 1: Waterford-3 License Amendment 248 dated 6/27/16 implemented NFPA-805 and reduced operator actions related to fire protection and consequently reduced the number of shift personnel needed to carry out fire protection related activities. All emergency related staffing and augmentation requirements continue to be met. Description of Item 2: Reduced the number of Remote Shutdown Operators included in On-Shift Staffing Analysis from two to one. Compliance for Item 2: Waterford-3 License Amendment 248 dated 6/27/16 implemented NFPA-805 and reduced operator actions related to fire protection and consequently 'reduced the number of shift personnel needed to carry out fire protection related activities. All emergency related staffing and augmentation requirements continue to be met. Previous NRC Commitments: The Licensing Research System was reviewed for potential NRC commitment changes as a result of this revision. This change does not affect any previous commitments made to the NRC. EN-EP-305 REV 4
ATTACHMENT 9.3 10 CFR 50.54(Q){3) EVALUATION SHEET2 OF4 Procedure/Document Number: N/A I Revision: 048 / 1 Equipment/Facility/Other: Waterford-3
Title:
Waterford-3 SES Emergency Plan I On-Shift Staffing Analysis Part IV. Description of Emergency Plan Planning Standards, Functions and Program Elements Affected by the Proposed Change: 10 CFR 50.4 7(b )(2) - Onsite Emergency Organization The process ensures that onshift emergency response responsibilities are staffed and as~igned. The process for timely augmentation of onshift staff is established and maintained. Sections IV.A.2.a-c, IV.A.3, and IV.C of Appendix E to 10 CFR 50 provide supporting requirements. Informing criteria appear in Section 11.B of NUREG-0654 and the licensee's emergency plan. r EN-EP-305 REV 4
AITACHMENT 9.3 10 CFR 50.54(Q){3) EVALUATION SHEET3 OF4 Procedure/Document Number: N/A , I Revision: 048 I 1 Equipment/Facility/Other: Waterford-3
Title:
Waterford-3 SES Emergency Plan I On-Shift Staffing Analysis Part V. Description of Impact of the Proposed Change on the Effectiveness of Emerg~ncy Plan Functions: '10 CFR 50.47(b)(2) - Onsite Emergency Organization The process ensures that onshift emergency response responsibilities are staffed and assigned. The pr~cess for timely augmentation of onshift staff is established and maintained Evaluation of Items 1 & 2: Waterford-3 has recently adopted a risk-informed, performance-based fire protection alternative per 10 CFR 50.48(c) which incorporates by reference NFPA-805 in accordance with NRC regulation. NFPA-805 describes the fundamental fire protection program elements and minimum design requirements for fire protection systems and features to satisfy regulatory performance criteria. NFPA-805 supersedes 10CFR50 Appendix Ras the licensing basis for Waterford-3. The voluntary adoption of 10 CFR 50.48(c) by Waterford 3 does not eliminate the need to comply with 10 CFR 50.48(a) and 10 CFR 50, Appendix A, GDC 3, Fire Protection. However, compliance with the new rule establishes compliance with these sections. This transition to NFPA-805 was approved by amendment 248 to the Waterford-3 Operating License dated June 27, 2016. This transition was evaluated and approved by EC-15959 (NFPA 805 Transition Base EC) and was implemented by various Engineering Changes which accomplish required licensing basis changes or modifications. The required changes to OP-901-502, Evacuation of Control Room & Subsequent Plant Shutdown, were evaluated and approved by EC-40610 (NFPA-805 Nuclear Safety Capability Assessment (NSCA), a child EC to parent EC-15959). This license amendment removed Appendix R actions that mandated additional shift personnel to assist with fire protection related activities. Revision 032 to OP-901-502 is in full accord with these referenced sburce documents, complies with the updated license, TRM and USFSAR. The position titles for the Remote Shutdown Operators as referenced in the Emergency Plan and in the On-Shift Staffing Analysis were the Field Operator and the Switchgear Operator. As a result of the implementation of NFPA-805; the duties of the Field Operator have ljieen deleted from OP-901-502. The duties of the Switchgear Operator, as well as the other on-shift operators have been significantly reduced by the implementation of NFPA-805 such that the 11eed for the Field Operator to complete the required actions for this off-normal procedure has been eliminated. It should be noted that neither position was added to provide an Emergency Planning function; rather these positions we*re present to complete shutdown activities so that Emergency Planning functions performed by others could be completed. As a result of the elimination of the duties of the Field Operator, the Emergency Planning functions can still be performed and these functions do not compete with the completion of the shutdown function. Therefore, there is no change to the completion of Emergency Planning functions as identified in the Emergency Plan and the capability to perform Emergency Plan functions remains in place. In addition, Section IV, Accident Scenarios, of the Waterford-3 Onshift Staffing Analysis was reviewed in light of the proposed reduction of onshift personnel to 16 persons. This review concludes that the reduction to 16 onshift staffing members does not impact the ability to implement plant response and Emergency Plan actions for any of the accidents or events listed in Section IV of the report. It is concluded that the proposed changes to the Waterford-3 Emergency Plan continue to meet the planning standards outlined in 10 CFR 50.47(b) 2. The effectiveness of the emergency plan is not reduced, and the Emergency Plan changes can be incorp,orated without prior NRC approval.
ATTACHMENT 9.3 10 CFR 50.54(0)(3) EVALUATION SHEET40F4 Procedure/Document Number: N/A I Revision: 048I1 Equipment/Facility/Other: Waterford-3
Title:
Waterford-3 SES Emergency Plan I On-Shift Staffing Analysis Part VI. Evaluation Conclusion Answer the following questions about the proposed change.
- 1. Does the proposed change comply with 10 CFR 50.47(b) and 10 CFR 50 Appendix E? !2JYES 0 NO
- 2. Does the proposed change maintain the effectiveness of the emergency plan (i.e., no reduction in effectiveness)?
!2JYES 0 NO
- 3. Does the proposed change constitute an emergency action level scheme change? DYES ~NO If questions 1 or 2 are answered NO, or question 3 answered YES, reject the proposed change, modify the proposed change and perform a new evaluation or abtain prior NRG approval under provisions of 10 CFR 50.90. If questions 1 and 2 are answered YES, and question 3 answered NO, implement applicable change process( es). Refer to step 5.8[8].
Part VII. Signatures Preparer Name (Print) Date: Aaron Ertel 3-2]-!7 (Optional) Reviewer Name (Print) L]_ Reviewer Signature Date:
/
Yi I/ Reviewer Name (Print) Date: Jack Lewis Nuclear EP Proje6t Manager Date:
>--z. f--r 7 EN-EP-305 REV 4}}