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| -1 NEBRASKA PUBLIC POWER DISTRICT ;
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| .l COOPER NUCLEAR STATION i
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| 1990 EVALUATED EXERCISE:
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| a JULY 25, 1990' 3
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| NEBRA8KA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION JULY 25, 1990 EVALUATED 3XERCISE TABLE OF CONTENTS PJLQE PART I GENERAL INFORMATION
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| ==1.0 INTRODUCTION==
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| 2.0 SCOPE AND OBJECTIVES 2.1 SCOPE
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| -2.2 ONSITE OBJECTIVES 3.0 EXERCISE INFORMATION 3.1 CONDUCT OF THE EXERCISE 3.2 PRECAUTIONS AND LIMITATIONS
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| '3. 3 EXERCISE ORGANIZATION 4.0 CONTROLLER / EVALUATOR INFORMATION 4.1 GENERAL INFORMATION 4.2 CONTROLLER INSTRUCTIONS 4.3 EVALUATOR INSTRUCTIONS
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| : 4. 4. PERSONNEL ASSIGNMENTS 5.0 PARTICIPANT INFORMATION 5.1 . GENERAL INFORMATION 5.2 PARTICIPANT GUIDELINES 6.0 SCHEDULE OF EVENTS PART II SCENARIO INFORMATION 7.0 SCENARIO 7.1 ~ SEQUENCE OF EVENTS 7.2 MASTER EVENTS
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| ==SUMMARY==
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| 7.3 NARRATIVE
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| ==SUMMARY==
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| 8.0 MESSAGES AND PLANT DATA 8.1 PLANT MESSAGES 8.2 P.I. MESSAGES 9.0 RADIOCHEMISTRY SAMPLE AND RADIOLOGICAL DATA 9.1 RADIO CHEMISTRY DATA 9.2 RADIATION AREAS DATA 9.3 PROCESS MONITOR DATA E
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| P NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION JULY 25, 1990 EVALUATED EXERCISE .
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| TABLE OF CONTENTS PAGE 10.'O METEOROLOGICAL AND RADIOLOGICAL RELEASE DATA 10.1 FORECAST 10.2 METEOROLOGICAL DATA i i
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| 10.3 RADIOLOGICAL RELEASE DATA 10.4 RADIOLOGICAL FIELD DATA 10.5 RADIOLOGICAL FIELD DATA
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| ==SUMMARY==
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| ATTACEMENTS CONTROLLER / EVALUATOR FORMS PARTICIPANT COMMENT FORMS CRITIQUE CHECKLIST
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| 1 i, j l 1 SECTION 1.0 !,
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| i l l 1' i s
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| INTRODUCTION l i
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| COOPER NUCLEAR STATION 1990 EVALUATED EEERCISE SECTION 1.0
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| ==1.0 INTRODUCTION==
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| The Cooper Nuclear Station Emergency Plan describes NPPD's capabilities to respond to a nuclear emergency at the Cooper Nuclear Stations with support from Federal, state, and local government agencies and rPivate organizationc. The CNS Emergency Plan provides for continuous emergency preparedness, including the conduct of an annual full-scale exercise.
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| The purpose of the exercise is to activate and evaluate major portions of the emergency response organization and facilities and other tspects of the Emergency Plan and associated Emergency Plan Implementing Procedures, in accordance with Nuclear Regulatory Commission (NRC) Regulation 10CFR50.47 (b) and Appendix E. The exercise is conducted jointly with appropriate State and local agencies in order to assess State and local government emergency response plans, as required by Federal Emergency Management Agency (FEMA) Regulation 44CFR350.9 (b). TP- .iuct and evaluation of the exercise l
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| provides additional training for a+1rgency response organization personnel and a means to further enhance Nebraskt Public Power District's emergency responsa capability.
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| This Exercise Manuel has been developed to provide the basis for the conduct of an emergency exercise simulating a radiological accident at the Cooper Nuclear Station located near Brownville in Nemaha County, Nebraska, through which the capabilities 4nd ef fectiveness of the Emergency Response Plans for the Nebraska Public Power District, the states of Nebraska, and Missouri and their respective counties, can be evaluated.
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| C00PER WUCLEAR STATION 1990 EVALUATED EXERCISE stCTION 1.0 1
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| This manual is to be utilized by the controllers and I evaluators from the NPPD, the inspectors and evaluatorn from the NRC, to initiate, control, and evaluate the activities of the participants in the exercise. This Exercise Manual consists of two parts. Part I provides a general description and overview of an emergency exercise. Part II contains the scenario and time schedule of simulated plant conditions and is subject to a limited, controlled distribution. Exercise "clavers" will not have erior knowledce of the nature of ths ,
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| simulated incident __or any earts thereof.
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| SECTION 2.0 SCOPE AND OBJECTIVES t
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| 2.0 SCOPE AMD ON ECTIVES 2.1 SCOPE The Cooper Nuclear Station (CNS) 1990 Emergency Exercise Program will test and provide the opportunity to evaluate Nebraska Public Power District's (NPPD) emergency plan 1 and procedures. It will also tJst the emergency response !
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| organization's ability to assess and respond to emergency j conditions and co-ordinate efforts with other agencies i for protection of the health and safety of the public.
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| The scenario will depict a simulated sequence of events, resulting in suf ficiently degraded conditions to warrant the mobilization of the NPPD emargency response organization. The Exercise will have full participation by the NPPD emergency response organization. Whenever practical, the exercise will incorpor.t *.e provisions for
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| " free play" on the part of the partic; pants.
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| 2.2 ONSITE ONECTIVES
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| .The Cooper Nuclear Station (CNS) 1990 Emergency Preparedness Exercise Program objectives are based on the Nuclear Regulatory Commission (NRC) requirements ,
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| delineated in 10CFR50.47 and 10CFR50 Appendix E.
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| Additional guidance provided in NUREG-0654, and FEMA-REP-1 revision 1, NUREG-0696, and NUREG-0737 supplement 1 was also utilized in developing these objectives.
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| The major objective of the exercise is to evaluate the integrated capability of a major portion of the basic elements existing within the onsite and of fsite emergency plans and participating emergency response organizations.
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| The specific objectives of the exercise to be demonstrated are lis ed below.
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| 9 CONTROL ROOM l
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| Demonstrate facility management and control as evidenced by 1.
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| close coordination with staff and supporting Emergency Response Facilities.
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| : 2. Demonstrate analysis of plant conditions and corrective actions, by proper and timely use of appropriate procedures.
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| : 3. Demonstrate detection and classification of emergency events by proper use of EPIP 5.7.1, "Energency Classification".
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| : 4. Demonstrate the ability to make protective action recommendations to offsite authorities using the EPA Protective Action Guides (PAGs) as guidance or plant conditions, by proper use of Protective Action Recommendations on notification forms.
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| : 5. Demonstrate the initial notification of Federal, State, local, corporate, and plant emergency personnel, according to procedure.
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| : 6. Demonstrate providing plant status updates to offsite authorities, until relieved by the TSC or the EOF.
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| : 7. Demonstrate the ability to implement protective actions.
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| : 8. Demonstrate the mechanism for recommending protective actions to the appropriate State and Local authorities as per EPIP 5.7.6, if required.
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| l-TECHNICAL SUPPORT CENTER (TSC)
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| : 1. Demonstrate activation of the Technical Support Center (T '0) within 60 minutes of the declaration of an Alert or higner classification.
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| : 2. Demonstrate facility management and control as evidenced by close coordination With staff and supporting Emergency Response Facilities.
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| : 3. Demonstrate accident assessment and classification as evidenced by multi-discipline input to classification process.
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| : 4. Demonstrate the ability to perform dose asser,sment , if applicable.
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| ability to make protectave action
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| : 5. Demonstrate the using the EPA recommendations to offsite authorities Protective Action Guides (PAGs) of as guidance or plant conditions, by proper use Protective Action Recommendations on notification forms.
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| : 6. Demonstrate providing plant status updates to facility activation, offsite until i
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| authorities, beginning after relieved by the EOF.
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| : 7. Demonstrate the ability to implement protective actions for on-site personnel.
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| : 8. Demonstrate assistance and support to the control room.
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| : 9. Demonstrate dispatch and coordination of monitoring teams, repair teams, and/or rescue teams.
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| : 10. Demonstrate the mechanism for recommending protective actions to the appropriate State and Local authorities as per EPIP 5.7.6, if required.
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| f 11. Demonstrate dose tracking and exposure control capability for emergency workers.
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| i EMERGENCY OPERATIONS FACILITY (EOFF
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| : 1. Demonstrate activation of the Emergency Operations Faci,lity (EOF) within 60 minutes of the declaration of a Site Area Emergency.
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| : 2. Demonstrate facility management and control as evidenced by close coordination with staff and supporting Emergency Response Facilities.
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| : 3. Demonstrate accident assessment and classification.
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| Demonstrate the ability to perform dose assessment, if 4.
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| applicable.
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| : 5. Demonstrate the ability to make protective action recommendations to offsite authorities using the EPA Protective Action Guides (PAGs) as guidance or plant conditions, by proper use of Protective Action
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| '(ecommendations on notification forms.
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| : 6. Demonstrate providing plant status updates to offsite authorities, beginning after facility activation, until the recovery panel is convened.
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| : 7. Demonstrate the ability to implenient protective actions for field teams, if necessary.
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| : 8. Demonstrate the ability to coordinate the emergency response resources of NPPD with State, and loc 41 organizations.
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| : 9. Demonstrate coordination of responsibilities and decision-making with offsite agencies in de-escalation or termination of the emergency. ,
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| : 10. Demonstrate coordination of responsibilities and decision making with of fsite agencies in planning reentry to evacuated areas.
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| : 11. Demonstrate the mechanism for recommending protective actions to the appropriate State and Local authorities as per EPIP 5.7.6, if required, t
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| OPERhTIONS SUPPORT CEN'? IRS (CSC)
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| : 1. Demonstrate activation of the operations Support Center (OSC) within 60 minutes of the declaration of an Alert.
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| : 2. Demonstrate facility management and control as evidenced by l coordination of staff and interface with the Technical Support Center.
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| : 3. Demonstrate performance of support functions. ,
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| GENERAL OFFICE EMERGENCY CENTER (GOECl-
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| : 1. Demonstrate notification of NPPD GOEC personnel as per CNEP 2.0.
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| : 2. Demonstrate the set-up of NPPD GOEC, equipment and materials.
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| : 3. Demonstrate the ability to establish voice communications I with the EOF. l
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| : 4. Demonstrate ability to declare the NPPD GOEC operational l within approximately 60 minutes of notifications to GOEC l c personnel. ,
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| : 5. Demonstrate the capability at the NPPD GOEC to obtain current and accurate information.
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| : 6. Demonstrate the ability to maintain status boards and logs in the NPPD GOEC.
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| : 7. Demonstrate the capability at the NPPD GOEC to coordinate and arsemble emergency information for dissemination to the media and/or the public.
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| : 8. Demonstrate the capability at the NPPD GOEC to respond ,
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| directly to questions from the media and/or public concerning the real and rumored events of an emergency at CNS.
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| : 9. Demonstrate the capability at the NPPD GOEC to disseminate accurate information concerning a CNS emergency to NPPD employees. This to be accomplished by providing information to Gerald Gentleman Station, Sheldon Station, Hastings Dispatch Center and the Regional Dispatch Centers.
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| : 10. Demonstrate the capability at the NPPD GOEC to identify rumors and correct false information concerning an emergency at CNS.
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| : 11. Demone.trate follow-up notifications of non-NPPD support agencies (i.e. Iowa Light & Power, Iowa Disaster Services, Kansas Division of Emergency Preparedness).
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| : 12. Demonstrate the capability to coordinate and plan Recovery operations with MRC and CNS ERF personnel.
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| 0FFSITE MONITORING. TEAMS I
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| : 1. Mobilize the offsite radiological monitoring teams within 30 minutes of activation of the EOF.
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| : 2. Demonstrate the appropriate use of instrumentation, procedures, and communications by the radiological monitoring '
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| teams. '
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| : 3. Demonstrate the collection and labeling of potentially radioactively contaminated sample media by the radiological monitcring teams.
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| i CORRICTIVE ACTION / RESCUE TEhWS
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| : 1. Demonstrate adequate performance of in-plant repair teams.
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| 2.- Demonstrate adequate instrumentation and procedures to monitor for contamination of emergency workers and equipment.
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| SECURITY / ACCOUNTABILITY
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| : 1. Demonstrate the ability to perform site assembly
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| * and accountability within about 30 minutes af ter the announcement for assembly and accountability has been made. (Personnel will re' trn to work.)
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| : 2. Demonstrato maintenance of accountability.
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| I MEDIA RELEASE CENTER (KRC)
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| : 1. Demonstrate notification of NPPD MRC personnel as per CNEP 2.0.
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| : 2. Demonstrate the set-up of NPPD MRC work areas, equipment and materials. >
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| : 3. Demonstrate the set-up of " Media Briefing" area and equipment at the NPPD MRC (Board of Equalization Chamber of LC level will be utilized for briefings).
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| : 4. Demonstrate the ability to establish voice communicati.ons with the EOF.
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| : 5. Demonstrate the capability to register NPPD, State, Federal, Media, and other personnel at the NPPD MRC.
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| : 6. Demonstrate the ability to declare the NPPD MRC operational within approximately 3 hours of initiating activation.
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| : 7. Demonstrate the capability to provide CNS/NPPD background information to the Media at the NPPD MRC.
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| : 8. Demonstrate the capability to coordinate and assemble current and accurate emergency information at the NPPD MRC.
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| : 9. ' Demonstrate the ability to maintain status boards and logs at the NPPD MRC.
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| : 10. Demonstrate the capability at the NPPD MRC to disseminata emergency information to the media and/or public (briefing..,
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| written statements, etc).
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| : 11. Demonstrate the capability at the NPPD MRC to-respond to inquiries of both a technical and political nature during
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| " media briefings".
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| : 12. Demonstrate the capability at the NPPD MRC of Public Assistance Hotline personnel to respond to inquiries from the public and/or media concerning real or rumored events of an emergency at CNS.
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| : 13. Demonstrate the capability at the NPP.9 MRC to identify rumors and correct false information concerung an emergency at CNS.
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| : 14. Demonstrate the capability to coordinate and plan Recovery operations with GOEC and CNS ERF personnel.
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| 10
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| 1 M-ENTRY /MCOVERY
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| : 1. Demonstrate the ability to plan recovery operations and identify need for additional resources. i l
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| i OBJECTIVES NOT. MLATED TO.h.8PECIFIC EU .
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| : l. Demonstrate the ability to develop a 24-hour emergency t
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| .; response roster for key positions.
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| : 2. Demonstrate the capability to warn all personnel within the Owner Controlled Area.
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| i C11T1003 !
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| : 1. Demonstrate the ability to self critique in order to' identity. -!
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| weak or deficient areas that need correction. :
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| SECTION 3.0 INFORMATION i
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| l COOPER NUCLEAR STATION ,
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| 1990 EVALUAlrD EXERCISk SECTION 3.0 3.0 EXERCISE..INFORMATION I 3.1 CONDUCT OF THE EXERCISE The exercise will simulate an abnormal radiological incident at the Cooper Nuclear Station. The effectiveness of selected l I
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| organizations, personnel and functions of the appropriate Emergency Plans and Implementing Procedures will be demonstrated. The simulated emergency will then terminate.
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| The Recovery Phase will be initiated, and the Exercise will then be terminated.
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| Emergency response actions during the simulated emergency will includes o recognition and classification of emergency conditions o assessment of onsite/offsite radiological consequences o alert / notification and mobilization of emergency response organizations o implementation of in-plant corrective actions o activation / operation of emergency response facilities and equipment-l o preparation of reports, messages, and record keeping o recommendation of protective actions, and termination of the emergency condition and limited recovery /re-entry l discussions 1
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| COOPER NUCLEAR STATION 1990 EVALUATED EXERCISE SECTION 3.0 ;
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| 6 The control Room will be the central point for distribution of exercise messages and is the key to ensuring that the exercise progresses on schedule. Simulated plant parameters and annunciators will be provided to the Control Room opert. tors using message forms and plant data cheets. A wide variety of plant information is provided so that at no time ;
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| will the messages prompt the players or provide undue assistance in recognition of events. Information available !
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| on SPDS will also be provided in the TSC and the EOF where output consoles are located. Contingency messages are delivered only when conditions dcscribed in the controller notes have been met.
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| Radiological and meteorological data presented in Sections 9.0 and 10.0 and information included in the supplemental scenarios will be disseminated by controllers when players demonstrate the capability to obtain the information from
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| appropriate tources. At no time, unless noted specifically as an exception, will information be interjected at a point where it would not be available in a real emergency. The Lead Controllers may interject other information or change a message to enuure that the exercise progresses as planned.
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| The exercise PJayers are expected to " free play" the scenario ;
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| to the extent practical. If corrective actions are postulated that would terminate the emergency, they should be identified to the Lead controller in the affected facility, so that the scenario will progress as designed.
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| Notifications of, and contact with, supervi.Lors , plant management, and offsite agencies will be made in accordance 2
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| l COOPER NUCLEAR STATION 1990 EVALUATED EXERCISE SECTION 3.0 Implementing Procedures. No simulations are to be allowed unless specifically noted in the Exercise Manual or directed by a controller for scenario purposes.
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| 3.2 PRECAUTIONS AND LIMITATIONS This section provides information for all exercise participants related to the rules and guidelines to be followed throughout the conduct of this Exercise. Prior to initiation of the exercise, a pre-exercise briefing will be held to review the entire exercise process with all the exercise controllers and observers.
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| e o Should, at any time during the conduct of this exercise, an actual emergency situation arise, all activities and communications related to the exercise vill be suspended.
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| It will be the responsibility of any exercise controller or observer that becomes aware of an actual emergency to
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| < suspend exercise response in his/her immediate area and to inform the Lead Exercise Controller of the situation.
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| Upon notification of an actual emergency, the Lead Exercise controller may notify all other controllers to suspend all exercise activities.
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| o Should, at any time during the course of the conduct of this exercise, an exercise controller or observer witness an exercise participant undertake any action which would, in the opinion of the controller, place either an individual or component in an unsafe condition, the controller is responsible for intervening in the individual's actions and terminating the unsafe activity immediately.
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| 4 COOPER WUCLEAR STAT 10N 1990 EVALUATED EXERCISE SECTICW 3.0 o No response to an exercise situation will be simulated without controller approval. No action will be taken that reduces the margin of safety in the plant.
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| o All repair activities associated with the scenario will be ' simulated with extreme caution emphasized around operating equipment. Manipulation of any plant operating systems, valves, breakers, or controls in response to tais exercise is to be simulated. There is to be no alteration of any plant operating equipment, systems, or circuits during the response of this exercise. No pressurization of fire hoses, discharging of fire extinguishers, or initiation of any fire suppression systems will be allowed for the exercise.
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| l o All telephone communications, radio transmissions, and public address announcements related to the Exercise must begin and end with the statement, "This is a drill".
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| Should a controller witness a drill participant not observing this practice, it is the controller's responsibility to remind the individual of the need to l-follow this procedure.
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| o Any motor vehicle response to this Exercise, whether it be ambulance, fire fighting equipment, police / security vehicles or field monitoring teams, should observe all normal motor vehicle operating laws including posted speed limits, stop lights / signs, one way streets, etc.
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| Red lights and sir.:ns will not be operated on emergency vehicles for the purposes of the Exercise.
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| COOPER NUCLEAR STATION i 1990 EVALUATED EXERCISE SECTION 3.0 1
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| Red lights and sirens will not be operated on emergency vehicles for the purposes of the Exercise.
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| o care must be taken to assure that any non-participating individuals who may observe exercise activities or overhear exercise communications are not misled into believing that an actual emergency exists. Any exercise Controller who is aware of an individual or group of individuals in the immediate vicinity who may have becoine alarmed or confused about the situation, should
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| (
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| approach that individual or group and explain the nature of the exercise and its intent.
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| 3.3 EXERCISE ORGANIZATION The organization for this exercise will consist of the Exercise Coordinator, the Lead Exercise Controller, the Controllers, the Evaluators, the observers, and the Players as follows:
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| 3.3.1 The Exercise Coordinatctr is responsible for the post exercise controller debriefing, the CNS exercise critique and the NRC critique and exit meeting. Subsequent to the exercise, he will direct the preparation of a consolidated evaluation I package and preparation of an itemized list of recommended corrective actions.
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| 3.3.2 The Lead Exere.ise controller is responsible for the conduct of a successful exercise and will coordinate exercise preparations including the development of the scenario and messages. The Lead 5
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| COOPER NUCLEAR STATION f 1990 EVALUATED EXERCISE SECTION 3.0 i
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| Exercise controller will ensure the safe conduct of ,
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| the exercise and is responsible for resolution of any scenario-related inter-facility questions, as l well as the assurance that the conduct of the exercise does not adversely impact the operation of i
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| the station. The Lead Exercise Controller will also coordinate the preparation of a consolidated evaluation package.
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| 3.3.3 The controllers are qualified personnel selected to perform functions as follows:
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| A. A Lead controller is assigned to each emergency response facility. The Lead Controller is responsible for all Controller, Evaluator, and Observer activities for that facility and, as appropriate, its associated teams. Controllars for teams or sub-areas of a facility report to the Lead Controller of that facility. l B. Controllers will deliver " Exercise Messages" to designated players at specified times and places during the exercise, inject or deliver contingency messages as required to prompt the appropriate p1.ayer response and keep the exercise actions moving according to the scenario, observe the exercise at other assigned locations, and prepare an evaluation. C Controllers will submit written recommendations to the Lead Controller, who 6
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| COOPER NUCLEAR STATION ,
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| 1990 EVALUATED EXERCISE '
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| SECTION 3.0 will summarize all comments for submittal to the Exercise coordinator. The Controllers are provided with instructions and evaluation forms as attachments to this manual.
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| 3.3.4 Evaluators are personnel who are assigned to judge the effectiveness of participating organizations, personnel, and activities in response to the scenario. They will evaluate performance on the basis of standards or requirements contained in the appropriate Emergency plan, Implementing Procedures, !
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| Exercise messages, and as described herein.
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| 3.3.5 observers may be authorized, on a limited baeis, to participate in the exercise for the ,
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| purpose of observing exercise activity for personal education.
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| 3.3.6 Inseectors are members of the NRC or FEMA evaluation teams and will have prior knowledge of the exercise scenario. At their assigned locations they will observe the exercise and prepara an evaluation to be presented at the exit meeting and critique.
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| 3.3.7 Plavers include station and other utility personnel assigned to perform emergency functions as described in the Emergency Plan and Implementing Procedures. Players from offsite organizations and agencies (county, 7
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| COOPER NUCLEAR STATION '
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| 1990 EVALUATED EXERCISE SECTION 3.0 State, and privata industry) are participants in the exercise as described in their respective emergency plans and standard operating procedures.
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| 4 SECTION 4.0 CONTROLLER INFORMATION-t-
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| l COOPER NUCLEAR STATION 1990 EVALUATED EXERCISE j SECTION 4.0 1
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| 4.0 CONTROLLER INFORMATION !
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| 1 4.1 GENERAL INFORMATION l
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| Each Controller should be familiar with the followingt l i
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| o The basic objectives of the exercise (Section 2.0) . ;
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| o The assumptions and precautions being taken (section 3.0).
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| o The exercise scenario, including the initiating events and the expected course of action to be taken (Section 7.0).
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| o The various locations that will be involved and the ,
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| specific items to be observed at those locations, o The evaluation checklists provided.
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| 1 4.2 CONTROLLER INSTRUCTIONS o Controllers will position themselves at their assigned locations 30 minutes prior to the activation of the facility or team for which they have responsibility.
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| .o Communications will be tested prior to exercise commencement. All watches and clocks will be.
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| synchronized with'the Control Room (Simulator) clock as part of the communications testing.
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| I COOPER NUCLEAR STATION 1990 EVALUATED EXERCISE SECTION 4.0 '
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| l o All Controllers will comply with instructions from the Lead Exercise Controller.
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| o Each controller will have copies of the messages l controlling the progress of the exercise scenario. No messages shall be delivered out of sequence or other than as written unless specifically authorized by the Lead Exercise Controller, o Controllers will D91 provide information to the Players regarding scenario progression or resolution of problems encountered in the course of the simulated emergency.
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| The r,xercise participants are expected to obtain inf:,rmation through their own organizations and exercise their own judgement in determining response actions and resolving problems.
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| o Some Players may insist that certain parts of the scenario are unrealistic. The Controllers have the sole authority to clarify any questions regarding scenario content.
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| o Ensure that all telephone, radio transmissions and public address announcements begin and and with the statement,
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| " Ibis is a drill". Remind players of the need to follow this procedure, if they fail to do so.
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| 4.3 EVALUATION INSTRUCTIONS
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| . o Each Controller will take detailed notes regarding the progress of the exercise and response of the exercise 2
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| COOPER NUCLEAR STATION 1990 EVALUATED EXERCISE SECTION 4.0 participants at their- assigned locations. Each controller should carefully note the arrival and departure times of participants, the times when major activities or ~ milestones occur, and- problem areas encountered. Controllers comments wi'' be used for the purpose of reconstructing the Exerciso chronology and preparing a written evaluation of the exercise.
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| : o. .:w. rollers are responsible for collecting of exercise documents (ef W cxercise) such as notification forms, log sheets, pi rsdure checklists, etc. used by players.
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| This documentation must be turned in to the Lead Facility Controllers at the completion of the exercise.
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| o Emergency Response Facility checklists . are taken from Attachment E of the Surveillance Procedure 6.3.11.1 of the CNS Operations Manual. these checklists must be completed by each Controller and Evaluator and provided to the Exercise coordinator at the ' conclusion of the
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| -exercise. Controller evaluation forms for each
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| . facility / team will be distributed at the pre-exercise controller briefing.
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| Y COOPER NUCLEAR STATION --!
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| 1990 EVALUATED EXERCISE.
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| SECTION 4.0:
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| -4.4 PERSONNEL ASSIGNMENTS The Personnel assignments for the controller organization are ;
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| as follows:
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| i g_ontrol Room j (LATER) t Technical Succort Center 4
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| .(LATER) ,
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| COOPER NUCLEAR STATION 1990 EVALUATED EXERCISE SECTION.4.0 e
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| ~
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| CONTROLLERS TELEPHONE LISI e
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| CONTROL ROOM TSC
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| - EOF
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| - MAINT OSC
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| -CHEM /HP CSC ELEC/I&c OSC DOWNWIND SURVEY IN-PLANT ~ TEAMS GOEC-MRC-TELEPHONE CONTROLLERS 5
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| SECTION 5.0 PLAYER INFORMATION
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| i COOPER NUCLEAR STATION 1990 EVALUATED EXERCISE-SECTION 5.0 5.O PARTICIPANT.INFORMATION 5.1 GENERAL INFORMATION This section provides information for all exercise Players.
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| 4 These guidelines should be followed throughout the conduct of the Exercise. A' pre-exercise briefing will be held for key players -to review the entire exercise process, including
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| " Precautions and Limitations" in Section 3.2, and the following information.
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| The success of the exercise is largely dependent'on player
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| (' performance, appropriate reaction to simulated emergency L conditions and~ demonstrated competence in the Emergency Plan and Implementing Procedures are the key criteria by which the players are evaluated. It is imperative, therefore, that all ;I p
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| player actions, and activities are witnessed by a controller, any actions that are to be simulated.must be brought.to the attention of the Controller to ensure that credit is awarded.
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| The-success of the exercise-is based on the demonstration of
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| .the predetermined exercise objectives.
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| l-1 5.2- PARTICIPANT GUIDELINES '!
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| 3 o Maintain a serious attitude throughout the exercise.
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| Refrain from non-business related conversations during o the exercise to help ensure that - noise levels in the emergency response facilities are maintained at an, acceptable level.
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| L l-i: o. Maintain courtesy and professionalism at all times.
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| COOPER NUCLEAR STATION 1990 EVALUATED EXERCISE SECTION 5.0 Re% ember that NRC Inspectors will also be observing and evaluaring the exercise, o Teamwork is essential! Do your job and then help other '
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| people do theirs. For example, if - you know certain information should be available, ask for it. This makes- j
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| you look good and may reduce a: deficiency for someone ,
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| else.
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| o THINK! Brainstorm and look for all possible solutions or consequences'of events. Maintain the " big picture" of what is happening.- i o Identify yourself by name and function to the . Controller in'your area.
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| Always wear your Player Identification.
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| o If'you are entering normal nuclear station radiation areas, observe all rules and procedures. No one (including Controllers) is exempt from normal station radiological practices and procedures.
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| NOTE DO NOT ENTER HIGH~ RADIATION AREAS'IN THE PLANT; !
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| ' FOLLOW ALARA PRINCIPLES.
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| o Observe all- normal security procedures. All normal' security procedures are in effect without exception. If a -security condition arises, obey immediately the
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| ' directions of Security Guards.
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| o Elements of exercise play will be introduced through use of controlled exercise messages and by information 2
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| j COOPER NUCLEAR STATION l 1990 EVALUATED EXERCISE j SECTION 5.0 I
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| I generated by Players. as a result of a particular emergency activity performed. Therefore, be responsible >
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| 1 for initjMinq actions in accordance with instructions and responsibilities. If you are unsure about the content or reaning of a message, ask the Controller for clarificatica.
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| o communications-should be concise and formal with use of abbreviations and slang terms minimized. Always include i the statement "This is a drill", a the beginning and the i and of each statement.
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| o Use and demonstrate knowledge of the Emergency Plan and Implementing Procedures. Remember to use Controlled copies only, o No response to an exercise situation will be simulated without-Controller approval. No action will be taken
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| ~that reduces the margin of safety in the plant. :l o Keep a list of items which you believe will improve the plan and/or procedures. Provide this to ~ your controller / Evaluator _at the end of the Exercise.
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| o- Remember, one of the main purposes of an exercise is for you sssure yourself that you are adequately prepared.
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| Areat for improvement or lessons learned,- when identified, will improve your overall emergency preparedness. Provide this information on your
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| " Participant Comment Form" during the facility critique.
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| SECTION 6.0 ;
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| SCHEDULE OF EVENTS 1 i
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| NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION 1990 EVALUATED EEERCISE SECTION 6.0 6.0 SCHEDULE OF EVENTS TIME LOCATION JULY 18, 1990 CONTROLLER WALKTHROUGH 01:00 PM EOF JULY 23,.1990 .
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| PLAYER BRIEFING 09:00 AM SEC. AUDIT 01:30 PM ROOM 301-302 q EVALUATOR BRIEFING 10:00 AM SEC. AUDIT 02:30 PM ROOM.301-302 l NRC ENTRANCE *02:00 PM SEC. AUDIT ,
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| NRC EVALUATOR BRIEFING *03:00 PM SEC. AUDIT JULY 25,'1990 EXERCISE-(Window) 07:00 AM ALL '
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| -04:00 PM FACILITIES FACILITY CRITIQUES FOLLOWING ALL FACILITIES CONTROLLER CRITIQUE FOLLOWING ALL FACILITIES JULY 26, 1990 MANAGEMENT BRIEFING 10:00 AM' TBA NRC CRITIQUE PRESENTATION *01:00 PM TBA NRC EXIT *02:00-PM TBA
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| * Times for NRC activities are subject to change without notice.
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| ~8ECTION 7.0 SCENARIO -l 4
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| ~SECTION 7.1 SEQUENCE OF EVENTS.
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| SECTION 7.1 EVALUATED EXERCISE JULY 25, 1990-EVALUATED EXERCISE SCENARIO SEQUENCE.OF EVENTS
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| . - . . . . - - - - - ~. - . __- .-
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| t COOPER NUCLEAR STATION 1990 EVALUATED EXERCISE EVALUATED EXERCISE SCENARIO SEQUENCE OF-EVENTS Actual- scenario Summary.
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| Time Time l 0745 -00:15. INITIAL CONDITIONS [
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| The reactor is at 100% power, and has been operating for 40 weeks. .The .
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| core is near EOL. [
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| Drywell leakage is' steady at 2.4 GPM identified and 0.5 unidentified, and has been steady for the past 3 weeks.
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| Dihsel Generator No.1 is inoperable, and in the 3rd day of a 7. day LCO.
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| Maintenance has just-found the HPCI, Steam Line High dP Indicating Switches out of tolerance and below the allowable range shown in the'- !
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| . Technical Specifications.- ~ An MWR has not yet been initiated.
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| l- All other plant systems are operable, l and in their normal configuration. ;
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| 1 L The National Weather Service at 5:001 am had issued. a Tornado Watch for-most of northeast Kansas,-northwest I Missouri, eastern Nebraska :and- !
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| western Iowa. Nemaha County --is -
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| included in this watch. The forecast
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| ! calls for rain with ' isolated and l; possible severe thunderstorms. Winds'. ,
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| L are out:of the southwest at,10. MPH gusting to 20 MPH. The temperature. '
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| is expected to reach a high in the mid to upper 90s. .
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| ! A van has been loaded in the Radwaste l' bay for shipping end disposal of ~
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| 1Section 7.1 07/25/90 i
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| h COOPER NUCLEAR STATION 1990 EVALUATED EXERCISE EVALUATED EXERCISE SCENARIO SEQUENCE OF EVENTS Actual Scenario Summary Time Time radioactive trash. The van contain a 15 LSA crates of compactible and non-compactible radioactive trash. The van is in the process of being moved to the security pen.
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| n Section 7.1 07/25/90 l
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| COOPER NUCLEAR STATION 1990 EVALUATED EXERCISE -
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| EVALUATED EXERCISE SCENARIO SEQUENCE OF EVENTS Actual Scenario Summary Time Time 0800 -00:00 Initial conditions are established.
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| Commence the Cooper Nuclear Station i 1990 Evaluated Exercise.
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| 0815 00:15 Radwaste truck has been moved'to the pen to be processed out by Security. '
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| While they are inspecting the truck, i Security sights a tornado headed -
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| towards tte s4te. -
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| They inform the Control Row , .tnd advise that they.
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| are ta Meg - shelter. immediately.
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| Operatio n attempts to start Diesel Generator No. 2-in accordance with ,
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| EP 5.1.2, but is unsuccessful, t 0820 00:20 The tornado hits the site and causes ,
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| loss of all offsite power. The loss of offsite power, coupled with the >
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| SITE AREA EMERGENCY unavailability of both Diesel-Generators, meets the criteria for declaration of a SITE AREA EMERGENCY. j l 0830 00:30 Security reports'that a portion of I the security fence.has been knocked down, and that the radwaste shipping van body is missing. The truck-cab. ,
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| is laying.on its side, just inside l the protected area. They tell the L ' Control Room that they can see several containers on the ground.
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| Security also informs the Control 1 Room that they see what appears to be substantial damage, but the danger appears to have passed now.
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| 0845 00:45 to A search.is initiated onsite for the L
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| 01:20 van body.
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| Section 7.1 07/25/90 l
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| !)F COOPER NUCLEAR STATION 1990 EVALUATED' EXERCISE t
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| EVALUATED EXERCISE SCENARIO SEQUENCE OF EVENTS Actual Scenario Summary ,
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| Time Time t
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| Attempts. to start Diesel Generator No. 2 continue to be unsuccessful.
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| The 345 KV switchyard has suffered <
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| extensive damage. Bus bar is damaged between ACBs 3310 and 3312. ACB'3304 is also damaged. The Startup Station Service Transformer disconnect support structure is down. The 69.
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| ,.s KV OPPD line is down.
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| The Radwaste van is found on the owner controlled property, northeast of the meteorological towers. The van is heavily damaged with two~ (2) crates still inside. Six -(6) additional crates,are found on the ground, in the general area. Two (2) of these containers have also been heavily damaged, with yellow material
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| .round the crates. The
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| : laying remaining four (4) have suffered only -t j- , minor damage.
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| 1000 02:00 The RCIC Turbine trips on overspeed, and cannot be reset from the Control _;
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| Room. .
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| ;. 1015 02:15 to The RCIC Turbine mechanical overspeed 02:30 mechanism is relatched. RCIC is returned to . service to- maintain reactor water. level.
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| [ -'
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| 1130 03:30 One (1) LSA Crate is found partially submerged, but still visible in the-l Missouri River (west bank) . The
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| :. crate is too heavy to be removed =by a small boat, but appears to be undamaged.
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| Section 7.1 07/25/90
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| l COOPER NUCLEAR STATION 1990 EVALUATED EXERCISE EVALUATED EXERCISE SCENARIO SEQUENC'1 0F EVENTS Actual. Scenario Summary Time Time 1230 04:30 Diesel. Generator No. 2 is repaired by the repair team. Operations starts Diesel Generator No. 2 and ties it to 4160v Bus 1G. The ALERT restoration of onsite power meets the criteria to downgrade from a' SITE AREA. EMERGENCY to an ALERT.
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| Two (2) LSA crates are found in Missouri, approximately one mile northeast of -the plant. One . (1) container ,is hea 'ily damaged with yellow material laying around the .t crates. The other container is only slightly damaged.
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| l' l 1330 . 05:30 Operators continue RHR. operation to L remove-decay heat from containment, v l and also continue efforts to attain '
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| L cold shutdown.
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| 1 One (1) LSA crate _'is found in i
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| Missouri, approximately _ two miles ,
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| L northeast of tho' plant. The container is heavily damaged with l
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| yellow material . laying around the 1 crates. ,
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| 13-l- .1430 06:30 Operators have the Plant stabilized.
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| L one (1) LSA crate is found in- !
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| l Missouri,_approximately three miles northeast ,of the plant. The .I container is heavily. damaged with !
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| yellow material laying around the crates, i
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| Section 7.1 07/25/90 i
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| COOPER NUCLEAR STATION 1990 EVALUATED EXERCISE EVALUATED EXERCISE SCENARIO. SEQUENCE OF EVENTS Actual scenario summary Tire Time i
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| A recovery organization is established.
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| Recovery planning. is initiated ~ with
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| , l long term organization and response plans formulated.
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| 1530 07:30 The 1990 Cooper Nuclear -Station ,
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| Evaluated Exercise is terminated. .
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| :n Section'7.1 07/25/90
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| HECTION 7.2 MASTER EVENTS
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| ==SUMMARY==
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| (To BE ADDED IN FINAL PACKAGE)
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| s.
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| SECTION 7.3 NARRATIVE
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| ==SUMMARY==
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| --------.---i.-- . . .
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| 1 COOPER NUCLEAR STATION 1990 EVALUATED EXERCISE NARRATIVE
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| ==SUMMARY==
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| This scenario is based on a STATION BLACKOUT (SBO) event.
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| Consistent with the expected plant response during an actual SBO l event of similar duration, core damage is not postulated to occur l during the course of this exercise. The scenario sequence of events meets the emergency action level for declaring a site Area Emergency (SAE).
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| Initial plant conditions establish the plant at 100 percent power and near EOL. Diesel Generator No. 1 is under LCO for repair.
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| Technicians have just reported finding the HPCI Steam Supply Line dP. switches set too low, and they are processing the paperwork to correct this. A radwaste ~ van is being processed out through security.
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| The National Weather Service has indicated that' atmospheric conditions are favorable for tornado development, and the area has been placed under a TORNADO WATCH.
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| Drill activities start when security reports sighting a tornado rapidly approaching the site. Security indicates that they are taking cover.
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| The tornado hits the site, and knocks out all above ground AC power to the plant. The operable Diesel Generator No. 2 starts, but trips before it ties to the bus. The contents of the radwaste truck are dispersed as the vehicle is tossed by the tornado. The strong wind tears off a portion of the turbine building as well.
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| A Site Area Emergency is declared after loss of all AC power.
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| The Control Room maintains reactor water level with RCIC in accordance with EOP's. The reactor is in hot shutdown following ,
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| the loss of AC power, and is stable.
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| Shortly, the Emergency Response facilities are staffed and
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| ,. activated. Onsite personnel accountability is completed. Security I responds to secure a portion of the perimeter fencing knocked down by the tornado.
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| Teams are dispatched to assess the damage to the switchyard and the reason for the diesel generator failure. A search is-initiated for the radwaste containers.
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| Conditions improve as the failed Diesel Generator No. 2 is repaired, started, and tied to the bus. Operators start the equipment necessary to remove decay heat from primary containment.
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| !- The News Center is activated.
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| l l Some time later, Field Teams report on the ' radwaste container l inventory and location. They lay out their recovery plan, and the I. plans to search for any remaining containers, t-
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| l SECTION 8.0 MESSAGES.AND PLANT DATA l-l 1
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| i SECTION 8.1 PLANT MESSAGES 1
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| .t 1990 EVALUATED EXERCISE TIME = 0745 Message Number 12__ t = - 00:15 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAQI Messace fort Control Room Simulated Plant Conditions _! See attached Plant Data Messaae:
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| 1
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| **** THIS IS A DRILL ****
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| Initial Conditions are as follows:
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| o .The reactor:is at 100% power, and has been operating for 70 weeks. The core is near EOL, and has been ,
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| I exposed ~for 466 days.
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| l o Drywell-identified leakage is 2.4 gpm. Drywell i unidentified-leakage is 0.5 gpm, and has bean steady t for the past 3 weeks.
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| o Diesel Generator No. 1 is in the third day of an LCO due to a problem with a generator bearing. The . -!
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| generator is dismantled, but maintenance crews have
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| ; been working 24 hours per day to make the repair.
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| L Latest estimates from Maintenance indicate that they l expect work to be completed in approximately-48 hours.
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| l o A.radwaste van has just been loaded. It is-being processed out by Security.
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| l
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| : o. HPCI surveillance was run satisfactorily -about an hour ago, except for what appeared to be a spurious High ;
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| Steam'Line dP annunciator which was received-twice
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| .during the run. HPCI steam line isolation did not occur, nor did the turbine trip. I&C-Technicians have
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| .just completed a preliminary investigation into the reason for the annunciator and have informed the Shift Supervisor that they suspect the dP switches were set.
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| too low after replacement last month. They cannot explain why this has not come to light sooner.
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| o All other plant systems are operable and in their normal operating configuration C .i
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| I o The weather forecast calls for rain with isolated-and possibly severe thunderstorms. Winds are out of the southwest at 20 MPH, gusting to 30 MPH. The temperature is expected to reach a high in the mid to upper 90s.-At 6:00 am, the National Weather Service has issued a Tornado Watch for most of northeast Kansas, northwest
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| = Missouri, eastern Nebraska and' western Iowa, effective until-11:00 am. Hemaha County is included in this ,
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| watch.
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| I 1 TIME = 0745 1990 EVALUATED EXERCISE Message Number IC t = - 00:15 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE FOR CONTROLLER USE ONLY i
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| i Controller Information:
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| o obtain S.S. approval signature on Procedure 6.3.11.1.
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| o Deliver Initial Conditions to the Control Room' exercise players. Explain abbreviations and acronyms. Review the data to ensure that all players understand the Initial Conditions.
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| o Conduct a pre-exercise. briefing. Explain that any
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| -player dispatched into the plant must first.go to the TSC to pick up a: controller. ,
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| .o Discuss;the rules for conduct of the exercise,
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| ' including what simulations will be allowed.
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| o Make:sure thaticontroller clocks are synchronized. J Expected Actions:
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| : o. Players should acknowledge understanding of the Initial Conditions.
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| ~1990 EVALUATED EXERCISE TIME =-0745-M:ssage Number _Is_ t = -00:15 L
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| COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT _pATA PANEL 9-3 PANEL _9_-5 STATUS PRESS (psig) ELQH(gpm) REACTOR POWER 12.Q_ % APRM :
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| RHR A STBY 50 0 REACTOR LEVEL _.2jl., " GEMAC :
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| RHR C STBY SO 0 REACTOR PRESS 99.8_- psig 8
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| RHR B STBY 50 0 ELOW (10 lbs/hr)
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| RHR D STBY 50 0 FEEDWATER A 131.
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| CS A STBY 50 0 FEEDWATER B ita_
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| CS B STBY 50 0 MAIN STEAM A 131_
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| lHPCI STBY 50 0 MAIN STEAM B Lul_
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| MAIN STEAM C 2,.ui DRYWELL PRESS. 0.25 psig MAIN STEAM D 2.3 TORUS LEVEL 122 8 ft CRD A FLOW L gpm CRD B FLOW 9 _ gpm QEIH CLOSED _
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| SLC TK LEVEL a.0_ %
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| MSIV STATUS 8 0 :
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| SLC PMP DISCH PRESS A 0 psig SLC PMP DISCH PRESS B o psig PANEL 9-4 MISCELLANEOUS PANELS STATUS PRESS (psig) ELQH(gpm) 4
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| .RCIC' STBY 50 0 DIESEL GEN 1 INOP .:
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| RWCU A AVAIL 0 0 DIESEL GEN 2 STBY :
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| RWCU B' OPER 1180 160 SBGT A STBY :
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| RRP A 100 % SPEED SBGT B STBY :
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| RRP B 100 % SPEED DRYWELL COOLING OPER :
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| TORUS WATER TEMP 88 F DRYWELL TEMP 116 *F
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| | |
| RADIATION MoHITORS 1990 EVALUATED EXERCISE- TIME = 0745 t= -00:15 STATION DESCRIPTI_ON READING (mR/hr) 1 Rx Bldg Fuel Pool Area (SE Sth Floor) 154 2 Rx Bldg Fuel Pool Area (SE Sth Floor) 1.5 3 Rx Bldg New Fuel Area (SE 5th Floor) .03 4 Rx Bldg Rx Water Cleanup Demineralizer 13.5 Area (SW 3rd Floor) 5 Rx Bldg Sludge and Decant Pump Area 0.8 (S 2nd Floor) 6 Rx Bldg Neutron Monitor System Index 164 Area (TIP Room 1st Floor) 7 Rx Bldg Neutron Monitor System Drive 1.8 Mech Area (SE 1st Floor) 8, Rx Bldg Control Rod Hydiculic Equipment .9 Area (S ist Floor) 9 Rx Bldg Control Rod Hydraulic Equipment 9 Area (N ist Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) .3 11 Rx Bldg RHR Pump Room (SW Ouad) 5.5 12 RX Bldg RHR Pump Room (NW Juad) __ 2 4 13 Rx Bldg RCIC/CS Pump Roor. (NE Quad) 2 14 Rx Bldg CS Pump Room (SF Quad) 4.5 15 Turbine Bldg Turbine Frant Standard 131 16 Turbine Bldg Mezz Control Corridor .17 17 Turbine Bldg Basement Control Corridor .05 18 Turbine Bldg Rx Feed Pump Area 6 19 Turbine Bldg Condensate Pump Area .12 20 Control Rocm Main Control Room .02 21 Grade Level Control Corridor .2
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| -22 'Radwaste Control Room .02 23 Radwaste Pump Room 5. 3-24 Radwaste Basement Equipment Area ~ 4 25 Radwaste Demineralizer Valve Room 1.2 26 Radwaste Conveyor Aisle operating Area 0.2 27' SPARE 28 Radwasta Lab Area 0.1 29 Centrifuge East 10 30 Centrifuge West 9 Panel 9-02 Personnel Airlock Area 903' 12 R/hr Panel 9-02 Ladder 903' to 2nd Level 7 R/hr OSH = offscale High
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| | |
| , RADIATION MONITORS p 1990 EVALUATED EXERCISE TIME = 0745 i t= -00:15 i PANEL VBDG -
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| Rx Bldg Vent Eff (RMV-RM-40 1.0E-3 uci/sec l ERP Stack Normal EFF (RMF-RM-3A) 5.5E-1 uci/see ERP Stack High Range (RMP-RM-3B) o uci/soe .
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| Turbine Bldg Vent Eff (RMV-RM-20A) 1.5E-3 uci/see Turbine Bldg !!igh Range (RMV-RM-208) o uci/sec ;
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| RW/ARW Bldg Combined Eff (RMV-RM-30A) 1.SE-3 uci/sec _
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| RW/ARW Bldg High Range (RMV-RM-30B)
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| I o _uci/see PANEL 9-10 ,
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| Main Steam Rad Monitor Ch. A1, B1 3_50 mR/jlt,.110 mRM I __ !
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| CH. A2, B2 300 mR/hr 170 mR/hr 3JAE Off Gas Log Rad Monitor Ch. A, B 3 5 mPiDL li5 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hr A 6 mR/hr 5
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| 5 t
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| .. ,- . . , , . _ - . . , %... _.. , , .,._ .m
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| b e 1990 EVALUATED EXERCISE TIME = 0800 Message Number _A1_ t = 00:00 COOPER RUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE 5
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| Messace fort Control Roos Simulated Plant Conditionst See attached Plant Data Messacet
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| **** THIS IS A DRILL ****
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| Make the following PA announcement:
| |
| "Attentivn all personnel. We are now commencing the 1990 Cooper Nuclear Station Emergency Preparedness Evaluated Exercise. All announce' :nts prefaced by 'This is a drill' are intended for desigtated drill participants only. If an actual emergency occurs during the course of the drill, an announcement will be made which will identify the actual emergency situation" (Repest this announcement once)
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| {'
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| y
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| -~.. -
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| 1990 EVALUATED EXERCISE TIME = _.0800 Message Number 01 t= 00:00 GOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE FOR CONTROLLFR USE ONLY:
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| Controller Information!
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| o Ensure that the PA announcement is made to begin the exercise.
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| Expected Actions o Operators should respond to the TORNADO WATCH by directing personnel to look for and secure any loose ,
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| equipment about the site.
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| o A discussion should be initiated regarding the problem with the HPCI steam line dP switches, HPCI operability, and Technical Specification applicability.
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| | |
| 1990 EVALUATED EXERCISE TIME = 0800 fM:ssage Number _Q1_ t= 00:00 COOPER NUCLEAR STATION EMERGENCY PREPAREQNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS EP' ws.n 319) ELQH(gpm) REACTOR POWER 100. % APRM :
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| RHR A STBY , JO O REACTOR LEVEL _21. " GEMAC :
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| RHR C _STBY __, f 0 REACTOR PRESS 998 psig RHR B STBY sc 0 ELQH (10^61bs/hr)
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| RHR D _STBY 50 0 FEEDWATER A ix1_
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| CS A STBY 50 0 FEEDWATER B A2a_ [
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| CS B STBY 50 0 MAIN STEAM A 2.d !
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| HPCI STBY 50 0 MAIN STEAM B 2 A ;
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| MAIN STEAM C 2.4_
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| DRYWELL PRESS, 0.25 psig MAIN STEAM D 2.d_
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| TORUS LEVEL 12.8 ft CRD A FLOW iq__ gpm CRD B FLOW 0 gpm QEIH CLOSED SLC TX LEVEL _.Q.Q_ %
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| MSIV STATUS 8 0 :
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| SLC PMP DISCH PRESS A 0 psig
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| $LC PMP DISCH PRESS B 0 psig PANEL 9-4 MISCELLANEOUS PANELS STATUS PRESS (psig) ELQH(gpm) l RCIC STBY 50 0 DIESEL GEN 1 INOP :
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| l
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| 'RWCU A AVAIL 0 __
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| 0 DIESEL GEN 2 STBY :
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| l RWCU B. OPER 1180 160 .;0GT A STBY :
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| l' 1 RRP A 100 % SPEED SBGT B STBY :
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| 1 i
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| RRP B 100 % SPEED DRYWELL COOLING OPER :
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| TORUS WATER TEMP 88 F DRYWELL TEMP 116 F
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| -~ _
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| RADIATION MONITORS 1990 EVALUATED EXERCISE TIME = 0800 t= 00:00 STATION DISCRIPTION READING _ ap A/hr) 1 Rx Bldg Fuel Pool Area (SE Sth Floor) 154 2 Rx Bldg Fuel Pool Area (SE Sth Floor) 1.5 3 Rx Bldg New Fuel Area (SE Sth Floor) .03 4 Rx Bldg Rx Water Cleanup Demineralizer 13.5 Area (SW 3rd Floor) 5 Rx Bldg Sludge and Decant Pump Area 0.8 (S 2nd Floor) 6 Rx Bldg Neutron Monitor System Index 164 Area (TIP Room ist Floor) 7 Rx Bldg Neutron Monitor System Drive 1.8 Mech Area (SE 1st Floor) 8 Rx Bldg control Rod Hydraulic Equipment .9 __.
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| Area (S 1st Floor) 9 Rx Bldg Control Rod Hydraulic Equipment 9 Area (N ist Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) .3 11 Rx Bldg Ri!R Pump Room (SW Quad) 5.5 ;
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| Rx Bldg RHR Pump Room (NW Quad) 24 12 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 2 14 Rx Bldg CS Pump Room (SE Quad) 4.5 ,_,
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| 15 Turbine Bldg Turbine Front Standard 131 16 Turbine Bldg Mezz Control Corridor .17 17 Turbine Bldg Basement Control Corridor .05 18 Turbine Bldg Rx Feed Pump Area 6 19 Turbine Bldg Condensate Pump Area .12 20 Control Room Main Control Room .02 21 Grade Level control Corridor .2 22 Radwaste Control Room .02 23 Radwaste Pump Room 5.3 24 Radwaste Basement Equipment Area 4 25 Radwaste Domineralizar Valve Room 1.2 26 Radwaste Conveyor Aisle Operating Area 0.2 _.
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| 27 SPARE !
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| 28 Radwaste Lab Area 0.1 i 29 Centrifuge East 10 30 Centrifuge West 9 Panel 9-02 Personnel Airlock Area 903' 12 R/hr Panel 9-02 Ladder 903' to 2nd Level 7 R/hr OSH = Offscale High
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| | |
| RADIATION Moti1 TORS .
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| 1990 EVALUATED EXERCISE TIME = 0800.
| |
| t= 00:00 i
| |
| E]WIL VBDG Rx Bldg Vent Eff (RMV-RM-40 1.0E-3 uci/see '
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| ERP Stack Normal EFF (RMP-RM-3A) 5.5E-1 uci/see ERP Stack High Rango (RMP-RM-3B) o uci/see Turbine Bldg Vent Eff (RMV-RM-20A) 1.5E-3 uci/swe Turbine Bldg High Range (RMV-RM-20B) 0 uci/see RW/ARW Bldg Combined Eff (RKV-RM-30A) 1.5E-3 uCi/see RW/ARW Bldg High Range (RMV-RM-30B) 0 uCi/see PANEL 9-10 Main Steam Rad Monitor Ch. A1, B1 350 mR/hr 350 mR/hr CH. A2, B2 300 mR/hr 270 mR/hr SJAE off Gas Log Rad Monitor Ch. A, B 35 mR/hr 25 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hr 0.6 mR/hr r
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| ?
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| l
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| 1990 EVALUATED EXERCISE TIME = 0810 Message Number _22_ t = 00:10 COOPER RUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAqE Messane fort Security Messacet_
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| **** THIS IS A DRILL ****
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| o A Radwaste shipment truck is in the pen to be processed out.
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| o You see a tornado headed directly for the site; it is approaching very rapidly, i
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| .1 I
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| I I
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| 1990 EVALUATED EXERCISE TIME = 0810 l I
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| Message Number 02 t= 00:10 !
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| )
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| COOPER NUCLEAR STATION g i
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| EMERGENCY PREPAREDNESS EXERCISE MESSAGE l
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| -i FOR CONTROTIFR USE ONLYt ;
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| i
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| ' Controller Informations !
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| o- Security BMAX notify the Control Room of the approaching-tornado within 2 to 3 minutes. l 1
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| Expected Actions:
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| l o security personnel notify the main Control Room of the approaching-tornado. ;
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| t
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| = , - - - -
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| 4 3 , . - -,=- e r v-r- w *- - e* '-e--w*-
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| | |
| i i
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| r s 1990 EVALUATED EXERCISE TIME = 0815' !
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| +
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| . Message Number _21_ t = 00:15 -
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| COOPER NUCtrAR STATION !
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| EMERGENCY PREPAREDNESS EXERCISE MESSAGE !
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| L' *
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| !=
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| )
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| t Messaae fort Control' Room.
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| simulated Plant conditionst .See attached Plant Data 't n i
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| /4 .r
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| ?
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| L Message:
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| i i
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| **** THIS IS A' DRILL **** ,
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| i f
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| 'I I t I
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| a;:' ' '
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| s
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| 1f L
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| . ... . . - . . .- - - - . . - . - . . . .. . - - . - . ~ .-. ,.
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| | |
| 1990 EVALUATED EXERCISE TIME = 0815 Message Number _21__ t = 00:15 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE FOR CONTROLLER USE ONLY:
| |
| Controller Informations o Security notifies the Control Room of an approaching tornado. This constitutes a Tornado Warnina, o operators attempting to start Diesel Generator No. 2 are to be given MESSAGE No. 03C, the Diesel trip message. If they have not attempted a start prior to 00:20, give them the message at that time.
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| o The inoperability of both Diesel Generators meets the criteria for NOTIFICATION OF UNUSUAL EVENT, but there will probably not be time to recognize this and make the declaration before all AC power is lost at 00:20.
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| Expected Actions:
| |
| o Any Operators which may have been dispatched to secure equipment in accordance with Emergency Procedure 5.1.2 should be recalica, or advised to seek shelter.
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| o The Operators should announce the Tornado Warnina, o operators should attempt to start Diesel Generator No.
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| 2.
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| o operators should obtain, and start to review, Emergency Procedures 5.2.5 and 5.2.5.1.
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| o operators should refer to EPIP 5.7.1 to determine if declaration of an EAL is appropriate.
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| E .
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| 1990 EVALUATED EXERCISE TIME = 0819
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| -Message Number _D1_ t= 00:15 COOPER NUCLEAR STATION I
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| EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) TICW(gpm) REACTOR POWER 12A_ % APRM :
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| RHR A STBY 50 0 R23CTOR LIVEL _11_ " GEMAC : }
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| RHR C STBY 50 0 REACTOR PRESS 998 psig RHR B STBY 50 0 FLOW (10^61bs/hr)
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| I RHR D 'STBY 50 0 FEEDWATER A 1.tS._
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| i CS A _S.TE. (_._ 50 0 FEEDWATER B A.i.lL.
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| CS B . STB C 50 0 MAIN STEAM A 1 A_
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| HPCI _EIf Y 50 _
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| 0 MAIN STEAM B 2._1 MAIN STEAM C 121_
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| DRYWELL PMESS. 0.25 psig MAIN STEAM D lui_
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| TORUS LEVEL 12.8 ft CRD A FLOW iQ__ gpm CRD B FLOW 0 gpm QEIH CLOSED SLC TK LEVEL 1Q_ % '
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| MSIV STATUS 8__ ,
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| O :
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| SLC PMP DISCH PRESS A 0 psig SLC PMP DISCH PRESS B 0 psig PANEL 9-4 MISCELLANEOUS PANELS ,
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| STATUS PRESS (psig) ELQH(gpm) l RCIC STBY 50 0 DIESEL GEN 1 INOP RWCU A AVAIL 0 0 DIESEL GEN 2 STBY :
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| RWCU B OPER 1180 160 SBGT A -STBY :
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| RRP A '100 % SPEED SBGT B STBY :
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| RRP B 100 % SPEED DRYWELL COOLING OPER' :
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| TORUS WATER TEMP 88 F -
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| 1 1
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| DRYWELL TEMP 116 F l
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| RADIATION MONITORS 1990 EVALUATED EXERCISE TIME = 0815 2 t= 00:15 STATION DESCRIPTION READING (mR/hr) l 1 Rx Bldg Fuel Pool Area (SE Sth Floor) 154 !
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| 2 Rx Bldg Fuel Pool Area (SE Sth Floor) 1.5 3 Rx Bldg New Fuel Area (SE 5th Floor) .03 4 Rx Bldg Rx Water Cleanup Demineralizer 13.5 Area (SW 3rd Floor) 5 Rx Bldg Sludge and Decant Pump Area 0.8 .
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| (S 2nd Floor) 6 Rx Bldg Neutron Monitor System Index 164 Area (TIP Room ist Floor) 7 Rx Bldg Neutron Monitor System Drive 1.8 Mech Area (SE 1st Floor)
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| * 8 Rx Bldg Control Rod Mydraulic Equipment .9 Area (S lat Floor) 9 Rx Bldg Control Rod Hydraulic Equipment 9 Area (N ist Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) .3 11 Rx Bldg RHR Pump Room (SW Quad) 5.5 12 RX Bldg RER Pump Room (NW Quad) 24 13 RX Bldg RCIC/CS Pump Room (NE Quad) 2 l 14 Rx Bldg CS Pump Room (SE Quad) 4.5 ,
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| 15 Turbine Bldg Turbine Front Standard 131 _
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| 16 Turbine Bldg Mezz Control Corridor .17 17 Turbine Bldg Basement Control Corridor .05 18 Turbine Bldg Rx Feed Pump Area 6 19 Turbine Bldg Condensate Pump Area .12 20 Control Room Main Control Room .02 21 Grade Level Control Corridor .2 22 Radwaste Control Room .02 23 Radwasta Pump Room 5.3 24 Radwastu Basement Equipment Area 4 25 Radwaste Domineralizer Valve Room 1.2 26 Redwaste conveyor Aisle operating Area 0.2 27 SPARE 28 Radwaste - Lab Area 0.1 29 Centrifuge East 10 30 Centrifuge West 9 l
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| l Panel 9-02 Personnel Airlock Area 903' 12 R/hr Panel 9-02 Ladder 903' to 2nd Level 7 R/hr l
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| OSH = Offscale High t
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| e r
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| RADIATION MONITORS 1990 EVALUATED EXERCISE TIME = 0815 t= 00:15
| |
| )
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| PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40 1.0E-3 uci/sec ERP Stack Normal EFF (RMP-RM-3A) 5.5E-1 uci/see ERP Stack High Range (RMP-RM-3B) 0 uCi/see Turbine Bldg Vent Eff (RMV-RM-20A) 1.5E-3 uCi/sec l Turbine Bldg High Range (RMV-RM-20B) o uci/soe__
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| RW/ARW Bldg Combined Eff (RMV-RM-30A) 1.5E-3 uci/see
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| ' RW/ARW Bldg High Range (RMV-RM-30B) o uci/see PANEL 9-10 Main Steam Rad Monitor Ch. A1, B1 350 mR/hr 350 mR/hr CH. A2, B2 300 mR/hr 270 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 35 mR/hr 25 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hr 0.6 mR/hr l
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| l
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| It may take an hour or more to determine that the fuel oil booster pump is the problem. Based on the Annunciator Response Procedure 2.3.2.42, l troubleshooting should cover the starting air system, the fuel oil system (including filters) and the starting logic.
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| j C. Restoration Guidelines Diesel Generator No. 2 repair is not allowed until !
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| 04:30. At that time maintenance can notify the control !
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| Room that repair is completed, and that the Diesel should be ready to start.
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| Once the cause of the zero oil pressure is determined )
| |
| to be the fuel oil booster pump motor, contingency messages will be used to provide the specific failure mode, depending on the time remaining until 04:30 into the Exercise:
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| i ling SDecific Fault l 10 - 15 mins. Brush binding in the brush holder. i 30 - 45 mins. Lug separated from conductor in ;
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| connector box.
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| 2-4 hours open winding in motor. They could ,
| |
| get a replacement motor from the warehouse, or they could take the- ,
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| one from the inoperable-DG #1.
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| I
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| )
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| l l
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| 1.
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| i W-
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| SUPPLEMENTAL SCENARIO No. 1 FAILURE OF DIESEL GENERATOR #2 TIMEt Scenario time 00:15 through 04:30 LOCATION: Diesel Generator Room No. 2 A. Initial Notification Early in the Exercise, Control Room operators are made aware that Diesel Generator #2 will not start and tie tothebus(MESSAGENO.ggjf). .. a.s h
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| * operators may be given the failure message if and when they attempt to manually start DG #2 due to the Tornado
| |
| ; Warning, otherwise, the message will be given when AC L
| |
| power is lost and the "G gets an automatic start signal on bus undervoltage.
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| B. Postulated Event ;
| |
| A failure occurs which will prevent Diesel Generator ,
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| No. 2 from being tied to the bus. This failure will render Diesel Generator #2 inoperable for approximately l 4 hours and 15 minutes. The problem is fixed at the end of that time, allowing the Diesel to be started. i The postulated failure is that of the fuel oil booster pump. With zero fuel oil pressure, the Diesel fails to reach 280 rpm in 20 seconds. As a result, an automatic shutdown occurs when control air dumps.
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| The Main Control Room will receive the. INCOMPLETE SEQUENCE and DG #2 TROUBLE annunciators when the Diesel !
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| start is attempted. They will have to dispatch an Operator to attempt to. start the Diesel locally.
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| At the Diesel, there will be a FAILURE TO START annunciator on the local panel. The only abnormal indication to the local operator will be zero fuel oil pressure (there is no annunciator for this). The local operator can only see that there is no fuel oil pressure when attempting a manual start, or when attempting to run the fuel oil booster pump manually (he would have red and green lights to indicate whether the pump was running or not).
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| i
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| l J
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| . 1990 EVALUATED EXERCISE TIME = +0810 -
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| :\ ' ,
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| , Message Number 03c t = 00:10 00:20 COOPER RUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Messaae for? Control Room Messacet ,
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| y
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| **** THIS IS A DRILL **** ,
| |
| o The INCOMPLETE SEQUENCE annunciator is lit.
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| o The DG # 2 TROUBLE annunciator is lit.
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| r 9
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| 0 v
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| Y i
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| q .
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| I 1990 EVALUATED EXERCISE TIME = 0820 .
| |
| 1 Message Number 04 t = 00:20 COOPER NUCLEAR STATION ;
| |
| EMERGENCY PREPAREDNESS EXERCISE MESSAGE Messaae forl Control Room i
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| Simulated Plant conditions: See attached Plant Data Messacet
| |
| **** THIS IS A DRILL **** ,
| |
| o The Main Turbine-Generator has tripped.
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| o All of the green control Rod full-in lights on Panel r 9-5 are lit.
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| o At least one valve indicating light for each line on the Primary Containment mimic on Panel 9-3 is green, ,
| |
| except for RCIC, which is operating. .i
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| {
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| o The following annunciators are lit: 1 HPCI ISOL SIG A/B INITIATED HPCI STEAM LINE D/P HPCI TURB TRIPPED START-UP STATION SERV TRANSFMR SECONDARY UNDERVOLTAGE l
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| EMERG STATION SERVICE TRANSTMR SECONDARY UNDERVOLTAGE' l 345 KV SWYD TROUBLE l ACB 3302 AUTO TRIP ACB 3304 AUTO TR*- .
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| ACB 3308 AUTO TRIP 1 I PMIS UPS SYSTEM TR',UBLE
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| F .
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| I 1990 EVALUATED EXERCISE TIME = 0820 Message Number 04 t = 00:20 COOPER NUCLEAR STATION ,
| |
| EMERGENCY PREPAREDNESS EXERCISE MESSAGE FOR CONTROLLER USE ONLY:
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| Controller Informations o The tornado does extensive damage to the switchyard.
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| offsito power will not be restored during the course of '
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| the Exorcise.
| |
| o The failure of all normal and emergency AC power supply transformers, coupled with the fail':re of the only operable Diesel Generator, results n. a Station Blackout.
| |
| The loss of all onsite and offsite AC power will ultimately result in the declaration of a SITE AREA EMERGENCY (once the total loss of AC power has lasted >
| |
| longer. than 15 minutes) . However, an ALERT may be declared within the next 15 minutes.
| |
| o Diesel Generator No. 1 cannot be repaired and used '
| |
| during the course of the Exercise.
| |
| o only those systems, components, controls and instrumentation powered by DC or NBPPs will be '
| |
| available until AC pover is restored. A great deal of the instrumentation upon which the operators usually rely to make decisions will not be available.
| |
| o Hastings control Center (is/is not) playing. Therefore, calls to this location should not be simulated.
| |
| o The attached graphs indicate the expected changes in -
| |
| DRYWELL PRESSURE, TORUS LEVEL, and TORUS WATER TEMPERATURE.
| |
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| e t
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| i 1990 EVALUATED EXERCISE TIME = 0820
| |
| * i Mesonge Number 04 (Page 2) t = 001.20 )
| |
| COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE 1
| |
| FOR CONTROLLER USE ONLY: (continued) s Expected Actions o The operators should respond to the event in accordance '
| |
| with Emergency Procedures:
| |
| - Pull-to-lock Breakers 1AS, 1BS, 1FS, 1GS, EG1 and EG2.
| |
| - Manually open condenser vacuum breakers.
| |
| - Attempt to start Diesel Generator No. 2.
| |
| o RCIC will be operated to maintain reactor water level.
| |
| o A discussion should take place relative to declaration of an ALERT and/or a SITE AREA EMERGENCY.
| |
| o A discussion should take place shortly relative to informing the Hastings Control Center, so that NPPD operating Transmission Instruction #7 may be instituted.
| |
| o operators will likely dispatch an operator to Diesel Generator No. 2 after they cannot get it to start from '
| |
| the Control Room. However, this may not occur until 00:30, when Security notifies the Control Room that the danger from the tornado appears to have passed.
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| i 1990 EVALUATED EXERCISE TIME = ..0820 f t= 00 20 M;2:: age Number _21_
| |
| COOPER NUCLEAR STATION I
| |
| EMERGENCY PREPAREDNESS EXERCISE PLANT DATA i l
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| PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) ELQH(gpm) REACTOR POWER 0 % SRM :
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| TRIP 0 0 REACTOR LEVEL o " GEMAC_: j RHR A RHR C TRIP 0 0 REACTOR PRESS 1010 psig l RHR B TRIP 0 0 ELQH (10' lbs/hr) !
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| 0 0 FEEDWATER A 0 : I RHR D TRIP !
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| TRIP 0 FEEDWATER B 0 :
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| CS A O 0 0 MAIN STEAM A 0 :
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| CS B TRIP ,_
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| ISOL 50 0 MAIN STEAM B 0 :
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| HPCI MAIN STEAM C 0 :
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| DRYWELL PRESS. O psig ,
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| MAIN STEAM D 0 :
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| TORUS LEVEL 0 ft CRD A FLOW IRIE gpm CRD B FLOW IB12 gpm QEIH CLOSED SLC TK LEVEL 0 %
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| MSIV STATUS 0 8 :
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| SLC PMP DISCH PRESS A 0 psig SLC PMP DISCH PRESS B 0 psig PANEL 9-4 MISCELLANEOUS PANELS ,
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| l STATUS PRESS (psig) ElQH(gpm)
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| OPER 1150 400 DIESEL GEN 1 INOP :
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| l RCIC' TRIP 0 0 DIESEL GEN 2 TRIP :
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| .RWCU A.
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| 0 SBGT A TRIP :
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| RWCU B TRIP 0 TRIP SPEED SBGT B TRIP :
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| RRP A % 1 TRIP SPEED DRYWELL COOLING TRIP :
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| l RRP B %
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| TORUS WATER TEMP 92 *F DRYWELL TEMP 121 'T
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| | |
| DRYWFI I PRESS NCREASE - 1990 EXERCISE COOFDt IS8 CLEAR STATM)N
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| TORUS LEVEL NCREASE - 1990 EXERCISE-NlEACIEAR STATIOps M
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| 1990 EVALUATED EXERCISE TIME = 0830 Message Number _21_ -t.= 00:30 i
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| COOPER NUCf.rAR STATION P -
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| L , EMERGENCY PREPAREDNESS EXERCISE MESSACE l
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| C' Messaae fort Control Room n Simulated Plant conditions: See attached Plant Data e
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| y, Massage:
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| ll
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| **** THIS IS A DRILL ****
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| 1990 EVALUATED EXERCISE TIME = 0830 Me: sage-Number 1 t = Q9L1Q j COOPER RUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRES $(psig) ELQH(gpm) REACTOR POWER 0 % SRM RHR A TRIP 0 0 REACTOR LEVEL 0 " GEMAC RHR C _IRIE__ 0 0 REACTOR PRESS 900 psig RHR B TRIP 0 0 ELQH (10^61bs/hr) ,
| |
| RHR D ' TRIP 0 0 FEEDWATER A 0 :
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| CS A TRIP 0 0 FEEDWATER B 0 :
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| CS B TRIP 0 0 MAIN STEAM A 0 t HPCI ISOL 50 0 MAIN STEAM B 0 t MAIN STEAM C 0 :
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| DRYWELL PRESS. O psig #
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| MAIN STEAM D 0 t TSRUS LEVEL 0 ft ,
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| 1 CRD A FLOW IEIE gpm CRD B FLOW IRIE gpm <
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| OPEN CLOSED SLC TX LEVEL 0 %
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| MSIV STATUS 0 8 :
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| SLC PMP DISCH PRESS A 0 psig SLC PMP DISCH PRESS B o psig i
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| PANEL 9-4 MISCELLANEOUS PANELS STATUS PRESS (psig) ELQH(gpm)
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| RCIC- OPER 1100 342 DIESEL GEN 1 INOP t RWCU A TRIP O O DIESEL GEN 2 TRIP RWCU B TRIP O O SBGT A TRIP t RRP A TRIP % SPEED SBGT B TRIP t RRP B TRIP- % SPEED DRYWELL COOLING TRIP t TORUS WATER TEMP 97 F DRYWELL TEMP 128 F
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| | |
| I RADIATION MON 3 TORS 1990 EVALUATED EXERCISE TIME = 0830 t= 00:30 STATION DESCRIPTION READING (mR/hr) 1 Rx Bldg Fuel Pool Area (SE 5th Floor) DOWNSCALE '
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| 2 Rx Bldg Fuel Pool Area (SE 5th Floor) DOWNSCALE 3 Rx Bldg New Fuel Area (SE 5th Floor) DOWNSCALE =
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| 4 Rx Bldg Rx Water Cleanup Demineraliter DOWNSCALE Area (SW 3rd Floor)
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| Rx Bldg Sludge and Decant Pump Area 5 _
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| DOWNSCALE (S 2nd Floor) 6 Rx Bldg Neutron Monitor System Index DOWNSCALE -
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| Area (TIP Room ist Floor) 7 Rx Bldg Neutron Monitor System Drive DOWNSCALE ,
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| Mech Area (SE ist Floor) 8 Rx Bldg Control Rod Hydraulic Equipment DOWNSCALE Area (S 1st Floor) 9 Rx Bldg Control Rod Hydraulic Equipment DOWNSCALE Area (N ist Floor) DOWNSCALE 10 Rx Bldg HPCI Pump Room (SW Quad) 11 Rx Bldg RHR Pump Room (SW Quad) . DOWNSCALE 12 Rx Bldg RHR Pump Room (NW Quad) DOWNSCALE '
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| 13 RX Bldg RCIC/CS Pump Room (NE Quad) DOWNSCALE 14' Rx Bldg CS Pump Room (SE Quad) DOWNSCALE 15 Turbine Bldg Turbine Front Standard DOWNSCALE 16 Turbine Bldg Mezz control Corridor DOWNSCALE ;
| |
| 17 Turbine Bldg Basement Control Corridor DOWNSCALE l 18 Turbine Bldg Rx Feed Pump Area DOWNSCALE 19 Turbine Bldg Condensate Pump Area DOWNSCALE 20 Control Room Main Control Room DOWNSCALE I 21 Grade Level Control Corridor DOWNSCALE 22 Radwaste Control Room DOWNSCALE 23 Radwaste Pump Room DOWNSCALE I R2 4 Radwaste Basement Equipment Area DOWNSCALE 25 Radwaste Demineralizer Valve Room DOWNSCALE 26 Radwaste Conveyor Aisle Operating Area DOWNSCALE 1 27 SPARE 28 Radwante Lab Area DOWNSCALE 29 Centrifuge East DOWNSCALE 30 Centrifuge West __
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| DOWNSCALE Panel 9-02 Personnel Airlock Area 903' 4 R/hr Panel 9-02 Ladder 903' to 2nd Level 2 R/hr OSH = Offscale High
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| l RADIATION MONITORS !
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| 1990 EVALUATED EXERCISE TIME = 0830 l t= 00:30 __
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| PANEL VBDQ i Rx Bldg Vent Eff (RMV-RM-40 0 uci/see ERP Stack Normal EFF (RMP-RM-3A) o uci/sec ,
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| ERP Stack High Range (RMP-RM-3B) o uci/see Turbine Bldg Vent Eff (RMV-RM-20A) o uci/sec l Turbine Bldg High Range (RMV-RM-20B) 0 uci/see RW/ARW Bldg Combined Eff (RMV-RM-30A) 0 uci/see l RW/ARW Bldg High Range (RMV-RM-30B) O qCi/see PANEL 9-10 Main Steam Rad Monitor Ch. A1, B1 50 mR/hr 50 mR/hr CH. A2, B2 25 mR/hr 25 mR/hr I
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| SJAE Of f Gas Log Rad Monitor Ch. A, B 5 mR/hr 5 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hr 0.6 mR/hr
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| 1990 EVALUATED EXERCISE TIME = +0830
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| > Message Number DiQ t = 00:30 00:40 COOPER NUCLEAR STATION .
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| M RGENCY PREPAREDNESS EXERCISE MESSAGE Operator at Diesel Generator No. 2
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| ~
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| Messaae for:
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| Messace:
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| **** THIS IS A' DRILL ****
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| i o The FAILURE TO START annunciator is lit. ,
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| i )- j-1 m.,
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| ,g j!t kb b
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| b''
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| r 1990 EVALUATED EXERCISE TIME: pjlla ',
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| Message Number 06 t=CO 30
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| .]
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| COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Messaaes fort Security (Main Gate) i r
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| Messaae:
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| **** THIS IS A DRILL ****
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| o The Tornado has passed. .You'see that the site is out of danger now, o You.see that some damage has been done in the area of the switchyard and-some of the high voltage lines, but you are not sure exactly what has been damaged.
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| o The driver of the truck vno had taken shelter in the security building i states "Where is my truck?". You see that the Radwaste truck is no-longer in the vehicle entrapment area. The inside gate of the vehicle entrapment area is torn down.
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| :o In looking back in the protected area you see the southeast corner of the security building is damaged along with the NRC/ Ambulance building.and the other trailers east'of the-security building.
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| o The' radwaste truck cab is laying on its side by the- fire protection water tank.- Laying close to the cab.are two large yellow - (actual color is orange) box containera with labels stating " Radioactive LSA". The two containers appear to be undamaged.
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| o You.also see that both the inner and outer. sections of the north security fence are down between the trailer and the' first fire protection water ,
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| tank. It appears that one of the damaged trailers ripped -down that !
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| .section of fence.
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| l' I
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| )
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| 1990 EVALUATED EXERCISE TIME: .QE22
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| . Message Number 06 t =00:30 COOPER NUCLEAR STATION EMERGENCY pREPAREDNELS EXERCISE MESSAGE FOR CONTROLLER USE ONLY (Main Cate)
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| Controller Information: Security-o The weather is clearing skies, no rain and windy.
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| o A Team member must approach and the investigate the containers to see the damage, o If requested, the radwaste driver states " Shipping Manifest is in the truck cab."
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| o The players see
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| - The Tornado has passed and are out of danger now.
| |
| - . damage has been done in the area of the switchyard and some of the.
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| high voltage lines, but you are not sure-exactly what has been-damaged.
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| - The Radwaste truck is no longer in the vehicle entrapment area, and the inside gate is torn down.
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| - In the protected area, the southeast corner of the security building is damaged along with the NRC/ Ambulance building and the-other trailers norteast of the security building.
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| - The radwaste truck cab is laying on its side'by the fire protection water tank. Laying close to the cab are two large yellow (actual color is orange) box containers with labels stating " Radioactive LSA". The two containers appear to be undamaged until they.
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| approach the containers and see the back side.
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| - The inner and outer sections of the north security fence are down between the QA trailer and the first fire protection water tank.
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| It appears that one of the daniged trei3ers ripped down that section of f3nce.
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| Expected Actions o Notify CR. (ensure this is performed within 2-3 minutes)
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| | |
| y.
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| 1 l
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| l o -- obtain the shipping Manifest from the cab. (provide this if they would retrieve:it.)
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| t it i l 5' g 65I,.
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| f!,1 -
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| . 1990. EVALUATED EXERCISE TIME = +0811
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| - Message Number qqq_ t = 00:35 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE
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| . 7, Messace for: Shift Supervisor Messace:
| |
| **** THIS IS A DRILL ****
| |
| o Declare a SITE AREA EMERGENCY in accordance with EPIP 5.7.1, Attachment A, 4.3.1, " Total loss of all AC Power (on and off-site sources) for > 15 min."
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| :p i,
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| 1990 EVALUATED EXERCISE TIME 911Q Msssage Number 07 t =00:40 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Cpntincency Messaae fort On-Site HP Survey Team, Radwaste Truck Cab Messacet
| |
| **** THIS IS A DRILL ****
| |
| o The driver of the truck who is standing by the security building states "Where is the rest of my truck?".
| |
| o :When looking in the protected area you see the southeast corner of the security
| |
| -building is damaged along with the NRC/ Ambulance building and the other trailers. east of the security building, o The-radwaste truck cab is laying on its side by the fire protection water tank. Laying close to the cab are two large yellow (actual color is orange) box containers with labels stating " Radioactive LSA". The two containers appear to be undamaged.
| |
| o _ You also see that both the inner and outer sections of the north security fence are_down-between the QA trailer and the first fire protection ~ water tank. It appears'that one of the damaged trailers ripped down that section of fence.
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| w
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| L i
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| i t
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| 1990 EVALUATED EXERCISE 1
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| Massage Humber os t =00: 45 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE FOR CONTROLLER USE-ONLY; !
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| t Controller Information: On-Site HP Survey Team, Radwaste Truck Cab o The weather is clearing skies, no rain and windy.
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| o: A Team member must approach the containers to see the demage on the back side and receive the contingency message no. OSC (900:45).
| |
| p sue.
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| s.
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| 'o If requested, the driver states "The Shipping' Manifest is in the truck cab."
| |
| )
| |
| < o The Health Physics team will see after closer inspection:
| |
| - Container 90-2-951 has a few large dents but does NOT appear to be ruptured.
| |
| The doses are 100 mR/hr at 3 inches and 8 mR/hr at 3 feet.
| |
| - Container 90-1-952 has a few large dents and has a large tear on the back side. Protruding-from the toar is wood and plastic. Laying on the ground by the container is a yellow plastic bag containing vacuum cleaner parts. T The doses are 6 mR/hr at 3 inches and <1 mR/hr at 3 feet. ,
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| - ~ They than 'small Diesel fuel and observe a small but continuous: leak- coming from the cab's diesel tanks o No contamination levels are found on the ground 1or containers
| |
| -Expected-Actions
| |
| -o Notify CR and fire brigade or Hazmat group of.the diesel fuel leak. The. team L . should also inform the CR of .the container numbers found.
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| : o. Obtain the shipping: Manifest from the cab, if not done already. ;
| |
| 1 I o Take radiation ac sarements and contamination surveys of the containers. Put-l up a temporary radiation / contamination barrier around the containers.
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| @ Remove the plastic bag from.the ground.
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| :o Team member should cover tear with Poly until moved.
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| o ~ Team members which approach the containers should routinely check themselves.
| |
| for contamination.
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| j' i 1
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| /=
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| TIME = 0845 1990 EVALUATED EXERCISE Message Number E ., t = 9_Q111 COOPER NUCLEAR STATION M RGENCY PREPAREDNESS EXERCISE MESSAGE Messaae for: Control Room Simulated Plant Conditions: See attached Plant Data Messaael
| |
| **** THIS IS A DRILL ****
| |
| | |
| if .
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| I 1990~ EVALUATED EXERCISE TIME: 0845 r =,-to/**
| |
| M:ssage Number. 08C t =00:45 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE J
| |
| contineency Messace for: On-Site HP Survey Team, Radwaste Truck Cab Messaae:
| |
| **** THIS IS A DRILL ****
| |
| o After' closer inspection You see the container / crate identification numbers; 90-2-951 and 90-1-952. Container 90-2-951 has a few large dents but does NOT appear to be " ruptured. Container 90-1-952 has a few large dents and has a
| |
| .large. tear on the back side. Protruding from the tear is wood and plastic.
| |
| Laying on the ground by the container is a yellow plastic bag containing vacuum cleaner parts.
| |
| You then smell Diesel fuel and observe a small but continuous' leak coming from
| |
| -o the cab's diesel tanks I
| |
| 4
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| _____u______________________._ :
| |
| | |
| 1990 EVALUATED EXERCISE TIME: 0845 r ,-n t */
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| * Message Number OBC t =00:45 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Contincency Messaae fort On-Site HP Survey Team, Radwaste Trurk Cab Messaae
| |
| **** THIS IS A DRILL ****
| |
| o A'fter closer inspection You see the container / crate identification numbers:
| |
| 90-2-951 and 90-1-952. Container 90-2-951 has a few large dents but does NOT
| |
| -appear to be ruptured. Container 90-1-952 has a few large dents and has a large tear on the back side. Protruding from the-tear is; wood and plastic.
| |
| Laying on the ground by the container is a yellow plastic bag containing vacuum cleaner parcs, o You then smell Diesel fuel and observe a small but continuous leak coming from--
| |
| _the cab's diesel tanks 1
| |
| | |
| '1990 EVALUATED EXERCISE TIME = 0845 MOCsage Number 09 t= 00:45 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3. PANEL 9-5 STATUS PRESS (psig) ELQH(gpm) REACTOR POWER 0 % SRM :
| |
| LRHR A TRIP O O REACTOR LEVEL 35 " GEMAC :
| |
| IUiR C TRIP O O REACTOR PRESS 995 psig RHR B TRIP O O FLOW (10^61bs/hr)
| |
| -RHR D TRIP O O FEEDWATER A 0 :
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| CS A TRIP 0 0 FEEDWATER B 0 :
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| 'CS B TRIP O O MAIN STEAM A 0 _: s HPCI ISOL 50 0 MAIN STEAM B 0 :
| |
| MAIN STEAM C 0 :
| |
| .DRYWELL PRESS. O psig MAIN STEAM D 0 :
| |
| TORUS LEVEL 0 ft CRD A FLOW TRIP gpm CRD B FLOW TRIE gpm >
| |
| OPEN CLOSED SLC TK LEVEL 0 %
| |
| MSIV STATUS 0 8 :
| |
| SLC PMP DISCH PRESS A 0 psig SLC PMP DISCH PRESS B 0 psig PANEL 9-4 MISCELLANEOUS PANELS STATUS PRESS (psig) FLOW (gpm)
| |
| RCIC' OPER- 1100 292 DIESEL GEN 1 INOP :
| |
| , RWCU A TRIP O O DIESEL GEN 2 TRIP :
| |
| 1 RWCU B TRIP O O SBGT A TRIP :
| |
| RRP.A TRIP % SPEED SBGT B TRIP :
| |
| L RRP B TRIP % SPEED DRYWELL COOLING TRIP :
| |
| y TORUS WATER TEMP 104 F DRYWELL TEMP 140 F 1
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| I
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| | |
| RADIATION MONITORS 1990'EVALUAT2D EXERCISE TIME = 0849 l t= 00:45 s
| |
| ' STATION DESCRIPTION READING (mR/hri 1 ~
| |
| Rx Bldg Fuel Pool Area (SE 5th Floor) DOWNSCALE 2 Rx Bldg Fuel Pool Area (SE Sth Floor) DOWNSCALE l 3 Rx Bldg New Fuel Area (SE Sth Floor) DOWNSCALE 4 RX Bldg Rx Water Cleanup Demineralizer DOWNSCALE Area (SW 3rd Floor) 5 RX-Bldg Sludge and Decant Pump Area DOWNSCALE (S ' 2nd Floor) 6 Ibc Bldg Neutron Monitor System Index DOWNSCALE Area -(TIP Room ist Floor) 7 Rx Bldg Neutron. Monitor System Drive DOWNSCALE-Mech Area (SE 1st Floor) 8 Rx Bldg Control Rod Hydraulic Equipment DOWNSCALE Area (S ist Floor) 9 Rx Bldg Control Rod Hydraulic Equipment DOWNSCALE
| |
| : Area (N ist Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) DOWNSCALE 11 Rx Bldg RHR Pump Room (SW Quad) DOWNSCALE 12 Rx Bldg RHR Pump Room (NW Quad) DOWNSCALE 13 Rx Bldg RCIC/CS Pump Room (NE Quad) DOWNSCALE .l 14 Rx- Bldg CS Pump Room (SE Quad)
| |
| DOWNSCALE 15 Turbine Bldg Turbine Front Standard DOWNSCALE 16 Turbine Bldg Mezz Control Corridor DOWNSCALE 17 Turbine Bldg Basement Control Corridor DOWNSCALE 18 Turbine Bldg Rx Feed Pump Area DOWNSCALE 19 -Turbine Bldg-Condensate Pump Area DOWNSCALE 20 ' Control Room Main Control Room DOWNSCALE 21 Grade Level Control Corridor DOWNSCALE 22 Radwaste Control Room DOWNSCALE 23~ ~Radwaste Pump Room DOWNSCALE 24 Radwaste Basement Equipment Area DOWNSCALE 25 Radwaste Demineralizer Valve Room DOWNSCALE 26 Radwaste Conveyor Aisle Operating Area DOWNSCALE i
| |
| : 27. SPARE 28 Radwaste Lab Area DOWNSCALE 29 Centrifuge East DOWNSCALE 30 Centrifuge West. DOWNSCALE Panel-9-02 Personnel Airlock Area 903' DOWNSCALE Panel 9-02 Ladder 903' to 2nd Level DOWNSCALE OSH = Offscale High
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| | |
| RADIATION MONITORS
| |
| ~
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| . 1990 EVALUATED EXERCISE TIME = 0845 t= 00:45 i
| |
| PANEL VBDG ERx Bldg Vent Eff (RMV-RM-40 0 uCi/sec 0 uCi/sec ERP~ Stack. Normal EFF'(RMP-RM-3A) o uCi/sec-
| |
| 'ERP Stack High Range (RMP-RM-3B)
| |
| Turbine Bldg Vent Eff (RMV-RM-20A) o uCi/sec Turbine Bldg High Range (RMV-RM-20B) o uCi/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 0 uC1/sec !
| |
| RW/ARW Bida High Range (RMV-RM-30B) o uCi/sec PANEL 9-10 Main Steam Rad Monitor Ch. A1, B1 15 mR/hr 15 mR/hr CH. A2, B2 15 mR/hr 15 mR/hr ;
| |
| 3JAE Off-Gas Log Rad Monitor Ch. A, B 1 mR/hr 1 mR/hr l Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hr 0.6 mR/hr
| |
| | |
| 1990: EVALUATED EXERCISE' TIME = +0045 Message .!hadoer .10 t = 0Q: 45 01:30 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE MESSAGE-FOR: Switchyard Damage Assessment Team
| |
| - MESSAGE:
| |
| *** THIS IS A DRILL ***
| |
| o See FIGURE 1.
| |
| o Bus Bar is damaged between ACB 3310 and 3312.
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| o ACB 3304 is damaged,.and a burning.small is noticed in the vicinity, but na smoke can be seen.
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| o The Startup Station Service Transformer disconnect support structure is down. The disconnect is broken, o A portion of the-69 KV OPPD line is down.
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| I.
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| i
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| SOONEYlLLE MAIKT,M3CRE NESAAEK A CITY
| |
| - St.JOAEPN LINE 344Se LINE SSISV LINE 3631v LINE 3499v 6 6 6 o
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| s s SUS 6 o.1 s
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| * j n '
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| "/ == t=3 "/
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| bc, , ,
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| O 346KV 1'
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| k.
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| * O O
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| AUSURNt.INE ma hm 6 6 l (3310l l3304l O O 2
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| gyg.
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| i REACTOR p g,ggy 1804 l1606l O O ipt.
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| REACTOR (330ej l3312j STARTUP l
| |
| S No.2 STATION SERVICE -
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| ) ym TRANSFORMER 1DN ,
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| 1CN ) '
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| MAIN POWER 1CS 108 TRANSFORMER [ l 4teow sus to 4100v SUS 1C
| |
| ( ERATOR [m l 8 1AM 1GN STATION ERVIC ggg TRANSFORMER ggg f 4190v SUS 18 4100v SUS 1A f 1SE j
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| AE
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| ,% - 4 = === = 5, M' 4 0v .U. i. .
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| A.0v SU.1.
| |
| : l. h j 1FA ')1gg
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| ,E 4100, gUS 10 4100v BUS 1F i
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| l
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| -l l)1OE l)S$10 SS1F ) tFE l)1PS 108 ) l l
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| ' I L I l M M l EMERGENCY N N l 480v BUS 10 f 480v BUS '1Fl o TRANSFORMER CONSTRUCTION
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| '"* ER _ _
| |
| 9\ OtESEL (* _
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| OtESEL GENERATOR 1 T GENERATOR 2 )
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| FIGURE 1~ SWITCHYARD /LINE DAMAGE l
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| l
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| ! j SUPPLEMENTAL SCENARIO No. 3
| |
| -t DAMAGE TO SWITCHYARD EQUIPMENT AND TRANSFORMERS l
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| J TIME: Scenario time approximately 00:45 to 01:20 LOCATION: 345 KV Switchyard area, 161 KV-Switchyard area, Station Service and Emergency Station Service Transf areas.
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| !A. ' Initial Notifjaation ,.
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| The Control Room is initially made aware of loss of offsito power by MLSSAGE No. *gf. Shortly thereafter, at approximately-00:30, Security notifies the Control Room that there appears to be extensive damage to overhead electrical lines and structures (MESSAGE No. *** . However, at that time, the specific nature and extenk)o) f the damage is unknown.
| |
| usu s.x 4*
| |
| B. Postulated Event The tornado has done extensive damage in the Switchyard and Transformer areas. Bus bar, breakers and support structures have'been damaged. No offsite power restoration will be possible during the course of the Exercise.
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| The Startup- Station Service Transformer cannot be energized because damage to the disconnect support structure has left i the disconnect-broken and unable to be reclosed.
| |
| The 69 KV OPPD line which supplies the Emergency Station Service Transformer is down..This cannot be repaired, and this ,
| |
| transformer cannot be reenergized_during the course of this Exercise.
| |
| ACB 3304 is open, and damaged. It cannot be closed. It is postulated that ACB 3306 is still closed and that power.is being supplied-to the Auto Transformer from the Booneville line via 345 KV Bus No. 2. ACB 110 is closed, and underground L 12.5 KV is available to the EOF. Any attempts towards creative
| |
| ~
| |
| power " cross-ties" to the underground 12.5 KV will be unsuccessful.
| |
| Bus bar is damaged between ACBs 3310 and 3312. This will prevent reclosure of either of these breakers. Therefore, any l ideas that players come up with related to backfeeding through l= the Main Power and Normal Station Service Transformers will be-unsuccessful.
| |
| SUPPLEMENTAL SCENARIO NO. 3 (Continued) h DAMAGE T0 SWITCHYARD EQUIPMENT AND TRANSFORMERS l
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| l l,
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| L--
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| | |
| L l
| |
| l C. Restoration Guidelines Offsite' power restoration =is not allowed during_the course of-this Exercise. The damage is postulated to be too extensive to be repaired-within this time.
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| l
| |
| | |
| Y e,
| |
| TIME: +12.Q1 1990 EVALUATED EXERCISE t =01:00- >
| |
| M:ssage Number _.11 .01:40 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE FOR CONTPOLLER USE ONLY:
| |
| "B" Team Member 4
| |
| Ccntroller Information: Contingency, Site o A search team member must approach within viewing range of the radwasteII C (@
| |
| shipping trailer behind the north warehouse to receive message no. gg 01:00- ). s.ss se i
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| i i
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| 1990 EVALUATED EXERCISE TIME: +0900
| |
| -Message Number __11C t =01:00 01:40 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Messaces fort Site "B" Search Team Messacet-
| |
| **** THIS IS A DRILL ****
| |
| At a distance, north of.the plant and behind the north warehouse, you egg a damaged truck trailer and yellow crates / containers.(actual color is orange).
| |
| | |
| r-
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| . T--
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| l' . ,
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| u ,
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| t
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| . 1990 EVALUATED EXERCISE TIME: +0920 Message Number 12- t =01:20 COOPER NUCLEAR STATION EMERGENCY PREk.S. REDNESS EXERCISE MESSAGE FOR CONTROLLER USE ONLY:
| |
| Controller Information: Contingency, Control Room If the radwaste shipping trailer has not been found, issue contingency control !
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| Room Message no. 12C (9 01:20).
| |
| 'I f
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| I 9
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| I 1
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| | |
| , l 1
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| i 1 l
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| - 8990: EVALUATED EXERCISE TIME: +0920 ;
| |
| Massage', Number 12C t =01:20 l COOPER NUCLEAR STATION i EMERGENCY PREPAREDNESS EXERCISE MESSAGE !
| |
| l Contincency Messaces for Control Room Messacet
| |
| **** THIS IS A DRILL ****
| |
| This is John Doe at the north warehouse. There is a truck trailer and yellow boxes (actual color is orange) out here by the north warehouse. I also see a lot of yellow material on the ground.
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| I
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| | |
| 1990 EVALUATED EXERCISE TIME: +Q900 Message Number 13 t =01:00-01: 40 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE FOR CONTROLLER USE ONLY Controller Information: Contingency, Site "B" Search Team o Upon finding the Radwaste trailer, the search team will see:
| |
| The Radwaste trailer is practically demolished. The trailer is laying on its top with the top front of the trailer crushed. -The sides of the middle and back portions are .almost torn away and the frame is badly twisted. There are four (4) yellow (actual Orange) box containers on the ground near the trailer. The containers are the same size and measure approximately 3ft high, 3ft wide and 5ft long. All the containers have labels stating " Radioactive LSA". Two containers, 90-3-902 and 90-2-905, are badly dented but do not appear to be ruptured. The other two, 89-7-904 and 90-1-902 are ripped open with their contents scattered on the ground.
| |
| Some of the shredded contents that you see on the ground can be identified as herculite, rubber boots, mop heads, paper, coveralls, fiberglass insulation,-rope, floor dry and sweeping compound.
| |
| When looking at the trailer closely, they can see a yellow container through a small tear in the trailer wall. They can not identify the container number. The trailer walls would need to be cut away in order to tell, o Determine the actions 'of the team . members. If they approach the ruptured containers, they will become contaminated. Contamination will be >100 cpm but limit to <l5,000 cpm. Tools and equipment which would be used near the l- containers could become contaminated. This will be left to the discretion of l the controller.
| |
| I o Identifiable radioactive / contaminated material is laying on the ground. All material found will have a dose rate less than 200 mR/hr. The controller will have free play to-identify pieces which were in the container.
| |
| o Soil and vegetation samples taken within the contaminated area, are as follows:
| |
| Sj2il Vecetation mR/hr CPM mR/hr CPM l Threuch bac Throuch bac L .1 - 1 400 - 4,000 .1 - 1 400 - 4,000 1
| |
| -* The controller can provide reading within the above ranges, i
| |
| | |
| '! ) .'a \ ., ,
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| i; ,p a ;
| |
| =ie ,
| |
| : p. 1990 EVALUATED' EXERCISE TIME: +0900
| |
| . Message Number 13 (continued) t =C1: 00-01:40 !
| |
| 1 COOPER NUCLEAR STATION
| |
| , EMERGENCY PREPAREDNESS EXERCISE MESSAGE l'
| |
| y FOR CONTROLLER USE ONLYt Controller Information: Contingency, Site "B" Search Team- ;
| |
| Expected Actions
| |
| * o' Notify CR. of the location and container numbers.
| |
| o Team members will put on protective clothing. Gloves and boots at a minimum.
| |
| - Team members will begin ground surveys to identify the extent of contamination.
| |
| .They should set up a radiological control access point.
| |
| L o , 'If Plastic is available, team members may try to cover the loose material, 1 such as floor dry and sweeping compound to prevent further spread of the 1 material. They may even begin-to pick up loose material and place in bags.
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| I i
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| l' i:
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| l i
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| l ''
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| l l
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| l:
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| i l
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| l
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| 1990 - EVALUATED - EXERCISE TIME: +2122 m .
| |
| Message Number 13C t =01:00-01:40 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Messaces fort-Site "B" Search Team Messace: [
| |
| **** THIS IS A DRILL **** ,
| |
| =o As you approach the trailer behind the warehouse, vou see that the Radwaste trailer is practically demolished. The trailer is laying on its top with the top front of the trailer crushed. The sides of the middle and back portions are almost torn away and the frame is badly twisted, o You see four (1) yellow (actual Orange) box containers on-the ground near the trailer. -The containers are the same size and measure approximately 3ft high, 3ft wide and 5ft long. All the containers have labels stating " Radioactive IJA". Two containers, 90-3-902 and 90-2-905, are badly dented but do not appear to be ruptured. The other two, 89-7-904 and 90-1-902 are ripped open-with their contents scattered on the ground. ;
| |
| o Some of the shredded contents that you see on the ground can be identified as herculite, rubber boots, mop heads, paper, coveralls, fiberglass .nsulation,.
| |
| spe, floor dry and sweeping compound.
| |
| o In looking at the trailer more closely, you can see a yellow container through a small tear in the trailer wall. You can not identify the container number.
| |
| The trailer walls would need-to be cut away in. order to tell.
| |
| | |
| !a990 EVALUATED EXERCISE TIME: +0900 Message Number ide t =01:00-02:00 COOPER ITUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE
| |
| .contineenev Messaces fort site "B"-Search Team, if tools are brought to cut open the trailer walls Messaget
| |
| **** THIS IS A DRILL ****
| |
| After removing part of the trailer wall, vou see that there are two (2) containers remaining in the trailer. The container numbers are 90-3-901 and 90-3-907. The two containers.are not ruptured.
| |
| | |
| e l
| |
| l 1990 EVALUATED EXERCISE- TIME = +0900
| |
| : Message Number 15..Q t = 01:00 c 03:45 I COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Messaae fort Maintenance crew at DG #2
| |
| .i Messaae:
| |
| **** THIS IS A DRILL ****
| |
| o There is an open winding in the Fuel Oil Booster Pump Motor.
| |
| l, i
| |
| l^
| |
| l ..
| |
| l ,
| |
| !u I
| |
| it) i e _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .
| |
| | |
| 1990 EVALUATED EXERCISE TIME = 0900 Message Number 1 t = 01:00 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Messace for: Control Room Simulated Plant Conditions: See attached Plant Data Messaae:
| |
| **** THIS IS A DRILL ****
| |
| l lt l
| |
| l l
| |
| l
| |
| | |
| 1990 EVALUATED EXERCISE TIME = 0900 1
| |
| .j MCcage' Number _11_ t= 01:00 l COOPER NUCLEAR STATIQd ;
| |
| 1 EMERGENCY PREPAREDNESS EXERCISE PLANT DATA 1 PANEL 9-3 PANEL 9-5 l l
| |
| STATUS PRESS (psig) ELQH(gpm) REACTOR POWER 0 % SRM : l RHR A TRIP O O REACTOR LEVEL _11_ " GEMAC :
| |
| RHR C' TRIP __
| |
| 0 0 REACTOR PRESS 900 psig RHR B TRIP O O ELQH (10^61bs/hr)
| |
| RHR D TRIP C 0 FEEDWATER A 0 :
| |
| CS=A TRIP O O FEEDWATER B o :
| |
| CS B TRIP O O HAIN STEAM A 0 :
| |
| HPCI ISOL 50 0 MAIN STEAM B 0 :
| |
| MAIN STEAM C 0 :
| |
| DRYWELL PRESS. O psig MAIN STEAM D 0 :
| |
| TORUS LEVEL 0 ft CRD A FLOW IEIE gpm CRD B FLOW IBIE gpm QEEH CLOSED SLC TK LEVEL 0 %
| |
| MSIV STATUS 0 8 :
| |
| SLC PMP DISCH PRESS A 0 psig SLC PMP DISCH PRESS ~B 0 psig ,
| |
| 4 PANEL 9-4 MISCELLANEOUS PANELS STATUS EEES1(Psig) ELQH(gpm)
| |
| RCIC OPER 1050 266 DIESEL GEN 1 INOP :
| |
| RWCU A TRIP O O DIESEL GEN 2 TRIP :
| |
| RWCU-B TRIP O O SBGT A TRIP :
| |
| * iRRP A TRIP % SPEED SBGT B TRIP :
| |
| RRP B TRIP % SPEED DRYWELL COOLING TRIP :
| |
| TORUS WATER TEMP 109 F DRYWELL TEMP _150 F
| |
| | |
| RADIAT80N MON 3 TORS i 1990 EVALUATED EXERCISE TIME = 0900 t= 01:00 STATIO,H DESCRIPTION READING (mR/hr) l 1 Rx "'dg Fuel Pool Area (SE 5th Floor) DOWNSCALE 2 Rx Bldg }tel Pool Area (SE Sth Floor) DOWNSCALE 3 Rx Bldg New Fuel Area (SE 5th Floor) DOWNSCALE, j 4 Rx Bldg Rx Water cleanup Demineralizer DOWNSCALE .
| |
| Area (SW 3rd Floor) l Rx Bldg Sludge and Decant Pump Area 5 DOWNSCALE (S 2nd Floor) 6 Rx Bldg Neutron Monitor System Index DOWNSCALE Area (TIP Room ist Floor) 7 Rx Bldg Neutron Monitor System Drive DOWNSCALE Mach Area (SE 1st Floor) 8 Rx Bldg Control Rod Hydraulic Equipment DOWNSCALE 1 Area (S ist Floor) 9 Rx Bldg Control Rod Hydraulic Equipment DOWNSCALE Area (N ist Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) DOWNSCALE 11 Rx Bldg RHR Pump Room (SW Quad) DOWNSCALE 12 Rx Bldg RHR Pump Room (NW Quad) DOWNSCALE 13 Rx Bldg RCIC/CS Pump Room (NE Quad) DOEEEQALE '
| |
| 14 Rx Bldg CS Pump Room (SE Quad) DOWNSCALE 15 Turbine Bldg Turbine Front Standard DOWNSCALE 16 Turbine Bldg Mezz Control Corridor DOWNSCALE 17 Turbine Bldg Basement Control Corridor DOWNSCALE 18 Turbine Bldg Rx Food Pump Area DOWNSCALE 19 Turbine Bldg Condensate Pump Area DOWNSCALE 20 Control Room Main Control Room DOWNSCALE 21 Grade Level Control Corridor DOWNSCALE 22 Radwaste Control Room DOWNSCALE 23 Radwaste Pump Room DOWNSCALE 24 Radwasta Basement Equipment Area DOWNSCALE 25 Radwaste Domineralizer Valve Room DOWNSCALE 26 Radwasta Conveyor Aisle Operating Area _ DOWNSCALE 27 SPARE 28 Radwasta Lab Area DOWNSCALE 29 Centrifuge East DOWNSCALE 10 Centrifuge West DOWNSCALE-Panel 9-02 Personnel Airlock Area 903' DOWNSCALE' Panel 9-02 Ladder 903' to 2nd Level DOWNSCALE OSH = Offscale High )
| |
| i 1
| |
| | |
| RADIATION MONITORS P
| |
| 1990 EVALUATED EXERCISE TIME = 0900 t= 01:00 PANEL VBDG Rx Bldg Vent.Eff (RMV-RM-40 0 uci/see ERP Stack Normal EFF (RMP-RM-3A) o uCi/see '
| |
| ERP Stack High Range (RMP-RM-3B) o uCi/see Turbine Bldg Vent Eff (RMV-RM-20A) 0 uci/see Turbine Bldg High Range (RMV-RM-20B) o uC1/see j RW/ARW Bldg Combined Eff (RMV-RM-30A) 0 uCi/see RW/ARW Bldg High Range (RMV-RM-30B) o uci/see PANEL 9-10 ,
| |
| Main Steam Rad Monitor Ch. A1, B1 15 mR/hr 15 mR/hr CH. A2, B2 15 mR/hr 15 mR/hr_,
| |
| SJAE Off Gas Log Rad Monitor Ch. A, B 1 mR/hr 1 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0 6 mR/hr 0.6 mR/hr a
| |
| 5 L
| |
| | |
| t 1990 EVALUATED EXERCISE TIME = 0915._
| |
| Message Number 12 t= h COOPER RUCLEAR STATIO!!
| |
| EMEP.GENCY PREPAREDNESS EXERCISE MESSAGE Massage fort Control Room Simulated plant'Conditionst See attached Plant Data Massaget
| |
| **** THIS IS A DRILL ****
| |
| : 2. J 6
| |
| 4 4
| |
| ,\'
| |
| | |
| 1990 EVALUATED EXERCISE TIME = 0919 Massage Number _11_ t= 01:15 '
| |
| COOPER ITUCLEAR STATION EMERGENCY PREPAREDNESS EXEPCISE PLANT DATA ,
| |
| PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) ELQH(gpm) REACTOR POWER 0 % SRM :
| |
| RHR A TRIP 0 0 REACTOR LEVEL _li_ " GEMAC :
| |
| RHR C TRIP 0 __ 0 REACTOR PRESS 1002 psig RHR B TRIP 0 0 ELQH (10^61bs/hr)
| |
| RHR D TRIP 0 0 FEEDWA7 *.R A 0 :
| |
| CS A TRIP 0 0 FEEDWATER B o :
| |
| CS B _ TRIP 0 0 KAIN STEAM A 0 :
| |
| HPCI ISOL__ 50 0 KAIN STEAM B 0 :
| |
| MAIN STEAM C 0 :
| |
| DRYWELL PRESS. O psig MAIN STEAM D 0 :
| |
| TORUS LEVEL 0 ft CRD A FLOW T.EIE gpm CRD .2 FLOW IRIE gpm QEEH GLOSED ,
| |
| SLC TK LEVEL 0 %
| |
| MSIV STATUS 0 8 : '
| |
| SLC PMP DISCH PRESS A 0 psig SLC PMP DISCH PRESS B 0 psig PANEL 9-4 MISCELLANEOUS PANELE l STATUS EEU.E(psig) ELQH(gpm)
| |
| RCIC OPER 1100 249 DIESEL GEN 1 INOP :
| |
| RWCU A _TRTP 0 0 DIESEL GEN 2 TRIP :
| |
| l RWCU B TRIP o O SBGT A TRIP :
| |
| g l
| |
| RRP A. TRIP % SPEED SBGT B TRIP :
| |
| g RRP B. TRIP % SPEED DRYWELL COOLING TRIP :
| |
| TORUS "ATER TEMP _114 F L DRYWELL TEMP 155 F l
| |
| | |
| RADIATION MONITORS ,
| |
| 1990 EVALUATED EXERCISE TIME = 0915 t= 01:15 EIATION DESCRIPTION READING (mR/hr)
| |
| .1 Rx Bldg Fuel Pool Area (SE Sth Floor) DOWNSCALE 2 Rx Bldg Fuel Pool Area (SE 5th Floor) DOWNSCALE ,
| |
| 3 Rx Bldg New Fuel Area (SE Sth Floor) DOWNSCALE i 4 Rx Bldg Rx Water Cleanup Demineralizer DOWNSCALE Area (SW 3rd Floor) 5 Rx Bldg Sludge and Decant Pump Area DOWNSCALE (S 2nd Floor) 6 Rx Bldg Neutron Monitor System Index _
| |
| DOWNSCALE ;
| |
| Area (TIP Room ist Floor) 7 Rx Bldg Neutron Monitor System Drive DOWNSCALE Mech Area (SE ist Floor) <
| |
| 8 Rx Bldg Control Rod Hydraulic Equipment DOWNSCALE Area (S ist FlOca) 9 Rx Bldg Control Rod Hydraulic Equipment DOWNSCALE Area (N ist Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) DOWNSCALE 11 Rx Bldg RHR Pump Room (SW Quad) DOWNSCALE ,
| |
| 12 Rx Bldg RHR Pump Room (NW Quad) DOWNSCALE 13 Rx Bldg RCIC/CS Pump Room (NE Quad) DOWNSCALE 14 Rx Dldg CS Pump Room (SE Quad) DOWNSCALE 15 Turbine Bldg Turbine Front Standard DOWNSCALE 16 Turbine Bldg Mezz Control Corridor DOWNSCALE 17 Turbine Bldg Basement Control Corridor DOWNSCALE 18 Turbine Bldg Rx Feed Pump Area DOWNSCALE 19 Turbine Bldg Condensate Pump Area DOWNSCALE 20 control Room Main Control Room DOWNSCALE
| |
| * 21 Grade Level Control Corridor DOWNSCALE 22 Radwaste Control Room DOWNSCALE 23 Radwaste Pump Room _
| |
| DOWNSCALE 24 Radwaste Basement Equipment Area DOWNSCALE 25 Radwaste Demineralizer Valve Room DOWNSCALE 26 Radwaste conveyor Aisle Operating Area DOWNSCALE 27 SPARE 28 Radwasta Lab Area DOWNSCALE 29 Centrifuge East DOWNSCALE 30 ' Centrifuge West DOWNSCALE l Panel 9-02 Personnel Airlock Area 903' DOWNSCALE Panel 9-02 Ladder 903' to 2nd Level . DOWNSCALE <
| |
| OSH = Offscale High I
| |
| I l
| |
| l r
| |
| : i. i RAD 3ATION MONITORS ;
| |
| J 1990 EVALUATED EXERCISE TIME = 0915 1 t= 01:15 l i
| |
| i PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40 0 uci/see ERP Stack Normal EFF (RMP-RM-3A) o uci/see i ERP Stack High Range (RMP-RM-3B) 0 uci/sec l Turbine Bldg Vent Eff (RMV-RM-20A) o uci/see Turbine Bldg High Range (RMV-RM-20B) o uci/see RW/ARW Bldg Combined Eff (RMV-RM-30A) o uci/sec RW/ARW Bldg High Range (RMV-RM-30B) o uci/sec PANEL 9-10 J
| |
| +
| |
| Main Steam Rad Monitor Ch. A1, B1 15 mR/hr 15 mR/hr CH. A2, B2 15 mR/hr 15 mR/hr ,
| |
| SJAE Of f Gas Log ..ad Monitor Ch. A, B 1 mR/hr 1 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hr 0.6 mR/hr r i
| |
| I
| |
| | |
| . I l
| |
| 1 1990 EVALUATED EXERCISE TIME: 212Q Message Number 18 t =01:20 COOPER NUCLEAR STATION EKERGENCY PREPAREDNESS EXERCISE MESSAGE Centineenev Messaaen fort Control Room ,
| |
| Messacet
| |
| **** THIS IS A DRILL ****
| |
| This is Jchn Doe at the north warehouse. There is a truck trailer and yellow boxes (actual color is orange) out here by the north warehouse. I also see a lot of yellow material on the ground.
| |
| | |
| - ... . ~ . . . - - . _ . . - _ . _ _
| |
| i i
| |
| l 1990 EVALUATED EXERCISE TIME = 0930 I Message Number 12 t = 01 30 l l
| |
| COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE i
| |
| i Massaae fort Control Room ;
| |
| sint*1ated Plant Conditionst See attached Plant Data j l
| |
| Mensace I
| |
| **** THIS IS A DRILL ****
| |
| l f
| |
| t i
| |
| e i
| |
| e i
| |
| L F
| |
| l l
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| l~ ,
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| _ _ _ _ . . . . - _ _ _ . ~.... _. - . _ ~ -
| |
| | |
| 1990 EVALUATED EXERCISE TIME = 0930 I M;; Cage Number _11. t= 01:30 CQQPER NUCLEAR STATION ,
| |
| i EMERGENCY PREPAREDMESS EXERCISE PLANT DAL\ )
| |
| l I
| |
| PANEL 9-3 PANEL 9-5 STATUS EREEE(psig) ELQH(gpm) REACTOR POWER 0 % SRM :
| |
| RHR A TRIP 0 0 REACTOR LEVEL _11. " GEHAC : J RHR C _ TRIP _ 0 0 REACTOR PRESS _10.00 psig RHR B TRIP O O ELQH (10^61bs/hr)
| |
| RHR D TRIP O 0 FEEDWATER A 0 :
| |
| CS A TRIP 0 0 TEEDWATER B o :
| |
| CS B TRIP 0 0 MAIN STEAM A .0 :
| |
| HPCI ISOL - 50 0 MAIN STEAM B 0 :
| |
| MAIN STEAM C 0 :
| |
| DRYWELL PRESS. O psig MAIN STEAM D 0 :
| |
| TORUS LEVEL 0 ft CRD A FLOW IRIE gpm CRD B FLOW IRIE gpm Q2EH CLOSED SLC TK LEVEL 0 %
| |
| MSIV STATUS 0 8 :
| |
| SLC PMP DISCH PRESS A 0 psig SLC PMP DISCH PRESS B 0 psig PANEL 9-4 MISCELLANEOUS PANELS L
| |
| STATUS PRESS (psig) ELQE(gpm) i
| |
| ! RCIC OPER 1100 237 DIESEL GEN 1 INOP :
| |
| RWCU A TRIP O O DIESEL GEN 2 TRIP :
| |
| 11 i RWCU B TRIP 0 0 SBGT A TRIP :
| |
| RRP A TRIP % SPEED SBGT B TRIP :
| |
| RRP B TRIP % SPEED DRYWELL COOLING TRIP :
| |
| TORUS WATER TEMP 120 F DRYWELL TEMP 158 F
| |
| '^
| |
| | |
| 1 RADIAT3ON MONITORS l 1990 EVALUATED EXERCISE TIME = _ 0930 t= 01:30 l
| |
| l STATION DESCRIPTION READING (mR/hr) 1 Rx Bldg Fuel Pool Area (SE 5th Floor) DOWNSCALE 2 Rx Bldg Fuel Pool Area (SE Sth Floor) DOWNSCALE 3 Rx Bldg New Puel Area (SE 5th Floor) DOWNSCALE 4 Rx Bldg Rx Water Cleanup Demineralizer DOWNSCALE l Area (SW 3rd Floor) 5 Rx Bldg Sludge and Decant Pump Area DOWNSCALE (S 2nd Floor) l 6 Rx Bldg Neutron Monitor System Index DOWNSCALE l Area (TIP Room ist Floor) i 7 Rx Bldg Neutron Monitor System Drive DOWNSCALE '
| |
| Mech Area (SE 1st Floor) I 8 Rx Bldg Control Rod Hydraulic Equipment DOWNSCALE Area (S 1st Floor) )
| |
| 9 Rx Bldg Control Rod Hydrhulic T.quipment DOWNSCALE ;
| |
| Area (N ist Floor) DOWNSCALE 10 Rx Bldg HPCI Pump Room (bW Quad) 11 Rx Bldg RHR Pump Room (SW Quad) DOWNSCALE 12 Rx Bldg RHR Pump Room (NW Quad) DOWNSCALE 13 Rx Bldg RCIC/CS Pump Room (NE Quad) DOWNSCALE 14 Rx Bldg CS Pump Room (SE Quad) DOWNSCALE 15 Turbine Bldg Turbine Front Standard DOWNSCALE 16 Turbine Bldg Mezz Control Corridor DOWNSCALE 17 Turbine Bldg Basement Control Corridor DOWNSCALE 18 Turbine Bldg Rx Feed Pump Area DOWNSCALE 19 Turbine Bldg Condensate Pump Area DOWNSCALE 20 control Room Main Control Room DOWNSCALE 21 Grade Level Control Corridor DOWNSCALE 22 Radwaste Control Room DOWNSCALE 23 Radwaste Pump Room ___DOWNSCALE 24 Radwaste Basement Equipment Area DOWNSCALE 25 Radwaste Demineralizer Valve Room DOWNSCALE ,
| |
| p 26 Radwaste Conveyor Aisle Operating Area DOWNSCALE
| |
| '' 27 SPARE ,
| |
| 28 Radwaste Lab Area DOWNSCALE 29 Centrifuge East DOWNSCALE 30 Centrifuge West DOWNSCALE Panel 9-02 Personnel Airlock Area 903' DOWNSCALE Panel 9-02 Ladder 903' to 2nd Level DOWNSCALE OSH = Offscale High 1
| |
| | |
| RADIATION MONITORS 1990 EVALUATED EXERCISE TIME = 0930 t= 01:30 r
| |
| i PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40 0 uCi/see ERP Stack Normal EFF (RMP-RM-3A) 0- uci/see ERP Stack High Range (RMP-RM-3B) 0 uCi/sec Turbine Bldg Vent Eff (RMV-RM-20A) 0 uCi/sep Turbine Bldg High Range (RMV-RM-208) 0 uCi/sec
| |
| * RW/ARW Bldg Combined Eff (RMV-RM-30A) 0 uCi/see RW/ARW Bldg High Range (RMV-RM-30B) 0 uC1/see PANEL 9-10 Main Steam Rad Monitor Ch. A1, B1 15 mR/hr 15 mR/hr CH. A2, B2 15 mR/hr 15 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 1 mR/hr 1 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.6 mR/Pr 0.6 mR/hr I
| |
| i' l
| |
| | |
| p: . {;
| |
| p .i. i i
| |
| g ,
| |
| ! i 1990 EVALUATED EXERCISE TIME = _0,111 !
| |
| : t. .
| |
| '7 . Message Number. 2.D._ ta DM i COOPER liUCTJAR STATION !
| |
| i EMERGENCY PRE % REDNESS EXERCISE MESS $QE f
| |
| .5 Massaae fort Control Room
| |
| . Simulated Plant' Conditions: See attached Plant Data f 1:.
| |
| {
| |
| }igssaget .i
| |
| **** THIS IS A DRILL **** .l
| |
| .'1 6
| |
| L 2
| |
| r t
| |
| t
| |
| 'f s
| |
| i h
| |
| 4 4
| |
| | |
| 1990 EVALUATED EXERCISE TIME = 0945 M sage Number _12_ t= 01:45 COOPER ffUCLEAR STATION ,
| |
| EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS EMSS(psig) ELQH(gpm) REACTOR POWER 0 % SPJ4 :
| |
| RHR A TRIP O O REACTOR LEVEL 30 " GEMAC :
| |
| RHR C TRIP O O REACTOR PRESS 799 psig '
| |
| RHR B TRIP 0 0 FLOW (10^ 61bs/hr)
| |
| RHR D TRIP O O FEEDWATER A 0 :
| |
| CS A TRIP 0 0 FEEDWATER B 0 :
| |
| {
| |
| CS B TRIP O O MAIN STEAM A 0 :
| |
| HPCI ISOL 50 0 MAIN STEAM B __0 :
| |
| MAIN STEAM C 0 :
| |
| DRYWELL PRESS. O psig MAIN STEAM D 0 :
| |
| TORUS LEVEL 0 ft CRD A FLOW TRIP gpm CRD B FLOW TRIP gpm OPEN CLOSED SLC TK LEVEL 0 %
| |
| MSIV STATUS __ 0 8 :
| |
| SLC PMP DISCH PRESS A 0 psig SLC PMP DISCH PRESS B 0 psig PANEL 9-4 MISCELLANEOUS PANELS STATUS PRESS (psig) FLOW (gpm)
| |
| RCIC OPER 900 390 DIESEL GEN 1 INOP :
| |
| RWCU A TRIP O O DIESEL GEN 2 TRIP :
| |
| RWCU B TRIP 0 0 SBGT A TRIP :
| |
| RRP A TRIP % SPEED SBGT B TRIP :
| |
| RRP B TRIP % SPEED DRYWELL COOLING TRIP :
| |
| TORUS WATER TEMP 123 F DRYWELL TEMP 162 F
| |
| | |
| RADIATION MON 8 TORS i
| |
| 1990 EVALUATED EXERC3SE TIME = 0945 t= 01:45 STATION DESCRIPTION READINO (mR/hri 1 Rx Bldg Fuel Pool Area (SE Sth Floor) DOWNSCALE 2 Rx Bldg Fuel Pool Area (SE Sth Floor) DOWNSCALE 3 Rx Dldg New Fuel Area (SE Sth Floor) DOWNSCALE 4 Rx Bldg Rx Water Cleanup Demineralizer DOWNSCALE Area (SW 3rd Floor) 5 Rx Bldg Sludge and Decant Pump Area DOWNSCALE (S 2nd Floor) 6 Rx Bldg Neutron Monitor System Index DOWNSCALE ,
| |
| Area (TIP Room ist Floor) 7 Rx Bldg Neutron Monitor System Drive DOWNSCALE Mech Area (SE lat Floor) 8 Rx Bldg Control Rod Hydraulic Equipment DOWNSCALE Area (S ist Floor) '
| |
| 9 Rx Bldg Control Rod Hydraulic Equipment DOWNSCALE Area (N ist Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) __ DOWNSCALE 11 Rx Bldg RHR Pump Room (SW Quad) DOWNSCALE 12 Rx Bldg RHR Pump Room (NW Quad) DOWNSCALE 13 Rx Bldg RCIC/CS Pump Room (NE Quad) DOWNSCALE 14 Rx Bldg CS Pump Room (SE Quad) DOWNSCALE 15 Turbine Bldg Turbine Front Standard DOWNSC. ALE 16 Turbine Bldg Mezz Control Corridor DOWNSCALE 17 Turbine Bldg Basement Control Corridor DOWNSCALE 18 Turbine Bldg Rx Feed Pump Area DOWNSCALE 19 Turbine Bldg Condensate Pump Area DOWNSCALE l
| |
| 20 Control Room Main Control Room DOWNSCALE 21 Grade Level Control Corridor DOWNSCALE 22 Radwaste Control Room DOWNSCALE 23 Radweste Pump Room DOWNSCALE 24 Radwaste Basement Equipment Area DOWNSCALE 25 Radwaste Demineralizer Valve Room DOWNSCALE 26 Radwaste Conveyor Aisle Operating Area DOWNSCALE 27 SPARE 28 Radwaste Lab Area DOWNSCALE 29 Centrifuge East DOWNSCALE 30 Centrifuge West DOWNSCALE Panel 9-02 Personnel Airlock Area 903' DOWNSCALE Panel 9-02 Ladder 903' to 2nd Level DOWNSCALE l
| |
| OSH = Offscale High ll L
| |
| l
| |
| | |
| RADIATION MON 3 TORS 1990 EVALUATED EXERCISE TIME = 0945 ,
| |
| t= 01:45 l I
| |
| PANEL VBQQ i i
| |
| Rx Bldg Vent Eff (RMV-RM-40 __
| |
| 0 uci/sec ERP Stack Normal EFF'(RMP-RM-3A) o uCi/see ERP Stack High Range (RMP-RM-3B) 0 uCi/see l
| |
| Turbine Bldg Vent Eif (RMV-RM-20A) o uCi/sec Turbine Bldg High Range (RMV-RM-LOB) o uCi/see RW/ARW Bldg Combined Eff (RMV-RM-30A) o uci/see RW/ARW Bldg High Range (RMV-RM-30B) 0 uC1/see PANEL 9-10 Main Steam Rad Monitor Ch. A1, B1 15 mR/hr 15 mR/hr CH. A2, B2 15 mR/hr 15 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 1 mR/hr 1 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hr 0.6 mR/hr !
| |
| l
| |
| | |
| 't i
| |
| l i
| |
| [
| |
| 1990 EVALUATED EXERCISE TIME = 0945 l 6
| |
| Message Number lig_ t = Q1 45 i t
| |
| COOPER RUCFFAR STATION {
| |
| EMERGENCY PREPAREDNESS EXERCISE MESSAGE r Messaae fort Control Room h Messaget t
| |
| * * *
| |
| * THIS IS A DRILL * * * * .i o Begin depressurization of the' Reactor in accordance t with Technical Specification 3.7.A.1.f. ,-
| |
| l
| |
| 'I i
| |
| r i i
| |
| \i:
| |
| -r l '. ,
| |
| t l :
| |
| 5
| |
| ' "1 1
| |
| 1 m
| |
| 4
| |
| \.
| |
| l.
| |
| L .
| |
| -- - . . . - - - , - , . . -m-.-- .- .--....m. - . , - . . - .. . .n - - . . y ,. ~ m-..m r--- --,,.-.r-...,,, -,, , e
| |
| | |
| .p .
| |
| SUPPLEMENTAL SCENARIO No. 2
| |
| ]
| |
| RCIC MECHANICAL OVERSPEED TRIP TIME Scenario time 02:00 to 02:30 LOCATION: RCIC Room A. Initial Notification The operators become aware of the RCIC Turbine trip at 02:00 via MESSAGE NO. *j*. , , y ,3, B. Postulated Event The RCIC mechanical overspeed mechanism becomes unlatched for no apparent reason, and the Turbine Trip-
| |
| & Throttle valve closes. An operator must be dispatched to reset the overspeed latching device locally.
| |
| During the time it takes for an operator to get to the RCIC room and relatch the mechanical overspeed device, no reactor makeup water is available (HPCI will not start). Therefore, reactor water level decreases, but -
| |
| at a relativaly slow rate.
| |
| With reactor water level decreasing, and no makeup system available, all players are likely to assume that core damage will occur within the next hour or so.
| |
| Operators will be attempting to get a makeup system back in operation, and offsite dose projections may be started based on plant parameters (in anticipation of core damage).
| |
| C. Restoration Guidelines The postulated failure is rectified when an operator relatches the mechanical overspeed device (MESSAGE NO.
| |
| ****), thereby allowing RCIC to be returned to service.
| |
| Reactor water level will be restored using RCIC, and core damage will be averted.
| |
| l l
| |
| | |
| l-t e
| |
| t 1990 EVALUATED EXERCISE 4 TIME = 1000 Message Number ll__ t = 02:00 COOPER NUCLEAR STATION EMERGENCY. PREPAREDNESS EXERCISE MESSAGE E9ssage fort- Control' Room Simulated Plant Conditional See attached Plant Data Massaae
| |
| **** THIS IS A DRILL-****
| |
| '- -o RCIC has tripped.
| |
| o Annunciator RCIC TURB TRIPPED is lit.
| |
| i l
| |
| 1
| |
| | |
| 1990 EVALUATED EXERCISE TIME = 1000 MD: sage Number _22_ t = _02:00 Co0PER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA i PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 0 % SRM :
| |
| RHR A TRIP 0 0 REACTOR LEVEL _11_ " GEMAC RHR C TRIP 0 0 REACTOR PRESS 600 psig ,
| |
| RMR B TRIP O _
| |
| 0 ELQH (10^61bs/hr)
| |
| RHR D TRIP O O FEEDWATER A 0 :
| |
| CS A TRIP 0 0 FEEDWATER B 0 :
| |
| CS B TRIP O O MAIN STEAM A 0 : .
| |
| HPCI IsoL 50 0 MAIN STEAM B 0 :
| |
| MAIN STEAM C 0 :
| |
| DRYWELL PRESS. O psig KAIN STEAM D 0 :
| |
| TORUS LEVEL 0 ft CRD A FLOW TRIP gpm CRD B FLOW IRI.E gpm QEEH CLOSED SLC TK LEVEL 0 %
| |
| MSIV STATUS 0 8 :
| |
| SLC PMP DISCH PRESS A 0 psig SLC PMP DISCH PRESS B 0 psig PANEL 9-4 MISCELLANEOUS PANELS STATUS PRESS (psig) ELQH(gpm)
| |
| I RCIC TRIP O O DIESEL GEN 1 INOP__:
| |
| RWCU A TRIP 0 0 DIESEL GEN 2 TRIP :
| |
| RWCU B TRIP 0 0 SBGT A TRIP :
| |
| RRP A TRIP % SPEED SBGT B TRIP :
| |
| RRP B TRIP % SPEED DRYWELL COOLING TRIP :
| |
| TORUS WATER TEMP 128 F DRYWELL TEMP 165 F
| |
| | |
| i RADIATION MONITORS 1990 EVALUATED EXERCISE TIME = 1000 t= 02:00 STATION DESCRIPTIQH READING (mR/hr) 1 Rx Bldg Fuel Pool Area (SE Sth Floor) DOWNSCALE 2 Rx Bldg Fuel Pool Area (SE 5th Floor) DOWNSCALE 3 Rx Bldg New Fuel Area (SE Sth Floor) DOWNSCALE 4 Rx Bldg Rx Water Cleanup Demineralizer DOWNSCALE Area (SW 3rd Floor) 5 Rx Bldg Sludge and Decant Pump Area __ DOWNSCALE I (S 2nd Floor) )
| |
| 6 Rx Bldg Neutron Monitor System Index DOWNSCALE I Area (TIP Room ist Floor) 7 Rx Bldg Neutron Monitor System Drive DOWNSCALE Mech Area (SE ist Floor) 8 Rx Bldg Control Rod Hydraulic Equipment DOWNSCALE i Area (S ist Floor) 9 Rx Bldg Control Rod Hydraulic Equipment DOWNSCALE Area (N ist Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) DOWNSCALE 11 Rx Bldg RHR Pump Room (SW Quad) DOWNSCALE l' 12 Rx Bldg RHR Pump Room (NW Quad) DOWNSCALE 13 Rx Bldg RCIC/CS Pump Room (NE Quad) DOWNSCALE 14 Rx Bldg CS Pump Room (SE Quad) DOWNSCALE 15 Turbine Bldg Turbine Front Standard DOWNSCALI 16 Turbine Bldg Mezz Control Corridor DOWNSCALE 17 Turbine Bldg Basement Control Corridor DOWNSCALE 18 Turbine Bldg Rx Feed Pump Area DOWNSCALE 19 Turbine Bldg Condensate Pump Area _
| |
| DOWNSCALE 20 Control Room Main Control Room DOWNSCALE 21 Grade Level Control Corridor DOWNSCALE 22 Radwaste Control Room DOWNSCALE 23 Radwaste Punj; Room DOWNSCALE 24 Radwaste Basement Equipment Area DOWNSCALE t 25 Radwaste Demineralizer Valve Room DOWNSCALE 26 Radwaste Conveyor Aisle Operating Area DOWNSCALE 27 SPARE 28 Radwaste Lab Area DOWNSCALE 29 Centrifuge East DOWNSCALE 30 Centrifuge West DOWNSCALE Panel 9-02 Personnel Airlock Area 9038 DOWNSCALE _
| |
| l Panel 9-02 Ladder 903 ' to 2nd Level DOWNSCALE OSH = Offscale High l
| |
| | |
| ~
| |
| . 1 1
| |
| RADIATION MONITORS 1990 EVALUATED EXERCISE TIME = 1000 t= 02:00 PANEL VBDG 1
| |
| Rx Bldg Vent Eff (RMV-RM-40 0 uci/see l ERP Stack Normal EFF (RMP-RM-3A) o uci/see ;
| |
| ERP Stack High Range (RMP-RM-3B) o uci/see i Turbine Bldg Vent Eff (RMV-RM-20A) o uci/see Turbine Bldg High Range (RMV-RM-20B) o uci/see i RW/ARW Bldg Combined Eff (RMV-RM-30A) 0 uci/see
| |
| -RW/ARW Bldg High Range (RMV-RM-30B) o uci/see PANEL 9-10 Main Steam Rad Monitor Ch. A1, B1 15 mR/hr 15 mR/hr CH. A2, B2 15 mR/hr 15 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 1 mR/hr 1 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hr 0.6 mR/hr 1
| |
| I
| |
| | |
| j
| |
| ), i l
| |
| i
| |
| ' t l' 1990 EVALUATED EXERCISE TIME'= 1000
| |
| .)
| |
| i Message Number 12_ t = 02:00
| |
| ?
| |
| e COOPER RUCffAR'STATIQH !
| |
| I EYERGENCY PREPAREDNESS EXERCISE MESSAGE ,
| |
| Messaae fari ' Control' Room. t Messager
| |
| *'.** THIS IS A DRILL **** l o HPCI *. solation cannot be reset. !
| |
| i i
| |
| I I
| |
| i t
| |
| Y P
| |
| ?
| |
| t
| |
| ?
| |
| )
| |
| A i
| |
| i
| |
| [
| |
| i
| |
| 'I1
| |
| ;l-r =
| |
| t . ..
| |
| +I >~
| |
| ~ - - - -
| |
| | |
| I 1990 EVALUATED EXERCISE TIME = 1000 Message Number 23 t = 02:00 COOPER fiUCLEAR STATION <
| |
| EMERGENCY PREPAREDNESS EXERCISE MESSAGE FOR CONTROLLER USE ONLY ;
| |
| Controller Information: I o RCIC has tripped on mechanical overspeed. Any attempt to start HPCI is unsuccessful.
| |
| o Reactor water level will begin to decrease slowly until RCIC is returned to service. -
| |
| o RCIC will be returned to service within approximately 30 minutes, and the core will remain covered.
| |
| Expected Actions:
| |
| o An operator should be dispatched to the RCIC room to relatch the. mechanical overspeed device.
| |
| o operators will probably intensify efforts to get HPCI in service.
| |
| o Possible discussion relative to declaration of a GENERAL EMERGENCY may occur at this time.
| |
| f
| |
| - .m_
| |
| | |
| l; I
| |
| a I
| |
| 1990 EVALUATED EXERC!SE TIME = 1015 Message Number _11_ t = 02:15 COOPER NUCLEAR STATION l EMERGENCY PREPAREDNESS EXERCISE MESSAGE l t
| |
| i i
| |
| Massace fort Control Room i
| |
| ;?
| |
| I simulated Plant conditions: See attached Plant Data f
| |
| Messaaet ;
| |
| **** THIS IS A DRILL **** !
| |
| t
| |
| +
| |
| t i
| |
| [
| |
| l I' +
| |
| lL f
| |
| I l .
| |
| _._________ _ _ ____j
| |
| | |
| 1990 EVALUATED _ EXERCISE TIME = 1015 ;
| |
| MD sage Number _11_ t= 02:15 {
| |
| COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) ELQH(gpm) REACTOR POWER 0 % SRM :
| |
| RHR A TRIP 0 0 REACTOR LEVEL 8 " GEMAC :
| |
| RHR C TRIP 0 0 REACTOR PRESS 600 psig '
| |
| RH3.B TRIP 0 0 FLOW (10^61bs/hr) ;
| |
| RHR D TRIP O O FEEDWATER A 0 : .
| |
| CS A TRIP 0 0 FEEDWATER B 0 CS B TRIP 0 0 MAIN STEAM A 0 :
| |
| HPCI ISOL- 50 0 MAIN STEAM B o :
| |
| * MAIN STEAM C 0 :
| |
| DRYWELL PRESS. O psig MAIN STEAM D 0 :
| |
| TORUS LEVEL 0 ft CRD A FLOW TRIP gpm ,
| |
| CRD B FLOW IRIE gpm QEIH , CLOSED SLC TK LEVEL 0 %
| |
| MSIV STATUS 0 8 :
| |
| l SLC PMP DISCH PRESS A 0 psig l
| |
| SLC PMP DISCH PRESS B 0 psig PANEL 9-4 MISCELLANEOUS PANELS 1
| |
| l STATUS PRESS (psig) ELQH(gpm) l RCIC TRIP O O DIESEL GEN 1 INOP :
| |
| RWCU A TRIP 0 0 DIESEL GEN 2 TRIP ;
| |
| RWCU B TRIP - 0 0 SBGT A TRIP :
| |
| RRP A TRIP % SPEED SBGT B TRIP :
| |
| RRP B TRIP % SPEED DRYWELL COOLING TRIP :
| |
| TORUS WATER TEMP 132 F DRYWELL TEMP 168 F
| |
| | |
| ^ ~
| |
| l l
| |
| RADZATION MON 8 TORS j 1990 EVALUATED EXERCISE TIME = 1015 t= 02:15 STATION DESCRIPTION READING (mR/hr) l l
| |
| 1 Rx Bldg Fuel Pool Area (SE 5th Floor) DOWNSCALE 2 RX Bldg Fuel. Pool Area (SE Sth Floor) DOWNSCALE 3 Rx Bldg New Fuel Area (SE 5th Floor) DOWNSCALE 4 Rx Bldg Rx Water Cleanup Domineralizer DOWNSCALE _
| |
| Area (SW 3rd Floor) 5 Rx Bldg Sludge and Decant Pump Area DOWNSCALE (S 2nd Floor) 6 Rx Bldg Neutron Monitor System Index DOWNSCALE Area (TIP Room ist Floor)
| |
| * 7 Rx Bldg Neutron Monitor System Drive DOWNSCALE Mech Area (SE ist Floor) 8 ?.x Bldg Control Rod Hydraulic Equipment DOWNSCALE Area (S 1st Floor) 9 Rx Bldg Control Rod Hydraulic Equipment DOWNSCALE Area (N 1st Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) DOWNSCALE 11 Rx Bldg RHR Pump Room (SW Quad) DOWNSCALE 12 Rx Bldg RHR Pump Room (NW Quad) DOWNSCALE 13 Rx Bldg RCIC/CS Pump Room (NE Quad) DOWNSCALE 14 Rx Bldg CS Pump Room (SE Quad) DOWNSCALE 15 Turbine Bldg Turbine Front Standard DOWNSCALE 16 Turbine Bldg Mezz Control Corridor DOWNSCALE 17 Turbine Bldg Basement Control Corridor DOWNSCALE 18 Turbine Bldg Rx Feed Pump Area DOWNSCALE 19 Turbine Bldg Condensate Pump Area DOWNSCALE 20 Control Room Main Control Room DOWNSCALE 21 Grade Level Control Corridor DOWNSCALE ,
| |
| i 22 Radwaste control Room DOWNSCALE 23 Radwaste Pump Room DOWNSCALE l 24 Radwaste Basement Equipment Area DOWNSCALE 25 Radwaste Domineralizer Valve Room DOWNSCALE 26 Radwaste Conveyor Aisle Operating Area DOWNSCALE 27 SPARE 28 Radwaste Lab Area DOWNSCALE 29 Centrifuge East DOWNSCALE 30 Centrifuge West DOWNSCALE Panel 9-02 Personnel Airlock Area 9038 DOWNSCALE L Panel 9-02 Ladder 903' to 2nd Level DOWNSCALE OSH = Offscale High I-l
| |
| | |
| RADIATION MON 8 TORS 1990 EVALUATED EXERCISE TIME = 1015 !
| |
| t= 02t15 j PANEL VBDG Rx Bldg vent Eff (RMV-RM-40 0 uci/ wee l ERP Stack Normal EFF (RMP-RM-3A) o uci/sec :
| |
| ERP Stack High Range (RMP-Rh-3P; o uci/sec 1 Turbine Bldg Vent Eff (RMV-RM-20A) o uci/sec l Turbine Bldg High Range (RMV-RM-208) o uci/sec }
| |
| RW/ARW-Bldg Combined Eff (RMV-RM-30A) o uci/see ,
| |
| RW/ARW Bldg High Range (RMV-RM-30B) 0 uci/sec ;
| |
| PANEL 9-10 ,
| |
| Main Steam Rad Monitor Ch. A1, B1 15 mR/hr 15 mR/hr CH. A2, B2 15 mR/hr 15 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 1 mR/hr 1 mR/hr !
| |
| Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hr 0.6 mR/hr 6 i
| |
| 6 M
| |
| P l
| |
| i t
| |
| I.
| |
| l i-
| |
| | |
| i i
| |
| i 1990 EVALUATED EXERCISE- TIME = +1015 !
| |
| Message Number 21g_ t = <02 30 COOPER NUCLEAR STATION f TJERGENCY PREPAREDNESS EXERCISE MESSAGE i
| |
| {
| |
| ? . l
| |
| 'Massaae' fort Operator in RCIC Room r
| |
| Messaget !
| |
| I
| |
| **** THIS IS A DRILL ****
| |
| i o You found the mechanical overspeed mechanism unlatched.
| |
| You have now reset it.
| |
| i i
| |
| t I
| |
| 4 t
| |
| i b
| |
| I j .' ,
| |
| l L
| |
| I- 1 L
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| . _- . . __ , . . . .m. . ,_ . . _ _. , _- . - _ . . , _ . . , _ . . -, . _ . _
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| i
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| , 1990 EVALUATED EXERCISE TIME = 1030 Message Number 1 t ='pl:lg p_OOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESS &qE ,
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| i Messaae for Control Room
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| _.e Simulated Plant Conditions: See attached Plant Data Messaae:
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| **** THIS IS A DRILL ****
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| a ,
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| 1990 EVALUATED EXERCISE TIME =- 1030 M csage Number _11_ t= 02:30 COOPER NUCLEAR STATION !
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| l EMERGENCY PREPAREDNESS EXERCISE PLANT DATA l 1
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| l PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 0 % SRM :
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| RHR A TRIP O O REACTOR LEVEL _11_ " GEMAC :
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| RHR C TRIP O O REACTOR PRESS 600 psig RHR B TRIP- 0 __
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| o FLOW (10^61bs/hr)
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| RHR D TRIP 0 0 FEEDWATER A 0 :
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| -CS A TRIP FEEDWATER B 0 :
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| O O CS B TRIP O O MAIN STEAM A 0 :
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| HPCI ISOL ..,_50 0 MAIN STEAM B -0 :
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| MAIN STEAM C 0 :
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| DRYWELL PRESS. O psig MAIN STEAM D o :
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| TORUS LEVEL 0- ft CRD A FLOW IBIE gpm CRD'B FLOW. IRIE gpm OPEN CIDSED SLC TK LEVEL 0 %
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| MSIV STATUS 0 8 :
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| SLC PMP DISCH PRESS A 0 psig SLC PMP DISCH PRESS B 0 psig l.
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| EANEL 9-4 MISCELLANEOUS PANELS -1 STATUS' PRESS (psig) FLOW (gpm)
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| RCIC OPER 700 400 DIESEL GEN 1 INOP :
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| L.
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| RWCU A TRIP. 0 0 DIESEL GEN 2 TRIP :-
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| RWCU B TRIP O O SBGT A TRIP ':
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| l l .RRP A TRIP % SPEED SBGT B TRIP :
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| RRP B ' TRIP _ % SPEED DRYWELL COOLING TRIP :
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| l: TORUS WATER TEMP 136 F 1
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| DRYWELL TEMP 172 F l
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| l
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| 1990 EVALUATED EXERCISE TIME'= 1045 Message Number 27' t = 02:45 i QOOPER NUCLEAR STATION ,
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| EMEEQRlLQJ PREPAREDNESS EXERCISE MESSAGE i
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| Messaae for: Control Room Simulated Plant Conditions: See attached Plant Data' Messace:
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| **** THIS IS A DRILL **** l 4
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| i i
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| i I
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| i i
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| f
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| ?
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| s i
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| !=
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| RADIATION MONITORS q l
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| 1990~ EVALUATED EXERCISE TIME = 1030 l t= 02:30 ;
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| STATION DESCRIPTION READING (mR/hr) 1 Rx Bldg Fuel Pool Area (SE Sth Floor) DOWNSCALE 2 Rx Bldg Fuel Pool Area (SE Sth Flcor) DOWNSCALE
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| .3' Rx Bldg New Fuel Area (SE Sth Floor) DOWNSCALE 4 Rx Bldg Rx Water Cleanup Demineralizer DOWNSCALE Area (SW 3rd Floor) 5 Rx Bldg Sludge-ar.d Decant Pump Area DOWNSCALE y .
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| '(S 2nd Floor) +
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| H 6 Rx Bldg Neutron Monitor System Index DOWNSCALE Area (TIP Room ist Floor) i 7 Rx Bldg Neutron Monitor System Drive DOWNSCALE '
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| Mech Area (SE 1st Floor) 8 Rx Bldg Control Rod Hydraulic Equipment DOWNSCALE Area (S 1st Floor) 9 Rx Bldg Control Rod Hydraulic Equipment DOWNSCALE Area (N ist Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) DOWNSCALE 11 Rx Bldg RHR Pump ' Room (SW Quad, DOWNSCALE 12 Rx Bldg RHR Pump Room (NW Quad) DOWNSCALE 13 Rx Bldg RCIC/CS Pump Room (NE Quad) DOWNSCALE 14 Rx Bldg CS Pump Room (SE Quad) DOWNSCALE 15 Turbine Bldg Turbine Front Standard DOWNECALE ,
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| 16 Turbine Bldg Mezz Control Corridor DOhJCCALE 17 Turbine Bldg Basement Control Corridor DOWNSCALE 18 Turbine Bldg Rx Feed Pump Area DOWNSCALE 19 Turbine Bldg Condensate Pump Area DOWNSCALE '
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| 20 Control Room Main Control Room DOWNSCALE 21 Grado Level Control Corridor DOWNSCALE L 22 Radwaste-Control Room DOWNSCALE
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| : l. . . 23 Radwaste Pump Room DOWNSCALE s 24 Radwaste_ Basement Equipment Area DOWNSCALE 25 'Radwaste Demineralizer Valve Room DOWNSCALE r 26 Radwaste Conveyor Aisle Operating Area DOWNSCALE L 27 . SPARE 28 Radwaste Lab Area DOWNSCALE 29 Centrifuga East DOWNSCALE 30 Centrifuge West DOWNSCALE
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| /
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| Panel 9-02 Personnel Airlock Area 903' DOWNSCALE L . Panel 9-02 Ladder 903' to 2nd Level DOWNSCALE OSH = Offscale'High
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| ~
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| 1 l :
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| l
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| \
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| l . - . . _ - _ _ _ - - _ _ _ ___-
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| t RADIATION MONITORS 1990 EVALUATED EXERCISE TIME = 1030 t= 02:30 PANEL VBDG Rx Bldg Vent Eff (RMV-RN-40 0 uCi/see ERP Stack Normal EFF (RMP-kM-3A) o uCi/see ERP Stack High Range (RMP-RM-3B) 0 uCi/see Turbine Bldg Vent Eff.(RMV-RM-20A) o uCi/see Turbine Bldg High Range (RMV-RM-208) 0 uCi/see RW/ARW Bldg Combined-Eff (RMV-RM-30A) 0 uCi/sec RW/ARW Bldg High Range (RMV-RM-308) o uCi/sec PANEL 9-10 i Main Steam Rad Monitor Ch. A1, B1 15 mR/hr 15 mR/hr CH. A2, B2 15 mR/hr 15 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 1 mR/hr 1 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hr 0.6 mR/hr i
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| >A.
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| 11990 EVALUATED EXERCISE TIME = 1045- '
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| M;acage Number _22_ t= 02:45 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA .
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| PANEL 9-3 PANEL 9-5 STATUS PRESg(psig) FLOW (gpm) REACTOR POWER 0 % SRM :
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| RHR A _ TRIP O O REACTOR LEVEL _).1_ " 9.EMAC : ,
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| RHR C- TRIR__ 0 0 REACTOR PRESS 300 psig RHR B TRIP O O FLOW (10^61bs/hr)
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| RER'D' TRIP 0 0 FEEDWATER A _2.
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| CS A TRIP O O FEEDWATER B 0 CS B TRIP O O MAIN STEAM A 0 :
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| HPCI ISOL 50 0 MAIN STEAM B 0
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| .KAIN STEAM C 0 : ;
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| DRYWELL PRESS. O psig MAIN STEAM D 0 : 1
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| ' TORUS LEVEL _.0 ft CRD A FLOW IRIE.gpm [
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| i CRD B FLOW TRIP gpm .
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| OPEN CLOSED ,
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| SLC TK LEVEL 0 %
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| MSIV STATUS 0 8 : ;
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| SLC PMP DISCH PRESS A 0 psig SLC PMP DISCH PRESS B: O psig PANEL 9-4 MISCELLANEOUS PANELS STATUS PRESS (psig) FLOW (gpm) 1 LRCIC' ODER 400 201 DIESEL GEN 1 INOP :
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| RWCU A TRIP 0- 0 DIESEL GEN 2 TRIP :
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| " TRIP :
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| 'LRWCU B TRIP- 0 0 SBGT A 4
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| RRP A TRIP % SPEED SBGT B TRIP :
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| RRP B TRIP % SPEED DRYWELL COOLING TRIP :
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| TORUS WATER TEMP 140 F DRYWELL TEMP 175 F ,
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| b RADIATION MONITORS-TIME = 1045
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| - 1990. EVALUATED EXERCISE- t= 02:45 -i TN L STATION DESCRIPTION READING (mR/hr)
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| Ri 1 Rx Bldg Fuel Pool Area (SE Sth Floor) r/OWNSCALE r 2 Rx Bldg Fuel Pool Area (SE 5th Floor) DOWNSCALE 3 .Rx-Bldg New Fuel Area (SE Sth Floor) DOWNSCALE 4 Rx Bldg Rx Water Cleanup Demineralizer 70RNSCALE -
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| F Area (SW 3rd Floor) 5- Rx Bldg Sludge and Decant Pump T. aa ff:$ SCALE (S ' 2r,d Floor) 6 Rx Bldg Neutron Monitor System Index DOWNSCALE >
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| Area (TIP Room ist 11oor)
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| -7 Rx Bldg Neutron Monitor System Drive __ DOWNSCALE Mech Area (SE 1st Floor) 8 Rx Bldg Control Rod Hydraulic Equipment DOWNSCALE '
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| Area (S ist Floor) 9' Rx Bldg Control Rod Hydraulic Equipment DOWNSCALE y Area (N ist Floor) 4 10 Rx Bldg HPCI Pump Room (SW Quad) DOWNSCALE ,
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| 11 Rx Bldg RHR Pump Room (SW Quad) DOWNSCALE 12 Rx Bldg RHR Pump Room (NW Quad) DOWNSCALE 13 Rx ' Bldg RCIC/CS Pump Room (NE Quad) DOWNSCALE ,
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| ' ~14 Rx Bldg CS Pump Room (SE Quad) DOWQQALE 15 Turbine Bldg. Turbine Front Standard _
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| DOWNSCALE 16 Turbine Bldg Mezz-Control Corridor DOWNSCALE 17 Turbine Bldg Basement Control Corridor DOWNSCALE 18 Turbine-Bldg Rx Feed Pump Area DOWNSCALE 19 Turbine Bldg Condensate Pump Area DOWNSCALE '
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| 20 Control Room Main Control Room DOWNSCALE 21 Grade Level' Control Corridor DOWNSCALE 22 Radwaste Control Room DOWNSCALE 23 Radwaste Pump Room DOWNSCALE 24 Radwaste Basement Equipment Area DOWNSCALE' I
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| 25 Radwaste Demineralizer Valve Room DOWNSCALE 26 Radwaste Conveyor Aisle Operating Area DOWNSCALE l, .27 SPARE 28 Radwaste Lab Area DOWNSCALE L
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| ! 29 Centrifuge East DOWNSCALE 30 Centrifuge West DOWNSCALE 4 I
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| L Panel 9-02 Personnel Airlock Area 903' DOWNSCALE Ladder 903' to 2nd Level DOWNSCALE-l . Panel 9-02 ->
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| OSH = Offscale High I
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| , . _ . m.
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| RADIATION MONITORS-1990 EVALUATED' EXERCISE TIME = 1045-t= 02:45 PANEL VBDG Rx Bldg Vent-Eff (RMV-RM-40 0 uCi/sec ERP Stack Normal EFF (RMP-RM-3A) 0- uci/sec ERP Stack High Range (RMP-RM-3B) 0 uci/see Turbine Bldg Vent 1Eff (RM7-RM-20A) 0 uci/see >
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| Turbine Bldg High Range (RMV-RM-20B) 0 uci/sec RW/ARW Bldg Conbined Eff (RMV-RM-30A) 0 uCi/see RW/ARW Bldg High Range (RMV-RM-30B) 0 uC1/sec PANEL 9-10 Main Steam Rad Monitor Ch. A1, B1 15 mR/hr is mR/hr CH. A2, B2 15 mR/hr 15 mR/hr
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| -SJAF Off Gas Log Rad Monitor Ch. A, B 1 mR/hr 1 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hr 0.6 mR/hr i 1
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| i L
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| f i
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| ll 1990 EVALUATED EXERCISE TIME = 11QO-L J
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| ." Message Number la__
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| - t = 03:00 ;
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| COOPER NUCLEAR STATION-EMERGENCY PREPAREDNESS EXERCISE MESSAGE -
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| Messace for: Control Room i
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| i, Simulated Plant Conditions 1 See attached Plant Data
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| 'Messace:
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| **** THIS IS A DRILL ****
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| l l !
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| 1' l !
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| o
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| ~
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| s
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| ?1990LEVALUATED EXERCISE TIME = 1100 MOcsage Number _21_ t= =03:00 l
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| COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS' EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) ELQH(gpm) REACTOR POWER 0 % 3RM :
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| 'RHR A TRIP' O O REACTOR LEVEL 35 " GEMAC :
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| ~RHR-C' TRIP O O REACTOR PRESS 200 psig RHR B ' TRIP 3 0 ELQH (10^61bs/hr)
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| RHR D. TRIP O O FEEDWATER A 0 :
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| CS A TRIP O O FEEDWATER B 0 :
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| CS B TRIP O O MAIN STEAM A 0 :
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| HPCI ISOL 50' 'O MAIN STEAM B 0 :
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| MAIN STEAM C 0 :
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| DRYWELL PRESS. O psig MAIN STEAM D 0 :
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| -TORUS LEVEL 0 ft CT- A FLOW IBIE gpm C.,/ B FLOW IRIE gpm QEEH CLOSED.
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| SLC~TK LEVEL 0 %
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| MSIV STATUS 0 _
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| 8' :
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| SLC PMP DISCH PRESS A 0 psig SLC PMP DISCH PRESS B 0 psig PANEL 9-4 MISCELLANEOUS PANRLE-STATUS. EBES1(psig) ELQH(gpm)
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| RCIC OPER 300 196 DIESEL GEN 1 INOP :
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| RWCU.A TRIP O O DIESEL GEN 2 TRIP :
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| 'RWCU B TRIP O O SBGT A TRIP :
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| RRP A TRIP % SPEED SBGT B TRIP :
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| RRP B TRIP % SPEED DRYWELL COOLING TRIP :
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| TORUS WATER TEMP 143 F DRYWELL TEMP 177 F l
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| RADIATION MONITORS 1990 EVALUATED. EXERCISE TIME = 1100 t= 03:00 STATION DESCRIPTION READING (mR/hr)-
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| Rx Bldg Fuel Pool Area (SE 5th Floor) DOWNSCALE 1 i Rx Bldg Fuel Pool Ares (SE Sth Floor) DOWNSCALE 2
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| Rx-Bldg New Fuel Area (SE Sth Floor) DOWNSCALE 3
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| Rx Bldg RX Water Cleanup Demineralizer DOWNSCALE '
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| 4 Area (SW 3rd Floor) DOWNSCALE 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) DOWNSCALE 6 Rx Bldg Neutron Monitor System Index Area (TIP Room ist Floor) DOWNSCALE 7 Rx Bldq Neutron Monitor System Drive Mech Area (SE 1st Floor) DOWNSCALE 8 Rx Bldg Control Rod-Hydraulic Equipment Area (S lst Floor) DOWNSCALE 9 Rx Bldg Control Rod Hydraulic Equipment _,
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| Area (N 2 0t Floor) DOWNSCALE 10 Rx Bldg HPCI Pump Room (SW Quad) ,
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| Rx Bldg RHR Pump Room (SW Quad) DOWNSCALE 11 DOWNSCALE 12 Rx Bldg RHR Pump Room (NW Quad)
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| Ibc Bldg RCIC/CS Pump Room (NE Quad) DOWNSCALE 13 DOWNSCALE 14 Rx Bldg CS Pump Room (SE Quad) 4 Turbine Bldg: Turbine Front' Standard DOWNSCALE 15 DOWNSCALE 16- Turbine Bldg Mezz Control Corridor DOWNSCALE
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| , l'7 Turbine Bldg Basement Control Corridor DOWNSCALE 18' Turbine Bldg Rx Feed. Pump Area DOWNSCALE 19 ! Turbine Bldg Condensate Pump Area DOWNSCALE 20 Control Room Main Control-Room DOWNSCALE ,
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| 21 Grade Level' Control' Corridor DOWNSCALE 22 Radwaste Control Room DOWNSCALE 23 Radwaste Pump Room .
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| Radwaste Basement Equipment Area. DOWNSCALE
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| -24 DOWNSCALE l- 25 Radwaste Demineralizer Valve Room DOWNSCALE 26 Radwaste Conveyor Aisle Operating Area L
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| l 27 SPARE DOWNSCALE L 28 Radwaste Lab Area DOWNSCALE Centrifuge East 29 DOWNSCALE 30 Centrifuge West DOWNSCALE Panel 9-02 Personnel Airlock Area 903' DOWNSCALE L Panel 9-02 ' Ladder 903' to 2nd Level 1- j j:
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| .OSH'= Offscale High l
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| e
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| ' RADIATION MONITORS 1990 EVALUATED EXERCISE- TIME = 1100 t= 03:00 PANET,VBDG Ibc Bldg Vent Ef f (RMV-RM-40 0 uCi/see ERP Stack Normal EFF (RMP-RM-3A) o uCi/sec ,
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| ERP Stack High Range (RMP-RM-3B) o uCi/sec Turbine' Bldg Vent Eff (RMV-RM-20A) 0 uCi/see Turbine-Bldg High Range (RMV-RM-20B) o uci/see RW/ARW Bldg Combined Eff (RMV-RM-30A) o uC1/see RW/ARW Bldg High Range (RMV-RM-30B) 0 uCi/see PANEL 9-10 Main Steam Rad Monitor Ch. A1, B1 15 mR/hr 15 mR/hr CH. A2, B2 15 mR/hr 15 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 1 mR/hr 1 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B ,_
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| 0.6 mR/hr 0,6 mR/hr g
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| l 1-l l
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| L '
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| l f
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| 1990 EVALUATED EXERCISE TIME = 1115 Message Number 21 t = 03:15 COOPER NUCLEAR STATION El,'ERGENCY PREPAREDNESS EXERCISE MESS AGE Messace for: Control Room Simulated Plept Conditions: See attached Plant Data Messace:
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| **** THIS IS A DRILL ****
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| 1
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| {
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| :i
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| 't i
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| r 4
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| 4 1990TEVALUATED' EXERCISE TIME = 1115-
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| , fMacsage Number',_21_. t= 03:15 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 ETATUS PRESS (psig) ELQH(gpm) REACTOR POWER 0 % S RM :
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| -RRR A TRIP O O REACTOR LEVEL _11_ " GEMAC :
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| RHR C _ TRIP O O REACTOR PRESS 160 psig RHR B TRIP O O FLOW (10^61bs/hr)
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| RHR D TRIP' O O FEEDWATER A 0 :
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| CS A TRIP O O FEEDWATER B 0 :
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| CS B TRIP O O MAIN STEAM A 0 :
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| HPCI ISOL 50 0 MAIN STEAM B 0 :
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| MAIN ~ STEAM C 0 :
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| 'DRYWELL PRESS. O psig MAIN STEAM D. G :
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| . TORUS LEVEL- O ft CRD A FLOW IBIE gpm CRD B FLOW- TRIP gpm QEEH CLOSED-SLC TK LEVEL 0 %
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| .MSIV STATUS 0 8 :
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| SLC PMP DISCH PRESS A 0 psig SLC PMP DISCH. PRESS B 0 - psig PANEL 9-4 MISCELLANEOUS' PANELS STATUS PRESS (psig) ELQW(gpm).
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| RCIC OPER 250 '192 DIESEL GEN 1 INOP :
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| 'RWCU A TRIP O O DIESEL GEN 2 TRIP :
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| 'RWCU B. TRIP O O SBGT A TRIP :
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| :RRP A TRIP % SPEED SBGT B TRIP :
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| RRP B TRIP %- SPEED DRYWELL COOLING TRIP :
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| TORUS WATER TEMP 147 F DRYWELL TEMP 179 F
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| RADIAT20N MONITORS TIME =
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| :1990 EVALUATED EXERCISE 1115 i t= 03:15 STATION DESCRIPTION READING (mR/hrP 1 Rx Bldg Fuel Pool Area (SE 5th Floor) DOWNSCALE 2 Rx Bldg Fuel Pool Area (SE 5th Floor) DOWNSCALE 3 Rx Bldg New Fuel Area (SE 5th Floor) ___DCWNSCALE 4 Rx Bldg Rx Water Cleanup Demineralizer DOWNSCALE Area (SW 3rd. Floor) 5 Rx Bldg Sludge and Decant Pump Area DOWNSCALE
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| '(S 2nd Floor) 6 Ibc Bldg Neutron Monitor System Index DOWNSCALE Area'(TIP Room 1st' Floor) 7- Rx Bldg Neutron Monitor System Drive DOWNSCALE ;
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| Mech Area (SE 1st Floor) 8 Rx Bldg Control Rod Hydraulic Equipment DOWNSCALE Area (S ist Floor) !
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| 9 Rx Bldg Control Rod Hydraulic Equipment DOWNSCALE Area (N ist Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) DOWNSCALE ;
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| 11 Ibc Bldg RER Pump Room (SW Quad) DOWNSCALE 12 Rx Bldg RHR Pump Room (NW Quad) DOWNSCALE L13 Rx Bldg RCIC/CS Pump Room = (NE Quad) DOWNSCALE 14 Rx Bldg CS Pump Room-(SE Quad) DOWNSCALE 15 Turbine Bldg Turbine Front Standard DOWNSCALE 16 Turbine Bldg Mezz Control Corridor DOWNSCALE 17= Turbine Bldg Basement Control Corridor DOWNSCALE 18- Turbine Bldg Rx. Feed Pump Area DOWNSCALE 19 ' Turbine Bldg Condensate Pump Area DOWNSCALE 20- Control Room Main Control Room DOWNSCALE 21 Grade' Level Control Corridor DOWNSCALE 22 Radwaste Control Room DOWNSCALE ,
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| 23 Radwaste Pump ~ Room DOWNSCALE
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| .24= Radwaste Basement' Equipment Area DOWNSCALE
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| '25 Radwaste Demineralizer Valve Room DOWNSCALE 26 Radwaste. Conveyor Aisle Operating Area DOWNSCALE 27 SPARE 28 Radwaste Lab Area- DOWNSCALE 29 Centrifuge East DOWNSCALE 3 0 ~- Centrifuge West DOWNSCALE g Panel 9-02 Personnel Airlock Area 903' DOWNSCALE Panel 9-02 Ladder 903' to 2nd Level DOWNSCALE l
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| l OSH = Offscale High L
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| l t
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| l l
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| ~
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| 1 1 ;
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| \. __a
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| RADIATION MONITOPS
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| ' 1990 EVALUATED EXERCISE- TIME = 1115 t= 03:15 PANEL VRQQ:
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| Rx' Bldg Vent Eff (RMV-RM-40 0 uCi/sec
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| : ERP Stack Normal EFF-(RMP-RM-3A) 0 uci/sec ERP Stack High. Range (RMP-RM-3B) o uCi/sec
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| -Turbine Bldg Vent Eff (RMV-RM-20A) 0 -uci/sec
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| . Turbine Bldg High Range (RMV-RM-20B) o uci/sec RW/ARW-Bldg Combined Eff (RMV-RM-30A). O uCi/sec RW/ARW Bldg High Range (RMV-RM-3 08) 0 uC1/sec PANET s-1?
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| M31n Steam Rad Monitor Ch. A1, B1 15 mR/hr 15 mR/hr CH. A2, B2 __
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| 15 mR/hr 15 mR/hr SJAE Off Gas Log Rad Monitor-Ch. A, B 1 mR/hr 1~mR/hr RX Bldg (Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hr 0.6 mR/hr 1
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| TIME = 1130
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| ~
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| '19.50 ' EVALUATED EXERCISE MacLage' Number _2g_ t= 03:30 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE' PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) ELQH(gpm) REACTOR POWER 0 % SRM :
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| - RHR ~- A TRIP _
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| 0 0 REACTOR LEVEL ' ,2jli._ " GEMAC :
| |
| RHR C TRIP _
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| 0 0 REACTOR PRESS -160 psig RHR B TRIP _. 0 0 ELQH' (10^ 61bs/hr)
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| RHR D TRIP O O FEEDWATER A 0 :
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| CS A TRIP 0 0 FEEDWATER B 0 :
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| CS B. TRIP O O MAIN STEAM A 0 :
| |
| HPCI. ISOL 50 0 MAIN STEAM B 0 :-
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| MAIN STEAM C 0 :
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| 'DRYWELL PRESS. O psig MAIN STEAM D 0 :
| |
| TORUS LEVEL 0 ft CRD A FLOW TBIE gpm CRD B FLOW IBIE gpm QEEE CLOSED SLC TK LEVEL' O %-
| |
| MSIV STATUS 0 8 :
| |
| SLC PMP DISCH PRESS A 0 psig SLC PMP DISCH PRESS B 0 psig PANEL 9-4 MISCELLANECUS PANELS STATUS' PRESS (psig) ELQH(gpm)
| |
| RCIC OPER 250 188 DIESEL GEN 1 INOP :
| |
| -RWCU A TRIP O O DIESEL GEN 2 TRIP ' :
| |
| RWCU B TRIP 0- 0 SBGT A TRIP :
| |
| RRP A TRIP % SPEED SBGT B TRIP :
| |
| RRP B TRIP- % SPEED DRYWELL COOLING TRIP :
| |
| TORUS WATER TEMP 150 F DRYWELL TEMP 182 F I
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| | |
| RADIATION MONITORS 1990 EVALUATED, EXERCISE TIME = 1130 t= 03:30 QTATION DESCRIPTION READING (mR/hr) 1 Rx Bldg Fuel Pool Area (SE Sth Floor) DOWNSCALE 2 Rx Bldg Fuel Pool Area (SE Sth Floor) DOWNSCALE 3 Rx Bldg New Fue.1 Area (SE 5th Floor) DOWNSCALE >
| |
| 4 Rx Bldg Rx Wat9r; Cleanup Demineralizer DOWNSCALE ,
| |
| Area (SW-3rd */loor) 5 Rx Bldg Sludge and Decant Pump Area DOWNSCALE (S 2nd Floor) 6 Rx Bldg Neutron Monitor System Index DOWNSCALE
| |
| - Area (TIP Room ist Floor) >
| |
| 7 Rx Bldg Neutron Monitor System Drive DOWNSCALE Mech Area (SE:1st Floer) l 8 RX Bldg Control Rod Hydraulic Equipment DOWNSCALE I Area (S 1st Floor)' ;
| |
| 9 Rx Bldg Control Rod Hydraulic Equipment DOWNSCALE Area'(N 1st Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) DOWNSCALE i 11 Rx Bldg RHR Pump Room (SW Quad) DOWNSCALE 12 Rx Bldg RHR Pump Room (NW Quad) DOWNSCALE-13 Rx Bldg RCIC/CS Pump Room (NE Quad) DOWNSCALE 14 Rx Bldg CS Pump Room (SE Quad) DOWNSCALE 15 Turbine Bldg-Turbine Front Standard DOWNSCALE 16 Turbine Bldg Mezz Control Corridor DOWNSCALE 17 Turbine Bldg Basement Control Corridor DOWNSCALE 18 Turbine Bldg Rx Feed ~ Pump Area DOWNSCALE 19 Turbine Bldg Condensate Pump Area DOWNSCALE 20 Control Room Main Control Room DOWNSCALE 21 Grade Level Control Corridor DOWNSCALE 22 Radwaste Control Room DOWNSCALE 23 Radwaste Pump Room DOWNSCALE 24 ~Radwaste Basement Equipment Area DOWNSCALE i 25 Radwaste Demineralizer Valve Room DOWNSCALE 1 26- Radwaste Conveyor-Aisle Operating Area DOWNSCALE 27 SPARE 28 Radwaste Lab Area DOWNSCALE 29 Centrifuge East DOWNSCALE 30 Centrifuge West DOWNSCALE Panel 9-02 Personnel Airlock Area 903' DOWNSCALE L Panel 9-02 Ladder 903' to 2nd Level DOWNSCALE '-
| |
| OSH = Offscale High l
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| l l-
| |
| | |
| RADIATION MONITORS 1990 EVALUATED EXERCISE TIME = 1130 t= 03:30 t
| |
| PANEL VBDG Rx Bldg Vent _Eff (RKV-RM-40 0 uci/see ERP. Stack Normal EFF (RMP-RM-3A)- 0 uci/see ERP Stack High Range (RMP-RM-3B) 0 uCi/sec Turbine Bldg Vent Eff (RMV-RM-20A) 0 uCi/see Turbine Bldg High Range (RMV-RM-20B) o uCi/sec RW/ARW Bldg Combined Ef f (RMV-RM-30A) 0 uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) o uCi/sec PANEL 9-10 Main Steam Rad Monitor Ch. A1, B1 15 mR/hr 15 mR/hr CH. A2, B2 15 mR/hr 15 mR/hr SJAE off Gas Log Rad Monitor Ch. A, B 1 mR/hr 1 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hr 0.6 mR/hr l
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| l
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| | |
| ?
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| ?
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| 1990 EVALUATED EXERCISE TIME: 1122 Message Number '31 t =03:30 COC PER RUCLEAR STATION EMERGENCY P.tEPAREDNESS EXERCISE MESSAGE I h
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| FOR CONTROLLER USE ONLY1 Controller Information: Conti' agency, Control Room If the radwaste shipping container 90-3-904, by the river has not been found, ;
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| issue contingency Control Room Message no. 31C.(9 03:30).
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| 3 i
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| V
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| [ -
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| ye o ,
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| s, :
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| s 1990' EVALUATED EXERCISE ~ TIME lila MOssage Number Sic t =03:30 COOPER NUCLEAR STATION
| |
| . EMERGENCY PREPAREDNESS EXERCISE MESSAGE i
| |
| contincency Messaces fort Control Room (CR)
| |
| - Messace:
| |
| **** THIS IS A DRILL **** ;
| |
| This is the Security Shift Supervisor in the CAS. The Protected Area Patrol Guard states that he sees a yellow (actual color is orange) crate outside the i
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| protected area fence on the northeast corner of the plant by the river, i
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| i I
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| !~
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| l !
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| m l'
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| - 1990. EVALUATED EXERCISE TIME: +1130 Message Number 32 t =03:30-04:00 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE EQR-CONTROLLER USE ONLY; controller Information: Contingency, Site "C" Search Party o ' ite weather is clear skies and gusty winds, o- Team members will not-be able to move the container without equipment that can lift /. move 3300 pounds. The container is at the river bank in about two feet of water.
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| o : CAUTION: Avoid injury. Ensure team member have safety. equipment (ie. safety rope, life vest) before approaching.the-container.
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| o The. radiation reading at the top of the box are 2 mR/hr at 3" and <1'mR/hr at
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| -3' feet. Water samples are as. read. .
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| Soil,~ vegetation and water samples are as read.
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| o
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| ' Expected Actions o- Notify EOF.
| |
| -o Team members will take water and possible soil'and vegetation samples.
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| I s
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| 4
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| _.__1____...__
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| | |
| 1990 EVALUATED EXERCISE TIME = 1145
| |
| ' Message. Number __2]_, t = 03:45 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Messace for: Control Room Simulated Plant conditions: See attached Plant Data i
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| Messaae:
| |
| **** THIS IS A DRILL ****
| |
| ,y-*
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| | |
| 1990 EVALUATED' EXERCISE TIME = 1145 MODcage Number _2)_. t = 103:45 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5
| |
| ~$TATUS PRESS (psig) ELQH(gpm) REACTOR POWER 0 % SRM :
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| RHR A TRIP O O REACTOR' LEVEL _11_ " GEMAC : ,
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| RHR C: TRIP O O REACTOR PRESS 160 psig RHR B- TRIP O O FLOW (10^61bs/hr)
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| RHR D TRIP O O FEEDWATER A 0' :
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| CScA TRIP O O FEEDWATER B 0 :
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| .CS B- TRIP O O MAIN STEAM A 0 :
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| HPCI ISOL 50 0 ~ MAIN STEAM B o :
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| MAIN STEAM C 0 :
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| DRYWELL PRESS. O psig MAIN STEAM D 0 :
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| ' TORUS LEVEL 0 ft CRD A FLOW TRIP gpm CRD B FLOW TRIP gpm ,
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| OPEN CLOSED ,
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| SLC TK LEVEL 0 %
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| MSIV-STATUS 0~ 8' :
| |
| SLC PMP DISCH PRESS A 0 psig SLC PMP DISCH PRESS B 0 psig_
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| PANEL 9-4 MISCELLANEOUS PANELS
| |
| ' STATUS PRESS (psig) FLOW (gpm)
| |
| RCIC- OPER 250 185 DIESEL GEN l' INOP :
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| RWCU A' _, TRIP 0 0 DIESEL GEN 2 TRIP :
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| 'RWCU B TRIP O O SBGT A TRIP :
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| , '_RRP A TRIP % SPEED SBGT B TRIP :
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| 'RRP B TRIP % SPEED DRYWELL COOLING TRIP :
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| TORUS WATER TEMP 154 F DRYWELL TEMP 186 F
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| | |
| RADIATION MONZTORS '
| |
| 1990 EVALUATED EXERCISE TIME = 1149 t= 03:45 STATION DESCRIPTION READING (mR/hr) t 1 Rx Bldg Fuel Pool Area (SE 5th Floor) DOWNSCALE 2 Rx Bldg Fuel Pool Arma (SE 5th Floor) DOWNSCALE i 3 Rx Bldg New Fuel Araa (SE Sth Floor) DOWNSCALE 4= Rx Bldg Rx, Water Cleanup Demineralizer DOWNSCALE Area-(SW 3rd Floor) 5 Rx Bldg Sludge and Decant Pump Area DOWNSCALE (S 2nd Floor) 6 Rx Bldg Neutron Monitor System Index DOWNSCALE Area-.(TIP Room ist Floor)
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| '7 Rx Bldg Neutron Monitor System Driva DOWNSCALE Mech Area (SE 1st Floor) 8 Rx Bldg Control Rod Hydraulic Equipment DOWNSCALE __
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| Area (S 1st Floor) 9 Rx Bldg Control Rod Hydraulic Equipment DOWNSCALE Area (N 1st Flour) 10 lbc Bldg HPCI Pump Room (SW Quai) DOWNSCALE 11 Rx Bldg RHR Pump Room (SW Quad) ' DOWNSCALE 12 Rx Bldg RHR Pump Room (NW Quad) DOWNSCALE 13 RX Bldg RCIC/CS Pump Room (NE Quad) DOWNSCALE 14 Rx Bldg CS Pump Room (SE Quad) DOWNSCALE 15 Turbine-Bldg Turbine Front Standard DOWNSCALE 16 Turbine Bldg Mezz Control Corridor DOWNSCALE 17 Turbine Bldg Basement Control Corridor DOWNSCALE 18 Turbine Bldg Rx Feed Pump Area DOWNSCALE '
| |
| 19 Turbine Bldg Condensate Pump Area DOWNSCALE 20 Control Room Main Control Room DOWNSCALE 21 Grade Level Control Corridor DOWNSCALE 22 Radwaste Control Room DOWNSCALE 23 Radwaste Pump Room DOWNSCALE 24 .Radwaste Basement Equipment Area DOWNSCALE 25 Radwaste Demineralizer. Valve Room DOWNSCALE 26 Radwaste Conveyor Aisle Operating Area DOWNSCALE 27 SPARE 28 Radwaste Lab' Area DOWNSCALE 29 ' Centrifuge' East DOWNSCALE 30' Centrifuge West DOWNSCALE Panel 9-02 Personnel Airlock Area 903' DOWNSCALE
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| ' Panel 9-02 Ladder 903' to 2nd Level DOWNSCALE
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| 'OSH = Offscale High 1
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| l l'
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| ll l
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| t \
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| RADIATION MONITORS ,
| |
| '1990 EVALUATED EXERCISE TIME = 1145 ,
| |
| t= 03:45 PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40. O uCi/see ERP Stack Normal EFF (RMP-RM-3A) 0 uCi/see ERP Stack High Range (RMP-RM-3B) 0 uCi/see Turbine Bldg Vent Eff (RMV-RM-20A) o uCi/see Turbine Bldg High Range (RMV-RM-208) 0 uCi/sec RW/ARWEBldg Combined Eff (RMV-RM-30A) o uci/sec RW/ARW Bldg High Range.(RMV-RM-30B) 0 uCi/see PANEL'9-10 ,
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| Main Steam Rad Monitor Ch. A1, B1 15 mR/hr 15 mR/hr .
| |
| CH. A2, B2 15 mR/hr 15 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 1 mR/hr 1 mR/hr i Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hr 0.6 mR/hr l^
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| l i
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| u
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| I 1990' EVALUATED EXEACISE TIME = +1145
| |
| . - Messe.ge Number lag t = 03:45 l
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| : h. . 04:00 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE
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| ~ Messane for: Maintenance crew at DG #2-Messace:
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| **** THIS IS A DRILL ****
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| : o. There is a lug separated from the conductor in the connector box.
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| I
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| * 2Y k
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| i e
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| \
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| 1 L
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| t 1990 EVALUATED EXERCISE TIME = 12AL r
| |
| Message Number lji- t = 04:00 COOPER NUCLEAR'STATIOb' EMERGENCY PREPAREDNESS EXERCISE MESSAJE Messace for Control Room Simulated Plant Conditions: See attached Plant Data Messace:
| |
| **** THIS IS A DRILL ****
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| -i
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| (
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| L 1
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| l >
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| l:
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| I
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| , 1990 EVALUATEO EXERCISE TIME = 1200 M;Csage Number _li_ t= 04:00 COOPER NUCLEAR STATE}H EMERGENCY PREP MDNESS EXERCISE PLANT DATA
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| =
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| PANEL 9-3 PANEL t-E 176121 PRESS (psig) FLOW (gpm) REACTOR POWER 0 % S RM :
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| RHR A _IRIP_ 0 0 REACTOR LEVEL 21. " GEMAC :
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| RHR C TRIP O O REACTOR PRESS 160 psig RHR B TRIP O O ElQH (10^61bs/hr)
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| "ER D TRIP 0 0 FEEDWATER A 0 :
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| CG A TRIP 0 0 FEEDWATER B 0 :
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| . CS B TRIP _ 0 0 MAIN STEAM A 0 :
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| H"13 _lEQL__ 50 0 MAIN STEAM B o :
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| MAIN STEAM C 0 :
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| LRYWELL PRESS. _0 psig MAIN STEAM D _0 : ,
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| ' TORUS LEVEL 0 ft CRD A FLOW IBIE gpm CRD B FLOW IRIE gpm QEEH CLOSED SLC TK LEVEL 0 %
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| M9IV STATUS 0 8 :
| |
| SLC PMP DISCH PRESS A 0 psig SLC PMP DISCH PRESS B 0 psig PANEL 9-4 MISCELLANEOUS PANELS h STATUS PRESS (psig) FLOW (gpm) l RCIC OPER 250 182 DIESEL GEN 1- INOP :
| |
| RWCU A TRIP O O DIESEL GEN 2 TRIP :
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| RWCU B TRIP O O SBGT A TRIP :
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| RRP A TRIP % SPEED SBGT B TRIP :
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| l l RRP B TRIP % SPEED DRYWELL COOLING TRIP : <
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| l TORUS WATER TEMP 157 F
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| , DRYWELL TEMP 189 F l
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| | |
| l RADIATION MON 3 TORS 1990 EVALUATED EXERCISE TIME = 1200 i t= 04:00 l STATION DESCRIPTION READING (mR/hrf 1 Rx Bldg Fuel Pool Area (SE 5th Flour) DOWNSCALE 2 Rx Bldg Fuel Pool Area (SE Sth Floor) DOWNSCALE i 3 Rx Bldg New Fuel Area (SE 5th Floor) DOWNSCALE 4 Rx Bldg Rx Water Cleanup Demineralizer DOWNSCALE Area (SW 3rd Floor) 5 Rx Bldg Sludge and Decant Pump Area DOWNSCALE (S 2nd Floor) 6 Rx Bldg Neutron Monitor System Index DOWNSCALE Area (TIP Room ist Floor) 7 Rx Bldg Neutron Monitor System Drive DOWNSCALE ,
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| Mech Area (SE 1st Floor) 8 Rx Bldg Control Rod Hydraulic Equipment DOWNSCALE Area (S 1st Floor) 9 Rx Bldg Control Rod Hydraulic Equipment DOWNSCALE '
| |
| Area (N lat Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) DOWNSCALE 11 Rx Bldg RHR Pump Room (SW Quad) DOWNSCALE 12 Rx Bldg RHR Pump Room (NW Quad) DOWNSCALE 13 RX Bldg RCIC/CS Pump Room (NE Quad) DOWNSCALE 14 Rx Bldg CS Pump Room (SE Quad) DOWNSCALE t 15 Turbine Bldg Turbine Front Standard DOWNSCALE 16 Turbine Bldg Mezz Control Corridor DOWNSCALE 17 Turbine Bldg Basement Control Corridor DOWNSCALI 18 Turbine Bldg Rx Feed Pump Area DOWNSCALE 19 Turbine Bldg Condensate Pump Area DOWNSCALE 20 Control Room Main Control Room DOWNSCALE 21 Grade Level Control Corridor DOWNSCALE ,
| |
| 22 Rarivasta Control Room DOWNSCALE 23 Raowt:te Pump Room DOWNSCALE 24 Radwaste Basement Equipment Area DOWNSCALE 25 Radwaste Demineralizer Valve Room DOWNSCALE____
| |
| 26 Radwaste Conveyor Aisle Operating Area DOWNSCALF, 27 SPARE 28 Radwaste Lab Area DOWNSCALE 29 Centrifuge East DOWNSCALE 30 Centrifuge West DOWNSCALE Panel 9-02 Personnel Airlock Area 903' DOWNSCALE Panel 9-02 Ladder 903' to 2nd Level DOWNSCALE OSH = Offscale High
| |
| | |
| )
| |
| RAD 3ATION MONITORS 1990 EVALUATED EXERCISE TIME = 1200 t= 04100 PANEL VBDG J Rx Bldg Vent Eff (RMV-RM-40 0 uci/see ERP Stack Normal EFF (RMP-RM-3A) o uci/pec ,
| |
| ERP Stack High Range (RMP-RM-3B) 0 uci,;see
| |
| . Turbine Bldg Vent Eff (RMV-RM-20A) 0 uci/see Turbine. 31dg High Range (RMV-RM-20B) o uci/sec ,
| |
| RW/ARW Bldg Combined Eff (RMV-RM-30A) o uci/see RW/ARW Bldg High Range (RMV-RM-30B) o uci/see ,
| |
| PANEL 9-12 Main Steam Rad Monitor Ch. A1, B1 15 mR/hr 15 mR/hr i CH. A2, B2 15 mR/hr 15 mR/hr
| |
| -SJAE Off Gas Log Rad Monitor Ch. A, B 1 mR/hr 1 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hr 0.6 mR/hr t
| |
| .f 4
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| n,. - -
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| c - 3 , w.-
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| | |
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| h . .i 6: - 3 ;. .. , .
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| -)
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| a 4
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| 1590 EVALUATED EXERCISE TIME = +1200 '{
| |
| .i a- :
| |
| sMessage Number 36 e t - = 9.1 1.D.Q !
| |
| 04:15 i CQQPER NUCLEAM STATION !
| |
| EMERGENCY PREPAREDNESS EXERCISE. MESSAGE '!
| |
| e i 1
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| A - h5=saae' fort 'Maintenanga crew at DG #2' :
| |
| p <-
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| ; t, l[/ ! *I p, Messaget
| |
| ~
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| c.
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| 'l D **** THIS IS A DRILL ~****
| |
| : h. ,
| |
| ;7 o':There is a brush bi,1 ding in the brush holder. .i
| |
| )
| |
| .i f t i; ' ' '.
| |
| (: .
| |
| 1
| |
| .p
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| [\ I 3
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| 3
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| f 4-1 I
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| 4.
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| I +, . . , - . , . . , - . , ,
| |
| +. -- - ., - -- - - . , ,. -r ,
| |
| | |
| 1990 EVALUATED EXERCISE TIME = 12.11 Message Number 37 t = .Qs.l.li COOPER NUCLEAR STATION EMERGENCY PREfAREDNESS EXERCISE MESSAGE Messace fort Control Room Simuisted Plant Conditionst See attached Plant Data Messaaei,
| |
| **=* THIS IS A DRILL ****
| |
| | |
| 1990 EVALGATED EXERCISE TIME = _1111 Message Number 37 t= 04:15 COOPER NUCLEAR STATION ,
| |
| EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 0 % SRM :
| |
| RHR A TRIP 0 0 REACTOR LEVEL _15_ " GEMAC :
| |
| RHR C TRIP 0 0 REACTOR PRESS .160 psig RHR B TRIP 0 0 El&H (10' 61bs/hr)
| |
| RHR D TRIP 0 0 FEEDWATER A 0 :
| |
| CS.A TRIP O O FEEDWATER B 0 :
| |
| CS B TRIP 0 0 MAIN STEAM A 0 :
| |
| HPCI _ISOL 50 0 MAIN STEAM B 0 :
| |
| MAIN STEAM C 0 :
| |
| DRYWELL PRESS. O psig MAIN STEAM D 0 :
| |
| TORUS LEVEL 0 ft CRD A FLOW IEIE apm CRD B FLOW IEIE gpm SLC TK LEVEL 0 %
| |
| .MSIV STATUS 0 __
| |
| 8 :
| |
| SLC PMP DISCH PRESS A 0 psig SLC PMP DISCH PRESS B 0 psig .
| |
| PANEL 9-4 MISCELLANEOUS PANELS STATUS PRPSS(psig) FLOW (gpm)
| |
| RCIC OPER 225 179 DIESOL GEN 1 INOP :
| |
| RWCU A TRIP O O DIESEL GEN 2 TRIP :
| |
| ! RWCU B TRIP O O SBGT A TRIP :
| |
| RRP A TRIP % SPEED SBGT B TRIP :
| |
| RRP B TRIP % SPEED DRYWELL COOLING TRIP :
| |
| TORUS WATER TEMP 160 F DRYWELL TEMP 192 F
| |
| | |
| l RADIATION MONITORS 1990 EVALUATED EXERC3SE TIME = 1225 )
| |
| t= 04:15 '
| |
| i STATION DESCRIPTION READING (mR/hrY i 1 Rx Bldg Fuel Pool Area (SE 5th Floor) DOWNSCALE 2 Rx Bldg Fuel Pool Area (SE Sth Floor) DOWNSCALE 3 Rx Bldg New Fuel Area (SE 5th Floor) __ DOWNSCALE 4 Rx Bldg Rx Water Cleanup Demineralizer DOWNSCALE Area (SW 3rd Floor) e Rx P'.dg Sludge and Decant Pump Area __,DOWNSCALE (S 2nd Floor) 6 Rx Bldg Neutron Monitor System Index DOWNSCALE Area (TIP Room ist Floor) 7 Rx Bldg Neutron Monitor System Drive DOWNSCALE Mach Area (SE ist Floor) ,
| |
| 8 Rx Bldg Control Rod Hydraulic Equipment DOWNSCALE Area (S ist Floor) 9 Rx Bldg Control Rod Hydraulic Equipment roWNSCALE Area (N ist Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) DOWNSCALE 11 Rx Bldg RHR Pump Room (SW Quad) DOWNSCALE 12 Rx Bldg RHR Pump Room (NW Quad) DOWNSCALE 13 RX Bldg RCIC/CS Pump Room (NE Quad) DOVNSCALE 14 Rx Bldg CS Pump Room (SE Quad) DO,,3CALE 15 Turbine Bldg Turbine Front Standard DOWNSCALE 16 Turbine Bldg Mezz Control Corridor DOWNSCALE 17 Turbine Bldg Basement Control Corridor DOWNSCALE 18 Turbine Bldg Rx Feed Pump Area DOWNSCALE 19 Turbine Bldg Condensate Pump Area DOWNSCALE 20 Control Room Main Control Room DOWNSCALE I
| |
| 21 Grade Level control Corridor DOWNSCALE l 22 Radwaste Control Room DOWNSCALE l 23 Radwaste Pump Room DOWNSCALE l 24 Radwaste Basement Equipment Area DOWNSCALE 25 Radwaste Demineralirar Valve Room DOWN3CALE 26 Radwaste Conveyor Aisle Operating Area DOWNSCALE 27 SPARE 28 Radwaste Lab Area DOWNSCALE l 29 Centrifuge East DOWNSCALE ,
| |
| 30 Centrifuge West DOWNSCALE
| |
| , Panel 9-02 Personnel Airlock Area 9038 DOWNSCALE
| |
| ! Panel 9-02 Ladder 903' to 2nd Level DOWNSCALE OSH = Offscale High l
| |
| | |
| , RAD 3ATION MONITORS TIME =
| |
| 1990 EVALUATED EXERCISE 1215 t= 04:15 PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40 0 uci/see ERP Stack Normal EFF (RMP-RM-3A) o uci/see ERP Stack High Range (RMP-RM-3B) o uci/see Turbine Bldg Vent Eff (RMV-RM-20A) o uci/see Turbine Bldg High Range (RMV-RM-208) o uci/see RW/ARW Bldg Combined Eff (RMV-RM-30A) - 0 uci/see RW/ARW Bldg High Range (RMV-RM-30B) o uci/see PANEL 9-10 Main Steam Rad Monitor Ch. A1, B1 15 mR/hr 15 mR/hr CH. A2, B2 15 mR/hr 15 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 1 mR/hr 1 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hr 0.6 mR/hr l
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| l l
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| e
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| l l
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| 4 1990 EVALUATED EXERCISE TIME = 1225 Message Number 10A, t = 04:25 i
| |
| COOPER NUCLEAR STATION ,
| |
| EMERGENCY PREPAREDNESS EXERCISE MESSAGE i
| |
| liessace fari Maintenance crew at Diesel Generator #2 Messaae:
| |
| **** THIS IS A DRILL ****
| |
| o The Fuel 011 Booster Pump Motor has now been repaired.
| |
| L T
| |
| f I
| |
| j.
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| p 1
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| ne j 4
| |
| Ii 1990 EVALUATED EXERCISE TIME =- 1230 -i i
| |
| Message Number _12_ t = 04:30 1 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE
| |
| .t 1
| |
| 1 Messaae fort Control Room ;
| |
| i i
| |
| Simulated Plant Conditions: See attached Plant Data !
| |
| -i Messaggi .[
| |
| ?
| |
| '* *** THIS IS A DRILL **** !
| |
| t i
| |
| i I
| |
| +
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| , . - ~ ,,. . -, ,, ., w . . - - - - -- - , - w
| |
| | |
| 1990 EVALUATED EXERCISE TIME = 1230 M Ocage Number _11_ t= 04:30 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) ELQH(gpm) REACTOR POWER 0 % SRM :
| |
| RHR A TRIP O O REACTOR LEVEL _11_ " 9EMAC :
| |
| RHR C _ TRIP 0 0 _ llEACTOR PRESS 160 psig RHR B .__
| |
| ELQH (10^ 61bs/hr)
| |
| RHk D __ FEEDWATER A 0 :
| |
| CS A TRIP 0 0 FEEDWATER B C :
| |
| CS B MAIN STEAM A 0 :
| |
| HPCI ISOL 60 0 MAIN STEAM B o :
| |
| XAIN STEAM C 0 :
| |
| DRYWELL PRESS. 2.29 psig MAIN STEAM D 0 :
| |
| TORUS LEVEL 13.68 ft CRD A FLOW IHH gpm CRD B FLOW gpm OPFN CLOSED SLC TK LEVEL O_ %
| |
| MSIV STATUS 0 8' _:
| |
| SLC PMP DISCH PRESS A 0 psig SLC PMP DISCH PRESS B o psig PANEL 9-4 MISCELLANEOUS PANELS STATUS PRESS (psig) ELQH(gpm)
| |
| RCIC OPER 225 179 DIESEL GEN 1 INOP :
| |
| 1RWCU A TRIP O O DIESEL GEN 2 OPER :
| |
| RWCU B SBGT A TRIP :
| |
| R9P A TRIP % SPEED SBGT B OPER :
| |
| l RRP B TRIP % SPEED DRYWELL COOLING :
| |
| TORUS WATER TEMP 164 F DRYWELL TEMP 196 F l
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| RADIATION MONZTORS 1990 EVALUATED EXERCISE TIME = 1230 t= 04:30,_
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| STATION DESCRIPTION READING (mR/hrt 1 Rx Bldg Fuel Pool Area (SE Sth Floor) 'DOWNSCALE 2 Rx Bldg Fuel Pool Area (SE Sth Floor) DOWNSCALE 3 Rx Bldg New Fuel Area (SE 5th Floor) DOWNSCALE 4 Rx Bldg Rx Water Cleanup Demineralizer DOWNSCALE Area (SW 3rd Floor) 5 Rx Bldg Sludge and Decant Pump Area .8 ,
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| (S 2nd Floor) 6 Rx Bldg Neutron Monitor System Index 151 Area (TIP Room ist Floor) 7- Rx Bldg Neutron Monitor System Drive DOWNSCALE Mech Area (SE 1st Floor) 8 Rx Bldq Control Rod Hydraulic Equipment DOWNSCALE Area (S 1st Floor) 9 Rx Bldg Control Rod Hydraulic Equipment DOWNSCALE Area (N ist Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) DOUNSCALE 11 Rx Bldg RHR Pump Room (SW Quad) 5.1 12 Rx Bldg RHR Pump Room (NW Quad) DOWNSCALE 13 Rx Bldg RCIC/CS Pump Room (NE Quad) DOWNSCALE 14 Rx Dldg CS Pump Room (SE Quad) 4.5 15 Turbine Bldg Turbine Front Standard 1 16 Turbine Bldg Mezz Control Corridor DOWNSCALE ,
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| 17 Turbine Bldg Basement Control Corridor DOWNSCALE 18 Turbine Bldg Rx Feed Pump Area 6 19 Turbine Bldg Condensate Pump Area DOWNSCALE
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| , 20 Control Room Main Control Room .02 l 21 Grade Level Control Corridor DOWNSCALE 22 Radwaste Control Room DOWNSCALE i 23 Radwaste Pump Room DOWNSCALE l
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| 24 Radwaste Basement Equipment Area DOWNSCALE i 25 Radwaste Domineralizer Valve Room DOWNSCALE ,_,
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| l 26 Radwaste Conveyor Aisle Operating Area DOWNSCALF, ,_
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| 27 SPARE _
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| l 28 Radwaste Lab Area .1 l 29 Centrifuge East 10 l
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| 30 Centrifuge West 9 Panel 9-02 Personnel Airlock Area 903' DOWNSCALE Panel 9-02 Ladder 903 ' to 2nd Level DOWNSCALI l OSH = Offscale High l
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| 'n .
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| t RADIATION MONITORS l 1990 EVALUATED EXERCISE TIME = 1230 ;
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| i t=_ 04:30 t
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| PANEL VBDG ,
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| Rx Bldg Vent Eff (RMV-RM-40 0 uci/see ERP Stack Normal EFF (RMP-RM-3A) o uci/see .
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| ERP Stack Hich Range (RMP-RM-3B) o uci/see :
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| Turbine Bldg Vent Eff (RMV-RM-20A) 0 uci/see Turbine 31dg High Rango (RMV-RM-208) o uci/see RW/ARW Bldg Combir;ed Eff (RMV-RM-30A) 0 uci/sec RW/ARW Bldg High Range (RMV-RM-30B) o uci/see PANEL 9-10 ,
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| Main Steam Rad Monitor- Ch. A1, B1 15 mR/hr 15 mR/hr -
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| CH. A2, B2 15 mR/hr 15 mR/hr i SJAE Off Gas Log Rad Monitor Ch. A, B 1 mR/hr 1 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hr 0.6 mR/hr l r 1
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| ?
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| 1990 EVALUATED EXERCISE TIME = 1230+
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| Message Number 40 t = 04:30 COOPER RUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE POR CONTROLLER USE ONLY:
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| Controller Informations o Diesel Generator No. 2 is repaired. It is allowed to be started upon notification of repair. Note that the high drywell pressure and bus undervoltage signals will be present which will allow the Diesel to auto-start. The loads (including RHR Service Water Booster and Station Service Water Pumps) will sequence on as if a LOCA were present.
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| o The high drywell pressure signal will cause RHR and CS pumps to auto-start, and they will inject unless Operators take action to prevent this, o The high drywell pressure will prevent RHR Shutdown Cooling operation (even after the RPV pressure permissive is met) unless it is jumpered, o From now until tho end of the Exercise, procedures will allow operators significant latitude as to the order in which they do things.
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| Therefore, in order to allow maximum play, the blanks in the plant data sheets will be filled in by hand as Operators make decisions and take the actions discussed below. The lead Control Room Controller must approve data sheets before they are given to the players.
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| Expected Actions:
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| o Operators should prevent injection of RHR and CS in accordance with EOP-1, o As loading limits allow, Operators should discuss starting of divisional equipment powered from Diesel Generator No. 2, which did not start automatically (Drywell Cooling, CRD Pump B, Station Air Comp. B, etc).
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| N 1
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| 1990 EVALUATED EXERCISE TIME = 1230+
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| * Message Number 40 (Page 2) t = 04:30 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE FOR CONTROLLER USE ONLY1 Expected Actions (continued) o Begin discussions related to torus cooling, drywell cooling, RPV depressurization, and Shutdown Cooling.
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| o May begin discussions relative to the possibility of downgrading from a SITE AREA EMERGENCY to an ALERT, since one division of AC power has been restored.
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| e -
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| .b> : -
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| t
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| <[r 1990 E".'.LUATED EXERCISE TIME: 1222 t Message Number 41 t ="4:30 c0OPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE FOR CONTROftFR USE ONLY!
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| - Controller Information Contingency, EOF
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| . If the radwaste shipping containers 90-2-904 and 90-901, in the f armers f acd lot-
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| . has'not been found, issue contingency EOF Message no. 41C (9 04:30).
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| 1 p
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| 4
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| ,, n . --, w a vg,
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| I
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| * i 1990 EVALUATED EXERCISE TIME: 1112 Message Number 41C t =04:30 COOPER !TUCLEAR STATION l EMERGENCY PREPAREDNESS EXERCISE MESSAGE 4
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| F Centincency Messaces *ert EOF Messacet ;
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| **** TFIJ IS A DRILL ****
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| Hey, I'm Frank Farmer. I have a couple of boxes that might belong to you in my feed lot. Both are yellow and one has " RADIOACTIVE" on it. I ouldn't tell on the other because its all torn apart and I'm not going near it. My pigs are eating whatever come out of that broken box. I live on a farm in Missouri; go two miles east of Brown #ville on Highway 136. Turn south (right) at highway "D",onthegravelroad.jGo2moremilesdowntheroadandIliveattheend of the road. ,
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| , #'s.2l d0 L
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| 1990 EVALUATED EXERCISE TIME: tilla 1 1
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| Message Number 42C t =04:30- l 05:15 COOPER NUCLEAR STATION EMERGENCY PREPARIDNESS EXERCISE MESSAGE ,
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| FOR CONTROLLER USE ONLY1 Controller Information: Contingency, Site "D" Search Team o Team members upon arriving at the f armer's feed lot seet
| |
| - Two (2) yellow - (actual color is orange) box containers on the ground.
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| One container, number 90-2-904, is labeled " Radioactive LS A" . It is badly dented but do not appear to be ruptured. The other, 90-1-901 is ripped open with its contents scattered on the ground. The f armer's pigs are eagerly eating material that had spread on the ground.
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| - . Some of the contents are seen on the ground are identifiable as herculite, rubber boots and gloves, mop heads, paper, coveralls, wood, rope, floor dry and sweep.tng compound.
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| o Dete rmine the actions of the team members. If they approach the ruptured containers, they will become contaminated. Contamination will be >100 cpm but limited to <l5,000 cpm above background. Tools and equipment which would be used near the containers could become contaminated. This will be left to tha discretion of the controller, o Identifiable radioactive / contaminated material is laying on the ground. All material _found will have a dose rate less than 200 mR/hr. The controller will have free play to identify pieces which were in the container.
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| o Soil and vegetation samples taken within the contaminated area, are as follows:
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| 1211 Veaetation mR/hr CPM mR/hr CPM L Throuch bac Throuch baa o .1 - 4 400 - 16,000 .1 - 1 400 - 4,000
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| * The controller can provide reading within the above ranges.
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| L
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| ( Expected Actionst o Notify EOF and obtain instructions from the EOF on what to do with the farmer's pigs.
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| o Team members will begin ground surveys to identify the extent of contamination.
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| They should set up a radiological control access point.
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| o Team members may try to cover the loose material, such as floor dry and sweeping compound to prevent further spread of the material. They may even begin to pick up loose material and place in bags.
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| 1 P
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| 1990 EVALUATED EXERCISE TIME: t1110 Message Number 47C t =04:30-05:15 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Messaces fort Site "D" Search Team f
| |
| Messacet
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| **** THIS IS A DRILL **** ,
| |
| o As you approach the containers you see two (2) yellow (actual color is ) range) box containers on the ground in a farmer's feed lot. One container, number 90-2-904, is labeled " Radioactive LSA". It is badly dented but do not appear to be ruptured. The other, 90-1-901 is ripped open with its contents scattered on the ground. The farmer's pigs are eagerly eating material that had spread on the ground.
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| o Some of the contents that you see on the ground are identifiable as herculite, rubber boots and gloves, mop heads, paper, coveralls, wood, rope, floor dry and sweeping compound.
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| \
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| 1990 EVAI/JATED EXERCISE TIME = 1245 -
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| 1 i
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| Message Number L t = 04 45 go0PER NUCLEAR STATION )
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| EMERGENCY PREPAREDNESS EXERCISE... MESSAGE ,
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| i
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| ' Massaae' fort Control Room ;
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| 44,
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| ,Eimulated Plant Conditionst See attached Plant Data ,
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| Massage t
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| **** THIS IS A DRILL ****
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| ..__;-..- _,- , - - . - - . - _ . _ - . . - . _ . - - . . i
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| ?
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| 1990 EVALUATED EXERC3SE TIME = 1245 Me0 sage Number 43 t= 04: 45 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 0 % SRM :
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| RHR A TRIP _ 0 0 REACTOR LEVEL _11_ " GEMAC :
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| RHR C TRIP 0 0 REACTOR PRESS psig RHR B ELQH (10^61bs/hr)
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| RHR D FEEDWATER A 0 : ,
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| CS A TRIP 0 0 FEEDWATER B 0 :
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| CS B MAIN STEAM A 0 :
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| HPCI ISOL 50 __ , p. MAIN STEAM B 0 :
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| MAIN STEAM C 0 :
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| DRYWELL PRESS, psig MAIN STEAM D 0 :
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| TORUS LEVEL ft CRD A FLOW IRIE gpm CRD B FLOW gpm QEIH CLOSED SLC TK LEVEL 0 %
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| MSIV STATUS 0 8 :
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| SLC PMP DISCH PRESS A 0 psig SLC PMP DISCH PRESS B 0 psig PANEL 9-4 MISCELLANEOUS PANELS <
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| STATUS PRESS (psig) ELQH(gpm)
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| DIESEL GEN 1 INOP
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| ! RCIC :
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| 1 RWCU A TRIP 0 0 DIESEL GEN 2 OPER :
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| RWCU B SBGT A TRIP :
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| 1 l RRP A TRIP % SPEED SBGT B OPER :
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| RRP:B TRIP % SPEED DRYWELL COOLING :
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| L TORUS WATER TEMP F DRYWELL TEMP F 1
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| 1
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| RADIATION MONITORS 1990 EVALUATED EXERCISE TIME = 1245 t= 04:45 STATION DESCRIPTION READING (mR/hr) 1 Rx Bldg Fuel Pool Area (SE Sth Floor) DOWNSCALE 2 Rx Bldg Fuel Pool Area (SE 5th Floor) DOWNSCALE 3 Rx Bldg New Fuel Area (SE 5th Floor) DOWNSCALE 4 Rx Bldg Rx Water Cleanup Demineralizer DOWNSCALE Area (SW 3rd Floor) 5 Rx Bldg Sludge and Decant Pump Area .8 (S 2nd Floor) 6 Rx Bldg Neutron Monitor System Index 151 Area (TIP Room ist Floor) 7 Rx Bldg Neutron Monitor System Drive DOWNSCALE Mach Area (SE lat Floor) 8 Rx Bldg Control Rod Hydraulic Equipment DOWNSCALE Area (S 1st Floon) 9 Rx Bldg Control hed Hydraulic Equipment DOWNSCALE Area (N 1st Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) DOWNSCALE 11 Rx Sidg RHR Pump Itoom (SW Quad) 5.1 12 Rx Bldg RHR Pump Itoom (NW Quad) DOWNSCALE 13 Rx Bldg RCIC/CS Pump Room (NE Quad) DOWNSCALE 14 Rx Bldg CS Pump Room (SE Quad) 4.5 15 Turbine Bldg Turbine Front Standard i 16 Turbine Bldy Mezz Control Corridor DOWNSCALE 17 Turbine Bldg Basement Control Corridor DOWNSCALE 18 Turbine Bldg Rx Feed Pump Area 6 19 Turbine Bldg Condensate Pump Area DOWNSCALE 20 Control Room Main Control Room .02 21 Grade Level Control Corridor DOWNSCALE 22 Radwaste Control Room DOWNSCALE 23 Radwaste Pump Room DOWNSCALE 24 Radwaste Basement Equipment Area DOWNSCALE 25 Radwaste Demineralizer Valve Room DOWNSCALE 26 Radwaste Conveyor Aisle Operating Area DOWNSCALE 27 SPARE 28 Radwaste Lab Area .1 29 Centrifuge East 10 30 Centrifuge West 9 Panel 9-02 Personnel nirlock Area 903' DOWNSCALE Panel 9-02 Ladder 903' to 2nd Level DOWNSCALE OSH = Offscale High l
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| 1 RADIATION MONITORS l 1990 EVALUATED EXERCISE TIME = 1245 l t=_ 04:45 l PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40 0 uci/see ERP Stack Normal EFF,(RMP-RM-3A) o uci/see ERP Stack High Range (RMP-RM-38) o uci/see Turbine Bldg Vent Eff (RMV-RM-20A) 0 uci/see Turbine Bldg High Range (RMV-RM-20B) o uci/see RW/ARW Bldg Combined Eff (RMV-RM-30A) o uCi/see RW/ARW Bldg High Range (RMV-RM-30B) o uci/ nee PANEL 9-10 Main Steam Rad Ponitor Ch. A1, B1 15 mR/hr 15 mR/hr CH. A2, B2 15 mR/hr 15 mR/hr SJAE Of f Gas Log Rad Monitor Ch. A, B 1 mR/hr 1 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hr 0.6 mR/hr l
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| . . . . .- . . - - . - . - . , - - . . - . . . . . . - . - . . - - ~ .
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| 1990 EVALUATED EXERCISE TIME = 1300 l
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| ;. Message Number L t = 05:00 (
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| t I" COOPER NUCTFAR STATION I
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| l EMERGENCY PREPAREDNESS EXERCISE MESSAGE j i
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| i i
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| Massaae fort- Control Room -
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| n j i
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| Simulated Pla11t Conditions t See attached. Plant Data .j i
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| " i r
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| tr Massaget i
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| i
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| **** THIS IS A DRILL **** t t I 1-. .
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| l,
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| , '. t w e.a . . . . . . -, -, ., . . ~ . . . , . , - . , . - .,n ,, .,. , - , , . . .w,, - --,, , - - - . , . . . - ,
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| l 1990 EVALUATED EXERCISE TIME = 1300-M OCage Number _A1_ t= 03:00 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) ELQH(gpm) REACTOR POWER 0 % SRM RHR A TRIP 0 0 REACTOR LEVEL _11_ " GEMAC :
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| TUIR C- _ TRIP 0 0 REACTOR PRESS psig RHR B ELQH (10^61bs/hr)
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| RHR D FEEDWATER A 0 :
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| CS A TRIP 0 0 FEEDWATER B o :
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| CS B MAIN STEAM A 0 :
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| HPCI ISOL 50 0 MAIN STEAM B o :
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| MAIN STEAM C _0 :
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| DRYWELL PRESS. psig MAIN STEAM D 0 :
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| TORUS LEVEL ft CRD A FLOW IRIE gpm CRD B FLOW gpm OPEN C LOSED SLC TK LEVEL 0 %
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| MSIV STATUS 0 8 :
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| SLC PMP DISCH PRESS A 0 psig SLC PMP DISCH PRESS B ..Q_ psig PANEL 9-1 MISCELLANEOUS PANELS STATUS EREEE(psig) FLOW (gpm)
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| RCIC DIESEL GEN 1 INOP._:
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| RWCU A TRIP O __
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| 0 DIESEL GEN 2 OPER RWCU B SBGT A TRIP :
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| RRP A TRIP % SPEED SBGT B OPER :
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| RRP B TRIP % SPEED DRYWELL COOLING :
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| TORUS WATER TEMP F DRYWELL TEMP F
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| RAD 3ATION MONITORS 1990 EVALUATED EXERCISE TZME = 1300 t= 05:00
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| ]
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| i STATION DESCRIPTION READING (mR/hr) i 1 Rx Bldg Fuel Pool Area (SE Sth Floor) DOWNSCALE 2 Rx Bldg Puel Pool Area (SE Sth Flocr) DOWNSCALE 3 Rx Bldg New Fuel Area (SE Sth Floor) DOWNSCALE 4 Rx Bldg Rx Water Cleanup Demineralizer DOWNSCALE Area (SW 3rd Floor) ,
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| 5 Rx Bldg Sludge and Decant Pump Area .8 (S 2nd Floor) 6 Rx Bldg Neutron Monitor System Index 151 Area (TIP Room ist Floor) 7 Rx Bldg Neutron Monitor System Drive DOWYL.- . 1, ,
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| Mach Area (SE ist Floor) 8 Rx Bldg Control Rod Hydraulic Equipment DOWh
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| * x.
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| Area (S ist Floor) 9 Rx Bldg Control Rod Hydraulic Equipment DOWNSL' 71 Area (N ist Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) DOWNSCALE 11 Rx Bldg RHR Pump Room (SW Quad) 5.1 12 Rx Bldg RHR Pump Room (NW Quad) DOWNSCALE 13 Rx Bldg RCIC/CS Pump Room (NE Quad) DOWNSCALE 14 Rx Bldg CS Pump Room (SE Quad) 4.5 15 Turbine Bldg Turbine Front Standard i 16 Turbine Bldg Mezz Control Corridor DOWNSCALE 17 Turbine Bldg Basement Control Corridor DOWNSCALE 18 Turbine Bldg Rx Feed Pump Area 6 19 Turbine Bldg Condonsate Pump Area DOWNSCALE 20 Control Room Main Control Room .02 ,
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| 21 Grade Level Control Corridor DOWNSCALE 22 Radwaste Control Room DOWNSCALE 23 Radwaste Pump Room DOWNSCALE '
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| 24 Radwaste Basement Equipment Area DOWNSCALE 25 Radwaste Domineralizer Valve Room DOWNSCALE 26 Radwaste Conveyor Aisle Operating Area DOWNSCALE 27 SPARE 28 Radwaste Lab Area .1 29 Centrifuge East 10 30 Centrifuge West 9 Panel 9-02 Personnel Airlock Area 903' DORNSCALE Panel 9-02 Ladder 903' to 2nd Level DOWNSCALE J
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| OSH = Offscale High i
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| RADIAT20M MONETORS TIME = l3 1990 EVALUATED EXERCISE _ o5 00 PANEL VBDG 0 uci/see Rx Bldg Vent Eff (RMV-RM-40 o uci/see ERP Stack Normal EFF (RMP-RM-3A) o uci/see ERP Stack High Range (RMP-RM-3B) o uci/see Turbine Bldg Vent Eff (RMV-RM-20A) o uci/see Turbine Bldg High Range (RMV-RM-20B) o uci/see
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| ~
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| RW/ARW Bldg Combined Eff (RMV-RM-30A) o uci/see RW/ARW Bldg High Range (RMV-RM-3 0B)
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| PANEL 9-10 Ch. A1, B1 15 mR/hr 15 mR/hr Main Steam Rad Monitor CH. A2, B2 -
| |
| 15 mR/hr 15 mR/hr_._
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| SJAE off Gas Log Rad Monitor Ch. A, B 1 mR/hr 1 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hr 0.6 mR/hr j
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| I i
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| o I
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| : 1. .<
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| 1990 EVALUATED EXERCISE TIME = 1315 l
| |
| <, i Message'Humber 16__ t = 05:15
| |
| , CQOPER RUCTIAR STATION
| |
| )
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| t, EMERGENCY PREPAREDNESS EXERCISE MESSAGE ,!
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| P i ;
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| Massaae for.1 Control Room I
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| L '
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| -Simulated Plant conditions: See attached Plant Data o
| |
| t Messagot -s
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| **** THIS IS A DRILL **** 'l b
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| -j
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| 'I
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| -i r*
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| 1 i
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| I I i
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| i l
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| I '
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| i t
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| -i 3
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| i E
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| L Y
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| 4, . . - . . - . . . . , ,- . .
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| n- -.
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| 19901 EVALUATED EXERCZSE TIME = 1315
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| ' Message ~Numberc 46 t= 05:15 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DAT&
| |
| PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) ELQH(gpm) REACTOR POWER 0 % SRM :
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| :RHR A TRIP O O REACTOR LEVEL _11_ " GEMAC :
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| RHR C TRIP O O REACTOR PRESS psig
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| -RHR.B _ ELQH (10^61bs/hr)
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| RHR D .. FEEDWATER A 0 :
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| CS A TRIP O O FEEDWATER B 0_:
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| CS'B MAIN STEAM A 0 :
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| HPCI. ISOL _ 50 0 MAIN STEAM B o :
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| MAIN STEAM C 0 :
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| DRYWELL !FLOS. psig MAIN STEAM D 0 :
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| TCRUS LEVEL ft CRD A FLOW - IBIE gpm CRD B FLOW gpm QEEE CLOSED SLC TK LEVEL 0 %
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| MSIV STATUS 0 8 :
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| SLC PMP DISCH PRESS A 0 psig SLC PMP DISCH PRESS B 0 psig PANEL 9-4 MISCELLANEOUS PANELS STATUS- P_RES3(psig) 7.LQW(gpm)
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| RCIC- . DIESEL GEN 1 INOP :
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| 'RWCU A TRIP O O DIESEL GEN 2 OPER :
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| RWOU'B SBGT A IBIE__:
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| RRP A; 1 TRIP % SPEED SEGT B OPER :
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| RRP B TRIP % SPEED DRYWELL COOLING :
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| TORUS WATER TEMP F DRYWELL TEMe F
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| RADIATION MONITORS 1990 EVALUATED EXERCISE TIME = 1319 t= 05:15
| |
| ' STATION DESCRI PTION READING (mR/hr) 1 Frc Bldg Fuel Pool Area (SE 5th Floor) DOWNSCALE 2 Rx Bldg Fuel Pool Area (SE Sth Floor) ___pQ.WNSCALE 3 Rx Bldg New Fuel Area (SE Sth Floor) DOWNSCALE 4 Rx Bldg Rx Water Cleanup Demineralizer LGWNSCALE Area (SW 3rd Floor) 5 Rx Bldg Sludge and Decant Pump Area .8 (S 2nd Floor) 6 RX Bldg Neutron Monitor System Index 151 .
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| Area-(TIP Room ist Floor) 7 Rx Bldg Neutron Monitor System Drive DOWNSCALE Mech Area (SE 1st Floor) 8 Rx Bldg Control Rod Hydraulic Equipment DOWNSCALE Area (S ist Flocr) 9 Rx Bldg Control Rod Hydraulic Equipment DOWNSCAL.E Area (N ist-Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) DOWNSCALE ;
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| 11 Rx Bldg RHR Pump Room (SW Quad) 5.1 52 Rx Bldg RIO Pump Room (NW Quad) DOWNSCALE 13 Rx Bldg RCIC/CS Pump Room (NE Quad) DOWNSCALE __
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| 14 Rx Bldg CS Pump Room _(SE Quad) 4c5 15 Turbine. Bldg. Turbine Front Standard . . 1 16~ Turbine Bldg Mezz Control Corridor DOWNSCALE 17 Turbine Bldg. Basement Control Corridor DOWNSCALE 18 Turbine Bldg Rx Feed Pump Area __
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| 6 19 Turbine Bldg _ Condensate Pump Area DOWNSCALE f 20 Control Room MainJControl Room .02-21 Grade Level Control Corridor DOWNSCALE
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| '22 Radwaste Control Room. DOWNSCALE '
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| L 23- Radwaste Pump Room DOWNSCALE 24 Radwaste-Basement Equipment Area - DOWNSCALE 25 Radwaste Demineralizer Valve Room DOWNSCALE 26 Radysste Conveyor Aisle Operating Area DOWNSCALE c 27- SPARE-L 28 Radwaste Lab Area- .1 L 29 ' Centrifuge East _ 10 30 Centrifuge West 9-L Panel 9-02 Perr'nnel Airlock Area 903' DOWNSCALE Panel-9-02 ' Ladder 903' to 2nd Level DOWNSCALE
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| 'OSH = Offscale High i
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| l s
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| __s __ , _ , _ , . _ _ _ - - - _ - - - - - _ _ - . _ _ _ - - - , _ _ _ -
| |
| | |
| ' l RADIATION MONITORS 1990 EVALUATED EXERCISE TIME = 1315 t= 05:15 PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40 0 uCi/see ERP Stack Normal EFF (RMP-RM-3A) 0 uCi/sec ERP Stack High Range (RMP-RM-3B) 0 uCi/see Turbine Bldg Vent Eff (RMV-RM-20A) 0 uci/see Turbine Bldg High Range (RMV-RM-20B) o uCi/see RW/ARW Bldg Combinec Eff (RMV-RM-30A) 0 uCi/sec ,
| |
| RW/ARW Bldg High Range (RMV-RM-308) 0 uC1/see PRIE l.12 Main Steam Rad Monitor Ch. A1, B1 15 mR/hr 15 mR/hr CH. A2, B2 15 mR/hr 15 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 1 mR/hr 1 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hr 0.6 mR/hr t
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| I
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| , e i
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| i 1 1990~ EVALUATED EXERCISE TIME = 133Q
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| \
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| Message Number 47 t = 05:30~ (
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| i COOPER NUCLEAR STATION i EMERGENCY PREPAREDNESS EXERCISE MESSAGE l
| |
| l Messace fort Control Room-Simulated Plant Conditions: See attached Plant Data i Messaae:
| |
| **** THIS IS A DRILL ****
| |
| a a
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| i a
| |
| I b
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| 1 l'
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| ?
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| |
| l
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| l
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| ' , 4
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| | |
| ~ 1990 EVALUATED EXERCISE TIME = 1330
| |
| ? Message' Number 47 t= 05:30 COOPER ITUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PIANT DATA PANEL 9-3 PANEL 9-5 STATUS EBEES(psig) ELQH(gpm) REACTOR POWER 0 % SRM :
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| RHR A TRIP O O REACTOR LEVEL _lE_ " GEMAC :
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| < J TRIP O O REACTOR PRESS psig RHR B ELQH (10^61bs/hr)
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| RHR D FEEDWATER A 0 :
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| CS A TRIP ,
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| 0 0 FEEDWATER B 0 :
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| CS B MAIN STEAM A ,0 :
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| HPCI ISOL 50 0 MAIN STEAM B 0 .:-
| |
| MAIN STEAM C 0 :
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| DRYWELL PRESS. psig MAIN STEAM D 0 :
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| TORUS LEVEL ft CRD A FLDW IBIE 7pm CRD B FLOW gpm QEEH CLOSED SLC TK LEVEL 0 %
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| MSIV-STATUS 0 8 :
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| SLC PMP DISCH PRESS A 0 psig SLC PMP DISCH PRESS B 0 psig PANEL 9-4 MISCELLANEOUS PANELS STATUS EEEEE(psig) ELQH(gpm)
| |
| RCIC' DIESEL GEN 1 INOP :
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| 'RWCU A TRIP 'O O DIESEL GEN 2 OPER :
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| RWCU B! SBGT A TRIP :-
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| RRP A TRIP % SPEED SBGT B OPER :
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| ;RRP B TRIP % SPEED DRYWELL COOLING :
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| TORUS WATER TEMP F DRYWELL TEMP F 2- --__ __
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| RADIATION MONITORS ,
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| .1990 EVALUATED EXERCISE T2ME = 1330 ,
| |
| t= 05:30 STATION DESCRIPTION REht 'd!G (mR/hr}
| |
| ^
| |
| 'l Rx Bldg Fuel Pool Area (SE Sth Floor) DOWNSCALE 2 Rx Bldg Fuel Pool Area (SE Sth Floor) DOWNSCALE 3 Rx Bldg New Fuel Area (SE Sth Floor) DOWNSCALE 4 Rx Bldg Rx Water Cleanup Deminerclizer DOWNSCALE Area (SW 3rd Floor) 5 Rx Bldg Sludge and Decant Pump Area .8 _
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| -(S 2nd Floor) 6 Rx Bldg Neutron Monitor System Index 151 Area (TIP Room ist Floor) 7 Rx Bldg Neutron Monitor System Drive DOWNSCALE Mech Area (SE ist Floor) 8 Rx Bldg Control Rod Hydraulic Equipment DOWNSCALE Area (S ist Floor) 9 Rx Bldg Control Rod Hydraulic Equipment DOWNSCALE Area (N ist Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) DOWNSCALE 11 Rx Bldg RHR Pump Room (SW Quad) 5.1 12 Rx Bldg RHR Pump Room (NW Quad) DOWNSCALE 13 Rx Bldg RCIC/CS Pump Room (NE Quad) DOWNSCALE
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| , 14 Rx Bldg CS Pump Room (SE Quad) 4.5 _ . .
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| L 15 -Turbine Bldg Turbine Front Standard 1 16 Turbine Bldg Mezz Control Corridor DOWNSCALE 17 -Turbine Bldg Basement Control Corridor DOWNSCALE 18 Turbine Bldg Rx Feed Pump Area 6
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| '19 Turbine Bldg Condensate Pump Area DOWNSCALE
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| '20 Control' Room Main Control Room .02 21 Grade Level Control Corridor DOWNSCALE 22- Radwaste Control Room _DOWNSCALE 23 Radwaste Pump Room DOWNSCALE 24 Radwaste Basement' Equipment Area DOWNSCALE t
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| 25- Radwaste Demineralizer Valve Room DOWNSCALE' .
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| l 26 Radwaste Conveyor Aisle Operating Area DOWNSCALE 27 SPARE 28- Radwaste Lab Area .1- 1
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| ~ 29. Centrifuge East 10 30 Centrifuge West. 9
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| : Panel 9-02 Personnel Airlock Area 903' .
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| DOWNSCALE' l Panel 9 Ladder 903' to 2nd' Level DOWNSCALE
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| 'OSH = Offscale High L
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| l l
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| \
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| f 1
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| l-
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| / i
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| ti' RADTATION MONITORS L 1990; EVALUATED EXERCISE TIME = 1330 t= 05:30
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| = PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40 0 uCi/sec ERP; Stack Normal EFF (RMP-RM-3A) o uCi/see ERP Stack High Range (RMP-RM-3B) 0 uci/see Turbine Bldg Vent Eff (RMV-RM-20A) o uCi/sec
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| + . Turbine Bldg High Range (RMV-RM-20B) o uci/sec
| |
| , RW/ARW Bldg Combined Eff (RMV-RM-30A) o uci/see RW/ARW Bldg High Range (RMV-RM-30B) o uci/see PANEL 9-10 Main Steam Rad Monitor Ch. A1, B1 15 mR/hr 15 mR/hr CH. A2, B2 15 mR/hr 15 mR/hr SJAE off Cas Log Rad Monitor Ch. A, B 1 mR/hr 1 mR/hr-Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hr 0.6 mR/hr a
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| i 1990 EVALUATED EXERCISE TIME: 1112 Message Number 48 t' =05:30 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE FOR CONTROLLER USE ONLYt Controller Information: Contingency,. EOF If the radwasta shipping container 90-2-903 located at Site E, by the abandoned farm house has not been found, issue contingency EOF Message no. 48C (0 05:30),
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| i 3
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| 1, le >
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| \ !!.
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| Id' 4
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| f
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| 4 s - +
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| N Y
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| . J 1
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| 1990 EVALUATED EXERCISE TIME: lla,q tl Contingency Message Number 48C t =o5:30 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Contincency Messaaes for: EOF Messace:
| |
| **** THIS IS A DRILL ****
| |
| I'm Ken Kmetz. I saw a yellow crate over by my land. I saw .the word
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| " RADIOACTIVE" on it. You can get there. by going two miles east of Brownville on Highway 136. Turn south (right) at highway "D" on the gravel road for 1/4 mile. Then turn lef t for another 1/4 mile and turn right. Go 1 mile down the dirt road. Itr, located at the abandoned hcose on the left. ,
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| ./ :
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| - n.
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| i
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| - .____m_ _ _ _ _ ____.__m
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| 4
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| : b. k 1
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| I
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| .1990 EVALUATED EXERCISE TIME: 1330+
| |
| ' Message Number 49 t =05:30-06:15 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Messaces for! Site "E" Search Team htkKASSL
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| **** THIS IS A DRILL ****
| |
| .o As you-approach an abandoned farm house, you see one (1) box container on the-ground. The container is-labeled "Radic;ctive LSA", contal.a.or number 90-2-903.
| |
| It is ripped open with its contents scattered on the ground.
| |
| o- Some of the contents that you see on the ground are identifiable as rubber boots and gloves, paper, coveralls, wood, rope, and paint cans.
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| i l.
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| -.f.-
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| t' i
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| 1990 EVALUATED SXERCISE TIME: 1MQd ,
| |
| M:ssage Number 49 t =05:30-06:15 <
| |
| COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE ,
| |
| m FOR-CONTROLLER _USE_0NLY;.
| |
| Controller Information: Contingency, Site "E" Search Team o Team members upon arriving at the abandoned farm house see:
| |
| - - one (1) yellow (actual color is orange) box container on the ground. The container is labeled " Radioactive LSA", container number 90-2-903. It is ripped open with its contents scattered on the ground.
| |
| - Some of the contents are seen on the ground are identifiable as rubber boots and-gloves, paper, coveralls, wood, rope, and paint. cans.
| |
| 'o Determine the actions of the team members. If they approach - the ruptured container, they will become contaminated. Contamination will be >100 cpm but limit to <8,000 cpm. Tools and equipment which would be used ' near the *
| |
| - containers could become' contaminated. This will be left to the discretion of the controller. 1 o- Identifiable radioactive / contaminated material. is laying on the ground. All The controller will
| |
| ' material- found- will have a dose' rate less than 200 mR/hr.
| |
| have free play to idertify pieces which were in the container.
| |
| 1-
| |
| ~o Soil and vegetation samples taken within the contaminated area, are as follows:-
| |
| M VecetatiqIl CPM mR/hr _
| |
| . mR/hr CPM Throur!h bac Throuch bac
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| -.1 - 2 400 --8,000 .1 - 1. 400 - 4,000
| |
| *;The controller can provide reading within the above ranges.
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| I l
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| Expected' Actions:
| |
| , 'o' Notify EOF.
| |
| o Team members will begin ground surveys to identify the extent of contamination.
| |
| They should set up.a radiological control access' point.
| |
| o' Team - members may try to cover the loose material, such as They floor may dry and even sweeping compound to prevent further spread of the material.
| |
| begin to pick up loose material and place in-bags.
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| h l 4 4
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| l- .
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| 19901 EVALUATED EXERCISE- TIME = 1345 Message Number 50 t = 05:45 .
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| i COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Mggsaae for: Control Room l LSimulated Plant Conditions: See attached Plant Data 1
| |
| j Messaae:
| |
| **** THIS IS A DRILL **** j
| |
| .i
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| :r 4
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| 4 L
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| k i
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| I, t
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| h iI j i
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| .[1990 EVALUATED EXERCISE TIME = 1345
| |
| . Message Number EQ__ t= 05:45 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA .
| |
| PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) ELQH(gpm) REACTOR- POWER _j2_ % SRM :
| |
| RHR A TRIP O O REACTOR LEVEL 35 ," GEMAC.:
| |
| RHR C TRIP O O REACTOR PRESS psig RHR B ELQH (10^61bs/hr) ju{R D . FEEDWATER A 0 :
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| CS A TRIP O O FEEDWATER B 0 :
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| .CS B MAIN STEAM A 0 .:
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| 4c HPCI' ISOL 50 0 MAIN STEAM B 0 :
| |
| MAIN STEAM C 0 :
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| 'DRYWELL PRESS. psig MAIN STEAM D 0 :
| |
| TORUS LEVEL ft CRD A FLOW THIE gpm CRD B FLOW' gpm 2EEE CLOSED SLC TK LEVEL 0 %-
| |
| EMSIV STATUS 0 8 __ :
| |
| SLC PMP DISCH PRESS A C psig-SLC PMP DISCH PRESS B 0 psig PANEL 9-4 MISCELLANEOUS PANELS
| |
| ~ STATUS- PRESS (psig) ELQH(gpm)
| |
| RCIC DIESEL GEN 1 INOP :
| |
| RWCU A TRIP O O . _ ,
| |
| _ DIESEL GEN 2 OPER :
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| .RWCU B: S$1T ' A TRIP :
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| RRP A- TRIP % SPEED SBGT B OPER :
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| RRP B TRIP % SPEED DR7WELL COOLING :
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| TORUS WATER TEMP F DRYWELL TEMP F
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| RADIATION MONZTORS ,
| |
| 1990' EVALUATED EXERCISE . TIME = 1349 t= 05:45
| |
| -(
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| STATION DESCRIPTION READING (mR/hr) 1 Rx Bldg Fuel Pool Area-(SE 5th Floor) DQHNSCALE 2 Rx Bldg Fuel Pool Area (SE 5th Floor) DOWNSCALE 3~ Rx Bldg New Fuel Area (SE 5th Floor) DOWNSCALE 4~ Rx Bldg Rx Water Cleanup Demineralizer DOWNSCALE Area (SW 3rd Floor) 5 Rx Bldg Sludge and Decant Pump Area .8 (S 2nd Floor)
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| -6 Rx Bldg Neutron Monitor System Index - 151 Area (TIP Room ist Floor).
| |
| Rx Bldg Neutron Monitor System Drive DOWNSCALE 17 '
| |
| Mech Area. (SE ist Floor) DOWNSCALE 8 RX Bldg Cor. trol Rod Hydraulic Equipment Area (S ist F1ror) 9 Rx Bldg Control Rod Hydraulic Equipment DOWNSCALE Area (N lst Floor) DOWNSCALE l
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| 10 Rx Bldg HPCI Pump Room (SW Quad) g 11 Rx Bldg RHR Pump haar. (SW Quad) 5.1 12 Rx Bldg RHR. Pump Room (NW Quad) DOWNSCALE 13 Rx Bldg RCIC/CS Pump Room-(NE Quad) DOWNSCALE 14' Rx Bldg CS Pump Room (SE , Quad) 4.5
| |
| : 15. Turbine Bldg Turbine Front Standard 1 16 ' Turbine Bldg Mezz Control Corridor DOWNSCALE
| |
| -- 17 Turbine Bldg Basement Control Corridor DOWNSCALE Turbine. Bldg Rx Feed Pump Area 6 't 18.
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| 19 Turbine Bldg-Condensate Pump Area DOWNSCALE Control Room Main Control Room .02 20 21 Grade. Level Control Corridor DOWNSCALE
| |
| .22 Radwaste Control' Room- DOWNSCALE 23 Radwaste Pump Room DOWNSCALE 24 Radwaste Basement Equipment Area DOWNSCALE 25 Radwaste Demineralizer Valve Room DOWNSCALE L
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| 26 Radwaste Conveyor Aisle Operating Area DOWNSCALE i 27 SPARE Radwaste Lab Area .1 h 28 29 Centrifuge East 10 Centrifuge West 9 L 30
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| . Panel 9-02 Personnel Airlock Area 903' DOWNSCALE Panel 9-02 Ladder 903' to 2nd Level DOWNSCALE OSH = Offscale High j l
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| L L
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| L l
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| I' '
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| +
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| i~
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| RADIATION MONITORS 1990~ EVALUATED EXERCISE TIME = 1349 t= 05:45 EANEL VBDG Rx Bldg Vent Eff (RMV-RM-40 0 uCi/see ERP Stack Normal EFF (RMP-RM-3A) o uCi/sec ERP Stack High Range (RMP-RM-3B) 0 uCi/see Turbine Bldg Vent Eff (RMV-RM-20A) 0 uCi/sec
| |
| . Turbine Bldg High Range (RMV-RM-20B) 0 uci/sec-RW/ARW Bldg Combined Ef f (RKV-RM-307.) o uCi/see RW/ARW Bldg High Range (RMV-RM-30B) o uC1/sec PANEL 9-10 Main Steam Rad' Monitor Ch. A1, B1 .
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| 15 mR/hr 15 mR/hr CH. A2, B2 15 mR/hr 15 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 1 mR/hr 1 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hr 0.6 mR/hr _
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| Y i
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| L L
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| 4 L
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| L .
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| l l'
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| - . = .
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| i i
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| 1990 EVALUATED EXERCISE TIME = 1400 Message Number 1 t = 06:00 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Messaae for: Control Room Simulated, Plant Conditions:_ See attached Plant Data Messace: ,
| |
| **** THIS IS A DRILL ****
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| E l
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| i; 4
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| '.);
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| : }
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| | |
| ~ ~
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| j 19901 EVALUATED EXERCISE TIME = _iil2 l M rdage Number .,5.l_, t = _ 25 LO_Q l
| |
| QQQEER NUCLEAR STATION EMERGENCY PP.EPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) ELQit.(gpm) REACTOR P9WER 0 % SRM :
| |
| .RHR A TRIP O O REACTOR LEVEL ,,,25__ " GEMAC :
| |
| c .
| |
| 'RHR C TRIP O O REACTOR PRESS poig l RHR B FLOW (10^61bs/hr)
| |
| RHR D FEEDWATER A 0 :
| |
| CS A' TRIP 0 0- FEEDWATER B _0 :
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| CS B KAIN STEAM A 0 :
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| HPCI ISOL' 50 0 MAIN STEAM B 0 :
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| MAIN STEAM C 0 :
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| DRYWELL PRESS. psig MAIN STEAM D 0 :
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| 3 TORUS LEVEL ft CRD A FLOW TEI.E gpm CRD B FLOW gpm QRSH CLOSED SLC TK LEVEL 0 %
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| MSIV STATUS 0 8 :
| |
| SLC PMP DISCH PRESS A 0 psig i
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| SLC PMP DISCH PRESS B 0 psig L PANEL 9-4 ' MISCELLANEOUS PANELS 1'
| |
| STATUS PRESS (psig) ELQW(gpm)
| |
| 'RCIC DIESEL GEN 1 INOP :
| |
| L i
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| __ 0 DIESEL GEN 2 OPER : -!
| |
| lRWCU A TRIP _ 0
| |
| 'RWCU B SBGT A TRIP :
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| TRIP SPEED SBGT B QEEE,__:
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| j; RRP A. %
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| DRYWELL COOLING :
| |
| RRP'B TRIP % SPEED
| |
| - - TORUS WATER TEMP F DRYWELL TEMP F t.
| |
| | |
| RADIATION MONITORS
| |
| -1990 EVALUATED EXERCISE TIME = 1400
| |
| .t = 06:00 STATION DESCRIPTION READING (mR/hrF 1- Rx. Bldg Fuel Pool Area (SE 5th Floor) DOWNSCALE 2 Rx Bldg Fuel Pool Area (SE 5th Floor) DOWNSCALE 3 Rx Bldg New Fuel Area (SE 5th Floor) DOWNSCALE
| |
| '4 Rx Bldg Rx Water Cleanup Demineralizer DOWNSCALE Area (SW 3rd Floor) 5 .Rx Bldg Sludge and Decant Pump Area .8 (S 2nd Floor) 151 6 Rx Bldg Neutron Monitor System Index Area (TIP Room ist Floor) 7 Rx Bldg Neutron Monitor System Drive DOWNSCALE Mech Area (SE 1st Floor) 8 Rx Bldg Control Rod Hydraulic Equipment DOWNSCALE Area (S ist Floor) 9 Rx Bldg Control Rod Hydraulic Equipment DOWNSCALE Area ' (N ist Floor) DOWNSCALE 10 Rx Bldg HPCI Pump Room (SW Quad) 11 Rx Bldg ISR Pump Room (SW Quad) 5.1 12 Rx Bldg RHR Pump Room (NW Quad) DOWNSCALE 13- Rx Bldg RCIC/CS Pump Room (NE Quad) DOWNSCALE 14 Rx Bldg CS' Pump Room (SE Quad) 4.5 15 Turbine Bldg Turbine Front Standard 1 16 Turbine Bldg Mezz Control Corridor DOWNSCALE 17 -TurbineLBldg Basement Control Corridor DOWNSCALE 18 TurbinaiBldg Rx Feed Pump Area 6 19' Turbine Bldg' Condensate Pump Area DOWNSCALE 20' Control Room Main Control-Room .02 2 11 Grade Level Control Corridor DOWNSCALE 22' Radwaste Control Room DOWNSCALE 23- Radwaste Pump Room- DOWNSCALE 24 Radwaste Basement Equipment Area DOWNSCALE 25 Radwaste Demineralizer Valve Room - DOWNSCALE 26 Radwaste conveyor' Aisle Operating Area -DOWNSCALE 27 SPARE 28 Radwaste Lab Area .1 29L . Centrifuge-East 10 30 Centrifuge West 9 Panel-9-02 Personnel Airlock Area 903' DOWNSCALE Panel 9-02 Ladder 903' to 2nd Level DOWNSCALE OSH = Offscale High
| |
| | |
| +
| |
| RADIA*SION MONITORS 1990 ' EVALt1ATi. .i.dnCISE- TIME = 1400 t= 06:00 PANEL VBDG
| |
| = Rx. Bldg Vent-Eff-(RMV-RM-40 0 uCi/sec ERP Stack Normal EFF-(RMP-RM-3A) o uCi/sec ERP Stack High Range (RMP-RM-3B) 0 uCi/see
| |
| ~ Turbine Bldg Vent Eff (RMV-RM-20A) o uCi/see Turbine Bldg High Range (RMV-RM-20B) o uCi/see RW/ARW Bldg Combined Eff (RMV-RM-30A) 0 uC1/see RW/ARW Bldg High Range (RMV-RM-30B) 0 uCi/sec PANEL 9-10
| |
| . Main Steam Rad Monitor Ch. A1, B1 15 mR/hr 15 mR/hr CH. A2, B2 15 mR/hr 15 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 1 mR/hr 1 mR/hr
| |
| ' Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hr 0.6 mR/hr f
| |
| | |
| e i
| |
| 1990 EVALUATED EXERCISE TIME = 1415-Message Number A t = 06:15 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE I
| |
| Messace for: Control Room Simulated Plant Conditions: See attached Plant Data Messaae:
| |
| **** THIS IS A DRILL ****
| |
| i
| |
| {
| |
| lo i
| |
| :)
| |
| ,' 4
| |
| | |
| TIME = _1415 I 1990' EVALUATED ~ EXERCISE M:Ccage. Number 11__ t= 06:15 COOPER ~ NUCLEAR STATION EMERGENCY' PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 )
| |
| STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 0 % SRM : ;
| |
| RHR'A TRIP O ,
| |
| O REACTOR LEVEL _.2jli_ " . GEM)LC._:
| |
| RHR;C. TRIP O O REACTOR PRESS . psig RHR B FLOW'(10^61bs/hr) ,
| |
| RHR D FEEDWATER A 0 :
| |
| CS A TRIP- 0 0 FEEDWATER B 0 :
| |
| , CS B MAIN STEAM A 0 :
| |
| HPCI ISOL 50 0 MAIN STEAM B 0 :
| |
| MAIN 6 TEAM C 0 :
| |
| DRYWELL PRESS. psig MAIN STEAM D 0 :
| |
| TORUS LEVEL ft CRD A FLOW TRIP gpm CRD B-FLOW gpm QEEE CLOSED SLC TK LEVEL ___Q._ %-
| |
| MSIV STATUS 0 8 :
| |
| L SLC PMP DISCH PRESS A _,2_ psig l
| |
| SLC PHP DISCH PRESS B 0 poig
| |
| ['
| |
| l PANEL 9-4 MISCELLF 'US PANELS >
| |
| STATUS PRESS (psi?) FLOW (gpm) ;
| |
| .RCIC __
| |
| DIESEL GEN 1 INOP :
| |
| ~RWCU A TRIP O O DIESEL GEN 2 OPER :
| |
| RWCU B SBGT A TRIP :
| |
| 1RRP:A TRIP % SPEED SBGT B OPER :
| |
| RRP B TRIP % SPEED DRYWELL COOLING :
| |
| TORUS WATER TEMP F DRYWELL TEMP F.
| |
| | |
| 4 RADIATION MONITORS 1990. EVALUATED EXERCISE TZME = 1419 t
| |
| t= 06:15 STATION DESCRIPTION READING (mR/hr) 1 Rx Bldg Fuel Pool' Area (SE Sth Floor) DOWNSCALE 2 Rx Bldg Fuel Pool Area (SE 5th Floor) DOWNSCALE 3 Rx Bldg New Fuel Area (SE Sth Floor). DOWNSCALE
| |
| .4 Rx Bldg Rx Water Cleanup Demineralizer DOWNSCALE Area (SW 3rd Floor) 5 Rx Bldg Sludge and Decant Pump Area .8
| |
| -(S 2nd Floor) 151 6 Rx Bldg Neutron Monitor System Index Area (TIP Room 1st- Flaor) 7 Rx. Bldg Neutron Monitor System Drive DOWNSCALE Mech Area (SE 1st Floor) 8 Rx Bldg Control Rod Hydraulic Equipment DOWNSCALE Area (S lat Floor) 9 Rx Bldg Control Rod Hydraulic Equipment DOWNSCALE Area (N ist Floor) DOWNSCALE 10 Rx Bldg HPCI Pump Room (SW Quad) 11 Rx Bldg RHR Pump Room (SW Quad) 5.1 12 Rx Bldg RHR Pump Room (NW Quad) DOWNSCALE 13 Rx Bldg RCIC/CS Purp Room (NE-Quad) DOWNSCALE 14 Rx Bldg CS Pump Room (SE Quad) 4.5
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| 't 15 Turbine Bldg Turbine Front Standard 1 j 16 Turbine Bldg Mezz Control Corridor DOWNSCALE 17- Turbine Bldg Basement Control Corridor DOWNSCALE Turbine Bldg RX Feed Pump Area 6 18 19 Turbine' Bldg Condensate Pump Area DOWNSCALE 20 Control Room' Main Control Room .02 21 Grade Level Control Corridor DOWNSCALE 22 Radwaste Control Room DOWNSCALE 23- Radwaste Pump Room DOWNSCALE 24 - _Radwaste Basement Equipment Area DOWNSCALE 25 Radwaste Demineralizer Valve Room DOWNSCALE 26 Radwaste Conveyor Aisle Operating Area DOWNSCALE 27 SPARE Radwaste Lab Area .1 28 29 Centrifuge East 10-30 Centrifuge West 9
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| . Panel 9-02 Personnel Airlock Area 903' DOWNSCALE Panel 9-02 Ladder 903' to 2nd Level DOWNSCALE OSH = Offscale High
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| RADIATION MONI' SORS 1990: EVALUATED EXERCISE TIME = 1419 t= 06:15 [
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| L
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| ' PANEL VBDG Rx' Bldg Vent Eff (RMV-RM-40 0 uCi/sec -
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| ERP Stack. Normal EFF (RMP-RM-3A) 0 uCi/see ERP Stack High Range (RMP-RM-3B) 0 uci/sec _
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| Turbine Bldg Vent Eff (RMV-RM-20A) o uci/sec .
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| Turbine Bldg High Range (RMV-RM-20B) 0 uCi/sec RW/ ARW Bldg Combined Ef f (RMV-RM-30A) o uci/see RW/ARW Bldg High Range (RMV-RM-30B)_ 0 uci/sec PANEL 9-10 Main Steam Rad Mor itor Ch. A1, B1 ,_ 15 mR/hr 15 na/hr-CH. A2, B2 15 mR/hr 15 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B. 1 mR/hr l'mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hr 0.6 mR/hr 1
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| i 1990 EVALUATED EXERCISE TIME = 1430 Message Number .53.. t = 06:30 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Messace for: Control-Room Simulated Plant Conditions: See attached Plant Data Messace:
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| **** THIS IS A DRILL ****
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| P 4
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| 1 i
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| !}}
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