ML20059C669
| ML20059C669 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 10/13/1993 |
| From: | CENTERIOR ENERGY |
| To: | |
| Shared Package | |
| ML20059C656 | List: |
| References | |
| NUDOCS 9311010253 | |
| Download: ML20059C669 (250) | |
Text
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1993 Evaluated Exercise TABLE OF CONTENTS FOR 1993 EXERCISE MANUAL
.O PART I GENERAL INFORMATION 1.0 SCOPE AND OBJECTIVES 1.1 Scope ;
1.2 Objectives (DBNPS) l 2.0 EXERCISE INFORMATION 2.1 Exercise Participants 2.2 Exercise Organization
- 2.3 Emergency Response Facilities 2.4 Exercise Conduct 2.5 Precautions and Limitations 2.6 Evaluation and Critique 2.7 Scenario Development Committee
3.0 REFERENCES
/ ABBREVIATIONS / DEFINITIONS 3.1 References 3.2 Abbreviations 3.3 Definitions
(} 4.0 CONTROLLER / EVALUATOR INFORMATION 4.1 Controller Instructions 4.2 Evaluator Instructions 4.3 Use of Simulator 4.4 Use of Control Cell 5.0 SCHEDULE OF EVENTS 5.1 Times and Places 5.2 Travel Information O i
1993 Evaluated Exercise TABLE OF CONTENTS FOR 1993 EXERCISE MANUAL (Cont.) ' PART II CONTROLLED INFORMATION 6.0 EXERCISE SCENARIO 6.1 Narrative Summary 6.2 Initial Conditions 6.3 Onsite Sequence of Events 7.0 PLANT CUE CARDS AND OPERATIONS DATA l 7.1 Plant Cue Lards l 7.2 Plant Parameters Summary 7.3 Plant Parameters Sheets
- 4 7.4 Control Room Alarm Panels 8.0 IN-PLANT RADIOLOGICAL, RADI0 CHEMISTRY AND MEDICAL DATA 8.1 In-Plant Radiation Monitors Summary 8.2 Radiation Element Data Sheets 8.3 Plant Radiation Maps 8.4 Radiochemistry Data Summary 8.5 Radiochemistry Data Sheets 8.6 Post Accident Sampling Data ,
8.7 Medical Drill Data 1 8.8 Medical Drill Cue Cards i l 9.0 0FFSITE DOSE ASSESSMENT DATA, PLUME MAPS AND PULLIC INFORMATION CUE CARDS l 9.1 Meteorological Forecast Data 9.2 Meteorological Data Summary 9.3 ECC Dose Assessment Center Cue Cards 9.4 Radiation Plume Maps 9.5 Public Information Cue Cards 10.0 EQUIPMENT STATUS AND REPAIR CUE CARDS 10.1 Equipment Status Summary 10.2 Equipment Status Sheets 10.3 Equipment Repair Data 10.4 Equipment Repair Cue Cards e 11 g e
1993 Evaluated Exercise O DAVIS-BESSE NUCLEAR POVER STATION DRILL / EXERCISE APPROVAL COVER SHEET DRILL TITLE: 1993 Evaluated Exercise DATE OF CONDUCT: October 13, 1993 TIME OF CONDUCT: 0700 DRILL LEAD CONTROLLER: B. V. Cepe l APPROVED: Nk Manager
* /- Emerg6dcy Preparedness 6-G-93 Pate APPROVED: O ? -(s - 9 R UT Ylant Man W ' Date -
APPROVED: M Vice President, Nuclear Date
)
O 1 l I 111
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1993 Evaluated Exercise DRI LL/EXERCI SE NOTIFICATION / AUT110RIZATION - 3 i DRILL TITLE: 1993 Evaluated Exercise 1 To be initiated October 13, 1993 at 0700 l Date Time Lead Controller: B. V. Cope i INITIATING CONDITIONS Cue Card N/A Alarm: Various control room alarms I Other: Turbine Generator failure i F Description of Initiating Condition (s): Lightning strike causes a load ' i i rejection and Turbine Generator failure Special Consideration (s): l 1 i i i
/'l CONTROL ROOM N T FICATIQN ,
Approval: Date b / O / - Time l' 4 Shift Supervisor , Disapproval *: Date / / Time Shift Supervisor Justification for Disapproval: l r i REVIEV Lead Controller: Date / / Supervisor - Onsite Emergency Preparedness: Date / / ,
- Disapproval must be forwarded to the Plant Manager, j cc: Assistant Plant Manager - Operations j s
iv
l 1993 Evaluated Exercise 4 DRILL / EXERCISE SCENARIO OBJECTIVE CHECK SHEET
- 1. Drill / Exercise
Title:
1993 Exercise- i
- 2. Time Frame: ,
- a. Season (Circle one)
Vinter Spring Summer Fal
- b. Period of the week (Circle one) eek Veekend Holiday
- c. When shall the drill begin (circle one)
. - - s.,
4 am - 6 pm 6 pm - 4 am ,
- d. Projected Drill / Exercise date 10 / 13/ 93
- e. The drill vill be (Circle one)
,..- O Announced ) Unannounced M '
- f. Date of last similar Drill / Exercise J _/ 13 / 92
- g. Real time span of Drill 8 hours, i day (s)
- h. Drill / Exercise time frame 8 hours, I day (s) '
- 3. Maximum Level of Classification Emergency:
- a. Classifications achieved during the Drill / Exercise (Check one)
Unusual Event Alert < Site Area Emergency Genatal Emergency Not a Classifiable Event
- 4. Organization / Facility Involvement: ,
I
- a. Onsite: I Control Room Staff Yes/No TSC /No v
i 1993 Evaluated Exercise 1 DRILL / EXERCISE SCENARIO OBJECTIVE CHECK SHEET (Cont.) i Onsite: (Cont.) Gl ECC /No Site Security s/No e Fire Brigade Ye / fig / ,
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OSC Yes/No RTL /No
/' 1 Public Information ges/No 1 CRER Organization Ye
- b. Offsite: l Ottava County EOC s/No Lucas County E0C /No r, \
Evacuation host county EOCs Tes No l Ottava County Sheriff's Department No Lucas County Sheriff's Department es/No l Carroll Township Fire Department Yes No l State of Ohio EOC Yes/No NRC Yes 4o ' ~ FEMA Yes to s State of Michigan Yes o EmergencyJedical (St. Charles, Yeg/No rem gruder hospitals) Ambulance /No
- 5. Communication:
- a. Do you desire to exercise the emergency communications s systems? es/No
- b. Do you desire to use the emergency paging system? io e
vi
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.O Communication: (Cont.)
- c. Should a news bulletin be prepared? e No .
-d. Do you desire to activate the Joint Public Information
/No Center?
- e. Do you desire to exercise the Computerized Automated Notification System (CANS)? No I r
Is a medical problem to be involved? hes/No
- 6. ,
No If yes, a) Onsite response? b) Offsite response? No c) Victim (s) injury (ies) fru.eduad OXe !] odorc.t sion c -l 0{ 4lu ricl4 St.~e a vm a-, A r; < [ + 4 $drb v s.a 1 v v a -l o n d . d ha eT/No d) Is the victim contaminated?
- e. If yes is answered for 6.b) above, describe involvement of offsite organization. dr ne t t.z,r -f cl.i a lar Ad-(h ,Au Emi a <
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- 7. Vill the exercise involve a fire? Ye h
- a. Onsite response? Yes/No N/1
- b. Offsite response? Yes/No e/d f
- c. Describe involvement of responder. O l
vii
1993 Evaluated E::ercise DRILL / EXERCISE SCENARIO OBJECTIVE SHEET (Cont.) O Communication: (cont.)
- 8. Vill the Security Force response be tested? Ye
- a. Sabotage / Bomb? Yes/No e/S
- b. Intruder? Yes/No s/n
- c. Evacuation? Yes/No oft
- d. Other M[Il
- 9. Radiological Release:
- a. Meteorological Capabilities:
- 1) Vill real-time meteorology be used? Ye.
e
- 2) Vill simulated meteorology be used? p No
- 3) Vill weather forecasting capability be required? Yes[
- b. Dose Assessment:
- 1) Vill dose projection be backed up by field monitoring?hNo
- 2) Vill long-term dose projections be calculated? Ye Source of radioactive release a c\ q u g - n e l,' A yl 4t, 3) d to.d e m .i m4 sdd uc,<4L S j cJ 4/ sido, 4
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- c. Post-accident Sampling:
- 1) Vill post-accident sampling cepabilities be exercised? Yesh
- 2) If yes, to what extent? M/4 Approved: ML _
Hanager - 2%ergency Preparedness 8r-C. - 93 Date viii
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1-1 1993 Evaluated Exercise 1.0 SCOPE AND OBJECTIVES 1.1 SCOPE The 1993 Davis-Bes^e Emergency Preparedness Exercise, to be conducted on October 13, 1993, will test and provide the opportunity to evaluate i the Onsite Davis-Besse Emergency Pian and Emergency Plan Procedures. It vill also test the onsite emergency response organization's ability to assess and respond to emergency conditions and take adequate actions to protect the health and safety of the public and Station personnel. The Exercise vill demonstrate the utilization of the Station's Emergency Response Organization and will involve activation and operation of major elements of offsite emergency response organizations. NOTE: Information necessary to conduct the offsite portion of the Exercise, including the objectives, extent of play, sequence , of events, cue cards and supporting information, is provided in a separate volume of the Exercise manual. Whenever practical, the drill incorporates provisions for " free play" on the part of the participants. Selected "real time" activities vill be conducted to allow repair teams the opportunity to provide service and repairs to station equipment during the course of the Exercise. These " repairs" vill allow the response organization to have an increased impact upon the direction that the Exercise proceeds as well l as impacting the completion of the Exercise activities. In addition, O the Control Room Simulator vill be used to permit a degree of " free play" on the part of the Operations staff. The extent of this " free ' play" may be partially restricted by Controllers as necessary to keep the sequence of events on track. The scenario vill simulate a sequence of events resulting in a - radiological release to the environment. This release vill be of a sufficient magnitude to warrant mobili-ation of state and local agencies in response to the simulated emergency. P The scenario vill also incorporate a Medical Drill with participation by local emergency medical services and a support hospital. I In the development of an accident sequence which is severe enough to adequately test the emergency response capabilities of participating
- organizations, it is necessary to postulate extremely unrealistic situations and multiple failures of redundant reactor protection functions and systems. However remote the possibility of these events occurring, Players are reminded to respond appropriately.
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i i i 1-2 1993 Evaluated Exercise i 1.2 DAVlS-BESSE NUCLEAR POVER STATION OBJECTIVES O REF. FACILITIES OBJECTIVE i A.1 Administrative CONDUCT AN EXERCISE OF THE DAVIS-BESSE NUCLEAR POVER STATION (DBNPS) EMERGENCY PLAN, ANNUALLY. , A.2 Administrative PROVIDE AN OPPORTUNITY FOR THE STATE OF OHIO, OTTAVA COUNTY, AND LUCAS COUNTY TO PARTICIPATE IN AN EXERCISE, ANNUALLY (FULL VS PARTIAL PARTICIPATION). ] j A.3 Administrative PREPARE AN EXERCISE INFORMATION PACKAGE TO MEET MINIMUM STANDARDS. A.4 Administrative CONDUCT A CRITIQUE OF THE EXERCISE. I A.5 Administrative ESTABLISH MEANS TO ENSURE COMPLETION OF CORRECTIVE ACTIONS. A.6 Administrative INVOLVE FEDERAL, STATE, COUNTY EP RESPONSE PERSONNEL AND , AGENCIES IN A JOINT EXERCISE AT LEAST ONCE EVERY TVO YEARS. i A.9 Administrative CONDUCT THE EXERCISE IN VARIOUS VEATHER CONDITIONS (DURING DIFFERENT SEASONS). B.1 All DEMONSTRATE THE DIRECTION OF THE EMERGENCY ORGANIZATION AND IMPLEMENTATION OF THE EMERGENCY PLAN AND EMERGENCY t PLAN PROCEDURES. B.2 Control Room, DEMONSTRATE THE TRANSFER OF THE EMERGENCY COORDINATOR ECC DUTIES. [ l B.3 All DEMONSTRATE THE ABILITY FOR TIMELY ACTIVATION AND i STAFFING OF THE EMERGENCY FACILITIES. B.4 All DEMONSTRATE THE ABILITY TO CONTROL ACCESS TO EMERGENCY FACILITIES. i B.7 RTL DEMONSTRATE THE CAPABILITY OF A CENTRAL POINT FOR THE i RECEIPT AND ANALYSIS OF ALL FIELD MONITORING DATA AND j COORDINATION OF SAMPLE MEDIA. 4 B.9 ECC DEMONSTRATE THE AVAILABILITY AND DISPATCH OF A TECHNICAL l LIAISON TO OFFSITE GOVERNMENTAL EOC'S (DEMONSTRATE ONLY l I VITH FULL OFFSITE PARTICIPATION). l C.1 Control Room, DEMONSTRATE THE ABILITY TO ASSESS THE INCIDENT l 2 TSC CONDITIONS. C.2 Control Room, DEMONSTR/TE THE ABILITY TO RECOGNIZE EMERGENCY ACTION l O ECC, TSC LEVELS (EA!.'S) AND PROPERLY CLASSIFY THE INCIDENT. ; i I i l 1 I
1-3 1993 Evaluated Exercise REF.
# FACILITIES OBJECTIVE D.1 Control Room, DEMONSTRATE THE ABILITY TO NOTIFY KEY OFFICIALS IN THE ECC EMERGENCY ORGANIZATIONS (STATION, CORPORATE, STATE OF OHIO, OTTAVA COUNTY, AND LUCAS COUNTY) VIA THE NOTIFICATION SYSTEM / PROCEDURES VITHIN 15 MINUTES OF CLASSIFICATION.
D.2 Control Room, DEMONSTRATE THE ABILITY TO NOTIFY THE NRC OF ANY ECC EMERGENCY CLASSIFICATION VITHIN ONE HOUR OF THE OCCURRENCE. D.3 All DEMONSTRATE THE CAPABILITY TO NOTIFY AND/0R ACTIVATE EMERGENCY PERSONNEL IN EACH RESPONSE ORGANIZATION. l D.4 Control Room, DEMONSTRATE THE ABILITY TO DEVELOP AND SEND AN INITIAL ECC EMERGENCY MESSAGE FOR OFFSITE NOTIFICATION. l D.5 Control Room, DEMONSTRATE THE ABILITY TO DEVELOP AND SEND FOLLOV-UP ECC MESSAGES FOR INFORMATION FOR OFFSITE AUTHORITIES. D.6 Control Room, DEMONSTRATE THE COMMUNICATIONS CAPABILITY AMONG THE TSC, ECC CONTROL ROOM, TSC AND ECC, AND AMONG DBNPS. THE STATE OF OHIO, OTTAVA COUNTY, AND LUCAS COUNTY EMERGENCY OPERATIONS CENTERS AND THE FIELD ASSESSMENT TEAMS, TO INCLUDE EVALUATION OF THE ABILITY TO UNDERSTAND MESSAGE CONTENT (COMMUNICATIONS DRILL REQUIREMENT). D.8 ECC DEMONSTRATE THE ABILITY TO DEVELOP A LEGITIMATE, INFORMATIVE, AND CLEARLY UNDERSTOOD MESSAGE TO BE SENT TO j STATE, AND COUNTY OFFICIALS WHO MAKE DECISIONS TO l l ACTIVATE THE ALERT AND NOTIFICATION SYSTEMS. D.9 ECC DEMONSTRATE THE COMMUNICATIONS CAPABILITY VITH STATE, OTTAVA COUNTY AND LUCAS COUNTY VITHIN THE PLUME EXPOSURE EPZ. (COMMUNICATION DRILL VERIFY OBERABILITY OF HARDWARE ONLY). D.12 OSC, SEC DEMONSTRATE THE COMMUNICATIONS CAPABILITY WITH FIXED AND MOBILE MEDICAL SUPPORT FACILITIES (MEDICAL DRILL REQUIREMENT). E.1 ECC DEMONSTRATE THE METHODS AND TECHNIQUES FOR DETERMINING THE SOURCE TERM OF RELEASES OR POTENTIAL RELEASES OF l RADIOACTIVE MATERIAL VITHIN PLANT SYSTEMS. E.2 ECC DEMONSTRATE THE METHODS AND TECHNIQUES FOR DETERMINING THE MAGNITUDE OF THE RELEASES OF RADIOACTIVE MATERIALS BASED ON PLANT SYSTEM PARAMETERS AND EFFLUENT MONITORS. E.3 ECC DEMONSTRATE THE ABILITY TO ESTIMATE INTEGRATED DOSE FROM PROJECTED AND ACTUAL DOSE RATES AND TO COMPARE THESE ESTIMATES VITH THE PAG'S. E.4 OSC, ECC DEMONSTRATE THE ABILITY TO IMPLEMENT EXPOSURE GUIDELINES.
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--l 1-4 1993 Evaluated Exercise REF.
()
# FACILITIES- OBJECTIVE E.5 OSC, ECC DEMONSTRATE THE ABILITY TO CONTINUOUSLY MONITOR AND '
CONTROL EMERGENCY VORKER EXPOSURE. , i E.7 ECC, RTL, RMT DEMONSTRATE THE RESOURCES AND CAPABILITY FOR FIELD MONITORING VITHIN THE PLUME EXPOSURE EPZ. E.11 OSC DEMONSTRATE THE AVAILABILITY OF RESPIRATORY PROTECTION, , PROTECTIVE CLOfHI"G AND KI. E.12 OSC, TSC DEMONSTRATE THE ORGANIZATIONAL ABILITY TO AUTHORIZE EMERGENCY VORKER EXPOSURE IN EXCESS OF 10CFR20 LIMITS. , E.15 OSC, SEC DEMONSTRATE THE CAPABILITY FOR TRANSPORTATION OF A RADIOLOGICAL ACCIDENT VICTIM (MEDICAL DRILL REQUIREMENT). E.17 DEMONSTRATE THE RESPONSE T0, AND ANALYSIS OF, SIMULATED ELEVATED AIRBORNE AND LIQUID SAMPLES AND DIRECT RADIATION MEASUREMENTS IN THE ENVIRONMENT. i F.1 ECC DEMONSTRATE THE ABILITY TO RECOMMEND PROTECTIVE ACTIONS TO APPROPRIATE OFFSITE AUTHORITIES; BASES OF RECOMMENDATIONS TO INCLUDE CONSIDERATION OF PROTECTION AFFORDED BY SHELTERING, AS VELL AS EVACUATION TIME , ESTIMATES. , F.2 JPIC DEMONSTRATE THE OPERATION OF THE JOINT PUBLIC INFORMATION t CENTER AND THE AVAILABILITY OF SPACE FOR THE MEDIA. ; F.3 JPIC DEMONSTRATE THE ABILITY TO BRIEF THE MEDIA IN A CLEAR, : J ACCURATE AND TIMELY MANNER. F.4 JPIC DEMONSTRATE THE ABILITY TO PROVIDE ADVANCE COORDINATION 1 0F INFORMATION RELEASED (DEMONSTRATED ONLY VITH FULL , OFFSITE PARTICIPATION). F.6 SEC DEMONSTRATE THE CAPABILITY TO EVACUATE NON-ESSENTIAL PERSONNEL. F.11 OSC DEMONSTRATE THE CAPABILITY FOR ONSITE FIRST AID (MEDICAL DRILL REQUIREMENT). F.12 OSC DEMONSTRATE THAT PROVISIONS ARE AVAILABLE FOR THE EVALUATION OF RADIATION EXPOSURE OF, AND RADIATION UPTAKE : IN A RADIOLOGICAL ACCIDENT VICTIM (MEDICAL DRILL i REQUIREMENT). G.1 All DEMONSTRATE PRELIMINARY DISCUSSIONS OF RELNTRY AND RECOVERY CAPABILITIES AND AVAILABILITY OF PROCEDURES. O k
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tl 2-1 1993 Evaluated Exercise 2.0 DRILL INFORMATION t 2.1 DRILL PARTICIPANTS t The participants in the Exercise vill include the following groups: 2.1.1 The Davis-Besse Nuclear Power Station (DBNPS) _
- 1. Control Room (CTRM) Simulator [
I
- 2. Technical Support. Center (TSC)
- 3. Operations Support Center (OSC)
- 4. Emergency Control Center (ECC)
- 5. Dose hssessment Center (DAC)
- 6. Radiological Testing Lab (RTL) ,
i
- 7. Radiation Monitoring Teams (RHTs) ;
- 8. Alternate Joint Public Information Center (JPIC) 'i
.1
- 9. Davis-Besse Nuclear Security Force (SEC) {
2.1.2 The State of Ohio vill participate. 2.1.3 Organizations from Sandusky, Ottava and Lucas Counties vill , be participating. l y 2.1.4 The Mid-County Emergency Medical Service and Fremont ., Memorial Hospital vill participate in the medical portion ! of the Exercise. ! 2.2 DRILL ORGANIZATION I The organization for this Exercise vill consist of the Exercise Coordinator, the Controllers, the Evaluators, the Players, and the , Observers, as follows: , 2.2.1 -The Exercise Coordinator is responsible for a successful- ! exercise, and vill coordinate all Exercise preparations. Subsequent to the conduct of the Exercise , he vill coordinate the preparation of a consolidated evaluation package, and prepare and follow up on the corrective actions recommended as a result of the evaluation and critique. , 2.2.2 The Lead Exercise Controller is responsible for the safe e conduct of.the Exercise. He vill coordinate the resolution of any scenario-related inter-facility questions, and ensure that the conduct of the Exercise does not adversely impact the operation of the Station. 1
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2-2 1993 Evaluated Exercise l 2.2.3 Controllers are personnel selected to perform functions as follows: 91
- 1. A Lead Facility Controller is assigned to each emergency ;
response facility. The Lead Facility Controller is j responsible for all Controller, Evaluator, and Observer ! activities in that facility and, as appropriate, its ! associated teams. Controllers for teams or subgroups of a facility report to the Lead Facility Controller.
- 2. The Controllers vill deliver " Cue Cards" to designated players at specified times and places during the Exercise, including contingency messages as required to keep the Exercise moving according to the scenario.
Controllers vill also observe the participants at their assigned locations, and prepare an evaluation. Con-trollers vill submit vritten evaluations to the Lead Facility Controllers, who vill summarize all comments for submittal to the Lead Drill Controller. Con-trollers are provided with instructions in Section 4.0 of this manual.
- 3. All Controllers vill act as Evaluators, as described below, and vill be identified as Controllers by vearing red arm bands.
2.2.4 Evaluators are personnel who are assigned to judge the effectiveness of participating organizations, personnel, and activities. Evaluators vill record their observations using the evaluation forms provided and make recommendations to the Lead Facility Controller. They vill evaluate perfor-mance on the basis of standards or requirements contained in the Emergency Plan, Implementing Procedures, Exercise messages, and appropriate evaluation criteria. Evaluators vill be identified by vearing red arm bands. 2.2.5 Players include all personnel assigned to perform emergency functions as described in the Emergency Plan and procedures. Players vill be identified by wearing blue arm bands only in those areas where there may be confusion between participants and non-participants. 2.2.6 Observers may be authorized, on a limited basis, to participate in the Exercise for the purpose of observing Exercise activity for personal education. Onsite Observers vill report initially to the DBNPS Emergency Preparedness Manager for credential review and authorized admittance. They vill be provided with orientation information and , appropriate exercise publications. Onsite Observers vill be identified by vearing green arm bands. Offsite observers ' vill report to the Lead Facility Controller for the respective facility and vill be identified by wearing green arm bands.
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2-3 1993 Evaluated Exercise t O Requests to' participate as an Observer should be made in writing and contain the Observer's full name, home address and phone number, and organizational. affiliation. Requests to participate as Onsite Observers must be submitted to the DBNPS Emergency Preparedness Manager no later than one week before the Exercise. 2.3 EMERGENCY RESPONSE FACILITIES During the Exercise, the following facilities vill be activated to manage, assess, and support emergency response activities. 2.3.1 Onsite Facilities i The Davis-Besse cmergency response facilities include:
- 1. Control Room (CTRH) !
The DBNFS Control Room, located on the 623' elevation ; of the Auxiliary Building, is the facility from which the routine operation of the plant is conducted. . During abnormal or emergency conditions, when the i Emergency Plan is implemented, the Shift Supervisor is given additional responsibilities as the Emergency Director. In this capacity, he is responsible for the i coordination of the Toledo Edison /DBNPS response to e i ( emergency until relieved. The initial response to this : scenario, and any emergency condition, is managed by the Operating Shift Crev in the Control Room. Once the
- Shift Supervisor is relieved of the responsibilities of Emergency Director, the Operating Shift Crev retains responsibility for operation of plant systems and equipment.
NOTE: For this Exercise the Davis-Besse Control Room Simulator located in the Training Center vill be used. (See Section 4.3)
- 2. Technical Support Center (TSC)
When emergency conditions escalate to an Alert status or higher, coordination of the operations aspects of - the emergency response vill shift from the Control Room to the TSC, located in the Davis-Besse Administration l Building. The primary function of the TSC is to I support an organization that provides technical assis- l tance to Station personnel during emergency conditions. l The TSC provides direct voice and data communications contact with the Corporate Emergency Response Organization (CERO). Control Room instrumentation can normally be observed using closed-circuit television () (CCTV) from the TSC, however, with Control Room
2-4 1993 Evaluated Exercise response occurring at the simulator, the CCTV vill not be available. The TSC also contains the DADS (Data Acquisition and Display System) and the SPDS (Safety Param2ter Display System) to enable the TSC staff to acquire plant data in support of technical evaluations needed to mitigate emergency conditions and recovery operations. The TSC contains work space for up to 25 people. > The Shift Supervisor's office, which is immediately adjacent to the Control Room, provides work space for the Emergency Assistant Plant Manager and a ' communicator. This location allows better management coordination of the emergency response functions by being closer to problems needing attention. NOTE: Personnel who would normally report to the Shift Supervisor's office vill be in the vicinity of the Control Room Simulator for this Exercise. f 1
- 3. Operations Support Center (OSC)
The OSC, located in the second floor lunchroom of the Personnel Shop Facility (PSF), provides a location for assembly and coordination of emergency response teams. The OSC is activated at Alert or higher emergency conditions, and may be activated for an Unusual Event at the discretion of the Shift Supervisor / Emergency Director. The purpose of the Operations Support Center is to pro-vide a pool of skilled manpover from which emergency response teams are assembled (e.g. First Aid, Opera-tions, Fire Brigade, Emergency Maintenance and Reentry teams). Also, it provides an assembly area for desig-nated plant personnel who are not on shift.
- 4. Emergency Control Center (ECC)
The ECC, located in the Davis-Besse Administration Building, is activated at Alert or higher emergency conditions. The ECC's primary function is to provide a centralized location for management of protective action planning, and continuous coordination and control of onsite and offsite emergency activities. The ECC staff evaluates the impact of actual or poten-tial radioactive releases, and provides management _ assistance in the decision-making process to protect the public health and safety. Recommendations to State , and County authorities are based on Station conditions as well as radiological and meteorological data. The ECC contains advanced systems to establish and maintain
k 2 1993 Evaluated Exercise ~ q communications with state, federal, and local offi-cials, and to enable coordination and control of Radia- ; tion Monitoring Teams (RMTs). : The ECC provides space for occupancy of at least 16 people. ,
- 5. Dose Assessment Center (DAC) -l A section of the ECC that controls the operation of the t Field Radiation Monitoring Teams to gather radiation '
i data for evaluation of the impact of actual or potential radioactive releases. Provides technical assistance in the decision to protect the public health-and safety. The Dose Assessment Center contains ; communication and computer equipment to contact RMT's and project radiation doses offsite. .
- 6. Radiological Testing Laboratory (RTL)
The RTL's primary function is to provide a location i near the ECC and TSC for radiological analysis of lov 'I level environmental samples. The RTL contains work '! areas for 4 people and additional space allotted for i temporary occupancy by field personnel. Major equip- l ment components in the RTL are designed to be removable l
\ for potential use in the field. !
- 7. Radiation Monitoring Team (RHTs)
Radiation Monitoring Teams are emergency responders ( trained to monitor radiological conditions outside the i Protected Area, and report these conditions to the Dose ' Assessment Center for evaluation. .g Joint Public Information Center (JPIC)
- 8. :
The Joint Public Information Center (JPIC) is the i emergency facility for coordinating news releases and providing joint briefings to the media during an event l at Davis-Besse. A primary and an alternate location are available to support this function. Toledo Edison Company, state, local and federal agencies represented ; at the JPIC jointly prepare news information for : release to the public via the news media. Equipment and work spaces for Public Information Officers and i their staffs are provided to support timely communi- ' cations on plant status and emergency response actions. . JPIC facilities. include news briefing areas for , approximately 200 electronic and prir,t media represen- i tatives. Facility operations and administrative { O support are coordinated by Toledo Edison. JPIC support i is available for any plant emergency. However, l l
2-6 1993 Evaluated Exer:ise facility activation is mandatory at (and above) the - Alert emergency classification level. NOTE: For the purposes of this Exercise, the primary JPIC will not be activated.
- a. Primary JPIC The primary JPIC is located in the Energy Education Center (EEC) at the Davis-Besse Administration Building. l 1
- b. Alternate JPIC The alternate JPIC is located in the Edison Club - !
Auditorium, 1036 River Road, Maumee, Ohio. i 2.4 EXERCISE CONDUCT , 1 I 2.4.1 Overview l The Exercise vill simulate an abnormal incident at Davis-Besse which will escalate over a period of several hours. The simulated emergency vill then terminate and the Recovery Phase vill be initiated. The conduct of the Exercise vill demonstrate the effectiveness of h participating organizations, personnel, and activities in support of the Emergency Plan and associated procedures. l i Unlike other drills or practice sessions, Controllers are not permitted to " coach" or otherwise assist Players in responding to l the simulated conditions. The Controllers can, however, provide ! clarification as necessary for Players to understand the intent of or the message given on a cue card. 2.4.2 Actions Emergency response actions during the simulated emergency will include: recognition and classification of emergency ; conditions; assessment of onsite/offsite radiological i consequences; alert / notification and mobilization of the emergency response organization; implementation of in-plant corrective actions; activation / operation of emergency response facilities and equipment; preparation of reports, messages, and recordkeeping. 2.4.3 Communications The Exercise vill test communications equipment operability and the ability of participants to demonstrate the effective , use of these systems. ll'
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2-7 1993 Evaluated Exercise () 2.4.4 Players The success of the Exercise is largely dependent upon player , reaction, knowledge of the Emergency Plan and objectives of the Exercise. Initial conditions which vill affect Player actions vill be provided to the Players at the time the i Exercise begins. Most elements of the Exercise vill be , introduced through the use of " Cue Cards". Players are ! responsible for initiating actions in accordance with ' Exercise instructions, their assigned responsibilities, and the procedures for their particular duties. Vith the exception of those actions that vill become intuitively - obvious, each Player vill advise his/her Controller prior to performing emergency response actions in order to ensure that credit is given for those actions.
- 1. The Simulator Control Room vill be the central point for distribution of the majority of cue cards / data ,
sheets, and is the key to ensuring that the Exercise is ! on schedule. Plant parameters vill be provided to the , Control Room operators using the simulator displays. ! The Control Room Operators are responsible for relaying pertinent plant drill data to other emergency faci]ities. The Data Acquisition and Display System (DADS) including the Safety Parameter Display System , (SPDS) and the TSC Plant Status display vill exhibit i O specific parameters. DADS and SPDS trends vill display gradual trend changes in plant parameters. The TSC will have point value and group displays available to ; monitor the current plant status. A redundant SPDS system vill continue to provide actual SPDS parameters ' and alarms. In the event of an actual emergency resulting in the termination of the Exercise, real-time SPDS vill be ; restored to the TSC within minutes. ,
- 2. In order to develop an accident sequence that ;
challenges the entire emergency response organization, it is necessary to suppose incredible situations. The ; Players must accept the Exercise messages as written. j Time shall not be spent discussing why a situation i could not occur. Players shall react as though it did. If corrective actions are proposed that would terminate the emergency, they should be identified to the Lead ! Facility Controller, so that he can acknowledge the corrective actions, but continue the scenario progress as designed. Players are expected to " free play" the scenario to the extent practical. Notifications of, and contact with supervisors, plant management, and offsite agencies vill be made in accordance with plant O procedures and any guidelines established at the start of the Exercise. l l l
2-8 1993 Evaluated Exercise j l Players are reminded not to be excessively concerned i with the mechanics or cause of the simulated malfunc-tions. This Exercise is designed to evaluate the Emergency Plan, Implementing Procedures, and Emergency j Preparedness Training Program; not the probability, feasibility, or detailed mechanics of the simulated accident. Players should note any needed improvements to Emergency Response Facilities and equipment, Emergency Procedures, or Emergency Preparedness Training that come to their attention during the Exercise. Players shall submit recommendations to the appropriate Controller at the conclusion of the Exercise. l 2.4.5 Simulation List As previously noted, Players vill be permitted as much free play as is possible pursuant to the continued safe operation of the plant. Those actions which do not have a direct bearing on actual plant operation should be performed. In i light of this and in accordance with this year's extent of play, Controllers and Players shall ensure that the following plant actions are simulated:
- 1. Evacuation of site personnel beyond the initial personnel accountability;
- 2. Offsite assembly of plant personnel;
- 3. Actual issuance or ingestion of potassium iodide (KI);
- 4. Personnel and/or area decontamination;
- 5. Collection and analysis of TLDs;
- 6. Reactor Containment Building entry;
- 7. Taking an actual reactor coolant sample using the Post l Accident Sampling System; ;
- 8. Operating or changing the alignment of actual plant equipment or systems; l l
- 9. Hanging drill-related tags on actual plant equipment i (applicable tags should be hung at the Simulator);
- 10. Pressurization of fire hoses (hoses should be deployed, l if required by drill conditions but not pressurized); :
- 11. Actual siren operation or release of emergency l information messages over the public alert and notification system; and gg
- 12. Cancellation of tours and training classes during site access control measures. l l
1
2-9 1993 Evaluated Exercise 2.5 PRECAUTIONS AND LIMITATIONS This section provides guidance on the conduct of this Exercise. Prior to initiation, a briefing vill be held to review the drill process with all Controllers and Evaluators. 2.5.1 Should an actual emergency situation arise at any time during the conduct of this Exercise, all activities related to the drill may be suspended by the Lead Exercise Control-ler. It is the responsibility of any Controller who becomes avare of an actual emergency to suspend Exercise activities i in his/ her immediate area and to inform the Lead Exercise ' Controller of the situation. Upon notification of an actual emergency, the Lead Exercise Controller shall notify all Lead Facility Controllers. The Lead Exercise Controller shall make a determination at that point whether to con- , tinue, place a temporary hold on, or terminate the Exercise. 2.5.2 Should, at any time during the conduct of this Exercise, a Controller witness any participant undertake an action which vould, in the opinion of the Controller, place either an individual or a component in an unsafe condition, the Controller is responsible for intervening and terminating the unsafe activity immediately. Upon termination of the activity, the Controller is responsible for contacting the Lead Exercise Controller and informing him of the situation. O The Lead Exercise Controller shall make a determination at i that point whether to continue, place a temporary hold on, 1 or terminate the Exercise. 2.5.3 Hanipulation of any plant operating systems, valves, breakers, or controls in response to this Exercise is to be , properly controlled by existing procedures and qualified personnel. There shall be no alteration of any plant operating equipment, systems, or circuits during the response to this Exercise without operators permission. Any equipment manipulation /vork vill be in accordance with proper station procedures and carried out by qualified personnel with operating crew authority and permission. I
- 2.5.4 All telephone communications, radio transmissions, and public address announcements related to the Exercise shall ,
begin and end with the statement, "This is a drill". Controllers are reminded not to " coach" Players, but shall ensure that Exercise communications are clearly identified ; as such, in order to avoid confusion with other activities. ; Repeated failure to identify that communications are part of an Exercise shall require intervention by a Controller. t i ! l r,- .a . - ... ,,- . - . , , ,, -- - . - - - - . , . - . . . - -- - . , - . . . , , , . . -- .- ,
2-10 1993 Evtluated Exercise 2.5.5 Care shall be taken to prevent any non-participating indivi-duals who may observe Exercise activities from believing that an actual emergency exists. Any Controller who is aware of an individual or group of individuals in the immediste vicinity who may have become alarmed or confused about the situation, should approach that individual or group and explain the nature of the Exercise and its intent. 2.5.6 Any motor vehicle response to this Exercise, whether it be ambulance, fire fighting equipment, police / security vehicles or field monitoring teams, shall observe all normal motor vehicle operating laws including posted speed limits, stop lights / signs, one way streets, etc. 2.5.7 Should any onsite security actions be required in response to this Exercise, participants are to cooperate as directed by the Security Force. Security representatives are to be
. prudent and tolerant in their actions.
2.5.8 While Exercise participants are to inject as much realism into the event as possible, the safety of the plant and personnel shall not be jeopardized. 2.6 EVALUATION AND CRITlQUE The Exercise vill be evaluated by individuals who have expertise in the activity in their assigned location. These Evaluators and Con-trollers will evaluate Exercise performance on the basis of require-ments contained in the Emergency Plan Implementing Procedures, and
" Cue Cards". Evaluators and Coatrollers shall prepare evaluation forms and provide recommendations to the Lead Exercise Controller.
After the Exercise is completed, the Lead Exercise Controller shall conduct a post-drill critique. Deficiencies in the Emergency Plan, Implementing Procedures, the emergency preparedness training program, facilities, equipment, and/or other areas shall be identified through the critique process. The deficiencies shall be documented by the Lead Exercise Controller and corrected by the individuals who have responsibility in the area of the identified deficiency. The schedule for the critiques is included in Section 5.0. O
i 2 1993 Evaluated Exercise . 2.7 SCENARlO DEVELOPMENT COMMITTEE Chairman, Dennis Gordon Emergency Preparedness-Assistant, George Reed Emergency Preparedness Plant Operations i s
- 1. Valt Molpus Operations (SRO) ,
- 2. Brian Young Simulator Staff (SRO) ~
- 3. Steve Laeng Simulator Staff (SRO) -
- 4. Larry Keller Operations Training :
- 5. Don Bondy Operations Training Radiological Control
- 1. Jay Shilling Emergency Preparedness
- 2. Regis Greenwood Radiological Controls Maintenance
- 1. Tim Tackett Electrical I
- 2. John-Harlock Mechanical >
- 3. Don Jones I&C Chemistry / PASS / Core Damage
() 1. Vince Capozziello Chemistry , Computer Support (DADS /SPDS/ MET)
- 1. Rick Bast Computer Group
- 2. Greg Hayes Computer Group -l Engineering
- 1. Bill Rowles Independent Safety ;
- 2. Jeff Blay Independent Safety Medical l l
1. Jeff Hildreth Industrial Safety
- 2. Chuck Devitz Emergency Preparedness ;
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2-12 1993 Evaluated Exercise j 1 l JPIC/ Corporate l
- 1. Jeff Basa Emergency Preparedness Security
- 1. Linda Hannan Security
- 2. Bob Zeiskoft Security Offsite Interfaces
- 1. Mitch Teal Emergency Preparedness
- 2. Jim Tackett Emergency Preparedness O
O
a 3-1 1993 Evaluated Exercise
3.0 REFERENCES
/ ABBREVIATIONS / DEFINITIONS L -
3.1 REFERENCES
3.1.1 DBNPS Emergency Plan - Toledo Edison Company, l (Rev. 16, 12/92) 3.1.2 DBNPS Emergency Plan Implementing Procedures 3.1.3 10 CFR 50.47, 50.54 and Appendix E 3.1.4 DBNPS Radiation Protection Manual 3.1.5 DBNPS, Unit 1, Technical Specifications 3.1.6 DBNPS Piping and Instrumentation Drawings. 3.1.7 DBNPS Updated Safety Analysis Report 3.1.8 DENPS Offsite Dose Calculation Manual 3.1.9 Toledo Edisen Corporate Emergency Response (CER) Plan 3.1.10 Public Information Emergency Response Procedures 3.2 ABBREVIATIONS () AFP ALARA Auxiliary Feed (Vater) Pump As Lov As Reasonably Achievable ARH Area Radiation Honitor ARTS Anticipatory Reactor Trip System ATHOS Atmosphere ATVS Anticipated Transient Vithout Scram AUX Auxiliary AVG Average BAAT Boric Acid Addition Tank BKVSH Back Vash BRKR Electrical Circuit Breaker i BVST Borated Vater Storage Tank { l CAM Continuous Air Honitor 1 CANS Computerized Automated Notification System CAS Central Alarm Station CCTV Closed Circuit Television CCV Component Cooling Vater System CERO Corporate Emergency Response Organization CPT Core Flood Tank CFR Code of Federal Regulations CNDS Condensate System COND Condenser CPH Counts Per Minute , CS Containment Spray System l CST Condensate Storage Tank l CT Circulating Vater and Cooling Tower System CTHT Reactor Containment Building CTRH Control Room 1
3-2 1993 Evaluated Exercise DADS Data Acquisition and Display System DBAD Davis-Besse Administrative Building DBNPS Davis-Besse Nuclear Power Station DEI Dose Equivalent Iodine DEMIN Demineralizer DHR Demsy Heat Removal DISCH Discharge DP Differential Pressure DVS Demineralize Vater System EAL Emergency Action Level ECC Emergency Control Center EDO Emergency Diesel Generator EEC Energy Education Center EFP Emergency Feed (Vater) Pump EMA Emergency Management Agency EOC Emergency Operations Center EOF Emergency Operations Facility l EPZ Emergency Planning Zone EVAL Evaluated FAT First Aid Team FEMA Federal Emergency Management Agency FT Feet FV Feed Vater l GPM Gallons Per Minute ! HDR Header BLCVT High Level Cooling Vater Tank HPI High Pressure Injection System HVAC Heating Ventilation and Air Conditioning System . HX Heat Exchanger I&C Instrument and Control Section IN Inch l INST Instrument JPIC Joint Public Information Center KI Potassium Iodide LP Lov Pressure ! LVL Level
- MISC Miscellaneous MSIV Main Steam Isolation Valve MTR Motor l MU Makeup System l NI Nuclear Instrumentation
[ NRC Nuclear Regulatory Commission l OTSG Once Through Steam Generator 005 Out of Service l OSC Operations Support Center l PA Public Address System l PASS Post Accident Sampling System l PC Protective Clothing PI Pressure Indication PHP Pump PORV Power Operated Relief Valve PPF Personnel Processing Facility PR Public Relations PSF Personnel Shop Facility i
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3-3 1993 Evaluated Exercise PSIA Pounds Per Square Inch Absolute ' PSIG Pounds Per Square Inch Gauge O' PT Periodic Test Pressurized Vater Reactor PVR PVST Primary Vater Storage Tank PZR Pressurizer RRA Radiologically Restricted Area RC Radiological Controls , RCP Reactor Coolant Pump j RCS Reactor Coolant System RE Fixed Radiation Instrument (Element) RLF Relief Valve ' RM Radiation Monitor RMT Radiation Monitoring Team RTL Radiological Testing Laboratory Rx Reactor SAS Secondary Alarm System SFP. Spent Fuel Pool SFAS Safety Features Actuation System , SFRCS Steam and Feed Vater Rupture Control System SJAE Steam Jet Air Ejector , SPDS Safety Parameter Display System .
'SPF Spent Fuel SRST Spent Resin Storage Tank '
ST Surveillance Test SV Service Vater System
/~' SYS System ,
( Tc Reactor Coolant System Cold Leg Temperature TC Thermocouple TDG Total Dissolved Gases
- Th Reactor Coolant System Hot Leg Temperature i
TPCV Turbine Plant Cooling Vater TRBL Trouble TSC Technical Support Center Volt Ohm Meter V0M r VG3. Vaste Gas Storage Tank , VK Veek VR Vide Range Instrument VTR Vater XFER Transfer i XMIT Transmit l t 6 P 9 e
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l 3 1993 Evaluated Exercise 3.3 DEFINITIONS
3.3.1 ALERT
The level of emergency classification which indicates that events are in progress or have accurred which involve an actual or potential substantial degradation of the level of safety of the plant. 3.3.2 ANTICIPATED TRANSIENT WITHOUT SCRAM (ATVS): -Failure of the reactor control rods to insert into the core u;,on a signal to do so from the Reactor Protection System or the failure of the Reactor Protection System to trip when limits have been exceeded. 3.3.3 ASSESSMENT ACTIONS: These actions taken during or after an accident to obtain and process information that is necessary to make decisions to implement specific emergency measures. 3.3.4 CONTROL ROOM (CTRM): The principle onsite location from which the reactor is controlled and from which emergency. control is initially exercised. The CTRM is located on the 623' elevation of the Auxiliary Building.
3.3.5 CONTROLLER
A member of the Exercise control group, assigned to one or more activities or functions for the purpose of keeping the action going according to a scenario, resolving scenario discrepancies, and supervising the actions of the players. 3.3.6 CORRECTIVE ACTIONS: Those emergency measures taken to improve or terminate an emergency situation.
3.3.7 DECONTAMINATION
The process by which the body or an object is relieved of radioactive substances (contamination). 3.3.8 DOSE ASSESSMENT: The process of estimating the amount of radiation a person vill potentially receive as a result of ! exposure to a radiological release. t
3.3.9 DRILL
A supervised event aimed at evaluating, developing, I and maintaining skills in a particular operation. 3.3.10 EMERGENCY ACTION LEVELS (EALs) - Radiological dose rates; specific contamination levels or airborne, waterborne, or surface-deposited concentrations of radioactivity; or specific plant conditions that may be used as thresholds for initiating specific emergency measures. 3.3.11 EMERGENCY CONTROL CENTER (ECC): The Toledo Edison emergency response facility from which overall direction and control are exercised for emergencies at DBNPS. The facility also provides a central point of contact for communications and i external (non-Toledo Edison) organizations, and is fully O activated for emergencies classified as an Alert or higher. 1
i l 3-5 1993 Evaluated Exercise 3.3.12 EMERGENCY OPERATIONS CENTER (EOC): An emergency response facility from which government officials exercise direction and control. The EOCs are located as follove: Ottava County: Basement of the Ottava County Courthouse Madison Ave. and Fourth St. Port Clinton, Ohio Lucas County: Subbasement of the Lucas County Correction Facility 1622 Spielbush Ave. Toledo, Ohio State of Ohio: Basement of the Robert B. Beightler Armory 2825 Vest Granville Rd. Vorthington, Ohio State of Michigan: Emergency Management Division Suite 300 3005 Vashington Square Lansing, Michigan 48913 3.3.13 EMERGENCY PLANNING ZONES (EPZs): The land areas encompassed within approximately 10 and 50 mile radii of the DBNPS, in which protective actions may be necessary to protect the public in the event of a nuclear plant accident. The 10 mile zone is referred to as the Plume Exposure EPZ; the 50 l) mile zone is termed the Ingestion Exposure EPZ (IPZ). 3.3.14 EMERGENCY RESPONSE FACILITY: Any of several onsite and offsite centers which are activated to coordinate emergency actions. Included in this category are the Control Room, Technical Support Center, Operations Support Center, Emergency Control Center, Joint Public Information Center, and State and local Emergency Operations Centers. 3.3.15 EVALUATOR: A member of the Exercise evaluation group, assigned to one or more activities or functions for the 4 purpose of evaluating and making recommendations for improvement. An evaluator may serve in a dual capacity as both a Controller and Evaluator. 1 3.3.16 EXCLUSION AREA: The area surrounding the DBNPS in which the l Toledo Edison Company has the authority to determine all ! activities including exclusion or removal of persons and j ' property from the area during accident conditions. i 3.3.17 EXERCISE: An event which tests the overall functions and l capabilities of organizations involved in responding to an ! emergency situation. An exercise vill usually simulate an i emergency that results in offsite radiological releases l vhich require response by offsite authorities. i
3-6 1993 Evaluated Exercise ~ 3.3.18 GENERAL EMERGENCY: The most severe level of emergency O classification which indicates that events are in progress or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity. Release of radioactive material can be reasonably expected to exceed PAG exposure levels offsite. 3.3.19 INGESTION PATHVAY: The exposure mode for which the zone of concern encompasses an area of approximately 50 mile radius around DBNPS. The principle exposure in this area would be from ingestion of contaminated water or foods; such as milk or fresh vegetables. The period of potential exposure could range in length from hours to months. 3.3.20 JOINT PUBLIC INFORMATION CENTER (JPIC): An emergency response facility, located in the Davis-Besse Administration Building, which is staffed by Company, local, State, NRC and FEMA officials. The JPIC provides a forum and point of contact for a coordinated release of news and information to the news media, general public, Company employees and the special interest groups. 3.3.21 OBSERVER: Any individual who is authorized to observe the Exercise, but is not authorized to interact with the players. 3.3.22 0FFSITE: All land and water areas outside the Ovner-Controlled Area fence surrounding the DBNPS. 3.3.23 ONSITE: All land and water areas within the Ovner-Controlled Area surrounding the DBNPS. 3.3.24 OPERATIONS SUPPORT CENTER (OSC): An onsite emergency response facility which provides a location where emergency response teams can be assembled and coordinated during an emergency. 3.3.25 OVNER-CONTROLLED AREA: The area around the DBNPS that'is owned and to which the access controlled, by the Toledo Edison Company. 3.3.26 PARTICIPANT: An individual who has some part in the Exercise, whether as an Evaluator, Controller, Player or Observer. 3.3.27 PLAYERS: All individuals who are assigned to perform functions of the emergency response organization, as described in the appropriate Emergency Plan and Emergency Plan Implementing Procedures. O l
3-7 1993 Evaluated Exercise 3.3.28 PLUME EXPOSURE PATHVAY: The exposure mode for which the zone of concern encompasses an area of approximately a 10 mile radius around DBNPS. The principle exposure sources in this area are: 1) whole body external exposure to gamma radiation from the plume and deposited material, and 2) inhalation exposure from the passing radioactive plume. The period of potential exposure could range from hours to days. 3.3.29 POPULATION AT RISK: Those persons for whom protective actions would be taken. 3.3.30 PROTECTED AREA: The area within the Site Boundary encompassed by physical barriers and to which access is controlled for security purposes. 3.3.31 PROTECTIVE ACTION: Those emergency measures taken after an accident or an uncontrolled release of radioactive materials has occurred, for the purpose of preventing or minimizing . radiological exposures to personnel that vould otherwise occur. 3.3.32 PROTECTIVE ACTION GUIDES (PAGs): Projected radiological doses to individuals in the general population which varrant protective action following a release of radioactive material. 3.3.33 RADI0 LOGICALLY RESTRICTED AREA (RRA): Any area accessed h which is limited by the licensee for the purpose of protecting individuals against undue risks from exposure to radiation or radioactive materials. 3.3.34 RADIOLOGICAL HONITORING TEAMS (RMTs): Two-person teams responsible for monitoring radiation levels in the environment and collecting soil, air, vegetation, snow, and water samples for laboratory analysis, i 3.3.35 SITE AREA EMERGENCY: The level of emergency classification l which indicates that events are in progress or have occurred l vhich involve actual or likely major failures of plant , functions needed for protection of the public. Any releases I of radioactive material are not expected to exceed l Protection Action Guide (PAG) exposure levels, except near j the Site Boundary. l l 3.3.36 TECHNICAL SUPPORT CENTER (TSC): An onsite emergency ; response facility for use by technical and management ; personnel in support of the command and control functions ; executed in the Control Room. 3.3.37 UNUSUAL EVENT: The lowest level of emergency classification, which indicates that events are in progress or have occurred which indicate a potential degradation of ' the level of safety of the plant.
4-1 1993 Evaluated Exercise 4.0 CONTROLLER AND EVALUATOR INSTRUCTIONS Each controller and Evaluator should be familiar with the following:
- 1. The objectives of the Exercise.
- 2. The assumptions and precautions being taken. ,
- 3. The Exercise scenario, including the initiating events and the ,
expected course of action to be taken.
- 4. The various locations that vill be involved and the specific items'to '
be observed at those locations.
- 5. The evaluation checklists provided herein.
4.1 CONTROLLER INSTRUCTIONS 4.1.1 Controllers shall position themselves at their assigned locations-a minimum of 30 minutes prior to the activation of the facility for which they have responsibility. (See Table 4.2-1) 4.1.2 Controller communications shall be tested prior to drill commencement. All vatches and clocks shall be synchronized with the ECC digital clock as'part of the communications ( testing. 4.1.3 All controllers shall comply with instructions from the Lead Exercise Controller. 4.1.4 No cue cards shall be delivered out of sequence or other than as written unless specifically authorized by the Lead Exercise Controller. 4.1.5 Cue cards controlling the progress of the scenario are noted with a number. Contingency cue cards are noted with a num-- ber followed by the letter "X" (e.g., 10X).- Contingency _ cue cards are only delivered if certain conditions indicated on use card are met. 4.1.6 Data sheets shall be distributed only in the Control Room, unless otherwise directed by the Lead Exercise Controller. 4.1.7 Controllers vill not provide information to the Players regarding scenario progression or resolution of problems encountered in the course of the simulated _ emergency. ' Participants are expected to obtain information through their own organizations and exercise their own -judgement in determining response actions and resolving problems. 4.1.8 Some Players may insist that parts of the scenario are unrealistic. The Lead Facility Controllers have the sole authority to clarify any questions regarding scenario content. t i i
4-2 1993 Evaluated Exercise j 4.2 EVALUATOR INSTRUCTIONS Each Evaluator shall take detailed notes regarding the progress of the l Exercise and the response of the Exercise participants at their assigned locations. Each Evaluator should carefully note the arrival and departure times of participants, the times when major activities or milestones occur, and problem areas encountered. The standards below should be used by the Controller / Evaluator to evaluate assigned areas pertaining to the emergency response. A dual purpose vill be served by this rating system. First, the capability of each facility or response area vill be evaluated, and second, the system vill provide a vehicle for directing improvement. The rating scale is as follows: Satisfactory - Personnel and equipment performed as expected. Any errors noted vere not severe and could be correcteo without undue labor or expense. Unsatisfactory - Personnel or equipment performed belov expectations, or there vere significant deficiencies noted. The area's ability to carry out its functions was diminished. N/A - Not Applicable to the situation. N/0 - Not Observed. As appropriate, Evaluator comments should consider the demonstration of the following facility and team evaluation elements: 4.2.1 Facility
- 1. Accurate and timely determination of emergency action levels.
- 2. Timely activation and staffing for each emergency action level.
- 3. Familiarity of personnel with appropriate emergency procedures, duties and responsibilities.
- 4. Timely notification of Toledo Edison, local, state and federal personnel / agencies (information updates performed).
- 5. Adequacy of internal information systems (e.g., message handling, displays, status boards and maps).
- 6. Properly controlled documentation and accurate, timely record keeping.
- 7. Use of correct communications procedures and techniques.
l 4-3 1993 Evaluated Exercise l
- 8. Capability of facility managers to interface with per-- :
sonnel and coordinate facility activities.
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- 9. Consideration for personnel safety (e.g., exposure ,
control).
- 10. Adequacy of interface between emergency response facilities.
- 11. Adequacy of equipment and supplies. .
- 12. Timely initiation of onsite protective / corrective [
actions.
- 13. Development of offsite protective action recommenda-tions. F
- 14. Radiological surveys and assessment of plant damage and hazardous conditions performed. ,
- 15. Timely requests for emergency support services.
- 16. Coordinated, accurate and timely dissemination of information to the news media.
4.2.2 Emergency Teams () 1. Timely notification and activation.
- 2. Adequacy of staffing.
- 3. Familiarity with appropriate emergency procedures, duties and responsibilities.
Availability and utilization of proper equipment.
- 4. ,
- 5. Performance of contamination control / decontamination.
- 6. Proper interface with emergency support personnel. ;
- 7. Use of correct communications instructions and i techniques.
E Adequacy of briefing sessions per the dispatch.
- 9. Direction and control by team leaders.
- 10. Timely requests for additional assistance.
- 11. Coordination and interface between emergency response team members.
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4-4 1993 Evaluated Exercise i
- 12. Proper interface with plant supervisory personnel.
- 13. Availability of reference documents.
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- 14. Utilization of proper radiological control practices (e.g., access control, protective clothing, shielding, ,
stay time).
- 15. Assessment of radiological conditions.
- 16. Timely and proper damage assessment.
- 17. Properly maintained records.
Evaluators vill record their comments and prepare a written evaluation of the exercise. Evaluation forms vill be pro-vided to each evaluator with more specific evaluation criteria. 4.2.3 Personnel Assignments Table 4.2-1 lists the personnel assignments for the Controller organization. 4.2.4 Evaluation Packages The following evaluation packages vill be provided to the appropriate Controllers / Evaluators at the pre-drill briefing: Control Room Operations Support Center Repair Teams First Aid Team Technical Support Center Emergency Control Center Joint Public Information Center Dose Assessment Center Padiation Monitoring Teams Security Radiological Testing Laboratory O
J l I 4-5 1993 Evaluated Exercise () 4.2.5 Evaluation Process All Evaluators shall maintain an Exercise chronology. This chronology shall be of sufficient detail to enable subsequent completion of the appropriate evaluation form. It should contain a synopsis of significant Exercise events, actions taken (or not taken) by Players, questions noted, and positive as well as negative assessments made by the Evaluator. This chronological record may be used to corroborate critique items that are questioned by participants. Each Evaluator shall also complete an evaluation form for " the facility or function to which they are assigned. Each Lead Facility Controller shall de-brief the evaluators in their facility and compile an Exercise Evaluation Report Sheet for that facility. This report sheet shall reflect an overall assesscent of the performance of that facility, and of the five (5) specific categories. Significant weaknesses or deficiencies shall Se itemized to ensure adequate follow-up attention is devoter. to resolution of the problem. Significant positive items shall be included here as well. The formal post-Exercise critique shall be conducted by the /N Lead Exercise Controller, with each Lead Facility Controller (s,) providing an evaluation of their facility. 4.3 USE OF SIMULATOR The Plant Simulator vill be used to drive the scenario sequence of events. A full shift crev vill be located at the Simulator and can respond to the conditions presented in the scenario as they vould from the actual Control Room. The data displays in the Technical Support Center and Emergency Control Center vill be driven with Simulator ; parameters allowing emergency classifications and engineering assessments to be performed in "real time" vith changes taking place as the operators manipulate the Simulator controls. It vill not interfere with the actual Control Room SPDS or DADS terminals. The simulator was used to confirm the viability of the initial scenario sequence of events and to identify changes, such as additional " traps" or equipment failures, necessary to propagate the plant conditions to the emergency action levels desired. Is was also ! used to provide baseline data printouts for generating the plant data sheets and area radiation maps used in the Exercise Manuals. During the Exercise, it vill be unnecessary for Controllers to issue the plant data sheets (i.e., primary and secondary plant parameters such as pressures, temperatures, levels and flow rates, etc., and meteorological parameters such as vind speed, direction and stability class) since the simulator information (through an intermediate O computer system) vill drive the Technical Support Center and Emergency Control Center data displays - both the Safety Parameter Display System (SPDS) and the Data Acquisition and Display System (DADS) , terminals. !
4-6 1993 Evaluated Exercise The simulator vill be heavily relied upon to conduct the Exercise; however, should it malfunction or go off-line (e.g., a loss of power to the Training Center), the Lead Exercise Controller has several options to choose from. They include: Stopping the Exercise and conducting it the following day (provided repairs can be performed).
- Continuing the Exercise using stored data (generated during prior Simulator practice runs).
Continuing the Exercise using the data sheets in the Drill Manual. Ending the Exercise if most of the objectives have been demonstrated. 4.4 USE OF CONTROL CELL In every drill or Exercise situation, there vill be non-participating individuals, organizations and agencies. These entities, for an actual emergency, have agreed to provide support to the primary emergency response organizations of the utility, state and local governments; however, due to the time and costs involved, they can not always support a drill or Exercise. In order to address this situation, a " Control Cell" is used to represent non-participants. The primary Control Cell vill be located in the Davis-Besse Administration Building down the hall from the Emergency Control Center. It vill consist of a bank of telephones, a fax machine, several reference manuals, and a group of three to five individuals. The Control Cell vill primarily be used to receive calls generated by the drill participants, but it vill also initiate calls (e.g., to demonstrate rumor control capabilities or to represent concerned citizens and the news media, etc.) and to send / receive material via fax (e.g., engineering drawings / data or administrative information, etc.). Additional individuals located offsite may serve a Control Cell function for the state and local agencies and/or the Toledo Edison Corporate Organization. Control Cell guidelines for this Exercise are as follows: The Control Cell should not take calls for:
- Any D-B Emergency Facility (e.g., TSC, ECC, etc.)
- D-B Security or Facility Services
- Centerior Corporate Response
- Babcock & Wilcox (B&V)
- Ottava, Sandusky, and Lucas Counties
- State of Ohio
- Mid-County Emergency Medical Services (EMS)
- Fremont Memorial Hospital
~ - . . .. . . . -
f 4-7 1993 Evaluated Exercise The Control Cell can take calls fors (f
- Federal agencies (e.g., NRC, DOE, Congressional Offices, etc.)
- Local entities other than those listed above (e.g.,. congregate care centers, fire departments, EMS, hospitals, police departments, host facilities, etc.) ;
- Other utilities / plants (e.g., Detroit Edison / Fermi, Perry, Beaver Valley, etc.) ;
- Vendors other than B&W (e.g., Bechtel Engineering, Radiation Management Consultants (RMS), Copes-Vulcan, Ingersoll-Rand, etc.)
- Institute of Nuclear Power Operations (INPO)
- Colleges /Univercities (e.g., Ohio State, University of Toledo, etc.)
- Nevs agencies
- National Veather Service (at Toledo Express Airport, see ;
Section 9.1)
- State of Michigan 9
O i 1 I i O u
O 4-8. 1993 Evaluated Exercise EXERCISE CONTROLLER ASSIGNMENTS O- TABLE 4.2-1 SIMULATOR CONTROL ROOM Ext. H.S.
- J. E. Blay Control Room Management 7810 1020 D. J. Gordon Lead Exercise Controller 8361 3360 L. G. Keller Control Room Operator 7111 5178 B. D. Young Simulator I.F. Coordinator 8497 5172 S. L. Laeng Simulator I.F. Operator 7630 5172 L
OSC ,
- A. P. Vise OSC Management 7564 1036 J. M. Hale OSC RP Coordinator 7263 1028-R. Schmidt OSC Management 7731 1026 J. S. Shilling OSC Management 7510 3360 B. J. Baumgardner OSC Response Team 7510 3360 D. P. Jones OSC Response Team 8538 1036 S. E. Vise OSC Response Team 7316. 2103 ;
V. N. Capozziello OSC Response Team 7262 1041 D. L. Bondy OSC Response Team C275 5178-S. D. Henry OSC Response Team 7681 1045 K. L. Dieterich OSC Response Team 7293 1002 T. G. Tackett OSC Response Team 8540 5186 ! O R. C. Chesko J. L. Scott OSC Response Team OSC Response Team 7580 8555 9085 1029 j L. H. Bovyer OSC Response Team 7876 1028 ; TSC , B. A. Humphrey Emergency RP Manager 7819 3387 ,
- T. E. Villiams TSC Hanagement 7491 3105 V. C. Rowles TSC Engineers 2363 1020 .
R. A. Bast TSC Computers 7407 3180 i ECC
- L. D. Hughes ECC Lead 7581 3290 ;
G. A. Gibbs Emergency Director 2356 3095 P. J. Smith CANS 7679 3360 : J. M. Priest Dose Assessment 8437 1029_ ; P = t
- Indicates Lead Facility Controller j
. ~_, - _ _ _ __ -.
4-9 1993 Evaluated Exercise EXERCISE CONTROLLER ASSIGNMENTS TABLE 4.2-1 (continued) , RTL Ext. M.S.
- P. J. Vadsworth RTL Coordinator 7889 1029 G. C. Stock RMT 7529 1045 J. D. Adams RMT 7742 3095 T. R. Mason RMT 8122 1029 A. C. Ashworth RMT 8283 3387 SECURITY
- L. M. Hannan Protected Area & Owner Controlled Area 7758 4000 R. L. Buchler Ovner Controlled Area 2462 5125 R. E. Zeisloft Security Supervisor 7557 4000 Assembly Area (?arking Lot)
CONTROL CELL i
- P. J. Smith Control Cell Lead 7679 3360 G. A. Bradley Simulated NRC Duty Officer 7530 3065 B. D. Kremer Emergency Preparedness Staff 8148 3360 D. F. Petersen Emergency Preparedness Staff 7887 3360 V. J. Kreinbihl Policy Management Loop Coordinator 8246 3040 ,
JPIC
- P. K. Harrison Company Spokesperson 161-86-5735 PYPTC M. R. White JPIC Rover 2409 3360 R. J. Jarosi Company Vorkroom 7719 1046 P. F. Timmerman Briefing Area 7314 5178 J. Kaufman Call Cell Coordinator Fermi OTHER B. V. Cope Protected Area Coordinator 8362 3360 G. G. Downing State of Ohio RMT 7225 1045 R. C. Leow State of Ohio RMT 7751 1045 G. J. Mitchel DBAB Rover 161-86-5321 PYPTC D. M. Perko Protected Area Rover 161-86-5049 PYPTC G. J. Reed DBAB Coordinator 8361 3360 L. L. Ring State of Ohio RMT 7196 1057 9
- Indicates Lead Facility Controller
I 5-1 1993 Evaluated Exercise 5.0 SCHEDULE OF EVENTS 5.1 TIMES AND PLACES Preparatory meetings held prior to the week of the Exercise vill be scheduled and coordinated by the Emergency Preparedness Staff. -The meetings scheduled for the week of the Exercise vill be held in accordance with Table 3.1-1. O 6 a O i
l 5-2 1993 Evaluated Exercise ; i () Schedule of Meetings Table 5.1-1
]
Date/ Time Vhere Vhat ; September 29, 1993 Energy Education Center Utility Controllers ! 12:30 - 15:00 DBNPS Administration Building Heeting , i t October 12, 1993 Energy Education Center Utility Controllers 9:00 - 11:00 DBNPS Administration Building Heeting October 12, 1993 DBAB Room 209-210 NRC Entrance 13:00 - 14:00 J October 12, 1993 Energy Education Center Utility Players 15:00 - 16:00 DBNPS Administration Building Briefing , l 5 October 13, 1993 All Facilities Exercise , All Day i October 14, 1993 Energy Education Center Utility Controllers 08:30 - 12:00 DBNPS Administration Building Debriefing ; October 15, 1993 Energy Education Center Utility Player /NRC_ ; 09:00 - 11:30 DBNPS Administration Building Critique l l l 1 i i l l
m . . - . . . _ . - _- _ ._. _ _. . .._ l 5-3 1993 Evaluated Exercise-i' 5.2 TRAVEL INFORMATION O' This section provides travel information to those individuals from Toledo
'i Edison,' other. utilities, local / state / federal government, and/or other !
organizations who.may participate in the Exercise. Permission to observe the Exercise must be obtained from: l i Mr. Brad DeMaison Manager - Emergency Preparedness > Toledo Edison Company, Stop 3360 300 Madison Avenue ; Toledo, OH 43652 (419) 321-7148 Once permission is obtained to attend the Exercise, accommodations can be. ; made as follows:
- 1. Air:
Detroit Metro Airport (70 miles from Davis-Besse) Detroit, MI Toledo Express Airport (50 miles from Davis-Besse) Toledo, OH Cleveland Hopkins Airport (85 miles from Davis-Besse) O Cleveland, OH t
- 2. Automobile: '
4 The Davis-Besse Station is located approximately 25 miles east of i Toledo, 10 miles northwest of Port Clinton, and 75 miles vest of Cleveland along State Route 2. -
- 3. Accommodations:
Phil's Inn (419) 734-4446 Best Vestern (800) 231-4871 l 1704 Perry St. Port Clinton, OH l Port Clinton, OH Fremont, OH j Comfort Inn (419) 732-2929 Comfort Inn (419) 691-8911-1723 East Perry 2930 Navarre Avenue (SR 2)- , Port Clinton, OH Oregon, OH Holiday Inn (s) (800) 465.4329 .: Island House (419) 734-2166 ! 102 Madison Street Toledo, OH Port Clinton, OH Fremont, OH Sandusky, OH Maumee. Bay Resort & Conference Center 1750 Park Road #2 O Oregon, O!! 43618-9700 (419) 836-1466 1
6-1 1993 Evaluated Exercise 6.0 EXERCISE SCENARIO (( ) This section provides a description of the Evaluated Exercise event , sequence and provides figures depicting key plant conditions. It is broken down into the following areas: 6.1 NARRATIVE
SUMMARY
This section provides a general overview of the Exercise event sequence for a quick understanding of the extent of play. 6.2 INITIAL CONDITIONS This section provides Players with basic information regarding plant external conditions that exist at the start of the Exercise. 6.3 ONSITE SEQUENCE OF EVENTS This section provides a detailed chronology of events for controller - guidance during conduct of the Exercise. Operational data and event timing for this scenario was developed in conjunction with practice runs of the Plant Simulator. Selected failures were injected into normal plant operations as depicted on the Simulator and i Operator response was permitted to take place on a "real time" basis. No O artificial time compressions vere injected into the time sequence. During the day this Exercise is conducted, plant equipment status vill be based on Control Room Operator response that day, which may be different than that which occurred during the practice runs. Controllers at the Simulator vill be trying to keep the sequence of events on track, however, ; they vill try to do this without the use of verbal overrides. Instead, should the Control Room Operators take a course of action that may significantly alter the outcome of the sequence of events, the Instructor , Facility (IF) Operator vill inject additional faults or malfunctions that . can thwart the Operator actions in a manner that is consistent with "real life" equipment failures or problems. , Because of the extensive freeplay being allotted to Control Room Operators, the IF Operator is authorized to take immediate action as deemed - appropriate to keep the sequence of events on track. If time permits, the injecting of additional equipment failures should be cleared with the Lead . Exercise Controller first. , Some Control Room Operator actions vill be permitted, even though they are not listed in Section 6.3, if the consequence of these actions do not significantly affect the overall outcome of the scenario. l O I
i 6-2 1993 Evaluated Exercise l 6.1 NARRATIVE
SUMMARY
Initial conditions are established with the plant running at 100% l power, all systems in automatic. A severe thunderstorm vatch is in effect for the area. The initiating event (refer to Figure 6.1-1) is caused by a lightning strike on one of the 345 KV lines. This creates a transient in the transmission lines and the main generator output. breakers in the switchyard open. The resulting turbine generator trip results in severe main turbine stresses, turbine damage, and turbine casing penetration. This meets the criteria for an ALERT. Additional damage in the turbine building includes a punctured discharge line from the condensate storage tanks, significant condenser casing damage with a loss of vacuum, and circulating vater system tube leakage. The voltage surge causes a Reactor Coolant Pump to vibrate, damaging it's impeller. The reactor trips on a high signal from the Anticipatory : Reactor Trip System (ARTS) based on the turbine trip. A maintenance worker is injured when a chain hoist breaks. The worker is contaminated and requires transport to an offsite medical facility for treatment. Fuel rod damage is caused by metal fragments from the Reactor Coolant Pump impeller being forced through coolant channels in the core. Gap activity is released into the coolant. In addition, the turbine and , O condenser damage creates a flooding condition in the basement of the Turbine Building causing a loss of various electrical components. After a period of time, the lov vater level in the condensate storage tanks vill cause the auxiliary.feedvater pump suction to be switched - to service water. This source vill eventually be lost causing a loss of all feedvater. A SITE AREA EMERGENCY vill be declared, and decay heat vill be removed through feed and bleed cooling supplying water to the reactor using the high pressure injection pumps, and removing it through the pilot operated relief valve to the containment. Containment pressure and radiation levels vill increase through this cooling method, and at some point, the containment vill be breached resulting in a release of radioactive material to the environment. A GENERAL EMERGENCY vill be declared. Dose assessment activities vill occur with field monitoring teams demonstrating their ability to locate and track the plume. Protective action recommendations vill be made, and offsite authorities vill follow up vith protective actions. The Joint Public Information Center vill demonstrate their ability to prepare news releases for the media, and mock news briefings vill be held. Eventually, the release vill be terminated and decay heat removal cooling vill be restored. Initial reentry and recovery discussions O vill be performed, and the Exercise vill be terminated.
- ~ . .
6-3 1993 Evalustad Exarcisa 1993 EVALUATED EXERCISE TIMELINE FIGURE 6.1-1 (08:00 AM) 0800 0900 2000 1100 2200 1300 1400 1500 1600 1700 I I I I I I I I I I Initial conditions established at simulator E Y a - A lightning strike on 345 EV transmission line causes reactor trip and turbine damage (A) E o - hetal f ragments released into primary coolant f rom vibrating 2-1 Reactor Coolant Pump V E e - A contaminated injury occurs requiring offaite support a T e - 364 gap activity released into primary coolant from RCP fragmente damaging fuel rode a a - Loss of water resources causes a '..otal lose of Feedwater (sAE)
* - cTNT penetration failure, offeito plume (CE) e - Release terr.inated o - Exercise anda E Main Generator Output Breakers trip on overcurrent (ACB 34560 & 34541) due to lightning striks 0 :
- U 1 low Pressure Turbine rotor breaks up, penetrating the turbina casing and condenser hotwell P. : >
0 circulating water rushes into condensee due to gross tube f ailures caused by turbir.e debrie U >
#2 kakeup Pump fails due to shaft seisure E
Lose of electrical componente due to flooding in Turbine Bldg. basement fram tw & the CST D > l U R Containment Penetration No. 59 Breach occurs A l : T I il Auxiliary Feed Pump governor fails and damages pump o > l N s 02 Auxiliary Feed Pump tripe due to instrument failure E M No UE will occur E R. A i I ( l C (0840) (1100) L SAE A ! ! 8 (1310) (1430) S. CE I I I i Legends e Indicates key event a Indleates key event that could be involved in emergency classification e Event is terminated at this time
+ Indicates event can be terminated by Pisyere et any time
> Repaire can not be empleted during the course of the Exercise O
0 64 1993 Evaluated Exercise () 6.2 INITIAL CONDITIONS 6.2.1 Close of Business, October 12, 1993 The plant is operating in Hode 1 at 100% power with all i systems in automatic. Heavy showers and thunderstorms are passing through the area. For the past 195 days, the plant has been operating at or , above 90% power. The core is at middle of life at 186 EFPD. NOTE: An " Exercise Only" Davis-Besse Daily Status sheet vill be provided to the Players through normal ' distribution channels,. attached to the back of the actual Daily Status sheet. 6.2.2 Start of Exercise, October 13, 1993 The plant is still operating in automatic at 100% power. Plant chemistry is in specification and stable. (Refer to Figure 6.2-1). All systems are operating normally with the following > exceptions:
- 1. The Technical Support Center CCTV is out of service due
- O to faulty underground cabling.
b
- 2. Additional equipment maintenance events are provided ,
on the " Exercise Only" Davis-Besse Daily Status sheet. NOTE: Refer to Section 10.0 of this manual for additional equipment servicing / repair information. , The temperature is 60*F vith vinds from the North blowing at 8% HPH. It is a dark, cloudy morning with a severe . ! thunderstorm watch in effect. (Refer to Section 9.1 of this manual for additional meteorological information.) , Simulator setup instructions for the IF Operator:
- 1. IC-27: 100% PVR
- 2. Ensure SETCLK in Ship Dir is used to allow simulated time to be real time synchronized with the ECC clock.
- 3. PC File = EP1993; See failures on the HALF list in the-IC.
i
- 4. Ensure program to drive the following indications is setup:
O " Heteorological parameters
- RE trending data
6-3 1993 Evaluated Exercise INITIAL PLANT CHEMISTRY DATA FIGURE 6.2-1 CRI-027-21 CHEMISTRY ANALYSES STATUS m PRIMARY SECONDARY (TEEDWATER) Times o7/ C Dates ,/g[,JpJ Times C7JC Dates /C h value Limits value Limits ppb 55 Ca C, #/8 ppb 5100 02 46 ppb 220 N 2Ee 35" ppb S150 c1' /,) ppb 520 sion 45" ppb - s150 r ),J Na g, 6) ppb
- Li* g, C[ ppm 53 pH 6,6 9 25'c sl0 re 4 /b ppb 25-50 E3 g,p, C7 cc/kg 55 c1* /, O ppb N2 My cc/kg 29.3 pH Q, M e 25'c S200 TDG y2,9 cc/kg Measured E*cond. g,2 6/ ps/cm !
51.0 DEI EC/E.3 pel/gm 50.2 *znorsanic H+ cond. o,g7g ps/cm f ppb ! 100/E specific Act. g,Q// $ pci/mi condensate Dissolved 02 3,O
- Per DB-CH-06900, Attachment 1 *Inoganic E* cond. is a calculated value COVER GA5 i
Tank %E2 %Da %N3 Time Date MGST Cg40 3a/O 9h,$Q e2030 /0/6)V3 cwRT 1 g,35 2,tfo $7, ,gg omogg jffj);gsy c"n* 3 0<70 R. IO 97,/o 6?/30 lb/fo/?3 BORON Comoentsa vessel PPM Time Date ncs 6So 0700 Jo//3/7.3 I/ PER [gg ( sws' Ro /7 i PHST 5^^T 1 / / c196 nAAT 2 faofg j CWRT 1 /g36 I cwRT 2 380 crt i ag97 crr 3 32203 t j srP p3CC p jL) l Refuel canal q5 ,a _n Y u-s.,1e..d b, w .iD.e. 07451 so4sb3 , sm ,
~. --
6-6 1993 Evaluated Exercise
. 6.3 SE0llENCE OF EVENTS Time Event CC#
T Time 00/00 0800 The Shift Supervisor is briefed in the Control 1 , Room and the Drill Authorization Form is ' approved. NOTE: The 1993 Evaluated Exercise vill : utilize the Control Room Simulator to , conduct Operator response instead of the actual Control Room. An off-shift Operations crev vill be pre-staged and briefed at the-Simulator with the exception of the , Equipment Operators who will , pre-stage in the plant. Pre-designated Maintenance, Chemistry and 1 Padiation Protection personnel vill ! assemble at the OSC once it is activated. Since Players vill not be able to use their normal conmunica-tions channels to contact each other, an " Exercise Phone List" vill be provided. , The pre-designated Continuous Service Chemistry 2 and Radiation Protection personnel receive the . initial conditions and stand by at their respective offices to begin Exercise response when contacted via phone. The pre-designated Maintenance personnel can be reached via , Gai-tronics. 00/10 0810 The Lead Exercise Controller at the Control Room 3 l Simulator vill direct the'following actions: ;
- 1. A Gai-tronics announcement for the start
- of the Exercise.
- 2. Activation of the ERO pager drill code, which advises all ERO pager carriers that I the pages which follow are related to the Drill. l 00/30 0830 A lightning strike in the switchyard on the- 4 l 345 KV transmission system resalts in the- 5 trip of the generator output breakers 6 ;
(ACB 34560_& 61). The rapid loss of load from _ the main turbine causes a high vibration trip of l the turbine. These sudden stress-related~ changes j catne several blaces to separate from the turbine 1 ' rotor and penetrate the casing. Additional damage _ f 4 inflicted by the blades-includes the condensate ; storage tanks, the Lov Pressure (LP) Condenser tubes, and the LP Condenser shell.
+
_ - - , , + , - . , r _ ---
=
6-7 1993 Evaluated Exercise CCN T: Time Time Event NOTE: Refer to Section 10.0 of this manual for additional description of equipment transients or failures. 00/33 0833 In response to the Reactor trip, the Control Room Operators attempt to start #2 Makeup Pump, however, it fails to start due to shaft seizure. 00/35 0835 The transient on the electrical grid induces a vibration on the 2-1 Reactor Coolant Pump (RCP), which ultimately results in impeller damage. RCP vibration and loose parts monitor alarms occur. An ALERT declaration is made per EAL 7.F.2 due 7 00/40 0840 to turbine failure causing casing penetration. As per the Alert procedure, HS-EP-01700: Station Alarm vill be sounded via a request from the Control Room (Simulator) to the real Control Room. The ALERT Gai-tronics announcement vill be made at the simulator.
- The Computerized Automated Notification System (CANS) vill be activated to notify and call out the on call Emergency Response Organization (ERO), notify the Toledo Edison Company Telephone Operator, and page the Davis-Besse NRC Resident Inspectors.
Ottava and Lucas Counties and the State of Ohio are notified of the Alert. NOTE: In order to minimize the activities demanded of the actual on-shift Control Room staff, the White Phone vill be simulated as out of service requiring the Simulator staff to use the alternate means of State and local notification via the Toledo < Edison Company Telephone Operator. The NRC vill be notified that the Drill has begun via the Emergency Notification System (ENS) Red Phone. Follov-up calls to NRC vill be made to the Control Cell. l
6-8 1993 Evaluated Exercise i CC# T: Time Time Event NOTE: These activities vill be performed with assistance from the on-shift operations personnel from the real Control Room. Reports from Turbine Building indicate severe 8X 00/42 0842 flooding in the East and Vest Condenser Pits. .i 7 00/45+ 08454 The Control Room (Simulator) staff vill be directing the on-shift crew to perform various plant shutdown functions (e.g., startup of the Auxiliary Boiler). > NOTE: Because of the Exercise artificiali-ties created by using the Simulator rather than the actual Control Room, the " Exercise Phone List" vill be ased to make these notifications. 00/50 0850 ERO staff begin to arrive in the Emergency Response Facilities (ERFs). The medical " victim", Controllers and Equipment Operstor are pre-staged at the accident scene () 00/50+ 0850+ for the Medical Drill. Non-essential personnel within the Protected 9 Area assemble in the designated Assembly Areas within the Personnel Shop Facilities (PSF) Building. Access to the Ovner Controlled Area, DBAB ERFs and the Protected Area are restricted as per Security procedure HS-EP-02510. NOTE: Access to the Ovner Controlled Area and Protected Area vill be restored by the Controllers after approxi-mately 30 minutes. Canceling of tours and training classes vill be simulated. Flooding in the Turbine Building basement causes a loss of most electrical equipment on that level, including the Motor Driven Fced Pump. Contingency input in the event an Alert has 10X 00/55 0855 not been declared by this time. 00/57 0857 Several fuel rods, aggravated by metal fragments from the 2-1 RCP impeller, begin releasing gap activity into the primary coolant. Activity equivalent to approximately 35% gap is eventually released into the coolant.
6-9 1993 Evaluated Exercise Time Event CC# T: Time 01/00 0900 For the Exercise, security access restrictions 11 are relaxed. Assembled personnel are returned 12 to work. 01/05 0905 Two maintenance individuals who did not hear the 13 announcement for site assembly are working in 14 the #3 Hechanical Penetration Room. A chain hoist is being used to lift some heavy equip-ment. Suddenly the hoist gives way, knocking one individual down into an area of the room with radioactive contamination. Part of the hoisting equipment crashes into Containment Penetration No. 59, breaking open the piping test connection. The uninjured maintenance worker notifies a roving Equipment Operator who contacts the Control Room (Simulator). The First Aid Team is called out. 01/15 0915 The letdown monitor (failed fuel monitor) alarms on high radiation. Upon inspection by the First Aid Team, the injured victim is found to have several abrasions, a broken vrist and tvisted knee. Contamination is present. The victim requests to be transported to the Fremont Memorial Hospital. The First Aid Team informs the Control Room (Simulator). Security monitors the First Aid Team communications and subsequently CAS/SAS calls for offsite assistance via the Ottava County Sheriff's Dispatcher. NOTE: Normally 911 vould be used, however, 15 a non-emergency telephone number vill be used for this Exercise. Priority at the Sheriff's Office vill be directed to real emergencies that may be reported on the 911 system. The Sheriff's Dispatcher vill tone out (page) Mid-County Emergency Medical Services and advise them that the individual is contaminated. 01/25 0925 The CAS/SAS Operator vill call Fremont Memorial 16 Hospital and advise them that a contaminated injured individual vill be transported from Davis-Besse. NOTE: The procedure stipulates Hagruder Hospital, however, for the purposes of this Exercise, if Magruder vill not be utilized. Refer to Section 8.7 of this manual for additional medical drill information.
h i 6-10 1993 Evaluated Exercise i T: Time Time Event CC# l 01/30 0930 Due to the indications of high coolant activity, Chemistry personnel vill be requested to take a Reactor Coolant System sample. f 01/30+ 0930+ An Auxiliary Feed Pump lov suction pressure alarm occurs due to the decreasing Condensate Storage Tank levels. Operators may transfer suction to the Service Water supply header. 01/40 0940 Chemistry personnel drav a RCS sample. ; NOTE: An actual RCS sample vill not be drawn, since it is not part of this year's extent of play. Refer to Section 8.6 of this manual for ' additional PASS information. 02/10 1010 Conditions created by the ruptured condensate piping causes the #1 Auxiliary Feed Pump governor to fail, making the pump overspeed : and eventually seize up. i 02/45 1045 condensate Storage Tanks are nearly empty and aside from the #2 Auxiliary Feed Pump (AFP) lined up.vith service water or the Fire Protection water O system, no other feedvater source is available to the Steam Generators. 02/50 1050 Suetian Pressure switch to #2 AFP fails, closing the steam supply valve, and stopping the pump. Personnel are dispatched to investigate, but the problem is not readily apparent. An attempt is made to cross-connect with the Fire Protection System, however, the cross-connect valve FP-27 von't open. 03/00 1100 A SITE AREA EKERGENCY declaration is made per 17 EAL 3.d.3 due to a loss of all feedvater when ; the condensate storage tanks go dry and service water is unavailable for auxiliary feedvater. As per the Site Area Emergency procedure, HS-EP-01800: Station Alarm vill be sounded and Site
- Area Emergency announcement made via a request from the ECC to the real Control ,
Room.
- the ERO, Toledo Edison Company Telephone Operator, and the Davis-Besse NRC Resident Inspectors are notified via phone contact or announcements in the ERFs. The CANS vill be utilized in this activity.
6-11 1993 Evaluated Exercise j CC# T: Time Time Event
' Ottava and Lucas Counties and the State of Ohio are notified of the Site Area l l
Emergency.
- The NRC Incident Response Center notifica-tions (i.e., Red Phone) are made to the Control Cell.
NOTE: Ovner Controlled Area assembly vill 18 19 be simulated. 03/00 1100+ Plant Operators Line-up systems for a Make-up/ High Pressure Injection Reactor Cooling mode. This provides water from the Borated Vater Storage Tank through the Reactor Coolant System out the Pressurizer Power Operated Relief Valve for the purpose of removing decay heat from the reactor. Due to the earlier fuel rod damage, ' radioactivity levels in the Containment Building atmosphere begin increasing dramatically. Contingency input in the event a Site Area 20X 03/10 1110 Emergency has not been declared by this time. lf 05/00 1300 Because of increasing Containment pressure and the damaged test connection, penetration No. 59 releases radioactivity into the No. 3 Mechanical Room allowing the emergency ventilation system to draw the activity out through the Station Vent (refer to Figure 6.3-1). NOTE: Refer to Section 8.1 of this manual for data indicating the changes in in-plant radiation levels caused by this event. This results in an offsite release to the environment, which produces increased dose assessment activities and efforts to track the plume with surveys taken by Radiation Monitoring Teams. NOTE: Refer to Section 9.4 of this manual for additional information on field moni-toring. 05/00+ 1300+ The dose assessment and/or field survey results vill be utilized to determine protective action recommendations for the public. These recommendations as a minimum should include sheltering in a two mile radius and out to five miles down vind.
6-12 1993 Evaluated Exercise-T: Time Time Event CC# 05/10 1310 A GENERAL EMERGENCY declaration is made per 21 EAL 6.D.3 due to projected radiation levels at the site boundary of greater than 1 Rem / hour Vhole Body or EAL 1.E.1 due to loss of 2 of 3 fission product barriers with a potential loss of the third. As per the General Emergency procedure, ' HS-EP-01900: Station Alarm vill be sounded and General Emergency announcement made via a request from the ECC to the real Control Room.
- The ERO, Toledo Edison Company Telephone Operator, and the Davis-Besse NRC Resident Inspectors are notified via phone contact or announcements in the ERFs. The CANS vill be utilized in this activity.
Ottava and Lucas Counties and the State of Ohio are notified of the General Emer-gency. The NRC Incident Response Center notifica-O tions (i.e., Red Phone) are made to the Control Cell. News releases are prepared and press briefings' , are held at the alternate Joint Public Information Cens.>r. The public alert and notification system activation is simulated. 05/15 1315 Operators may shift to Decay Heat Removal'at this time. Data in this package supports this action, however, procedural guidance is limited and engineering judgement may be used to determine an alternate course of action. 05/25 1325 Contingency input in the event a General 22X Emergency has not been declared by this time. 05/45 1345 Additional dose assessment is performed (refer to Table 6.3-1). Offsite protective action recommendations are upgraded because of increased offsite radiation levels. The revised protective actions are forwarded to - State and local officials. 06/02 1402 A Repair Team succeeds in sealing the b:oten test O connection on penetration No. 59 storping the release of radioactive materials from CTMT. The Station Vent monitor begins to lover in value as i the remaining radioactive material in the Auxiliary Building is purged out.
6-13 1993 Evaluated Exercise Time Event CC# T: Time The Station Vent monitor reading drops off - the O '06/15 ~1415 release has ended. Declassification d2scussions occur. 23X 06/30 1430 The Evaluated Exercise is terminated. 24 06/45 1445 25 Termination announcement is made over the Gai-tronics and in all ERFs.
- The ERO pager all clear code is activated.
This advises all ERO pager carriers that the Exercise is over.
- The NRC vill be notified via the red phone that the Davis-Besse drill activities have ended.
A short break vill be taken. Following the break critiques vill be held in each of the participating facilities. 07/45 1545 Recovery meeting occurs in DBAB Rooms 209/210 26 O 1
6-14 1993 Evaluated-Exercise PROTECTIVE ACTION RECOMMENDATIONS TABLE 6.3 1 Pagel/2 ..- PROTECTIVE ACTION GUIDELINE REPORT 10/13/93 13:45 ; STATION VENT RELEASE WHOLE BODY Noble Gas Activity RE 4598, Channel 1, uC1/cc 27.1 t Noble Gas release rate, C1/sec : 1180.0 Unit Vent Flow Rate F885 [or F883], kcfm : 92.4 Time Since Reactor Shutdown in Hours : 5.20 Downwind Distance 1 MILE 2 MILES 5 MILES 10 MILES 20 MILES WHOLE BODY UOSE RATE Rem /hr a 5.93 1.63 0.310 0.0904 0.0254 WEATHER REPORT s, / Lower Differential Temperature : -1.80 F Stability Class : C Slightly Unstable Wind Speed 1.90 mph Wind Speed 0.849 m/sec ' The Wind is Blowing from : 80 degrees The Wind is Blowing to 260 degrees Sector : N i
6-15 1993 Evaluated Enercise PROTECTIVE ACTION RECOMMENDATIONS TABLE 6.3-1 (Cont'd) Page2/2 10/13/93 13:45 PROTECTIVE ACTION GUIDELINE REPORT VALUE VARIABLE DESCRIPTION --------------- (HrsiMins) 01:12 Release Duration 00:45 Elapsed Time From Release (Hrs: Mins) (Hrs Mins) 00:00 Estimated Time To Release 13:00 Release Start Time (Hrs: Mins) Release Stop Time (Hrs: Mins) 14:17 Oct - April Time of Year Midday Time of Day N.A. Day of Week Weather Good Weather Housing Structural Shielding Factor 0.900 5 Miles Evacuation Distance is 03:05 Evacuation Time (Hrs Mins)
-------------- ALL TIME IN HRS: MINS 0-2 Miles 2-5 Miles 5-10 Miles 00:32 01:03 02:38 l Plume Travel Time -00:09 01:26 i Time To Exposure -00:40 03:45 03:14 01:39 Exposure Time 01:12 Evacuation Exposure Period 01:12 01:12
---- ------------ ALL DOSE IN REMS 0-2 Miles 2-5 Miles 5-10 Miles I Projected Whole Body Dose 7.12 1.96 0.373 7.12 1.96 0.373 Evacuation Dose 1.77 0.335 i Shciter Dose 6.41 i
Recommmended Protective Action SUBAREA 0-2 Miles : SHELTER 1 EVACUATE 12 1 12 2-5 Miles : SHELTER AS A MINIMUM 2 10 5-10 Miles : NO ACTION 3 11 Report reviewed by / q N I O
i-i 6 1993 Evaluated'Exereise j DOVNGRADING FROM THE EMERGENCY-TABLE 6.3-2 Players should be cognizant of the following conditions in order to consider downgrading from the emergency and commencing reentry / recovery discussions:-
- 1. Plant vent radiation monitors decrease.to negligible levels.
- 2. A source of decay heat removal is available.
- 3. The primary system is cooled down and depressurized.
- 4. All required notifications have been made.
- 5. TSC and ECC agree that downgrading is appropriate.
- 6. State and County Officials concur.
O ' O - i
I 6-17 1993 Evaluatsd Exsrcisa OFTSITE RELEASE PATH . FIGURE 6.3-1
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A TNOSPHERIC REL EASE PA THVAYS @ **u'sn =n*
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u. P perus 4 some sui,i gu ,,,, $ ves to, i,en i
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- ,n.n : .rt.n. :..n.n.: 'r!.o : ..,,,,n
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- .n..n c.n..n ::.n..n :> nun um i nos m:n Y m's m!m n!n m.m mim um som en wm en um es,, [ g,,,,A .
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'wS=e A B C D k b. U D '"
A- tab needs
- Chemistry Offices 0
- Av.ul.li.a.rI.Svil.d,ing ne s.r C- f eel Handitng Area D- neehenisei reaetrat**a n ee.
Dessy Hest Coolet Roses (CC3 Peep Reems Containment Annulus Nats-up Psep Beses 2- RCP impeller fragmente damage fuel cladding ceasing 350 gap metivity to be released into the primary coolant. 2- Loes of feedwater requires decay heat to be removed by injecting cooler water into primary plant and venting it into the containment atmosphere thru the Pressuriser relief valve. 3- staintenance activities damage Containment Penetration glo. 59 allowing radioactivity to be released into #3 Mechanical Penetration Rooin. 4- The maergency ventilation system (rvs) transports the radioactivity out of the penetration roosas to the station Vent. j i s , 1 l 1
.. DAVIS-BESSElDAIL%STATUSM.,m..p,..A .wC. .
t Clme of Business October 12, 1993 ITACIIR CRERATlR IFXKE (GM) i Gross Output (KJ) 933 PCS identified 0.09 Mode 1 RCS thidentied 0.24 Pw er (%) 13 tiet Generation 24 hrs. (Ka) 21251 Cycle 9 EFID 1_86 IEAR-70-DUE HRIUM'fG HEASLIES
- 1. Ib Licensee Evmt reports. '
- 2. The plant has bem on line for 195 continuous days. p Ibb WU5ss W I H= 5
- 3. Ymr to Date Availability: 97.3%; Capacity Factor 97.9%
OEPLEEED EVEIES
- Instrunent air dryers 3 and 4 retumed to service follwirg prevmtative maintenance.
- Ebel harxiling area exhaust fan #2 preventative naintenance. ,
PUIND EVEFUS O - Seismic mmitoring systen troubleshooting.
- Complete Domestic Vater outage wrk ite:s.
- Complete repairs and retest of CDir Purge radiation mmitor PE 5052.
- #2 Statim air cwws r prevm tative maintenance.
IUIHUIAL PUNT HELDG
- ICAOR 93-0097; As built not in accordance with dravings.
- PCA019%0090; Material specifications not in accordance with ASME code.
PUNTBEFGWlG
- Plant chmistry in specificatim and stable.
- Condensate dissolved oxygm 3J ppb (Goal <4 ppb)
- Plant heat rate 10201 BnJ/kv-br, both MSR drain tanks to condenser. i
- Radiation Monitors:
Tech Spec 17 of 18 operable Ibn Tech Spec 33 of _54 functioral (PE 5052 high flow prob 1m) (RE 8433 rectifier) i l l l l DRILLUSE ONLY O
6-19 1993 Evaluated Dcercise 1HIMCAL SPECIFICAIIQi ACIIai SLGMNIS System Tec. Spec. Ihte/ Time Prevent PCAO Estinated Mditimal tkrber Action is Restart Vritten Completion Information Paluired Ihte 3.3.3.8 Complete Ib tb 8PID Special Report
- 1. Fire Detection 1-93-1 436-00 HE 410
- Dmotes Intentional Entry.
_ _ _ DRILLUSE ONLY Backlog Paintenance Work Orders: 635 Backlog Work Requests: _235 FDS 429 SECRITY e DRILL USE ONLY e
DAVIS-BESSE DAILY STATLIS. N O OM)0 October 13, 1993 . i REACitR THAIIR IEAKA2 (GM) ,
% 1 Gross Output (KJ) -933 RCS idmtified 0.09 ;
Power (%) y RCS Unidentiei 0.24 lbt Generation 24 hrs. (Ha) 21251 Cycle 9 EFID 187 YEta-10-DUE 1HFUWJG HEASUPIS
- 1. ?b Licmsee Event reports. l U UR1 5
- 2. The plant has been on lire for 196 cmtinuous days.
- 3. Year to [hte Availability: 97.3%; Capacity Factor 97.9%
OMTEDD EVi2HS
- Seismic monitorirg systen troubleshootirg.
- Cmtainment persmnel hatch local Imk rate test.
- Repairs and retest of CDC Purge radiation monitor RE 5052.
- #2 Station air compressor preventative naintenance.
r PU1ND EVINIS
- Canplete Ibmestic Vater outage work itens.
- Hoisture Separator Demin skid raintmance m inlet valve ID 5366.
- Omtaiment Im Spray Header pressure instrument PI 1559.
IUIHEIAL PUNT IHIRDG
- IOG 93-W)9; Part dimmsion discrepancy in ron installed equipnmt.
- IOG 93-0100; Timely resolution of USAR required feature not pursued.
PUNT PERFUWiG
- Plant chemistry in specifimtion ard stable.
- Cadmsate dissolved oxygm 4J ppb (Goal < 4 ppb)
- Plant heat rate 10201 HIU/kv-hr, both MSR drain tanks to cordmser.
- Radiation Hmitors:
Tech Spec 18 of 18 operable rim Tech Spec 53 or 54 functional (PE 8433 rectifier) o DRILLUSE ONLY a- --_- w w --- - w- w - _ - - _ yr -#--- - - y, +-v- g
6-21 1993 Evaluated D:ercise IIIINICfL SPEGICATICN NXIm STA1DMS System Tec. Spec. Date/ Tine Prevent PCAO Estinnted Additional
!bmber Action is Restart Vrittm Cmpletion Informtion Required [hte
- 1. Fire Detection 3.3.3.8 Complete Ib tb 8 RID Special Peport FIE 410 1-93-1 436-00
- Dmotes Intentional Entry.
___ LLUS Backlog Vork Requests: M Backlog Maintenance Vork Ordets: 635 FIPI WA101 SI M S VA101 Q]MPIIGAlmY ME/LSUPE FDS-429 SB[ilPIIT FDS-323 SEURITY FDS 400 SEUIGIY DRILLUSE ONLY e
7-1 1993 Evaluated Exercise-l
- 7.0 PLANT-CUE CARDS AND OPERATIONS DATA -
This section provides message and data necessary to describe the scenario - conditions to the Players at the plant. l 7.1 PLANT CUE CARDS , This section provides Player messages that setup-the initial conditions and assist in controlling the progress of the scenario at , the plant. > I 7.2 PLANT PARAMETERS
SUMMARY
j This section provides plant equipment parameter indications in a l tabular format for ease of reviev and for ease of locating a : particular instrument reading in a timely manner. i 7.3 PLANT PARAMETERS SHEETS This section provides individual Control Room equipment data sheets to be passed out to Players on a 15 minute basis should the Control Room Simulator become unavailable to conduct the Exercise. 7.4 CONTROL ROOM ALARM PANELS i This section provides individual Control Room annunciator alarm sheets' to be passed out to Players in the event the Control Room Simulator becomes unavailable to conduct the Exercise. , 4 1
)
O R
~ . -- -- .. .
1 4 7-2 1993 Evaluated Exercise ! I 7.1 PLANT CUE CARDS The Cue Cards that follov assist in controlling the progress of the scenario. Controllers should issue the Cue Cards at the times indicated unless directed otherwise by the Lead Drill Controller. Cards indicated with an "X" following their number are for contingency
~
purposes and should not be issued unless the Players appear to be headed in the wrong direction. O , l t O 1
7-3 1993 Evaluated Exercise j I DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD i SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. 1 TO: Control Room Simulator Staff TIME: 08:00 1 T: 00/00
- .********4***************************+****** I l
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
- w********************************************************
INFORMATION: It is a dark, cloudy morning with a severe thunderstrom vatch in effect. Temperature is 60'F vith vinds from the North blowing at 8% MPH. Refer to the Simulator control boards and the " Drill Only" Davis-Besse Daily Status Sheet for the initial operating conditions. Special Guidelines
- 1. All communications outside of the Simulator must include the phrase "This is a Drill".
- 2. Players at the Simulator, TSC, ECC and RTL are not required to vear arm bands.
- 3. All contacts to non-participating agencies, facilities or organizations you would normally make based on the events that occur in the scenario are to be made to the Control Cell using the Drill Phone List.
4 When the Station alarm is needed as part of Gai-tronics announcements, contact the Control Room Controller at extension 8500 to perform these actions. THIS IS A DRILL
.. .- . . . -- ..- . . ~ . -- , - - - . - . . . - . . 7-4 1993 Evaluated Exercise-DBNPS' EMERGENCY PREPAREDNESS. CUE CARD (Cont'd). CUE CARD NO. 1 T0: Lead Drill Controller TIME: 08:00 > T: 00/00 j ANTICIPATED RESPONSE: Players should review the Daily Status Sheet and the 100% power steady state ; operating conditions indicated on the Simulator control boards. ; INSTRUCTIONS:
- 1. Provide initial briefing to the Simulator personnel. Ensure they have a clear understanding of the initial conditions indicated on the Daily Status Sheet. l
- 2. Ensure Players have a copy of the Drill Phone List.
- 3. Get all participants at the simulator to sign the attendance sheet. ;
Contact the Controller at the real Control Room. . Verify that the Shift l O 4. Supervisor has been briefed and the Exercise Authorization Form has been ; approved.
- 5. Direct the Control Room Controller to initiate Cue Card No. 2 for the initial Plant Gai-tronics announcement.
Note: If the Gai-tronics module is working at the Simulator, then this could be performed by the Operations Crev at the Simulator under the direction ; of the Lead Controller. The Control Room Controller in this arrangement needs only to monitor the announcement for clarity and to notify the Lead Controller should it turn out to be inaudible. Should the Gai-tronics capability at the Simulator fail to work, the Control Room Controller must then resume responsibility for performing this l announcement from the real Control Room.
- 6. Ensure that activation of the ERO pager drill code occurs at approximately 08:10.
O THIS IS A DRILL
.- - - - __i.___ __z_._.
7-5 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exereire CUE CARD NO. 2 TO: Continuous Service Maint., Chem, & RP; TIME: 08:00 OSC Manager and Staff T: 00/00 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
- .***************************+***
INFORMATION: INITIAL CONDITIONS The plant is operating in Mode 1 at 100% power with all systems in automatic. Plant chemistry is in specification and stable. For the past 162 days, the plant has been operating at or above 90% power. The core is at middle of life at 158 EFPD. All systems are operating normally. h The ter..perature is 60" F vith vinds from the North blowing at 8% MPH. It is a dark, cloudy morning with a severe thunderstorm vatch in effect. Drill participants for today are:
- Shift Supervisor Shift Manager RP Supervisor Chem Supervisor Maintenance Supervisor
- +*******************+**********++++
THIS IS A DRILL
. . . , , . ~ . , ,. .- ,. - . . - l 7-6 1993 Evaluated Exercise- -t DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd):- 'l CUE CARD NO. 2-TO: OSC Controller (s) TIME: 08:00 T: 00/00 . 1 i ANTICIPATED RESPONSE: INSTRUCTIONS: , Fill in the names of the participants before handing out this cue. card. , Provide this cue card to the Continuous Service Maintenance, Chemistry and , Radiation Protection personnel who are to participate with-the Control Room Simulator at the start of the Exercise. Later, upon OSC activation, provide this cue card to the OSC Manager and his'
- staff.
i 9 S THIS IS A DRILL ,
*****************++***********************************************************
]
7-7 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. 3 T0: Control Room Staff TIME: 08:10 T. 00/10 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. INFORMATION: The DBNPS 1993 Exercise vill be conducted today. Vith the exception of making drill announcements that include sounding the Station alarms, all Control Room activities vill be conducted at the Simulator. All efforts vill be made to minimize your involvement. Make the following Gai-tronics announcement twice: " ATTENTION ALL PERSONNEL, ATTENTION ALL PERSONNEL. THE 1993 EMERGENCY EXERCISE IS COMMENCING. ALL ANNOUNCEMENTS PROCEEDED BY 'THIS IS A DRILL' ARE FOR PARTICIPANTS ONLY. IF AN ACTUAL EMERGENCY OCCURS, AN ANNOUNCEMENT VILL BE MADE THAT THE DRILL HAS BEEN SUSPENDED UNTIL FURTHER NOTICE. ALL PERSONNEL ARE REQUESTED TO MINIMIZE THE USE OF THE GAI-TRONICS UNTIL THE DRILL HAS BEEN TERMINATED." i THIS IS A DRILL 9i
- +*+**+*
7-8 1993 Evaluated Exercise t DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) CUE CARD NO. 3 i TO: Control Room Controller TIME: 08:10 T: 00/10 ANTICIPATED RESPONSE: .; A Control Room staff member can make the announcement. i i s INSTRUCTIONS:
- 1. Contact the Lead Drill Controller at the Simulator and' inform him'that the !
start of Drill has been announced over the Stetion Gai-tronics. i i Note: If the Gai-tronics module is working at the Simulator, then this cue' card should be performed by the Operations Crew at the Simulator under ! the direction of the Lead Controller. The Control Room Controller in this arrangement needs only to monitor the announcement for clarity and s to notify the Lead Controller should it turn out to be inaudible. Should the Gai-tronics capability at the Simulator fail to.vork, the Control Room controller must then resume responsibility for performing this announcement from the real Control Room.
- 2. Ensure that the Equipment Operators participating in the Drill use the
" backup" radios, in order that the primary radios remain available for-the ,
on-shift operators. j l Note: Following the Alert declaration and facility activation, the Control , Room Controller should monitor the Technical Data Loop vith the headset on mute in order to remain cognizant of Player actions as the Exercise j I progresses.
?
L i t
'I I *************************+**********************+**************************+++ .;
i THIS IS A DRILL
*****++***********************************************************************
l
7-9 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD CUE CARD NO. 4 SCENARIO NO. 1993 Evaluated Exercise T0: Simulator Shift Supervisor TIME: 08:30 T: 00/30 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. INFORMATION: A Control Cell phone talker should call the Control Room (Simulator) at Ext. 7399 and report the following: "This is a drill. This is a drill. This is site security. A security officer on tour of the site, witnessed a lightning strike on the transmission lines in the main switchyard. This is a drill". THIS IS A DRILL
******************+**********+++++*********++*********************************
7-10 1993 Evaluated Exercise [ DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) CUE CARD NO. 4 , TO: Control Cell Controller TIME: 08:30 T: 00/30 , ANTICIPATED RESPONSE: { Control Room Operator acknowledges message and informs Shift Supervisor of this information, which could be the cause of the plant transient. I l I INSTRUCTIONS: - Control Cell should not initiate this call unless a Controller at the Simulator verifies that the transient has been initiated by the Instructor Facility (IF) i Operator. t h 9 9 6 l
~ l
****************************************************************************** I THIS-IS A DRILL
********************************+++****************++***********************++
. _ . . . ._ , _~. .
7-11 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NC. 1993 Evaluated Exercise CUE CARD NO. 5 O, T0: Players On or Near the Turbine Deck TIME: 08:30+ T: 00/30+
****************************************++++++*********+**********************
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
************+******************************************************+**********
INFORMATION: You've just heard a loud noise followed by a hissing sound emanating f rom the Main Turbine. O
***************************************sA************************+********.***
THIS IS A DRILL
- m. . .__ _ _
L l s 7-12 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) i f-~)g s
' -CUE CARD NO. 5 _
{ TO: In-Plant Controllers TIME: -08:30+-
]
T: 00/30+ 1
-i ANTICIPATED RESPONSE:
Players should investigate and then notify the Control Room (Simulator).
~
INSTRUCTIONS: r
- 1. Verbally inform players in the vicinity of the Turbine Deck, the l information in the message. ;
r i
- 2. Inform Players who look out on the Turbine Deck that.they see steam ,
shooting from the North Lov Pressure Turbine hood.
- 3. At approximately 08:31, inform the Players that the steam leak stopped following closure of the Main Steam Isolation Valves.
- 4. Provide additional indications of plant damage as directed in Section 10.3' of this manual. ;
3 k 1 e THIS IS A DRILL !
*********.*********************++*++++++++++++++**************+****+++++++++*+ l i
r~ j 7-13 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD , SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. 6 TO: Players In or Near the Condenser Pit TIME: 08:30+ - T: 00/30+ THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
************************************************************************+++***
INFORMATION: You've just heard several loud bangs followed by the sound of rushing water. O
******k***********************************************************************
THIS IS A DRILL l l
7-14 '1993' Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD CUE CARD NO. 6 , T0: -In-Plant Controllers TIME: 08:304 I. T: 00/30+ t ANTICIPATED RESPONSE: i Players should investigate and then notify the Control Room (Simulator). ; i INSTRUCTIONS:
- 1. Verbally inform Players in the vicinity of the Condenser Hot Vell, the information in the message. .
5
- 2. Inform Players who look along the east side of the Main Condenser, that they see water shooting from holes in the shell of the condenser.and the ;
expansion joint of a Circulating Vater pipe. ( ,
- 3. Provide additional indications of plant damage caused by flooding as i directed in Section 10.3 of this manual.
l d l I e ****************************************************************************** THIS IS A DRILL
7-15 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. 7 TO: Control Room Controller TIME: 08:45 T: 00/45
- +*********************************+****
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. INFORMATION: Perform the following actions when directed by the Lead Drill controller and informed that an ALERT has been declared. Announce "THIS IS A DRILL, THIS IS A DRILL." Sound the Initiate Emergency Procedures Alarm. Make the following announcement: "THIS IS A DRILL. ATTENTION ALL PERSONNEL; ATTENTION ALL PERSONNEL: AN ALERT HAS BEEN DECLARED. ALL MEMBERS OF THE ONSITE EMEPGENCY ORGANIZATION REPORT TO YOUR DESIGNATED EMERGENCY RESPONSE FACILITIES. ALL NONESSENTIAL PERSONNEL GO TO THE NEAREST DESIGNATED EMERGENCY ASSEMBLY AREA AND STAND BY. THIS IS A DRILL. ATTENTION ALI, PERSONNEL; ATTENTION ALL PERSONNEL: AN ALERT HAS BEEN DECLARED. ALL MEMBERS OF THE ONSITE EMERGENCY ORGANIZATION REPORT TO YOUR DESIGNATED EMERGENCY RESPONSE FACILITIES. ALL NONESSENTIAL PERSONNEL GO TO THE NEAREST DESIGNATED EMERGENCY ASSEMBLY AREA AND STANDBY. THIS IS A DRILL." i I
- I THIS IS A DRILL
- +*************************++*****************************4****
l i I l
7-16 1993 Evaluated Exercise
, DBNPS EMERGENCY PREPAREDNESS CUE' CARD (Cont'd)
CUE CARD NO. 7 TO: Control Room Controller _ TIME: 08:45 , T: 00/45 ANTICIPATED RESPONSE: , A Control Room staff member can sound the alarm and make the announcements. INSTRUCTIONS:
- 1. Make this announcement when contacted by a Controller at.the Simulator.
This contact may occur as early as 08:30 or as late as 09:00.
- 2. Coordinate this action with the real Shift Supervisor. ,
f s . ? 3 l t h r J THIS IS A DRILL ,
.*********************..*****.***.***++.****+.***++****+++*******++***+*****+++ J
'l
7-17 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS CUE CARD SCENARIO No. 1993 Cvaluated Exercise CUE CARD NO. 8X TO: Control Room Operator TIME: 08:42 T: 00/42
- ++**********+++*****************************
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
- k*****************
INFORMATION: Call the Simulator Control Room and report the following: "This is a drill. It appears that water is being forced from the condenser into the East Pit. A Cire k'ater rupture may exist. This is a drill." O l l 1
)
l l l l l l i i l l
- l THIS IS A DRILL 9II
- ++**************++++******++++++*+++++++****************++++++++******
t 7-18 1993' Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) g-sg V CUE CARD NO. BX l TO: IF Operator TIME: 08:42 l T: 00/42 ANTICIPATED RESPONSE: , Operators should carry out actions per the Circulating Vater rupture . procedure. INSTRUCTIONS: , Provide the information on this card only if it appears Control Room personnel - are unaware of the severity of the Condenser ruptures. Due to the difficulty of conveying " imagined" flooding conditions in the Plant, Players who report the
+
incident may not relay sufficient information for the Control Room Operators to ; be aware of the significance of the event. l l
+
l [ a t r THIS IS A DRILL j
*.*****************************************************++++++++++*++++++++++++ j
, , , - - ~ -,~=
7-19 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO No. 1993 Evaluated Exercise CUE CARD NO. 9 T0: Emergency Director, Emergency Plant Manager, TIME: 08:50+ Emergency Security Manager, OSC Manager T: 00/50+
- f***********************************.
THIS IS A DRILL DO NOT initiate actions af fectittg normal plant operations.
- k*********************************************************w************
INFORMATION: " Simulate" the following actions:
- 1. Dismissal of training classes.
- 2. Sending non-essential contractors and visitors home.
Visitor tours should not be cancelled, however, access to emergency facilities should be restricted. Only Controller / Evaluators, Players and authorized observers should be permitted access to the emergency facilities. I 1 I I l 1 I I
- .***************.+****
THIS IS A DRILL
7-20 1993-Evaluated Exercise r
- DBNPS EMERGENCY PREPAREDNESS CUE. CARD (Cont'd) I 9
CUE CARD NO. 08:50+ TO: ECC, TSC, Security and OSC Controllers TIME: T: 00/50+ 4 ANTICIPATED RESPONSE: Training classes and tours are not disrupted. , INSTRUCTIONS: Try to maintain normal Station operations. Exercise activities should have minimal impact on most Station activities. h { i
?
r t l t
?
i THIS IS A DRILL
*********************************+************************************.******** ;
l 7-21 1993 Evaluated Exercise , DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. 10X O.l! i TO: Emergency Director TIME: 08:55 i (Shift Supervisor at Simulator) T: 00/55
- +******************************************************
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
- ww***************
INFORMATION: Declare an ALERT in accordance with EAL 7.F.2. An ALERT must be declared at this time in order to keep the Exercise sequence of events on schedule. O
- +**********************************
THIS IS A DRILL
,, . ~ . . . , _. . . . . . . . -. - -
7-22 .1993 Evaluated Exercis'e DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) O CUE CARD NO. 10X TO: Lead Drill Controller TIME: 08:55 T: 00/55 l ANTICIPATED RESPONSE: , Shift Supervisor vill declare an Alert and carry out actions per procedure i HS-EP-01700. , A
'i INSTRUCTIONS: ;
i Provide this card to the Shift Supervisor only if an Alert has not been declared i by this time. If an Alert has already been declared, then disregard this- -{* message. I () i 1 I f f
****************************************************************************** I O THIS IS A DRILL ,
i 1 r t
- c. ~ . . , - - . . . _
7-23 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. 11 9 TO: Emergency Security Manager TIME: 09:00 T: 01/00 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
- A*************************************************************************
INFORMATION: For the purposes of the Drill, relax access restrictions to the Owner Controlled Area and Protected Area. O THIS IS A DRILL
7-24 1993 Evaluated Exercise DBNPS EHERGENCY PREPAREDNESS CUE CARD (Cont'd) CUE CARD NO. 11 , T0: Lead Security Controller TIME: 09:00 T: 01/00 ANTICIPATED RESPONSE: i Normal access to the Owner Controlled Area (OCA) and Protected Area (PA) is restored.
'l l
1 INSTRUCTIONS: Give this message to the Emergency Security Manager after OCA and-PA access ; control has been demonstrated. NOTE: If traffic backs up with more than six-vehicles at the OCA gate, at your discretion access can be restored sooner, s_s/ . l l l j i l l i I i l 1 l THIS IS A DRILL
******************************************+***********************************
7-25 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO No. 1993 Evaluated Exercise CUE CARD NO. 12 TO: Assembly Area Coordinator TIME: Approx. 09:05 T: Approx. 01/05
- +******************+*****************
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. INFORMATION: Have all assembled personnel return to work. Inform the Emergency facilities Services Manager that you have been directed by a Controller to take this action. O 1s1S 1S oR m O
- l 7-26 1993 Evaluated' Exercise DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) ;
O~ CUE CARD NO. 12 - i TO: Assembly Area Controller TIME: Approx. 09:05 T: Approx. 01/05 ANTICIPATED RESPONSE: Non-essential personnel are returned to work. - t a 1 INSTRUCTIONS: 1 Give this to the Assembly Area Coordinators after assembly of the' Protected' Area ' has been completed (approximately 30 minutes after the ALERT Gai-tronics announcement). i 5 e h
)
's.
h THIS IS A DRILL
****************************************************************************++
b i e .- .. ,,-n , , , . . - , , , , - .n ,
7-27 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD No. 13 T0: Roving Equipment Operator TIME: 09:05 T: 01/05 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
- .**************************d************************************
INFORMATION: Contact the Control Room (Simulator) via radio and report the following: "THIS IS A DRILL. THERE IS AN INJURED MAN NEEDING ASSISTANCE IN THE #3 MECHANICAL PENETRATION ROOM OF THE AUXILIARY BUILDING. THIS IS A DRILL." Answer any questions the Control Room Operator may have. The following information can be used: Victim - Maintenance Vorker
- Victim's name - , Supervisor -
Victim appears to have several abrasions, a broken vrist and a tvisted knee. ' Victim is requesting to be transported to the Fremont Memorial Hospital. THIS IS A DRILL I
7-28 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) CUE CARD NO. 13
~TO: First Aid Team Controller TIME: 09:05 i T: 01/05 ANTICIPATED RESPONSE:
First Aid Team is notified and responds to the scene. i INSTRUCTIONS: Fill in the Player's (victim's) name and his Supervisor's name during setup.the morning of the Exercise. This vill ensure the badge information matches the cue card. Use this cue card to initiate the Medical Drill, then utilize the data provided in Section 8.7 to play through the events that vill follow. Mid-County EMS should respond to transport the victim. ! Fremont Memorial Hospital vill receive and treat the victim. i I i
. -l l
THIS IS A DRILL , I
**********************************+ **++****+*********************************
'l
'I
- - - - . - - . - -. - .. . - . . .a
7-29 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. 14 TO: Control Room Controller TIME: 09:05+ T: 01/05+ THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
- Ak+*********************+***********************************
INFORMATION: Perform the following actions when directed by the Lead Drill Controller and informed that a medical emergency has been initiated. Announce "THIS IS A DRILL, THIS IS A DRILL." Sound the Initiate Emergency Procedures Alarm. Make the following announcement: "THIS IS A DRILL, THIS IS A DRILL. ATTENTION STATION PERSONNEL. A MEDICAL EMERGENCY EXISTS IN THE #3 MECHANICAL O PENETRATION ROOM, 585 FOOT ELEVATION OF THE AUXILI ARY BUILDING. FIRST AID TEAM REPORT TO THE #3 MECHANICAL PENETRATION ROOM. THIS IS A DRILL. ATTENTION STATION PERSONNEL. A MEDICAL EMERGENCY EXISTS IN THE #3 MECHANICAL PENETRATION ROOM, 585 FOOT ELEVATION OF THE AUXILIARY BUILDING. FIRST AID TEAM REPORT TO THE #3 MECHANICAL PENETRATION ROOM. THIS IS A DRILL."
- ++++++*****************************+*********+++.
1H1S 15 A DR m 9
l 7-30 1993 Evaluated Exercise' s- DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) CUE CARD NO. 14 TO: Control Room Controller TIME: 09:05+ l T: 01/05+ ANTICIPATED RESPONSE: A Control Room staff member can sound the alarm and make the announcement. INSTRUCTIONS:
- 1. Make this announcement when contacted by a Controller at the Simulator.
This contact may occur as early as 09:05 or as late as 09:20.
- 2. Coordinate this action with the real Shift Supervisor.
-f.
r
}
B 3
~g ******************************************************************************. Ji THIS IS A DRILL
********************************+*********************************************
\
7-31 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD CUE CARD No. 15 SCENARIO NO. 1993 Evaluated Exercise TO: CAS/SAS Operator TIME: Approx. 09:20 T: Approx. 01/20
- w****************************************************************
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
- 1'******************************* .*****f****++
INFORMATION: DO NOT USE 911. Call the Ottava County Sheriff's Dispatcher at 734 4404 to report the simulated medical emergency. O l l I THIS IS A DRILL
******************************************+***********************************
- .- . . ~ . - . - . . - . . - . . - = . 7-32. 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) , CUE CARD No. 15 T0: CAS/SAS Controller TIME: Approx. 09:20' T: Approx. 01/20
.i ANTICIPATED RESPONSE: .)
Player vill call Sheriff's Dispatcher on non-emergency number. INSTRUCTIONS: Give this card to the player when he/she attempts to call the Sheriff's Dispatcher. 1 5 THIS IS A DRILL
*****++****************************++++*****+*****+++++***********+***********
5 e - . , . - , - - - , , . . . . ..--.: -,. N--- - , . - . , - - - , - --e .,-n e 1-, ,- --e,,.,- , - , -
7-33 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. 16 G. TO: CAS/SAS Operator TIME: Approx. 09:25 T: Approx. 01/25 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. INFORMATION: Notify Fremont Memorial Hospital at 332-7321 vith the following information: "This is a drill. This is a drill. A simulated medical emergency has occurred inside the Protected Area at the Davis-Besse Nuclear Power Station. An ambulance from Mid-County EMS will be transporting a contaminated injured person to your facility. This is a drill". l l l 1 THIS IS A DRILL 9!
- ++++***************************++****
7-34 1993 Evaluated Exercise j
~
t DBNPS EMERGENCY PREPAREDNESS EXERCISE-CUE CARD (Cont'd) !
. SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. 16 ,
TO: CAS/SAS Controller ' TIME: Approx. 09:25 T: _ Approx. 01/25 i ANTICIPATED RESPONSE: ; Upon getting word of the victim's request. the CAS/SAS operator notifies Fremont Memorial Hospital. ; INSTRUCTIONS: i
- 1. They should only perform this action after being contacted by Station i personnel that the victim is requesting the Fremont hospital.
- 2. Controller should ensure that only Fremont Memorial Hospital.is contacted.
4 s i I THIS IS A DRILL l 1 t e -, , , , - - - - - , .- , , . - - - , - - .
7-35 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO No. 1993 Evaluated Exercise CUE CARD NO. 17 T0: Control Room Controller TIME: 11:00 T: 03/00
- +*********+****v<****************44**+**++***
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
- 4**************************************
INFORMATION: Perform the following actions when directed by the Lead Drill Controller and informed that a Site Area Emergency has been declared. Announce "THIS IS A DRILL, THIS IS A DRILL." Sound the Initiate Emergency Procedures Alarm. Make the following announcement: "THIS IS A DRILL, THIS IS A DRILL. ATTENTION ALL PERSONNEL; ATTENTION ALL PERSONNEL: A SITE AREA EMERGENCY HAS BEEN DECLARED. ALL MEMBERS OF THE ONSITE EMERGENCY ORGANIZATION REPORT TO YOUR DESIGNATED EMERGENCY RESPONSE FACILITIES. ALL NONESSENTIAL PERSONNEL VITHIN THE PROTECTED AREA EVACUATE TO THE TRAINING CENTER ASSEMBLY AREA IMMEDIATELY. ATTENTION ALL PERSONNEL; ATTENTION ALL PERSOUNEL: A SITE AREA EMERGENCY HAS BEEN DECLARED. ALL MEMBERS OF THE ONSITE EMERGENCY ORGANIZATION REPORT TO YOUR DESIGNATED EMERGENCY RESPONSE FACILITIES. ALL NONESSENTIAL PERSONNEL VITHIN THE PROTECTED AREA EVACUATE TO THE TRAINING CENTER ASSEMBLY AREA IMMEDIATELY. THIS IS A DRILL." THIS IS A DRILL
a 7-36 1993 Evaluated Exercise l 4 DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) CUE CARD NO. 17
+
T0: Control Room Controller and TIME: 11:00
- PPF Assembly Area Controller T: 03/00 ANTICIPATED RESPONSE: 4 A Control Room staff member can sound the alarm and make the announcements.
INSTRUCTIONS: For Control Room Controller: ! 1
- 1. Make this announcement when contacted by a controller at the Simulator. <
This contact may occur as early as 10:45 or as late as 11:15,
- 2. Coordinate this action with the real Shift Supervisor.
For PPF Assembly Area Controller: >
- 1. As non-essential personnel exit the Security Gate House, direct them to assemble in the PPF Parking Lot instead of the Training. Center.
- 2. Once accountability is completed, release the assembled personnel to return to their normal work locations. '
l l 4 i 4 o 1
*************************************************************+A***************
THIS IS A DRILL I
7-37 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. 18 T0: Emergency Facilities Service Manager TIME: 11:00+ T: 03/00+ __,
- n*************************
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. INFORMATION: When you call the Assembly Area Coordinators, inform them owner Controlled Area Assembly is being simulated. Have them get their kits and call you back with an estimate of the number of people who would assemble in their area. When they call back with an estimate of the number of people who would assemble tell them no further action is required at this time. O THIS IS A DRILL 9i, l I
7-38 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) s CUE CARD NO. 18 T0: ECC Controller TIME: -11:00+ T: 03/00+ ANTICIPATED RESPONSE: Player calls Assembly Area Coordinators. INSTRUCTIONS: l
- 1. Give this cue card to Emergency Facilities Service Manager when he/she starts to call Assembly Area Coordinators.
- 2. If he/she does not start to call within 2 minutes of' Site Area Emergency declaration, direct him/her to due so.
6 I I l l l
)
******t***********************************************************************
THIS IS A DRILL
****************+*****++**************++**+++**+++****+++******++*************
7-39 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. 19 T0: Emergency Facilities Service Manager TIME: 11:00+ T: '03/00+
- +***++*
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. INFORMATION: This is the Training Center Assembly Area Coordinator, an additional 236 individuals have arrived (simulated) at the Training Center from the Protected Area. O d***************************************************************************** i THIS IS A DRILL GI C*********************************************w*******************4*********** i
.1 7-40 1993 Evaluated Exercise.
DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) CUE CARD NO 19 TO: ' ECC Controller TIHE: 11:00+ T: 03/00+ l d ANTICIPATED RESPONSE: : The Emergency Offsite Manager is informed of the assembly status. + l t INSTRUCTIONS: ,
-I Issue this cue card after the Training Center Assembly Area Coordinators have reported their initial assembly numbers.
(:) -
?
^
P T
.k THIS IS A DRILL i
]
i
7-41 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD l) CUE CARD NO. 20X SCENARIO NO. 1993 Evaluated Exercise T0: Emergency Director (at ECC) TIME: 11:10 T: 03/10
- k*************************************************************
TilIS IS A DRILL D0 f]OT initiate actions affecting normal plant operations. INFORMATION: Declare a SITE AREA EMERGENCY in accordance with EAL 3.D.3. A SITE AREA EMERGENCY must be declared at this time in order to keep the Exercise sequence of events on schedule. O Tills IS A DRILL
- &**********k*****************k********
7-42 1993 Evaluated Exercise DBNPS EMERGENCY FREPAREDNESS CUE CARD (Cont'd)
.O CUE CARD NO. 20X e
T0: Emergency Director Controller TIME: 11:10 T: 03/10 ANTICIPATED RESPONSE: Emergency Director vill declare a Site Area Emergency and carry out actions per procedure HS-EP-01800. INSTRUCTIONS: Provide this card to the Emergency Director only if a Site Area Emergency has not been declared by this time. If a Site Area Emergency has already been declared, then disregard this message. l O 1 i O THIS IS A DRILL I
7-43 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. 21 O TO: Control Room Controller TIME: 13:10 T: 05/10 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. INFORMATION: Perform the following actions when directed by the Lead Drill Controller and informed that a General Emergency has been declared. Announce "THIS IS A DRILL, THIS IS A DRILL." Sound the Initiate Emergency Procedures Alarm. Make the following announcement: "THIS IS A DRILL, THIS IS A DRILL. ATTENTION ALL PERSONNEL; ATTENTION ALL PERSONNEL: A GENERAL EMERGENCY HAS BEEN DECLARED. NO EATING, DRINKING OR SM0 KING UNTIL FURTHER NOTICE. ALL MEMBERS OF THE ONSITE EMERGENCY ORGANIZATION REPORT TO YOUR DESIGNATED EMERGENCY RESPONSE FACILITIES. OVNER CONTROLLED AREA EVACUATION IS BEING SIMULATED. ATTENTION ALL PERSONNEL; ATTENTION ALL PERSONNEL: A GENERAL EMERGENCY IIAS BEEN DECLARED. NO EATING, DRINKING OR SM0 KING UNTIL FURTHER NOTICE. ALL MEMBERS OF THE ONSITE EMERGENCY ORGANIZATION REPORT TO YOUR DESIGNATED EMERGENCY RESPONSE FACILITIES. OWNER CONTROLLED AREA EVACUATION IS BEING SIMULATED. THIS IS A DRILL."
- S****
THIS IS A DRILL
l o
~
7 44 1993 Evaluated Exercise j ~ - . DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) l CUE CARD NO. 21 TO: Control Room Controller- TIME: 13:10 T: 05/10 ANTICIPATED RESPONSE: A Control Room staff person can sound the alarm and make the announcements. d INSTRUCTIONS:
- 1. Make this announcement when contacted by a Controller at the Simulator.
This contact may occur as early as 13:00 or-as late as 13:25.
- 2. Coordinate this action with the real Shift Supervisor.
L l THIS IS A DRILL
******************************+++********************************************* ,
7-45 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. 22X TO: Emergency Director TIME: 13:25 T: 05/25 THIS IS A DRILL DO NOT initiate actions atfecting normal plant operations.
- +******+*****************************
INFORMATION: Declare a GENERAL EMERGENCY in accordance with EAL 6.D.3. A GENERAL EMERGENCY must be declared at this time in order to keep the Exercise sequence of events on schedule. O
- +**************************************
THIS IS A DRILL O . 1
c -A m .. . _ 7-46 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) 7-~g
- Q CUE CARD NO. 22X T0: Emergency Director Controller TIME: 13:25 T: 05/25 ANTICIPATED RESPONSE:
Emergency Director vill declare a General Emergency and carry out actions'per procedure HS-EP-01900. s INSTRUCTIONS: Provide this card to the Emergency Director if a General Emergency has not been declared by this time. If a General Emergency has already been declared, then disregard this message. O . 4
<' h h hh hhh h hh hhhhhhh*hhhhhhhhhhhhhhhhhhhhhhhhh *hhh *hh THIS IS A DRILL
**************h************************************************************+*+
7-47 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. 23X TO: Emergency Director TIME: 14:30 T: 06/30 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
- w***************************************************
INFORMATION: For purposes of the Exercise, begin declassification discussions at this time. O Q***************************************************************************** THIS IS A DRILL O c********************************************************************'*********
7-48 '1993 Evaluated Exercise i DBNFS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) CUE CARD NO. 23X TIME: 14: 30 T0: ECC Controller T: 06/30 i ANTICIPATED RESPONSE: Players review current plant conditions and consider down-grading the classification through discussion with the TSC staff and State of Ohio officials. i
')
INSTRUCTIONS: If declassification discussions have already been initiated, do not issue this
't message.
i i
.. f h
k kN Nkk kk*kN*kkkkkNNkkkk8kkkkkkkkkkkkkdNkk*kONNkkNdkNkkkNNkkkkkkkkkk
\
THIS IS A DRILL
**************++***+++++++******+++*k*******************++++++*++k*********++*
b
7-49 1993 Evaluated Exercise i DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD No. 24 TO: Control Room Staff TIME: 14:45 T: 06/45
- +++************************************
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
- .********************************++****************************++*******
INFORMATION: The DBNPS 1993 emergency exercise has been completed. Make the following Gai-tronics announcement: " ATTENTION ALL PERSONNEL, ATTENTION ALL PERSONNEL: THE 1993 EMERGENCY EXERCISE HAS ENDED. ATTENTION ALL PERSONNEL: THE 1993 EMERGENCY EXERCISE HAS ENDED. REGARD ALL FUTURE ALARMS AND ANNOUNCEMENTS."
- ++****++++**************+***+++++++*
THIS IS A DRILL O
7-50 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) CUE CARD NO. 24 T0: Control Room Controller TIME: 14:45 T: 06/45 ANTICIPATED RESPONSE: A Control Room staff member should make the announcement. I INSTRUCTIONS:
- 1. Make this announcement when contacted by the Lead Drill Controller.
- 2. Cather all materials used during the Exercise and return it to the Lead '
Drill Controller. Note: If the Gai-tronics module is working at the Simulator, then this cue ' \ card should be performed by the Operations Crew at the Simulator under the direction of the Lead Controller. The Control Room Controller in this arrangement needs only to monitor the announcement for clarity and to notify the Lead Controller should it turn out to be inaudible. , Should the Gai-tronics capability at the Simulator fail to work, the Control Room Controller must then resume responsibility for performing. this announcement from the real Control Room.
- 3. If instructed by the Lead Drill Controller, have a Control Room staff member contact the NRC via the red phone to inform the NRC that the drill activities for Davis-Besse have ended for the day.
I k k kk kkk k *kkk kkk kk *hkk k kk THIS IS A DRILL
********************************************************++********************
1
7-51 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO No. 1993 Evaluated Exercise CUE CARD NO. 25 TO: All Facility Managers TIME: 14:45 T: 06/45
- k*****
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. INFORMATION: The DBNPS 1993 Exercise has ended. Do not erase the status boards. Players associated with and located outside the facility should be contacted and directed to return to the facility. Take a short break, however, during this time, instruct Players that if they have any comments or recommendations to write them down so they can be discussed during the critique and forwarded to Emergency Preparedness. Notify those individuals involved with reentry / recovery per Cue Card No. 26. Once everyone has returned to the facility, conduct a critique. Refer to the status boards as necessary to review specific conditions or situations. Vhen the critique is over, erase the status boards and gather all facility logs and report forms for the Lead Controller. THIS IS A DRILL
.. . - . . ~ . , . .
1 7-52 1993 Evaluated'Exercisef t DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) , CUE CARD NO. 25 T0: All Controllers TIME: 14:45 T: -06/45 , ANTICIPATED RESPONSE: .j The Exercise ends and facility critiques are performed. n INSTRUCTIONS:
- 1. Stop the Exercise play when directed by the Lead Drill Controller. Ensure '
individuals involved with reentry / recovery discussions are sent to Rooms 209/210 per Cue Card No. 26.
- 2. Ensure all facility logs and report forms are returned to_the Emergency Preparedness Group.
- 3. All drill-related forms-(i.e., Drill Phone List, Data Sheets, etc.) should. i be removed'from the facilities so that they don't get mixed in with the l' real forms and procedures.
- 4. All radiological equipment (i.e., dosimeters, TLDs, survey meters, etc.)
should be returned to their storage location, and properly placed in 6 storage. _ Vall status boards should be erased and any chairs, tables or.other
- 5. ,
miscellaneous equipment used during the Exercise.should be returned to their original condition or location. f I THIS IS A DRILL 1 3 - ~ . . . , .. -. _ .. . - . . , , . , , . , ., . , . , . ,,,p. ,, ,y, <. .~d.-,_.
7-53 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO No. 1993 Evaluated Exercise CUE CARD NO. 26 T0: Emergency Director TIME: 15:45 T: 07/45
- +++++
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. INFORMATION: The following individuals should attend the recovery meeting in DBAB Rooms 209/210 at 1545:
' Emergency Director
- Emergency Offsite Manager
- Emergency Plant Manager
- TSC Engineering Manager
- Emergency RP Manager " Dose Assessment Coordinator
' Emergency Security Manager
- OSC Manager
- Company Spokesperson
- NRC Liaison Representative *
- Recovery Advisor
- Emergency Assistant Plant Manager lh
- Due to the distance to the JPIC, for purposes of the Exercise, an alternate to the Company Spokesperson vill be present at the recovery meeting.
I THIS IS A DRILL
*+***************+****************++++++++++*****+***********++++**+*++****++*
l I 1
7-54~ 1993 Evaluated' Exercise E, DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) , f 3 - CUE CARD NO. 26 i T0: ECC Controller TIME: 15:45' T: 07/45 'I ANTICIPATED RESPONSE: , The preliminary reentry / recovery meeting is held. ,
- s i
?
INSTRUCTIONS: Issue this cue card to limit the extent of reentry / recovery activities. . 1 1 t l p i W k N k kk kk kkkk k k kkkN k *k kkk kkN k *kkkkkkk i THIS IS A DRILL , t
- v w , w,
7-55 1993 Evaluated' Exercise. 7.2 PLANT PARAMETERS
SUMMARY
This section provides plant equipment parameter = indications in a tabular format for ease of review and for ease of locating a particular-instrument reading in a. timely manner.
l i I 7-56 1993 Evaluated Exercise 1 l PLANT PARAMETERS DATA
SUMMARY
RCS Boron RCS . T Time Time Pressure T AvQ. T Hot T Cold Conc. Subcool'a l 00/00 0800 2170.4 581.7 605.5 557.8 650.0 43.1 00/15 0815 2170.2 581.7 605.5 557.8 650.0 43.1 00/30 0830 2171.3 581.7 605.5 557.8 650.0 43.1 < 00/45 0845 2052.3 551.9 552.5 551.2 652.0 88.0 01/00 0900 2148.4 549.1 549.7 548.5 671.7 97.4 01/15 0915 2108.9 529.5 529.8 529.3 672.6 114.7 01/30 0930 2006.0 529.6 529.9 525.1 701.7 107.4 01/45 0945 1991.4 524.0 524.6 523.5 702.8 111.7 02/00 1000 1916.3 520.0 514.2 513.5 713.2 116.7 02/15 1015 1592.1 520.0 499.2 499.0 721.6 106.3 02/30 1030 830.8 520.0 485.2 485.0 727.3 39.7 02/45 1045 723.5 520.0 464.8 463.5 727.3 44.3 03/00 1100 676.0 520.0 465.7 453.6 727.3 48.2 03/15 1115 587.0 520.0 429.4 422.2 727.3 57.2 03/30 1130 552.6 520.0 414.1 408.7 727.3 66.5 03/45 1145 547.9 520.0 397.3 392.9 727.3 82.5 04/00 1200 330.1 520.0 388.5 384.5 727.3 42.3 04/15 1215 334.7 520.0 393.7 386.1 727.3 38.5 04/30 1230 323.6 520.0 385.6 388.6 727.3 43.1 04/45 1245 324.1 520.0 383.9 358.6 727.3 45.0 05/00 1300 285.1 520.0 383.9 274.9 727.3 33.8 05/15 1315 238.5 520.0 383.0 228.7 727.3 20.6 05/30 1330 212.5 520.0 386.4 178.9 727.3 16.8 05/45 1345 197.7 520.0 369.1 162.7 727.3 18.9 06/00 1400 141.8 520.0 357.4 152.2 727.3 21.2 06/15 1415 122.1 520.0 364.1 167.5 727.3 28.9 06/30 1430 106.3 520.0 362.1 175.0 727.3 33.4 06/45 1445 94.4 520.0 361.0 167.0 727.3 37.6 07/00 1500 72.8 520.0 350.3 138.2 727.3 41.8 Units -> (psig) ("F) ('F) ('F) (ppm) ("F) PZR PZR RCS Flow Block Spray Time Temp. Level Loop 1 Loop 2 PORV Valve Valve 0800 648.4 221.8 76.6 76.0 AUTO OPEN AUTO 0815 648.0 222.0 76.6 76.0 AUTO OPEN AUTO 0830 648.1 221.4 76.6 76.1 AUTO OPEN AUTO 0845 641.5 101.7 81.3 36.5 AUTO OPEN AUTO 0900 648.1 102.7 81.8 36.6 AUTO OPEN AUTO 0915 642.9 105.3 83.6 37.6 AUTO OPEN AUTO 0930 638.6 113.0 83.5 37.5 AUTO OPEN AUTO 0945 636.4 103.1 84.0 37.7 AUTO OPEN AUTO 1000 632.4 96.2 84.8 38.0 AUTO OPEN AUTO 1015 609.7 93.4 85.6 38.4 AUTO OPEN AUTO 1030 528.8 87.0 85.6 38.6 AUTO OPEN AUTO 1045 510.8 78.0 85.6 39.4 AUTO OPEN AUTO 1100 492.8 209.2 0.0 49.9 OPEN OPEN AUTO 1115 457.5 320.0 0.0 50.8 OPEN OPEN AUTO 1130 438.2 320.0 0.0 51.5 OPEN OPEN AUTO 1145 420.4 320.0 0.0 52.1 OPEN OPEN AUTO 1200 408.5 320.0 0.0 40.1 OPEN OPEN AUTO 1215 402.8 320.0 0.0 0.0 OPEN OPEN AUTO 1230 394.2 320.0 0.0 0.0 OPEN OPEN AUTO 1245 386.8 320.0 0.0 0.0 OPEN OPEN AUTO 1300 379.7 320.0 0.0 0.0 OPEN OPEN AUTO 1315 374.2 320.0 0.0 0.0 OPEN OPEN AUTO 1330 373.8 320.0 0.0 0.0 OPEN OPEN AUTO 1345 347.8 320.0 0.0 0.0 OPEN OPEN AUTO 1400 321.1 321.1 0.0 0.0 OPEN OPEN AUTO 1415 300.2 300.2 0.0 0.0 OPEN OPEN AUTO 1430 303.6 303.6 0.0 0.0 OPEN OPEN AUTO 1445 306.7 306.7 0.0 0.0 OPEN OPEN AUTO 1500 301.0 301.0 0.0 0.0 OPEN OPEN AUTO Units -> ('F) (in.) (Mpph) (Mpph) .........................................................................=.....
- -- - - = .
7-57 1993 Evaluated Exsrcise-PLANT PARAMETERS DATA. SUM"NtY [V] - Block Letdown Reactor Coolant Pump Seal Flows . . . . . . Time Valve Flow Total RCP 1-1 RCP 1-2 RCP 2-1 RCP 2-2 0800 OPEN 75.4 33.6 7.6 8.7 .8.0 8.4 0815 OPEN 75.3 33.8 7.7 8.7 8.0 8.4 0830 OPEN 75.4 33.7 7.6 8.7 8.0 8.4 0845 OPEN 74.2 32.6 9.2 4.2 9.7 9.5 0900 OPEN 75.2 32.2 9.1 4.1 9.6 9.4 0915 OPEN 74.7 32.3 9.2 4.1 9.6 9.4 ' 0930 OPEN 73.7 32.8 9.2 4.4 9.7 9.5 0945 OPEN 73.7 32.3 9.3 4.6 9.8 9.6 , 1000 OPEN 72.8 32.8 9.2 4.4 9.7 9.5 ! 1015 OPEN 69.7 33.2 8.9 4.9 9.5 9.6 1030 OPEN 58.7 33.2 8.9 4.9 9.5 9.6 1045 OPEN 56.0 32.7 8.9 4.5 9.5 9.5 1100 OPEN 63.6 32.8 7.6 9.0 7.5 12.4 1115 OPEN 0.7 4.3 6.1 8.2 6.6 11.8 1130 OPEN 0.5 6.3 6.1 8.2 6.6 11.9 1145 OPEN 0.5 0.0 0.0 0.0 0.0 4.3 1200 OPEN 0.5 0.0 0.0 0.0 0.0 6.3 1215 OPEN 0.5 0.0 0.0 0.0 0.0 0.0 1230 OPEN 0.5 0.0 0.0 0.0 0.0 0.0 1245 OPEN 0.6 0.0 0.0 0.0 0.0 0.0 1300 OPEN 0.6 0.0 0.0 0.0 0.0 0.0 1315 OPEN 0.5 0.0 0.0 0.0 0.0 0.0 1330 OPEN 0.5 0.0 0.0 0.0 0.0 0.0 k 1345 OPEN 0.6 0.0 0.0 .0.0 0.0 0.0 1400 OPEN 0.5 0.0 0.0 0.0 0.0 0.0 1415 OPEN 0.6 0.0 0.0 0.0 0.0 0.0 1430 OPEN 0.6 0.0 0.0 0.0 0.0 0.0 1445 OPEN 0.6 0.0 0.0 0.0 0.0 0.0 1500 OPEN 0.5 0.0 0.0 0.0 0.0 0.0
) Units -> (gpm) (gpm) (gpm) (gpm)
(gpm). (gpm) Quench Tank Source Range Intermediate Range Power Range Time Level Pressure NI-1 NI-2 NI-3 NI-4 NI-5 0800 8.7 24.7 0.1 0.1 0.633E-04 0.620E-04 99.9 0815 8.7 24.7 0.1 0.1 0.633E-04 0.620E-04 99.9 0830 8.7 24.7 0.1 0.1 0.633E-04 0.621E-04 100.0 0845 8.7 24.7 0.1 0.1 0.101E-10 0.100E-10 0.0 0900 B.7 24.7 8.8 8.2 0.101E-10 0.100E-10' O.0 0915 8.7 24.7 7.4 6.7 0.101E-10 0.100E-10 0.0 0930 8.7 24.7 6.9 6.6 0.101E-10 0.100E-10 0.0 0945 8.7 24.7 6.9 6.6 0.101E-10 0.100E-10 0.0 1000 8.7 24.7 6.9 6.4 0.101E-10 0.100E-10 0.0 1015 8.7 24.8 7 . 0- 6.5 0.101E-10 0.100E-10 0.0 1030 8.7 24.8 7.3 6.6 0.101E-10 0.100E-10 0.0 1045 9.7 24.8 7.2 6.6 0.101E-10 0.100E-10 0.0 1100 8.7 24.8 6.8 6.4 0.101E-10 0.100E-10 0.0 1115 12.5 0.0 5.1 4.8 0.101E-10 0.100E-10 0.0 . 1130 12.5 0.0 4.5 4.0 0.101E-10 0.100E-10 0.0
- 1145 12.5 0.0 4.0 3.7 0.101E-10 0.100E-10 0.0 1200 12.5 0.0 3.8 3.5 0.101E-10 0.100E-10 0.0 1215 12.5 0.0 3.7 3.3 0.101E-10 0.100E-10 0.0 1230 12.5 0.0 3.3 3.2 0.101E-10 0.130E-10 0.0 i 1245 12.5 0.0 3.1 3.0 0.101E-10 0.100E-?f 0.0 1300 12.5 0.0 3.2 2.9 0.101E-10 0.100E-10 0.0 1315 12.5 0.0 3.1 2.9 0.101E-10 0.100E-10 0.0 1330 12.5 0.0 3.3 3.0 0.101E-10 0.100E-10 0.0 1345 12.5 0.1 3.3 3.1 0.101E-10 0.100E-10 0.0 1400 12.5 0.2 3.4 3.1 0.101E-10 0.100E-10 0.0 '
1415 12.5 0.0 3.3 3.2 0.101E-10 0.100E-10 -0.0 1430 12.5 0.0 3.4 3.2 0.101E-10 0.100E-10 0.0 1445 12.5 0.2 3.4 3.2 0.101E-10 0.100E-10 0.0 1500 12.5 0.1 3.4 3.2 0.101E-10 0.100E-10 0.0 Units -> (ft) (paig) (cps) (cps) (amps) (amps) (t) l
............................................................................=..
l 1
7-58 1993 Evaluated Exercise PLANT PARAMETERS DATA
SUMMARY
Power Range (Cont'd) Highest Makeup Makeup Tank Time NI-6 NI-7 NI-8 Core TH Flow Level Pressure 0800 100.1 99.9 100.1 615.6 17.6 66.1 30.0 0815 100.1 99.8 100.1 616.0 18.3 66.1 30.0 0830 100.2 99.9 100.1 615.2 17.5 66.1 30.0 0845 0.0 0.0 0.0 586.2 54.5 83.5 30.0 0900 0.0 0.0 0.0 558.1 89.4 71.3 30.0 0915 0.0 0.0 0.0 540.5 146.6 83.8 30.0 0930 0.0 0.0 0.0 534.5 13.4 83.4 30.0 0945 0.0 0.0 0.0 529.6 102.7 74.2 30.0 1000 0.0 0.0 0.0 518.6 14.0 77.8 30.0 1015 0.0 0.0 0.0 503.5 16.4 80.4 30.0 1030 0.0 0.0 0.0 492.2 21.6 77.6 30.0 1045 0.0 0.0 0.0 475.6 213.2 76.4 30.0 1100 0.0 0.0 0.0 468.9 98.7 86.6 30.0 1115 0.0 0.0 0.0 447.0 62.1 90.0 30.0 1130 0.0 0.0 0.0 428.3 15.6 90.8 30.0 1145 0.0 0.0 0.0 412.4 58.9 91.1 30.0 1200 0.0 0.0 0.0 400.2 16.3 68.2 30.0 1215 0.0 0.0 0.0 392.2 19.3 77.4 30.0 1230 0.0 0.0 0.0 380.8 19.1 56.1 30.0 1245 0.0 0.0 0.0 371.5 19.5 81.0 30.0 1300 0.0 0.0 0.0 364.1 22.6 76.9 30.0 1315 0.0 0.0 0.0 361.1 22.6 80.5 30.0 1330 0.0 0.0 0.0 318.1 18.7 85.4 30.0 1345 0.0 0.0 0.0 228.1 19.0 85.5 30.0 1400 0.0 0.0 0.0 217.2 18.9 85.7 30.0 1415 0.0 0.0 0.0 210.7 20.9 85.9 30.0 1430 0.0 0.0 0.0 206.9 22.1 86.8 30.0 1445 0.0 0.0 0.0 198.9 21.9 87.2 30.0 1500 0.0 0.0 0.0 192.5 21.0 87.4 30.0 Units -> (%) (%) (%) ('T) (gpm) (in.) (psig) Core Flood Tank #1 Core Flood Tank #2 HP Injection Line Flow Time Level Pressure Level Pressure 1-1 1-2 2-1 0800 12.9 605.7 12.9 605.6 0.0 0.0 0.0 0815 12.9 605.6 12.9 605.6 0.0 0.0 0.0 0830 12.9 605.9 12.9 605.9 0.0 0.0 0.0 0845 12.9 606.1 12.9 606.1 0.0 0.0 0.0 0900 12.9 606.3 12.9 606.3 0.0 0.0 0.0 0915 12.9 606.5 12.9 606.5 0.0 0.0 0.0 0930 12.9 606.7 12.9 606.7 0.0 0.0 0.0 0945 12.9 606.9 12.9 606.8 0.0 0.0 0.0 1000 12.9 607.0 12.9 607.0 0.0 0.0 0.0 1015 12.9 607.1 12.9 607.1 0.0 0.0 0.0 1030 12.9 607.2 12.9 607.2 0.0 0.0 0.0 1045 12.9 607.2 12.9 607.2 0.0 0.0 0.0 1100 12.9 607.2 12.9 607.2 543.5 541.6 547.6 1115 12.9 611.3 12.9 611.3 403.2 290.0 246.9 1130 12.9 617.2 12.9 617.2 447.2 292.2 250.1 1145 12.9 624.4 12.9 624.4 406.8 341.3 297.6 1200 12.9 631.2 12.9 631.3 194.2 252.4 222.2 1215 12.9 636.8 12.9 636.8 194.0 252.2 275.2 1230 12.9 641.9 12.9 642.0 198.0 253.4 276.3 1245 12.9 646.3 12.9 646.4 197.3 253.1 276.0 1300 12.9 650.3 12.9 650.3 199.8 256.3 227.4 1315 12.9 653.4 12.9 653.4 202.9 260.2 175.0 1330 12.9 655.8 12.9 655.9 212.2 262.8 165.7 1345 12.9 657.8 12.9 657.8 0.0 0.0 0.0 1400 12.9 658.9 12.9 658.9 0.0 0.0 0.0 1415 12.9 659.4 12.9 659.4 0.0 0.0 0.0 1430 12.9 659.1 12.9 659.1 0.0 0.0 0.0 1445 12.9 658.8 12.9 658.8 0.0 0.0 0.0 1500 12.9 658.2 12.9 658.2 0.0 0.0 0.0 Units -> (ft) (psig) (ft) (psig) (gpm) (gpm) (gpm)
7-59 1993 Evaluated Exercise PLANT PARAMETERS DATA
SUMMARY
\
HPI (Cont'd) LPI Line Flow DHR Ex Inlet Temp. CTMT Spray Flow Time 2-2 1-1 1-2 #1 #2 #1 #2 0800 0.0 0.0 0.0 70.0 70.0 0.0 0.0 0815 0.0 0.0 0.0 70.0 70.0 0.0 0.0 0830 0.0 0.0 0.0 70.0 70.0 0.0 0.0 0845 0.0 0.0 0.0 70.0 70.0 0.0 0.0 0900 0.0 0.0 0.0 70.0 70.0 0.0 0.0 0915 0.0 0.0 0.0 70.0 70.0 0.0 0.0 0930 0.0 0.0 0.0 70.0 70.0 0.0 0.0 . 0945 0.0 0.0 0.0 70.0 70.0 0.0 0.0 1000 0.0 0.0 0.0 70.0 70.0 0.0 0.0 1015 0.0 0.0 0.0 70.0 70.0 0.0 0.0 1030 0.0 0.0 0.0 70.0 70.0 0.0 0.0 1045 0.0 0.0 0.0 70.0 70.0 0.0 0.0 1100 544.0 0.0 0.0 89.2 79.6 0.0 0.0 1115 398.8 0.0 0.0 85.2 81.7 0.0 0.0 1130 404.0 0.0 0.0 79.8 82.6 0.0 0.0 1 1145 400.6 0.0 0.0 78.0 79.6 0.0 0.0 1200 329,7 0.0 0.0 78._ 77.6 0.0 0.0 l 1215 327.1 0.0 0.0 78.6 79.0 0.0 0.0 l 1230 328.4 0.0 0.0 77.4 78.7 0.0 0.0 j 1245 328.1 0.0 0.0 78.7 76.5 0.0 0.0 1300 273.2 0.0 0.0 76.4 77.3 0.0 0.0 l 1315 142.2 0.0 0.0 79.3 78.0 0.0 0.0 1330 134.6 0.0 3058.3 78.4 229.5 0.0 0.0 1345 0.0 0.0 3089.8 79.8 176.1 0.0 0.0 1400 0.0 0.0 3004.2 77.7 170.2 0.0 0.0 1415 0.0 0.0 3010.4 75.9 163.8 0.0 0.0 1430 0.0 0.0 3067.9 74.6 157.3 0.0 0.0 1445 0.0 0.0 3074.3 72.3 153.4 0.0 0.0 1500 0.0 0.0 3065.4 70.6 149.6 0.0 0.0 Units -> (gpm) (gpm) (gpm) (*F) (*F) (gpm) (gpm)
===============================================================================
BWST Containment Sump S/G #1 S/G #2 Time Level Press. Temp. Level Level Press. Level Press. 0000 40.4 14.9 89.3 0.5 194.3 910.5 200.7 910.1 0815 40.4 14.9 89.2 0.5 194.2 911.0 200.6 910.2 0830 40.4 14.9 89.4 0.5 194.4 910.7 200.8 909.9 0845 40.3 14.9 89.4 0.5 50.8 997.0 51.1 997.1 0900 40.2 14.9 89.4 0.5 50.9 972.3 50.9 971.0 0915 40.1 14.9 89.5 0.5 51.5 843.0 51.6 840.6 0930 40.1 14.9 89.6 0.5 51.3 830.9 51.2 830.3 0945 40.1 14.9 89.7 0.5 51.2 787.6 51.2 787.3 1000 40.1 14.9 89.7 0.5 51.4 722.4 51.1 714.1 1015 40.0 14.9 89.8 0.6 37.2 639.6 50.7 602.5 1030 40.0 14.9 89.7 0.6 45.9 556.2 51.2 527.0 1045 39.9 14.9 89.6 0.6 36.9 445.8 42.2 438.8 1100 39.7 14.9 89.6 0.6 38.4 477.7 46.7 474.7 1115 38.5 15.7 102.5 4.1 44.4 320.0 48.9 359.5 1130 37.5 16.5 114.2 6.5 46.3 268.4 49.7 299.3 1145 36.4 17.2 127.2 9.2 48.0 218.6 50.7 243.8 i 1200 35.5 17.8 134.9 11.8 48.7 195.2 50.9 217.8 l 1215 34.8 18.2 139.0 15.2 48.4 191.3 49.7 199.7 1230 34.0 18.6 141.9 17.6 47.8 200.8 49.0 201.6 1245 33.3 18.8 143.8 19.4 47.0 194.6 48.0 191.9 1300 32.5 19.0 145.1 20.9 46.3 186.9 47.5 179.2 1315 31.9 19.1 145.5 21.8 46.3 181.9 47.7 155.6 1330 31.3 19.1 145.2 22.6 48.6 117.9 49.4 83.8 1345 30.5 19.1 144.3 23.2 51.6 41.9 50.6 21.6 1400 30.3 19.0 144.0 18.9 51.9 23.9 51.8 41.9 1415 30.3 18.9 143.7 18.4 52.1 24.4 51.8 50.3 1430 30.2 18.9 143.2 17.6 52.0 24.4 51.5 61.3 1445 30.2 18.7 142.6 17.1 52.0 24.5 51.5 62.0 1500 30.2 18.4 142.0 16.7 52.0 24.5 51.4 56.6
/ Units -> (ft) (psia) (*F) (ft) (in.) (psig) (in.) (psig)
===============================================================================
7-60 1993 Evaluated Exercise PLANT PARAMETERS DATA
SUMMARY
S/G Shell Temp. Turbine MSIV Main Feedwater Flow Time #1 #2 Hdr. Press. Position Loop #1 Loop #2 0800 518.8 517.9 854.8 OPEN 5.8 5.8 0815 518.9 517.6 855.0 OPEN 5.8 5.8 0830 519.0 517.6 854.7 OPEN 5.8 5.8 0845 522.3 521.2 1.6 CLOSED 0.4 0.4 0900 522.3 521.2 1.0 CLOSED 0.0 0.0 0915 521.9 520.9 0.7 CLOSED 0.0 0.0 0930 520.9 519.8 0.4 CLOSED 0.0 0.0 0945 519.7 518.7 0.3 CLOSED 0.0 0.0 1000 518.7 517.6 0.2 CLOSED 0.0 0.0 1015 516.5 515.5 3.7 CLOSED 0.0 0.0 1030 514.3 512.7 0.5 CLOSED 0.0 0.0 1045 511.4 509.0 0.6 CLOSED 0.0 0.0 1100 507.9 505.0 1.0 CLOSED 0.0 0.0 1115 504.7 502.9 1.3 CLOSED 0.0 0.0 1130 501.5 499.7 1.4 CLOSED 0.0 0.0 1145 497.8 496.5 1.5 CLOSED 0.0 0.0 1200 493.4 493.3 1.5 CLOSED 0.0 0.0 1215 489.6 489.7 2.2 CLOSED 0.0 0.0 1230 486.4 486.6 2.1 CLOSED 0.0 0.0 1245 483.1 403.3 2.0 CLOSED 0.0 0.0 1300 479.7 479.9 2.0 CLOSED 0.0 0.0 1315 476.5 476.7 2.1 CLOSED 0.0 0.0 1330 473.0 472.6 1.7 CLOSED 0.0 0.0 1345 468.1 467.3 1.7 CLOSED 0.0 0.0 1400 463.2 461.7 1.1 CLOSED 0.0 0.0 1415 458.9 456.5 1.7 CLOSED 0.0 0.0 1430 454.5 451.0 1.6 CLOSED 0.0 0.0 1445 450.3 445.7 1.6 CLOSED 0.0 0.0 1500 446.4 440.6 1.6 CLOSED 0.0 0.0 Units -> (*F) (*F) (psig) (Mppm) (Mppm) Condenser Hotwell CST Level AFP Flow MDFP Time Level Press. #1 #2 #1 #2 Flow 0800 4.0 4.6 46.5 46.5 0.0 0.0 0.0 0815 3.9 4.6 '5.0 46.0 0.0 0.0 0.0 0830 3.9 4.6 46.0 46.0 0.0 0.0 0.0 0845 3.0 3.5 37.0 37.0 27.0 27.0 0.0 0900 7.0 10.0 24.2 24.2 235.9 205.9 0.0 0915 7.0 10.0 21.4 21.4 57.1 53.2 0.0 0930 7.0 10.0 18.5 18.5 160.0 127.5 0.0 0945 7.0 10.0 15.7 15.7 151.3 142.1 0.0 1000 7.0 10.0 13.0 13.0 108.0 141.4 0.0 1015 7.0 10.0 10.2 10.2 0.0 306.7 0.0 1030 7.0 10.0 B.1 8.1 0.0 286.3 0.0 1045 7.0 10.0 7.3 7.3 0.0 278.0 0.0 1100 7.0 10.0 6.5 6.5 0.0 0.0 0.0 1115 7.0 10.0 5.6 5.6 0.0 0.0 0.0 1130 7.0 10.0 4.8 4.8 0.0 0.0 0.0 1145 7.0 10.0 3.9 3.9 0.0 0.0 0.0 1200 7.0 10.0 3.1 3.1 0.0 0.0 0.0 1215 7.0 10.0 2.3 2.3 0.0 0.0 0.0 1230 7.0 10.0 1.4 1.4 0.0 0.0 0.0 1245 7.0 10.0 0.6 0.6 0.0 0.0 0.0 1300 7.0 10.0 0.0 0.0 0.0 0.0 0.0 1315 7.0 10.0 0.0 0.0 0.0 0.0 0.0 1330 7.0 10.0 0.0 0.0 0.0 0.0 0.0 1345 7.0 10.0 0.0 0.0 0.0 0.0 0.0 1400 7.0 10.0 0.0 0.0 0.0 0.0 0.0 1415 7.0 10.0 0.0 0.0 0.0 0.0 0.0 1430 7.0 10.0 0.0 0.0 0.0 0.0 0.0 1445 7.0 10.0 0.0 0.0 0.0 0.0 0.0 1500 7.0 10.0 0.0 0.0 0.0 0.0 0.0 Units -> (ft) (in. Hg) (ft) (ft) (gpm) (gpm) (gpm)
7-61 1993 Evaluated Exercise PLANT PARAMETERS DATA
SUMMARY
O E1ectriea1 Buses . . . . . . . . . . . . EDG Time A B C1 C2 D1 D2 #1 0800 NORM NORM NORM NORM NORM NORM OFF 0815 NORM NORM NORM NORM NORM NORM OFF 0830 NORM NORM NORM NORM NORM NORM OFF 0845 NORM NORM NORM NORM NORM NORM OFF 0900 NORM NORM NORM NORM NORM NORM OFF 0915 NORM NORM NORM NORM NORM NORM OFF , 0930 NORM NORM NORM NORM NORM NORM OFF i 0945 NORM NORM NORM NORM NORM NORM OFF s 1000 NORM NORM NORM NORM NORM NORM' OFF 1015 NORM NORM NORM NORM NORM NORM OFF 1030 NORM NORM NORM NORM NORM NORM OFF 1045 NORM NORM NORM NORM NORM NORM OFF 1100 NORM NORM NORM NORM NORM NORM OFF 1115 NORM NORM NORM NORM NORM NORM OFF 1J30 NORM NORM NORM NORM NORM NORM ON 1145 NORM NORM NORM NORM NORM NORM OFF 1200 NORM NORM NORM NORM NORM NORM OFF 1215 NORM NORM NORM NORM NORM NORM OFF 1230 NORM NORM NORM NORM NORM NORM OFF 1245 NORM NORM NORM NORM NORM NORM OFF 1300 NORM NORM NORM NORM NORM NORM OFF 1315 NORM NORM NORM NORM NORM NORM OFF , 1330 NORM NORM NORM NORM NORM NORM OFF 1345 NORM NORM NORM NORM NORM NORM OFF 1400 NORM NORM NORM NORM NORM NORM OFF 1415 NORM NORM NORM NORM NORM NORM OFF 1430 NORM NORM NORM NORM NORM NORM OFF 1445 NORM NORM NORM NORM NORM NORM OFF 1500 NORM NORM NORM NORM NORM NORM OFF g =============================================================================== EDG 480 250/125 Inst. Generator Instr. Serv. Time #2 VAC VAC AC Wattmeter Air Air 0800 OFF NORM NORM NORM 898.7 NORM NORM-0815 OFF NORM NORM NORM 898.9 NORM NORM , 0830 OFF NORM NORM NORM 898.6 NORM NORM 0845 OFF NORM NORM NORM 0.0 NORM NORM l 0900 OFF NOT NORM NORM NORM 0.0 NORM NORM ' 0915 OFF NOT NORM NORM NORM 0.0 NORM NORM 0930 OFF NOT FORM NORM NORM 0.0 NORM NORM 0945 OFF NOT NORM NORM NORM 0.0 NORM NORM 1000 OFF NOT NORM NORM NORM 0.0 NORM NORM 1015 OFF NOT NORM NORM NORM 0.0 NORM NORM-1030 OFF NOT NORM NORM NORM 0.0 NORM NORM 1045 OFF NOT NORM NORM NORM 0.0 NORM NORM l 1100 OFF NOT NORM NORM NORM 0.0 NORM NORM i 1115 OFF NOT NORM NORM NORM 0.0 NORM NORM l 1130 ON NOT NORM NORM NORM 0.0 NORM NORM i 1145 OFF NOT NORM NORM NORM 0.0 NORM NORM l 1200 OFF NOT NORM NORM NORM 0.0 NORM NORM : 1215 OFF NOT NORM NORM NORM 0.0 NORM NORM 1230 OFF NOT NORM NORM NORM 0.0 NORM NORM l i 1245 OFF NOT NORM NORM NORM 0.0 NORM NORM i 1300 OFF NOT NORM NORM NORM 0.0 NORM NORM 1315 OFF NOT NORM NORM NORM 0.0 NORM NORM 1330 OFF NOT NORM NORM NORM 0.0 NORM NORM 1345 OFF NOT NORM NORM NORM 0.0 NORM NORM 1400 OFF NOT NORM NORM NORM 0.0 NORM NORM 1415 OFF NOT NORM NORM NORM 0.0 NORM NORM 1430 OFF NOT NORM NORM NORM 0.0 NORM NORM i 1445 OFF NOT NORM NORM NORM 0.0 NORM NORM l 1500 OFF NOT NORM NORM NORM 0.0 NORM NORM Units -> (MW)
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7-62 1993 Evaluated Exercise PLANT PARAMETERS DATA
SUMMARY
Spent Fuel Pool CCW Surge Tank Level CCW Hx Outlet Temp. Time Level Temp. #1 #2 #1 #2 0800 23.5 100.1 51.0 52.0 95.0 93.4 0815 23.5 100.0 51.0 52.0 93.4 95.0 0830 23.5 99.9 51.0 52.0 93.4 95.0 0845 23.5 99.8 51.0 52.0 93.4 95.0 0900 23.5 99.8 51.0 52.0 93.4 94.5 0915 23.5 99.7 51.0 52.0 93.4 94.7 0930 23.5 99.7 51.0 52.0 93.4 95.0 0945 23.5 99.6 51.0 52.0 93.4 95.0 1000 23.5 99.6 51.0 52.0 93.4 94.9 1015 23.5 99.6 51.0 52.0 93.4 94.8 1030 23.5 99.6 51.0 52.0 93.4 94.5 1045 23.5 99.6 51.0 52.0 93.4 94.6 1100 23.5 99.6 50.0 51.0 95.2 95.0 1115 23.5 99.6 50.0 51.0 88.2 93.4 1130 23.5 99.7 50.0 51.0 85.6 95.2 1145 23.5 99.7 50.0 51.0 79.6 81.4 1200 23.5 99.9 50.0 51.0 78.5 79.4 1215 23.5 99.9 49.0 50.0 78.3 78.9 1230 23.5 99.9 49.0 50.0 78.3 78.8 1245 23.5 99.9 49.0 50.0 78.3 78.8 1300 23.5 100.0 49.0 50.0 78.3 78.8 1315 23.5 100.0 49.0 50.0 78.3 78.8 1330 23.5 100.0 49.0 50.0 78.4 105.8 1345 23.5 100.1 48.0 49.0 79.5 100.4 1400 23.5 100.1 48.0 49.0 79.7 95.8 1415 23.5 100.1 48.0 49.0 79.8 92.1 1430 23.5 100.2 48.0 49.0 79.9 88.4 1445 23.5 100.2 48.0 49.0 79.9 86.3 1500 23.5 100.2 48.0 49.0 80.0 82.2 Units -> (ft) (*F) (in.) (in.) (*F) (*F) O
7-63 1993 Evaluated Exercise i t \ 7.3 PLANT PARAMETERS SHEETS This section provides individual. control Room parameter data sheets to' be passed out to Players on a 15 minute basis should.the Control Room simulator become unavailable to conduct the Exercise. ,- g -h t k P l
DAVIS-BESSE NUCLEAR POWER STATION PLANT PARAMETER SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 0800 To: Control Room Operators T: 00/00 THIS IS A DRILL DO NOT initiate actions affecting normal operations. REACTOR COOLANT CONTAINMENT RCS Pressure 2170.4 psig CTMT Pressure 14.9 psia T Avg. 581.7 *F CTMT Temperature 89.3 *F T hot /T cold 605.5/ 557.8 'F CTMT Radiation (see separate RE Data Sheet) Coron concentration 650.0 ppm CTMT Sump Level 0.5 ft RCS Subcool. Marg. 43.1 F P2R Temperature 648.4 *F STEAM GENERATORS PZR Level 221.8 in S/G 1 Level / Pressure 194.3 in/ 910.5 psig RCD Flow (Loop 1/2) 76.6/ 76.0 Mpph S/G 2 Level / Pressure 200.7 in/ 910.1 psig PORV AUTO Block Valve OPEN S/G Shell Temp. (1/2) 518.8 *F/ 517.9 F Cpray Valve AUTO Block Valve OPEN Turbine Edr. Pressure 854.8 psig Lotdown Flow 75.4 gpm MSIV Position OPEN -4 RCP Seal Flows 33.6 gpm (TOTAL) $ 1-1 7.6 gpm 2-1 8.0 gpm FEED & CONDENSATE o 1-2 8.7 gpm 2-2 8.4 gpm Main FW Flow (Loop 1/2) 5.8/ 5.8 Mppm quanch Tank Level / Pressure 8.7 ft/ 24.7 psig Hotwell Level / Press. 4.0 ft/ 4.6 in Hg CST Level (1/2) 46.5/ 46.5 ft REACTOR CORE Aux. Fleed Flow (1/2) 0.0/ O.0 gpm Source Range Level (NI-1/NI-2) 0.1/ 0.1 cps Motor Driven Feed Pump Flow 0.0 gpm Intermediate Range (NI-3/NI-4)O.633E-04/O.620E-04 amps Power Range (NI-5/NI-6) 99.9/ 100.1 % ELECTRICAL (NI-7/NI-8) 99.9/ 100.1 % BUS A/B NORM / NORM Core Thermocouple (HIGHEST) 615.6 *F BUS C1/C2 NORM / NORM BUS D1/D2 NORM / NORM MAKEUP AND ECCS EDG 1/2 OFF/OFF MHeup Flow 17.6 gpm 480 VAC Distribution NORM Makeup Tank Level / Press. 66.1 in/ 30.0 psig 250 VAC/125 VAC Dist. NORM CFT 51 Level / Press. 12.9 ft/ 605.7 psig Inst. AC NORM - CFT 82 Level / Press. 12.9 ft/ 605.6 psig Generator Wattmeter (Gross) 898.7 Mw $ w HPI Line Flow (1-1) 0.0/(1-2) 0.0 (2-1) 0.0/(2 '1) 0.0 m LPI Line Flow (1-1) 0.0/(1-73 0.0 gpm OTHER DHR HI Inlet Temp. (1/2) 70.0/ 70.0 *F Instrument / Service Air NORM /NORH $ CTNT Spray Flow (1/2) 0.0/ 0.0 gpm Spent Fuel Pool Level / Temp. 23.5 ft/ 100.1 *F c CCW Surge Tank Level (1/2) 51.0/ 52.0 in % BWST Level 40.4 ft CCW Hz Outlet Temp. 95.0/ 93.4 *F 0 4 M M n e O O O
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( a DAVIS-BESSE NUCLEAR POWER STATION PLANT PARAMETER SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 0815 I TO: Control Room Operators T: 00/15 THIS IS A DRILL DO NOT initiate actions affecting normal operations. REACTOR COOLANT CONTAINMENT RCS Pressure 2170.2 psig CTMT Pressure 14.9 psia T Avg. 581.7 *F CTMT Temperature 89.2 *F T hot /T cold 605.5/ 557.8 *F CTMT Radiation (see separate RE Data Sheet) coron concentration 650.0 ppm CTMT Sump Level 0.5 ft , RCS Subcool. Marg. 43.1 F i PZR Temperature 648.0 *F STEAM GENERATORS P2R Level 222.0 in S/G 1 Level / Pressure 194.2 in/ 911.0 psig RCS Flow (Loop 1/2) 76.6/ 76.0 Mpph S/G 2 Level / Pressure 200.6 in/ 910.2 psig PORV AUTO Block Valve OPEN S/G Shell Temp. (1/2) 518.9 *F/ 517.6 F L Spray Valve AUTO Block Valve OPEN Turbine Edr. Pressure 855.0 psig Letdown Flow 75.3 gpm MSIV Position OPEN -J RCP Seal Flows 33.8 gpm (TOTAL) 1 l 1-1 7.7 gpm 2-1 8.0 gym FEED & CONDENSATE vi 1-2 8.7 gpm 2-2 8.4 gpm Main FW Flow (Loop 1/2) 5.8/ 5.8 Mppm Qusnch Tank Level / Pressure 8.7 ft/ 24.7 psig Hotwell Level / Press. 3.9 ft/ 4.6 in Bg CST Level (1/2) 46.0/ 46.0 ft REACTOR CORE Aux. Fleed Flow (1/2) 0.0/ 0.0 gpm Source Range Level (NI-1/NI-2) 0.1/ 0.1 cps Motor Driven Feed Pump Flow 0.0 gpm l Intermediate Range (NI-3/NI-4)0.633E-04/0.620E-04 amps Power Range (NI-5/NI-6) 99.9/ 100.1 1 ELECTRICAL (NI-7/NI-8) 99.8/ 100.1 % BUS A/B NORM / NORM Core Thermocouple (HIGHEST) 616.0 *F BUS C1/C2 NORM / NORM BUS D1/D2 NORM / NORM MAKEUP AND ECCS EDG 1/2 OFF/OFF Wakeup Flow 18.3 gpm 480 VAC Distribution NORM Makeup Tank Level / Press. 66.1 in/ 30.0 psig 250 VAC/125 VAC Dist. NORM CFT 51 Level / Press. 12.9 ft/ 605.6 psig Inst. AC NORM H CFT 82 Level / Press. 12.9 ft/ 605.6 psig Generator Wattmeter (Gross) 898.9 Mw $ w HPI Line Flow (1-1) 0.0/(1-2) 0.0 (2-1) 0.0/(2-2) 0.0 to LPI Line Flow (1-1) 0.0/(1-2) 0.0 gpm OTHER 4 DHR Ex Inlet Temp. (1/2) 70.0/ 70.0 *F Instrument / Service Air NORM / NORM $ CTNT Spray Flow (1/2) 0.0/ 0.0 gpm Spent Fuel Pool Level / Temp. 23.5 ft/ 100.0 *F C CCW Surge Tank Level (1/2) 51.0/ 52.0 in % BWST Level 40.4 ft CCW Ex Outlet Temp. 93.4/ 95.0 *F. e
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DAVIS-BESSE NUCLEAR POWER STATION PLANT PARAMETER SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 0830 TO: Control Room Operators T: 00/30 THIS IS A DRILL DO NOT initiate actions affecting normal operations. REACTOR COOLANT CONTAINMENT iMS Pressure 2171.3 psig CTMT Pressure 14.9 psia T Avg. 581.7 *F CTNT Temperature 89.4 *F T hot /T cold 605.5/ 557.8 'F CTMT Radiation (see separate RE Data Sheet) Coron concentration 650.0 ppm CTHT Sump Level 0.5 ft RCS Subcool. Marg. 43.1 F PZR Temperature 648.1 'F STEAM GENERATORS P2R Level 221.4 in S/G 1 Level / Pressure 194.4 in/ 910.7 psig RCS Flow (Loop 1/2) 76.6/ 76.1 Mpph S/G 2 Level / Pressure 200.8 in/ 909.9 psig PORV AUTO Block Valve OPEN S/G Shell Temp. (1/2) 519.0 "F/ 517.6 F Cpray Valve AUTO Block Valve OPEN Turbine Bdr. Pressure 854.7 psig Latdown Flow 75.4 gpm MSIV position OPEN -J RCP Seal Flows 33.7 gpm (TOTAL) $ 1-1 7.6 gpm 2-1 8.0 gpm FEED & CONDENSATE m 1-2 8.7 gpm 2-2 8.4 gpm Main FW Flow (Loop 1/2) 5.8/ 5.8 Mppm Quznch Tank Level / Pressure 8.7 ft/ 24.7 psig Hotwell Level / Press. 3.9 ft/ 4.6 in Hg CST Level (1/2) 46.0/ 46.0 ft REACTOR CORE Aux. Fleed Flow (1/2) 0.0/ O.0 gpm Source Range Level (NI-1/NI-2) 0.1/ 0.1 cps Motor Driven Feed Pump Flow 0.0 gpm Intermediate Range (NI-3/NI-4)0.633E-04/0.621E-04 amps Power Range (NI-5/NI-6) 100.0/ 100.2 % ELECTRICAL (NI-7/NI-8) 99.9/ 100.1 % BUS A/B NORM / NORM Core Thermocouple (HIGHEST) 615.2 'F BUS C1/C2 NORM / NORM BUS D1/D2 NORM / NORM MAKEUP AND ECCS EDG 1/2 OFF/OFF Makeup Flow 17.5 gpm 480 VAC Distribution NORM Makeup Tank Level / Press. 66.1 in/ 30.0 poig 250 VAC/125 VAC Dist. NORM CFT $1 Level / Press. 12.9 ft/ 605.9 psig Inst. AC NORM M CFT 82 Level / Press. 12.9 ft/ 605.9 psig Generator Wattmeter (Gross) 898.6 Mw $ w HPI Line Flow (1-1) 0.0/(1-2) 0.0 (2-1) 0.0/(2-2) 0.0 m LPI Line Flow (1-1) 0.0/(1-2) 0.0 gpm OTHER DHR Ex Inlet Temp. (1/2) 70.0/ 70.0 *F Instrument / Service Air NORM / NORM $ c CTMT Spray Flow (1/2) 0.0/ 0.0 gpm Spent Fuel Pool Level / Temp. CCN Surge Tank Level (1/2) 23.5 ft/ 99.9 "F 51.0/ 52.0 in % BNST Level 40.4 ft CCW Ex Outlet Temp. 93.4/ 95.0 *F e
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% ,q DAVIS-BESSE NUCLEAR PONER STATION PLANT PARAMETER SHEET SCENARIO NO. 1993 Evaluated Exercise._ TIME: 0945 TO: Control Room Operators T 00/45 THIS IS A DRILL DO NOT initiate actions affecting normal operations.
REACTOR COOLANT CONTAINMENT iiCS Pressure 2052.3 psig CTNT Pressure 14.9 psia T. Avg. 551.9 *F CTNT Temperature 89.4 "F T hot /T cold 552.5/ 551.2 *F CTNT Radlation (see separate RE Data Sheet) Eoron concentration 652.0 ppm CTHT Sump Level O.5 ft RCS Subcool. Marg. 88.0 F PER Temperature 641.5 "F STEAM GENERATORS PZn Level 101.7 in S7G 1 Level / Pressure 50.8 in/ 997.0 psig RCS Flow (Loop 1/2) 81.3/ 36.5 Mpph S/G 2 Level / Pressure 51.1 in/ 997.1 psig PORV AUTO Block Valve OPEN S/G Shell Temp. (1/2) 522.3 "F/ 521.2 F Spray Valve AUTO Block Valve OPEN Turbine Bdr. Pressure 1.6 psig Lotdown Flow 74.2 gpm MSIV Position CLOSED w RCP Seal Flows 32.6 gpm (TOTAL) 1 1-1 9.2 gpm 2-1 9.7 gpm FEED & CONDENSATE 4 1-2 4.2 gpm 2-2 9.5 9pe Main FW Flow (Loop 1/2) 0.4/ O.4 Mppm Qu:nch Tank Level / Pressure 8.7 ft/ 24.7 psig Hotwell Level / Press. 3.0 ft/ 3.5 in Hg CST Level (1/2) 37.0/ 37.0 ft REACTOR CORE Aux. Fleed Flow (1/2) 27.0/ 27.0 gpm Source Range Level (NI-1/NI-2) 0.1/ O.1 cps Motor Driven Feed Pump Flow 0.0 gpm Intermediate Range (NI-3/NI-4)O.101E-10/O.100E-10 amps Power Range (NI-5/NI-6) 0.0/ O.0 % ELECTRICAL (NI-7/NI-8) 0.0/ O.0 % BUS A/B NORH/ NORM Core Thermocouple (HIGHEST) 586.2 "F BUS C1/C2 NORM / NORM BUS D1/D2 NORM / NORM MAKEUP AND ECCS EDG 1/2 OFF/OFF iiiEeup Flow 54.5 9pm 480 VAC Distribution NORM Makeup Tank Level / Press. 83.5 in/ 30.0 psig 250 VAC/125 VAC Dist. NORM CFT 81 Level / Press. 12.9 ft/ 606.1 psig Inst. AC NORM P CFT $2 Level / Press. 12.9 ft/ 606.1 psig Generator Wattmeter (Gross) 0.0 Mw $ w HPI Line Flow (1-1) 0.0/(1-2) 0.0 (2-1) 0.0/(2-2) 0.0 n LPI Line Flow (1-1) 0.0/(1-2) 0.0 gpm OTHER < DHR Ex Inlet Temp. (1/2) 70.0/ 70.0 *F Instrument / Service Air NORM / NORM h CTNT Spray Flow (1/2) 0.0/ O.0 gpm Spent Fuel Pool Level / Temp. 23.5 ft/ 99.8 "F c CCN Surge Tank Level (1/2) 51.0/ 52.0 in % ENST Level 40.3 ft CCN ax Outlet Temp. 93.4/ 95.0 *F e CL M e 2 e _ _ _ _ _ _ _ . _ _ _ _ ________________.__m _ _ _ _ _ _ _ _ _ _ _ _ -__ _
DAVIS-BESSE NUCLEAR POWER STATION PLANT PARAMETER SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 0900 TO: Control Room Operators T: 01/00 THIS IS A DRILL DO NOT initiate actions affecting normal cperations. REACTOR C00LANT CONTAINMENT RCS Pressure 2148.4 psig CTMT Pressure 14.9 psia T Avg. 549.1 "F CTMT Temperature 89.4 'F T hot /T cold 549.7/ 548.5 'F CTNT Radiation (see separate RE Data Sheet) Eoron Concentration 671.7 gpm CTMT Sump Level O.5 ft RCS Subcool. Marg. 97.4 r PZR Temperature 648.1 'r STEAM GENERATORS P2R Level 102.7 in S/G 1 Level / Pressure 50.9 in/ 972.3 psig RCS Flow (Loop 1/2) 81.8/ 36.6 Mpph S/G 2 Level / Pressure 50.9 in/ 971.0 psig PORV AUTO Block Valve OPEN S/G Shell Temp. (1/2) 522.3 'F/ 521.2 F Spray Valve AUTO Block Valve OPEN Turbine Bdr. Pressure 1.0 psig Lotdown Flow 75.2 gpm MSIV Position CLOSED -J RCP Seal Flows 32.2 gpm (TOTAL) $ 1-1 9.1 gpm 2-1 9.6 gpm FEED 5, CONDENSATE cn 1-2 4.1 gpm 2-2 9.4 gpm Main FW Flow (Loop 1/2) 0.0/ O.0 Mppm Qusnch Tank Level / Pressure 8.7 ft/ 24.7 psig Hotwell Level / Press. 7.0 ft/ 10.0 in Hg CST Level (1/2) 24.2/ 24.2 ft REACTOR CORE Aux. Fleed Flow (1/2) 235.9/ 205.9 gpm Source Range Level (NI-1/NI-2) B.8/ 8.2 cps Motor Driven Feed Pump Flow 0.0 gpm Intermediate Range (NI-3/NI-4)O.101E-10/O.100E-10 amps l Power Range (NI-5/NI-6) 0.0/ O.0 1 ELECTRICAL (NI-7/NI-8) 0.0/ O.0 % BUS A/B NORM / NORM Core Thermocouple (HIGHEST) 558.1 'r BUS C1/c2 NORM / NORM BUS D1/D2 NORM / NORM MAKEUP AND ECCS EDG 1/2 OFF/OFF M'.keup Flow 89.4 gpm 480 VAC Distribution NOT NORM M:keup Tank Level / Press. 71.3 in/ 30.0 psig 250 VAC/125 VAC Dist. NORM CFT 81 Level / Press. 12.9 ft/ 606.3 psig Inst. AC NORM M CFT 82 Level / Press. 12.9 ft/ 606.3 psig Generator Wattmeter (Gross) 0.0 Mw $ , HPI Line Flow (1-1) 0.0/(1-2) 0.0 w (2-1) 0.0/(2-2) 0.0 m LPI Line Flow (1-1) 0.0/(1-2) 0.0 gpm OTHER DHR Hz Inlet Temp. (1/2) 70.0/ 70.0 *F Instrument / Service Air NORM / NORM h CINT Spray Flow (1/2) 0.0/ O.O gpm Spent Fuel Pool Level / Temp. 23.5 ft/ 99.C *F C CCW Surge Tank Level (1/2) 51.0/ 52.0 in $ ENST Level 40.2 ft CCW Fx Outlet Temp. 93.4/ 94.5 'F G D-
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m m m DAVIS-BESSE NUCLEAR POWER STATION PLANT PARAMETER SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 0915 TO: Control Room Operators T: 01/15 THIS IS A DRILL DO NOT initiate actions affecting uormal operations. REACTOR COOLANT CONTAINMENT RdS Pressure 2108.9 psig CTMT Pressure 14.9 psia T Avg. 529.5 "F CTMT Temperature 89.5 "F T hot /T cold 529.8/ 529.3 "P CTMT Radiation (see separate RE Data Sheet) Eoron Concentration 672.6 ppm CTMT Sump Level O.5 ft RCS Subcool. Marg. 114.7 F PZH Temperature 642.9 "F STEAM GENERATORS PZR Level 105.3 in S/G 1 Level / Pressure 51.5 in/ 843.0 psig RCs Flow (Loop 1/2) 83.6/ 37.6 Mpph S/G 2 Level / Pressure 51.6 in/ 840.6 psig PORV AUTO Ble:::k Valve OPEN S/G Shell Temp. (1/2) 521.9 "F/ 520.9 F Spray valve AUTO Block Valve OPEN Turbine Rdr. Pressure 0.7 psig Lotdown Flow 74.7 gpm MSIV Position CLOSED -J RCP Seal Flows 32.3 gpm (TOTAL) $ l-1 9.2 gpm 2-1 9.6 gpm FEED & CONDENSATE w 1-2 4.1 gpm 2-2 9.4 gpm Main Fw Flow (Loop 1/2) 0.0/ O.0 Mppm quench Tank Level / Pressure 8.7 ft/ 24.7 psig Hotwell Level / Press. 7.0 ft/ 10.0 in Hg CST Level (1/2) 21.4/ 21.4 ft REACTOR CORE Aux. Fleed Flow (1/2) 57.1/ 53.2 gpm Source Range Level (NI-1/NI-2) 7.4/ 6.7 cps Motor Driven Feed Pump Flow 0.0 gpm Intermediate Range (NI-3/NI-4)O.101E-10/O.100E-10 amps Power Range (NI-5/NI-6) 0.0/ O.0 % ELECTRICAL (NI-7/NI-B) 0.0/ O.0 % BUS A/B NORM / NORM Core Thermocouple (HIGHEST) 540.5 "F BUS C1/C2 NORM / NORM BUS D1/D2 NORM / NORM MAKEUP AND ECCS EDG 1/2 OFF/OFF Rikeup rlow 146.6 gpm 480 VAC Distribution NOT NORM Hr.keup Tank Level / Press. B3.8 in/ 30.0 psig 250 VAC/125 VAC Dist. NORM CFT 81 Level / Press. 12.9 ft/ 606.5 psig Inst. AC NORM w CFT 82 Level / Press. 12.9 ft/ 606.5 psig Generator Wattmeter (Gross) 0.0 Mw $ HPI Line Flow (1-1) 0.0/(1-2) 0.0 w (2-1) 0.0/(2-2) 0.0 m LPI Line Flow (1-1) 0.0/(1-2) 0.0 gpa OTHER 4 DHR Hz Inlet Temp. (1/2) 70.0/ 70.0 "F Instrument / Service Air NORM / NORM $ CTNT Spray Flow (1/2) 0.0/ O.0 gpm Spent Fuel Pool Level / Temp. 23.5 ft/ 99.7 *F c CCW Surge Tank Level (1/2) 51.0/ 52.0 in % BWST Level 40.1 ft CCW Ex Outlet Temp. 93.4/ 94.7 *F e ......................**...................................... ....... **....****..***** ...........***...... D-M i 2 e
DAVIS-BESSE NUCLEAR POWER STATION PLANT PARAMETER SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 0930 TO: Control Room Operators T: 01/30 THIS IS A DRILL DO NOT initiate actions affecting normal operations. REACTOR COOLANT CONTAINMENT iics Pressure 2006.0 psig UMT Pressure 14.9 psia 529.6 *F CTMr Temperature 89.6 'F T T Avp/T ho. cold 529.9/ 529.1 'F CTMT Radiation (see separate RE Data Sheet) Eoron Concentration 701.7 ppe CTMT Sump Level 0.5 ft RCS Subcool. Marg. 107.4 F PER Temperature 638.6 *F STEAM GENERATORS PZn Level 113.0 in S/G 1 Level / Pressure 51.3 in/ B30.9 psig RCS Flow (Loop 1/2) 83.5/ 37.5 Mpph S/G 2 Level / Pressure 51.2 in/ 830.3 psig POHV AUTO Block Valve OPEN S/G Shell Temp. (1/2) 520.9 "F/ 519.8 F Spray Valve AUTO Block Valve OPEN Turbine Bdr. Pressure 0.4 psig Latdown Flow 73.7 gpm MSIV Position CLOSED J C.CP Seal Flows 32.8 gpm (TOTAL) $ 1-1 5.2 gpm 2-1 9.7 gpm FEED & CONDENSATE o 1-2 4.4 gpm 2-2 9.5 gpa Main FW Flow (Loop 1/2) 0.0/ 0.0 Mppm Qucach Tank Level / Pressure 8.7 ft/ 24.7 psig Hotwell Level / Press. 7.0 ft/ 10.0 in Hg CST Level (1/2) 18.5/ 18.5 ft REACTOR CORE Aux. F1eed Flow (1/2) 160.0/ 127.5 gpm Source Range Level (NI-1/NI-2) 6.9/ 6.6 cps Motor Driven Feed Pump Flow 0.0 gpm Intermediate Range (NI-3/HI-4)O 101E-10/0.100E-10 amps Pow 2r Range (NI-5/NI-6) 0.0/ 0.0 % ELECTRICAL BUS A/B (NI-7/NI-8) 534.5 0.0/
*F 0.0 %
BUS C1/C2 NORM / NORM NORM / NORM j Core Thermocouple (HIGHEST) BUS D1/D2 NORM / NORM MAKEUP AND ECCS EDG 1/2 OFF/0FF Makeup Flow 13.4 gpm 480 VAC Distribution NOT NORM Makeup Tank Level / Press. 83.4 in/ 30.0 psig 250 VAC/125 VAC Dist. NORM w CFT 81 Level / Press. 12.9 ft/ 606.7 psig Inst. AC NORM CFT 82 Level / Press. 12.9 ft/ 606.7 psig Generator Wattmeter (Gross) 0.0 Mw $ w HPI Line Flow (1-1) 0.0/(1-2) 0.0 (2-1) 0.0/(2-2) 0.0 m LPI Line Flow (1-1) 0.0/(1-2) 0.0 gpm OTHER DHR Ex Inlet Temp. (1/2) 70.0/ 70.0 'F Instrument / Service Air NORM / NORM h CTMT Spray Flow (1/2) 0.0/ O.0 gpm Spent Fuel Pool Level / Temp. 23.5 ft/ 99.7 'F c CCW Surge Tank Level (1/2) 51.0/ 52.0 in $ e EWST Level
.......................... ........................................................................'F 40.1 ft CCW Ex Outlet Temp. 93.4/ 95.0
.......... D-M 2
e O O O
r -- , ,q r% i DAVIS-BESSE NUCLEAR POWER STATION l PLANT PARAMETER SHEET l SCENARIO NO. 1993 Evaluated Exercise TIME: 0945 TO: Control Room Operators T: 01/45 THIS IS A DRILL DO NOT initiate actions affecting normal operations. REACTOR COOLANT CONTAINMENT RCS Pressure 1991.4 psig CTMr Pressure 14.9 psia T Avg. 524.0 'F CTMT Temperature 89.7 'F T hot /T cold 524.6/ 523.5 'F CTMT Radiation (see separate RE Data Sheet) Eoron Concentration 702.8 ppe CTMT Sump Level 0.5 ft RCS Subcool. Marg. 111.7 F PER Temperature 636.4 *F STEAM GENERATORS PZ3 Level 103.1 in S/G 1 Level / Pressure 51.2 in/ 787.6 psig RCS Flow (Loop 1/2) 84.0/ 37.7 Mpph S/G 2 Level / Pressure 51.2 in/ 787.3 psig PORV AUTO Block Valve OPEN S/G Shell Temp. (1/2) 519.7 'F/ 518.7 F Spray Valve AUTO Block Valve OPEN Turbine Bdr. Pressure 0.3 psig Letdown Flow 73.7 gpm MSIV Position CLOSED -J RCP Seal Flows 32.3 gpm (TOTAL) $ 1-1 9.3 gpm 2-1 9.8 gpm FEED & CONDENSATE P 1-2 4.6 gpm 2-2 9.6 gpm Main FW Flow (Loop 1/2) 0.0/ O.0 Mppm Qusnch Tank Level / Pressure 8.7 ft/ 24.7 psig Hotwell Level / Press. 7.0 ft/ 10.0 in Hg CST Level (1/2) 15.7/ 15.7 ft REACTOR CORE Aux. Fleed Flow (1/2) 151.3/ 142.1 gpm Source Range Level (NI-1/NI-2) 6.9/ 6.6 cps Motor Driven Feed Pump Flow 0.0 gpm Intermediate Range (NI-3/NI-4)0.101E-10/0.100E-10 amps Power Range (NI-5/NI-6) 0.0/ O.0 % ELECTRICAL (NI-7/NI-8) 0.0/ O.0 % BUS A/B NORM / NORM Core Thermocouple (HIGHEST) 529.6 'F BUS C1/c2 NORM / NORM BUS D1/D2 NORM / NORM MAKEUP AND ECCS EDG 1/2 OFF/OFF Makeup Flow 102.7 gpm 480 VAC Distribution NOT NORM Makeup Tank Level / Press. 74.2 in/ 30.0 psig 250 VAC/125 VAC Dist. NORM CFT 51 Level / Press. 12.9 ft/ 606.9 psig Inst. AC NORM N CFT 82 Level / Press. 12.9 ft/ 606.8 psig Generator Wattmeter (Gross) 0.0 Mw $' w HPI Line Flow (1-1) 0.0/(1-2) 0.0 (2-1) 0.0/(2-2) 0.0 m LPI Line Flow (1-1) 0.0/(1-2) 0.0 gpa OTHER DHR Hz Inlet Temp. (1/2) 70.0/ 70.0 'F Instrument / Service Air NORM / NORM $ c CTMT Spray Flow (1/2) 0.0/ 0.0 gpm Spent Fuel Pool Level / Temp. 23.5 ft/ 99.6 'F CCW Surge Tank Level (1/2) 51.0/ 52.0 in % BNST Level 40.1 ft CCW Hz Outlet Temp. 93.4/ 95.0 2-
.............**..................******.......** ...**........................ ..**.............** .'r......... D-M e
2
; a
DAVIS-BESSE NUCLEAR POWER STATION PLANT PARAMETER SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 1000 TO: Control Room Operators T: 02/00 THIS IS A DRILL DO NOT initiate actions affecting normal operations. REACTOR COOLANT CONTAINMENT iidS Pressure 1916.3 psig CTMT Pressure 14.9 psia T Avg. 520.0 'F CTNT Temperature 89.7 *F T hot /T cold 514.2/ 513.5 *F CTNT Radiation (see separate RE Data Sheet) Coron concentration 713.2 ppm CTNT Sump Level 0.5 ft RCS Subcool. Marg. 116.7 F PZR Temperature 632.4 *F STEAM GENERATORS PZR Level 96.2 in S7G 1 Level / Pressure 51.4 in/ 722.4 psig RCS Flow (Loop 1/2) 84.8/ 38.0 Mpph S/G 2 Level / Pressure 51.1 in/ 714.1 psig PORV AUTO Block Valve OPEN S/G Shell Temp. (1/2) 518.7 "F/ 517.6 r Spray Valve AUTO Block Valve OPEN Turbine Bdr. Pressure 0.2 psig Letdown Flow 72.8 gpm MSIV Position CLOSED w RCP Seal Flows 32.8 gpm (TOTAL) 1 1-1 9.2 gpm 2-1 9.7 gpm FEED & CONDENSATE M 1-2 4.4 gpm 2-2 9.5 gpm Main FW Flow (Loop 1/2) 0.0/ 0.0 Mppm Qusnch Tank Level / Pressure 8.7 ft/ 24.7 psig Hotwell Level / Press. 7.0 ft/ 10.0 in Hg CST Level (1/2) 13.0/ 13.0 ft REACTOR CORE Aux. Fleed Flow (1/2) 108.0/ 141.4 gpm Source Range Level (NI-1/NI-2) 6.9/ 6.4 cps Motor Driven Feed Pump Flow 0.0 gpm Inter 1nediate Range (NI-3/NI-4)O.101E-10/O.100E-10 amps Power Range (NI-5/NI-6) 0.0/ 0.0 % ELECTRICAL (NI-7/NI-8) 0.0/ O.O % BUS A/B NORM / NORM Core Thermocouple (HIGHEST) 518.6 *F BUS C1/C2 NORM / NORM BUS D1/D2 NORM / NORM MAKEUP AND ECCS EDG 1/2 OFF/OFF M:keup Flow 14.0 gpm 480 VAC Distribution NOT NORM M keup Tank Level / Press. 77.8 in/ 30.0 psig 250 VAC/125 VAC Dist. NORM CFT $1 Level / Press. 12.9 ft/ 607.0 psig Inst. AC NORM +-- CFT 82 Level / Press. 12.9 ft/ 607.0 psig Generator Wattmeter (Gross) 0.0 Mw $ w HPI Line Flow (1-1) 0.0/(1-2) 0.0 (2-1) 0.0/(2-2) 0.0 m LPI Line Flow (1-1) 0.0/(1-2) 0.0 gpm OTHER < DHR Ex Inlet Temp. (1/2) 70.0/ 70.0 *F Instrument / Service Air NORM / NORM $ CTNT Spray Flow (1/2) 0.0/ 0.0 gpm Spent Fuel Pool Level / Temp. 23.5 ft/ 99.6 *F c CCW Surge Tank Level (1/2) 51.0/ 52.0 in % gwST Level 40.1 ft CCW Hz outlet Temp. 93.4/ 94.9 *F G
................................................................*** .**..**.......****.**.....**............. D-M S
2 0 e O O O - _
O O O DAVIS-BESSE NUCLEAR POWER STATION PLANT PARAMETER SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 1015 TO: Control Room Operators T: 02/15 THIS IS A DRILL DO NOT initiate actions affecting normal operations. REACTOR COOLANT CONTAINMENT RCS Pressure 1592.1 psig CTMT Pressure 14.9 psia T Avg. 520.0 'F CTMT Temperature 89.8 *F T hot /T cold 499.2/ 499.0 *F CTMT Radiation (see separate RE Data Sheet) Eoron Concentration 721.6 ppm CTMT Sump Level O.6 ft RCS Subcool. Marg. 106.3 F PZR Temperature 609.7 'F STEAM GENERATORS PZR Level 93.4 in S7'G 1 Level / Pressure 37.2 in/ 639.6 psig KCS Flow (Loop 1/2) 85.6/ 38.4 Mpph S/G 2 Level / Pressure 50.7 in/ 602.5 psig PORV AUTO Block Valve OPEN S/G Shell Temp. (1/2) 516.5 'F/ 515.5 F Spray Valve AUTO Block Valve OPEN Turbine Edr. Pressure 3.7 psig Letdown Flow 69.7 gpm MSIV Position CLOSED 4 RCP Seal Flows 33.2 gpm (TOTAL) .', 1-1 8.9 gpm 2-1 9.5 gpm FEED & CONDENSATE w 1-2 4.9 gpm 2-2 9.6 gpm Main rw Flow (Loop 1/2) 0.0/ O.0 Mppm Qusnch Tank Level / Pressure 8.7 ft/ 24.8 psig Hotwell Level / Press. 7.0 ft/ 10.0 in Mg CST Level (1/2) 10.2/ 10.2 ft REACTOR CORE Aux. Fleed Flow (1/2) 0.0/ 306.7 gpm Source e Level Rarg[e Range(NI-1/NI-2) 7.0/ 6.5 eps (NI-3/NI-4)O.101E-10/O.100E-10 amps Motor Driven Feed Pump Flav O.0 gpm Intermedia Power Range (NI-5/NI-6) 0.0/ O.0 % ELECTRICAL (NI-7/NI-8) 0.0/ O.0 % BUS A/B NORM / NORM Core Thermocouple (HIGHEST) 503.5 'F BUS C1/C2 NORM / NORM BUS D1/D2 NORM / NORM MAKEUP AND ECCS EDG 1/2 OFF/OFF Uakeup FTow 16.4 gpm 480 VAC Distribution NOT NORM Makeup Tank Level / Press. 80.4 in/ 30.0 psig 250 VAC/125 VAC Dist. NORM CFT I1 Level / Press. 12.9 ft/ 607.1 psig Inst. AC NORM 6-* CFT #2 Level / Press. 12.9 ft/ 607.1 psig Generator Wattmeter (Gross) 0.0 Mw $ HPI Line Flow (1-1) 0.0/(1-2) 0.0 w (2-1) 0.0/(2-2) 0.0 to LPI Line Flow (1-1) 0.0/(1-2) 0.0 gpm OTHER DHR Hx Inlet Temp. (1/2) 70.0/ 70.0 'F Instrument / Service Air NORM / NORM h CTMT Spray Flow (1/2) 0.0/ O.0 gpm Spent Fuel Pool Level / Temp. 23.5 ft/ 99.6 *F c CCW Surge Tank Level (1/2) 51.0/ 52.0 in % BNST Level o .........**.............**............**........... *********.**........**................./ 40.0 ft CCW Ex Outlet Temp. 93.4 94.8 'F
.................. CL O
t e
DAVIS-BESSE NUCLEAR POWER STATION PLANT PARAMETER SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 1030 TO: Control Room Operators T: 02/30 THIS IS A DRILL DO NOT initiate actions affecting normal operations. REACTOR COOLANT CONTAINMENT RCS Pressure 830.8 psig CTMT Pressure 14.9 psia T Avg. 520.0 "F CTNT Temperature 89.7 "F T hot /T cold 485.2/ 485.0 *F CTMT Radiation (see separate RE Data Sheet) coron Concentration 727.3 ppm CTMT Sump Level O.6 ft RCS Subcool. Marg. 39.7 F PZR Temperature 528.8 *F STEAM GENERATORS PZR Level 87.0 in S/G 1 Level / Pressure 45.9 in/ 556.2 psig RCS
- low (Loop 1/2) 85.6/ 38.6 Mpph S/o 2 Level / Pressure 51.2 in/ 527.0 psig PORV AUTO Block valve OPEN S/G Shell Temp. (1/2) 514.3 **/ 512.7 F Spray Valve AUTO Block Valve OPEN Turbine Edr. Pressure 3.5 psig Intdown Flow 58.7 gpm MSIV Position CLOSED -J RCP Seal Flows 33.2 gpm (TOTAL) b 1-1 8.9 gpm 2-1 9.5 gpm FEED & CONDENSATE 1-2 4.9 gpm 2-2 9.6 gpm Main rw Flow (Loop 1/2) 0.0/ O.0 Mppm Qusach Tank Level / Pressure 8.7 ft/ 24.8 psig Hotwell Level / Press. 7.0 ft/ 10.0 in Hg CST Level (1/2) 8.1/ 8.1 ft REACTOR CORE Aux. Fleed Flow (1/2) 0.0/ 286.3 gpm Source Range Level (NI-1/NI-2) 7.3/ 6.6 cps Motor Driven Feed Pump Flow 0.0 gpm Intermediate Range (NI-3/NI-4)O.101E-10/O.100E-10 amps Power Range (NI-5/NI-6) 0.0/ O.0 % ELECTRICAL BUS A/B (NI-7/NI-8) 0.0/ O.0 % NORM / NORM Core Thennocouple (HIGHEST) 492.2 "F BUS C1/C2 NORM / NORM BUS D1/D2 NORH/ NORM MAREUP AND ECCS EDG 1/2 OFF/OFF Mskeup Flow 21.6 gpm 480 VAC Distribution NOT NORM Mskeup Tank Level / Press. 77.6 in/ 30.0 psig 250 VAC/125 VAC Dist. NORM CFT $1 Level / Press. 12.9 ft/ 607.2 psig Inst. AC NORM CFT 82 Level / Press. 12.9 ft/ 607.2 psig Generator Wa.ttmeter (Gross) 0.0 Hw $
w HPI Line Flow (1-1) 0.0/(1-2) 0.0 (2-1) 0.0/(2-2) 0.0 m LPI Line Flow (1-1) 0.0/(1-2) 0.0 gpm OTHER DHR Ex Inlet Temp. (1/2) 70.0/ 70.0 *F Instrument / Service Air NORM / NORM h c CTMT Spray Flow (1/2) 0.0/ O.0 gpm Spent Fuel Pool Level / Temp. 23.5 ft/ 99.6 *F CCW Surge Tank Level (1/2) 51.0/ 52.0 in $ swST Level 40.0 ft CCW Hz Outlet Temp. 93.4/ 94.5 "F e
.................****.......................**....****..........................**..............***.......... a M
e 2 e O O O
3I C- %l DAVIS-BESSE NUCLEAR POWER STATION PLANT PARAMETER SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 1045 TO: Control Room Operators T: 02/45 THIS IS A DRILL DO NOT initiate actions affecting normal operations. REACTOR COOLANT CONTAINMENT RCS Pressure 723.5 psig CTMT Pressure 14.9 psia T Avg. 520.0 'F CTNT Temperature 89.6 'F T hot /T cold 464.8/ 463.5 "F CTMT Radiation (see separate RE Data Sheet) Coron Concentration 727.3 gpm CTMT Sump Level O.6 ft RCS Subcool. Marg. 44.3 F PER Temperature 510.8 "F STEAM GENERATORS PZR Level 78.0 in S/G 1 Level / Pressure 36.9 in/ 445.8 psig RCS Flow (Loop 1/2) 85.6/ 39.4 Mpph S/G 2 Level / Pressure 42.2 in/ 438.8 gsig PORV AUTO Block Valve OPEN S/G Shell Temp. (1/2) 511.4 'F/ 509.0 F Spray Valve AUTO Block Valve OPEN Turbine Bdr. Pressure 0.6 psig Letdown Flow 56.0 gpm MSIV Position CLOSED 4 RCP Seal Flows 32.7 gpm (TOTAL) 1 1-1 8.9 gpm 2-1 9.5 gpm FEED & CONDENSATE m 1-2 4.5 gpm 2-2 9.5 gym Main Fw Flow (Loop 1/2) 0.0/ O.0 Mppm Quonch Tank Level / Pressure 8.7 ft/ 24.8 psig Hotwell Level / Press. 7.0 ft/ 10.0 in Hg CST Level (1/2) 7.3/ 7.3 ft REACTOR CORE Aux. Fleed Flow (1/2) 0.0/ 278.0 gpm Source Range Level (NI-1/NI-2) 7.2/ 6.6 cps Motor Driven Feed Pump Flow O.0 gpm Intermediate Range (NI-3/NI-4)O.101E-10/O.100E-10 amps Power Range (NI-5/NI-6) 0.0/ O.0 % ELECTRICAL BUS T./B (NI-7/NI-8) 475.6 0.0/ O.O % BUS C1/C2 NORM / NORM NORM / NORM' Core Thermocouple (HIGHEST) 'F BUS D1/D2 NORM / NORM MAKEUP AND ECCS EDG 1/2 OFF/OFF Rikeup Flow 213.2 gym 480 VAC Distribution NOT NORM Makeup Tank Level / Press. 76.4 An/ 30.0 psig 250 VAC/125 VAC Dist. NORM w CFT 51 Level / Press. 12.9 ft/ 607.2 psig Inst. AC NORM CFT 82 Level / Press. 12.9 ft/ 607.2 psig Generator Nattmeter (Gross) 0.0 Mw $ w HPI Line Flow (1-1) 0.0/(1-2) 0.0 (2-1) 0.0/(2-2) 0.0 g,, LPI Line Flow (1-1) 0.0/(1-2) 0.0 gpm OTHER <: DHR Ex Inlet Temp. (1/2) 70.0/ 70.0 'F Instrument / Service Air NORM / NORM $ CTMT Spray Flow (1/2) 0.0/ O.0 gpm Spent Fuel Pool Level / Temp, 23.5 ft/ 99.6 *F c CCN Surge Tank Level (1/2) 51.0/ 52.0 in $ BwST Level 39.9 ft CCW Hz Outlet Temp. 93.4/ 94.6 "F e D-t'! m 2 e
DAVIS-BESSE NUCLEAR POWER STATION PLANT PARAMETER SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 1100 l l
- TO
- Control Room Operators T: 03/00
..........................................c..... ............................................................
THIS IS A DRILL DO NOT initiate actions affecting normal operations. REACTOR COOLANT CONTAINMENT RCS Pressure 676.0 psig CTMT Pressure 14.9 psia T Avg. 520.0 F CTMT Temperature 89.6 'F T hot /T cold 465.7/ 453.6 *F CTMT Radiation (see separate RE Data Sheet) Coron Concentration 727.3 ppe CTMr Sump Level O.6 ft RCS Subcool. Marg. 48.2 F PZR Temperature 492.8 'F STEAM GENERATORS PZR Level 209.2 in S/G 1 Level / Pressure 38.4 in/ 477.7 psig ECD Flow (Loop 1/2) 0.0/ 49.9 Mpph S/G 2 Level / Pressure 46.7 in/ 474.7 psig PORV OPEN Block Valve OPEN S/G Shell Temp. (1/2) 507.9 'F/ 505.8 F Spray Valve AUTO Block Valve OPEN Turbine Rdr. Pressure 1.0 psig Latdown Flow 63.6 gpm MSIV Position CLOSED -4 RCP Seal Flows 32.8 gpm (TOTAL) b m 1-1 7.6 gpm 2-1 7.5 gpm FEED & CONDENSATE 1-2 9.0 gpm 2-2 12.4 gpm Main Fw Flow (Loop 1/2) 0.0/ O.0 Mppm Qusnch Tank Level / Pressure 8.7 ft/ 24.8 psig Hotwell Level / Press. 7.0 ft/ 10.0 in Bg CST Level (1/2) 6.5/ 6.5 ft REACTOR CORE Aux. Fleed Flow (1/2) 0.0/ O.0 gpm Source Range Level (NI-1/NI-2) 6.8/ 6.4 cps Motor Driven Feed Pump Flow 0.0 gpm Intermediate Range (NI-3/NI-4)O.101E-10/O.100E-10 amps Power Range (NI-5/NI-6) 0.0/ O.0 % ELECTRICAL (NI-7/NI-8) 0.0/ O.0 % BUS A/B NORM / NORM Core Thermocouple (HIGHEST) 468.9 *F BUS C1/C2 NORH/ NORM BUS D1/D2 NORM / NORM MAKEUP AND ECCS EDG 1/2 OFF/OFF Makeup Flow 98.7 gpm 480 VAC Distribution NOT NORM M2keup Tank Level / Press. 86.6 In/ 30.0 psig 250 VAC/125 VAC Dist. NORM CFT 81 Level / Press. 12.9 ft/ 607.2 psig *1st. AC NORM ** CFT 82 Level / Press. 12.9 ft/ 607.2 psig Generator Wattmeter (Gross) 0.0 Mw $ w HPI Line Flow (1-1) 543.5/ 1-2) 541.6 (2-1) 547.6/ 2-2) 544.0 m LPI Line Flow (1-1) 0.0/ 1-2) 0.0 gpm OTHER < DBR Ex Inlet Temp. (1/2) 89.2/ 79.6 *F Instrument / Service Air NORM / NORM h c CTMT Spray Flow (1/2) 0.0/ O.0 gpm Spent Fuel Pool Level / Temp. 23.5 ft/ 99.6 "F CCW Surge Tank Level (1/2) 50.0/ 51.0 in %
................***................**..................................*................../
EwST Level 39.7 ft CCW Ex Outlet Temp. 95.2 95.0 *F m D-M e 2 O O O
(
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N DAVIS-BESSE NUCLEAR POWER STATION PLANT PARAMETER SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 1115 TO: Control Room Operators T: 03/15 THIS IS A DRILL DO NOT initiate actions affecting normal operations. REACTOR COOLANT CONTAINMENT WCS Pressure 587.0 psig CTMr Pressure 15.7 psia T Avg. 520.0 *F CTMT Temperature 102.5 *F T hot /T cold 429.4/ 422.2 *F CTMr Radiation (see separate RE Data Sheet) Coron Concentration 727.3 ppm CTMT Sump Level 4.1 ft RCS Subcool. Marg. 57.2 F PZR Temperature 457.5 *F STEAM GENERATORS PZR Level 320.0 in S/G 1 Level / Pressure 44.4 in/ 320.0 psig RCS Flow (Loop 1/2) 0.0/ 50.8 Mpph S/G 2 Level / Pressure 48.9 in/ 359.5 psig PORV OPEN Block Valve OPEN S/G Shell Temp. (1/2) 504.7 *F/ 502.9 *F Spray Valve AUTO Block Valve OPEN Turbine Hdr. Pressure 1.3 psig Lotdown Flow 0.7 gpm MSIV Position CLOSED -J RCP Seal Flows 4.3 gpm (TOTAL) $4 1-1 6.1 gpm 2-1 6.6 gpm FEED & CONDENSATE 1-2 8.2 gpm 2-2 11.8 ope Main FW Flow (Loop 1/2) 0.0/ O.0 Mppa Qusnch Tank Level / Pressure 12.5 ft/ O.0 psig Hotwell Level / Press. 7.0 ft/ 10.0 in Eg CST Level (1/2) 5.6/ 5.6 ft REACTOR CORE Aux. Fleed Flow (1/2) 0.0/ O.0 gpm Source Range Level (NI-1/NI-2) 5.1/ 4.8 cps Motor Driven Feed Pump Flow 0.0 gpm Intermediate Range (NI-3/NI-4)O.101E-10/O.100E-10 amps Power Range (NI-5/NI-6) 0.0/ O.0 % ELECTRICAL BUS A/B (NI-7/NI-8) 0.0/ O.0 1 NORM / NORM Core Thermocouple (HIGHEST) 447.0 *F BUS C1/C2 NORM / NORM BUS D1/D2 NORM / NORM MAKEUP AND ECCS EDO 1/2 OFF/OFF M2keup Flow 62 1 gpm 480 VAC Distribution NOT NORM Makeup Tank Level / Press. 90.0 in/ 30.0 psig 250 VAC/125 VAC Dist. NORM CFT 51 Level / Press. 12.9 ft/ 611.3 psig Inst. AC NORM w CFT 82 Level / Press. 12.9 ft/ 611.3 psig Generator Wattmeter (Gross) 0.0 Hw $ HPI Line Flow (1-1) 403.2/(1-2) 290.0 w (2-1) 246.9/(2-2) 398.8 m LPI Line Flow (1-1) 0.0/(1-2) 0.0 gpm OTHER DH2 Ex Inlet Temp. (1/2) 85.2/ 81.7 *F Instrument / Service Air NORM / NORM $ CTMT Spray Flow (1/2) 0.0/ O.0 gym Spent Fuel Pool Level / Temp. 23.5 ft/ 99.6 *F c CCW Surge Tank Level (1/2) 50.0/ 51.0 in % EWST Level 38.5 ft CCW Hz Outlet Temp. 88.2/ 93.4 "F m D-j .........................................** .....*********.***..**.........**......*******..***.************* M l 2 e
- . _ _ . - -- -. .. - - ,~
I. DAVIS-BESSE NUCLEAR POWER STATION PLANT PARAMETER SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 1130 To: Control Room Operators T: 03/30 THIS IS A DRILL l DO NOT initiate actions affecting normal operations. REACTOR COOLANT CONTAINMENT RCS Pressure 552.6 psig CTMT Pressure 16.5 psia T Avg. 520.0 *F CTMT Temperature 114.2 *F T hol/T cold 414.1/ 408.7 *F CTNr Radiation (see separate RE Data Sheet) Coron concentration 727.3 ppe CTMT Sump Level 6.5 ft RCS Subcool. Marg. 66.5 P PZR Temperature 438.2 *F STEAM GENERATORS PZR Level 320.0 in S7G 1 Level 7 Pressure 46.3 in/ 268.4 psig RCS Flow (Loop 1/2) 0.0/ 51.5 Mpph S/G 2 Level / Pressure 49.7 in/ 299.3 psig PORV OPEN Block Valve OPEN S/G Shell Temp. (1/2) 501.5 *F/ 499.7 F Spray Valve AUTO Block Valve OPEN Turbine Edr. Pressure 1.4 psig Lutdown Flow 0.5 gpm MSIV Position CLOSED -J RCP Seal Flows 6.3 gpm (TOTAL) $ l-1 6.1 gpm 2-1 6.6 gpm FEED & CONDENSATE m 1-2 8.2 gpm 2-2 11.9 gpm Main FW Flow (Loop 1/2) 0.0/ O.0 Mppm Qusnch Tank Level / Pressure 12.5 ft/ O.d psig Hotwell Level / Press. 7.0 ft/ 10.0 in Hg CST Level (1/2) 4.8/ 4.8 ft REACTOR CORE Aux. Fleed Flow (1/2) 0.0/ O.0 gpm Source Range Level (NI-1/NI-2) 4.5/ 4.0 cps Motor Driven Feed Pump Flow 0.0 gpm Inter 1 mediate Range (NI-3/NI-4)O.101E-10/O.100E-10 amps Power Range (NI-5/NI-6) 0.0/ O.0 % ELECTRICAL BUS A/B (NI-7/NI-8) 0.0/ O.0 % NORH/ NORM Core Thermocouple (HIGHEST) 428.3 *F BUS C1/C2 NORM / NORM BUS D1/D2 NORH/ NORM MAKEUP AND ECCS EDG 1/2 ON/ON Makeup Flow 15.6 gpa 480 VAC Distribution NOT NORM Makeup Tank Level / Press. 90.8 in/ 30.0 psig 250 VAC/125 VAC Dist. NORM CFT $1 Level / Press. 12.9 ft/ 617.2 psig Inst. AC NORM - CFT 82 Level / Press. 12.9 ft/ 617.2 psig Generator wattmeter (Gross) 0.0 Mw $ w HPI Line Flow (1-1) 447.2/(1-2) 292.2 (2-1) 250.1/(2-2) 404.0 m LPI Line Flow (1-1) 0.0/(1-2) 0.0 gpm OTHER DBR Ex Inlet Temp. (1/2) 79.8/ 82.6 *F Instrument / Service Air NORM / NORM $ c CTMT Spray Flow (1/2) 0.0/ O.0 gpm Spent Fuel Pool Level / Temp. 23.5 ft/ 99.7 *F CCw Surge Tank Level (1/2) 50.0/ 51.0 in $ EWST Level 37.5 ft CCW Hz Outlet Temp. 85.6/ 95.2 *F e D-M 2 7 e O O O
O ' O DAVIS-BESSE NUCLEAR POWER STATION PLANT PARAMETER SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 1145 To: Control Room Operators T: 03/45 THIS IS A DRILL DO NOT initiate actions affecting normal operations. REACTOR COOLANT CONTAINMENT RCS Pressure 547.9 psig CTMT Pressure 17.2 psia T Avg. 520.0 'F CTNT Temperature 127.2 'r T hot /T cold 397.3/ 392.9 'F CTNT Radiation (see separate RE Data Sheet) Eoron Concentration 727.3 ppe CTMT Sump Level 9.2 ft RCS Subcool. Marg. 82.5 F PER Temperature 420.4 'F STEAM GENERATORS PZR Level 320.0 in S/G 1 Level 7 Pressure 48.0 in/ 218.6 psig RCS Flow (Loop 1/2) 0.0/ 52.1 Mpph S/G 2 Level / Pressure 50.7 in/ 243.8 gsig PORV OPEN Block Valve OPEN S/G Shell Temp. (1/2) 497.8 'F/ 496.5 F Spray Valve AUTO Block Valve OPEN Turbine Edr. Pressure 1.5 psig Letdown Flow 0.5 gpm MSIV Position CLOSED -J RCP Seal Flows 0.0 gpm (TOTAL) $ e 1-1 0.0 gpm 2-1 0.0 gpm FEED & CONDENSATE 1-2 0.0 gym 2-2 4.3 gpm Main Fw Flow (Loop 1/2) 0.0/ 0.0 Mppm Qusnch Tank Level / Pressure 12.5 ft/ 0.0 psig Hotwell Level / Press. 7.0 ft/ 10.0 in Hg CST Level (1/2) 3.9/ 3.9 ft REACTOR CORE . Aux. Fleed Flow (1/2) 0.0/ 0.0 gpm Source Range Level (NI-1/NI-2) 4.0/ 3.7 cps Motor Driven Feed Pump Flow 0.0 gpm Intermediate Range (NI-3/NI-4)O.101E-10/0.100E-10 amps Power Range (NI-5/NI-6) 0.0/ O.0 % ELECTRICAL (NI-7/NI-8) 0.0/ O.0 % BUS A/B NORM / NORM Core Thermocouple (HIGHEST) 412.4 "F BUS C1/C2 NORM / NORM BUS D1/D2 NORM / NORM i MAKEUP AND ECCS EDG 1/2 OFF/OFF . Eikeup Flow 58.9 gpa 480 VAC Distribution NOT NORM M2keup Tank Level / Press. 91.1 in/ 30.0 psig 250 VAC/125 VAC Dist. NORM CFT $1 Level / Press. 12.9 ft/ 624.4 psig Inst. AC . NORM w CFT $2 Level / Press. 12.9 ft/ 624.4 psig Generator wattmeter (Gross) 0.0 Mw w HPI Line Flow (1-1) 406.8/(1-2) 341.3 (2-1) 297.6/(2-2) 400.6 m LPI Line Flow (1-1) 0.0/(1-2) 0.0 gpm OTHER DBR Hz Inlet Temp. (1/2) 78.9/ 79.6 'F Instrument / Service Air NORM / NORM $ CTMT Spray Flow (1/2) 0.0/ O.0 gpm Spent Fuel Pool' Level / Temp. 23.5 ft/ 99.7 'F c CCW Surge Tank Level (1/2) 50.0/ 51.0 in % e ...................................................................................................'r twST Level 36.4 ft CCw Ex Outlet Temp. 79.6/ 81.4
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DAVIS-BESSE NUCLEAR POWER STATION PLANT PARAMETER SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 1200 l TO: Control Room Operators T: 04/00 l ............................................................................................................. THIS IS A DRILL DO NOT initiate actions affecting normal operations. REACTOR COOLANT CONTAINMENT RCS Pressure 330.1 psig CTMT Pressure 17.8 psia ! T Avg. 520.0 'F CTMT Temperature 134.9 *F ! T hot /T cold 388.5/ 384.5 'F CTMT Radiation (see separate RE Data Sheet) Coron Concentration 727.3 gj_s CTMT Sump Level 11.8 ft RCS Subcool. Marg. 42.3 F PER Temperature 408.5 *F STEAM GENERATORS PZR Level 320.0 in S7G 1 Level / Pressure 48.7 in/ 195.2 psig RCS Flow (Loop 1/2) 0.0/ 40.1 Mpph S/G 2 Level / Pressure 50.9 in/ 217.8 psig
- PORV OPEN Block Valve OPEN S/G Shell Temp. (1/2) 493.4 'F/ 493.3 F l Spray Valve AUTO Block Valve OPEN Turbine Hdr. Pressure 1.5 psig Letdown Flow 0.5 gpa MSIV Position CLOSED -J l RCP Seal Flows 0.0 gpm (TOTAL) 5, 1-1 0.0 gpm 2-1 0.0 gpm FEED & CONDENSATE o 1-2 0.0 gym 2-2 6.3 gpm Main FW Flow (Loop 1/2) 0.0/ O.0 Mppm Qusnch Tank Level / Pressure 12.5 ft/ 0.0 psig Hotwell Level / Press. 7.0 ft/ 10.0 in Hg CST Level (1/2) 3.1/ 3.1 ft REACTOR CORE Aux. Fleed Flow (1/2) 0.0/ 0.0 gpm cource Range Level (NI-1/NI-2) 3.8/ 3.5 cps Motor Driven Feed Pump Flow 0.0 gpm Intermediate Range (NI-3/NI-4)O.101E-10/0.100E-10 amps l Power Range (NI-5/NI-6) 0.0/ O.0 % ELECTRICAL (NI-7/NI-8) 0.0/ 0.0 % BUS A/B NORM / NORM Core Thermocouple (HIGHEST) 400.2 'F BUS C1/C2 NORM / NORM BUS D1/D2 NORM / NORM MAREUP AND ECCS EDG 1/2 OFF/OFF Hakeup Flow 16.3 gpm 480 VAC Distribution NOT NORM Mikeup Tank Level / Press. 68.2 in/ 30.0 psig 250 VAC/125 VAC Dist. NORM CFT 51 Level / Press. 12.9 ft/ 631.2 psig Inst. AC NORM w CFT 82 Level / Press. 12.9 ft/ 631.3 psig Generator Watteeter (Gross) 0.0 Mw $
HPI Line Flow (1-1) 194.2/(1-2) 252.4 w (2-1) 222.2/(2-2) 329.7 m LPI Line Flow (1-1) 0.0/(1-2) 0.0 gpm OTHER < l DHR Hz Inlet Temp. (1/2) 78.9/ 77.6 'F Instrument / Service Air NORM / NORM $ CTMT Spray Flow (1/2) 0.0/ O.0 gym Spent Fuel Pool Level / Temp. 23.5 ft/ 99.8 *F c CCW Surge Tank Level (1/2) 50.0/ 51.0 in %
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BNST Level 35.5 ft CCW Ex Outlet Temp. 78.5 79.4 "F e a N N 3 1 7 e O O O
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O DAVIS-BESSE NUCLEAR POWER STATION PLANT PARAMETER SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 1215 TO: Control Room Operators T: 04/15 THIS IS A DRILL DO NOT initiate actions affecting normal operations. REACTOR COOLANT CONTAINMENT RCS Pressure 334.7 psig CTMr Pressure 18.2 psia T Avg. 520.0 *F CTHT Temperature 139.0 'F T hot /T cold 393.7/ 386.1 'T CTMT Radlation (see separate RE Data Sheet) Boron Concentration 727.3 gpm CTMT Sump Level 15.2 ft RCS Subcool. Marg. 38.5 P PZR Temperature 402.8 'T STEAM CENERATORS P2R Level 320.0 in S/G 1 Level / Pressure 48.4 in/ 191.3 psig RCS Flow (Loop 1/2) 0.0/ O.0 Mpph S/G 2 Level / Pressure 49.7 in/ 199.7 psig PORY OPEN Block Valve OPEN S/G Shell Temp. (1/2) 489.6 "F/ 489.7 F Spray Valve AUTO Block Valve OPEN Turbine Bdr. Pressure 2.2 psig Lotdown Flow 0.5 gpm MSIV Position CLOSED -J RCP Seal Flows 0.0 gpm (TOTAL) d, 1-1 0.0 gpa 2-1 0.0 gpm FEED & CONDENSATE F 1-2 0.0 gpm 2-2 0.0 gpm Main FW Flow (Loop 1/2) 0.0/ 0.0 Mppm Quench Tank Level / Pressure 12.5 ft/ 0.0 psig Hotwell Level / Press. 7.0 ft/ 10.0 in Hg CST Level (1/2) 2.3/ 2.3 ft REACTOR CORE Aux. Fleed Flow (1/2) 0.0/ 0.0 gpm Source Range Level (NI-1/NI-2) 3.7/ 3.3 cps Motor Driven Feed Pump Flow 0.0 gpm Intermediate Range (NI-3/NI-4)O.101E-10/O.100E-10 amps Power Range (NI-5/NI-6) 0.0/ O.0 % EECTRICAL (NI-7/NI-8) 0.0/ 0.0 % BUS A/B NORM / NORM Core Thermocouple (HIGHEST) 392.2 *F BUS C1/C2 NORM / NORM BUS D1/D2 NORM / NORM MAREUP AND ECCS EDG 1/2 OFF/OFF RikW p Flow 19.3 gpm 480 VAC Distribution NOT NORM Makeup Tank Level / Press. 77.4 in/ 30.0 psig 250 VAC/125 VAC Dist. NORM CFT 51 Level / Press. 12.9 ft/ 636.8 psig Inst. AC NORM N CFT 82 Level / Press. 12.9 ft/ 636.8 sig Generator Wattmeter (Gross) 0.0 Mw HPI Line Flow (1-1) 194.0/(1-2) 252. (2-1) 275.2/(2-2) 327.1 m LPI Line Flow (1-1) 0.0/(1-2) 0.0 gpm OTHER < DHR Ex Inlet Temp. (1/2) 78.6/ 79.0 'F Instrument / Service Air NORM / NORM $ CTHT Spray Flow (1/2) 0.0/ O.0 gym Spent Fuel Pool Level / Temp. 23.5 ft/ 99.9 *F c CCW Surge Tank Level (1/2) 49.0/ 50.0 in % CwST Level 34.8 ft CCW Hx Outlet Temp. 78.3/ 78.9 'F e . . . . . . . . . . . . . . . . . . . . * * * * . . . . . . . . . . . . . . . . . . . . . * * . . . . . . * * * . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . D-M e 2 e m____ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
1 l i DAVIS-BESSE NUCLEAR POWER STATION PLANT PARAMETER SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 1230 , TO: Control Room Operators T: 04/30 l l ............................................................................................................. THIS IS A DRILL ( DO NOT initiate actions affecting normal operations. REACTOR COOLANT CONTAINMENT iiCS Pressure 323.6 psig CTMT Pressure 18.6 psia T
. 520.0 *F CTMT Temperature 141.9 *F T Avg hot /T cold 385.6/ 388.6 "P CTMT Radiation (see separate RE Data Sheet)
Coron concentration 727.3 ppe CTNT Sump Level 17.6 ft RC3 Subcool. Marg. 43.1 F P2R Temperature 394.2 *F STEAM GENERATORS PZR Level 320.0 in S/G 1 Level / Pressure 47.8 in/ 200.8 psig RC3 Flow (Loop 1/2) 0.0/ O.0 Mpph S/G 2 Level / Pressure 49.0 in/ 201.6 psig PORV OPEN Block Valve OPEN S/G Shell Temp. (1/2) 486.4 "F/ 486.6 F Spray Valve AUTO Block Valve OPEN Turbine Bdr. Pressure 2.1 psig Lstdown Flow 0.5 gpa MSIV Position CLOSED -J RCP Seal Flows 0.0 gpm (TOTAL) $ 1-1 0.0 gpm 2-1 0.0 gpm FEED & CONDENSATE PJ 1-2 0.0 gpm 2-2 0.0 apa Main FN Flow (Loop 1/2) 0.0/ O.0 Mppm Qusnch Tank Level / Pressure 12.5 ft/ O.O psig Hotwell Level / Press. 7.0 ft/ 10.0 in Hg CST Level (1/2) 1.4/ 1.4 ft REACTOR CORE Aux. Fleed Flow (1/2) 0.0/ O.0 gpm Source Range Level (NI-1/NI-2) 3.3/ 3.2 cps Motor Driven Feed Pump Flow 0.0 gpm Intermediate Range (NI-3/NI-4)O.101E-lO/O.100E-10 amps Power Range (NI-5/NI-6) 0.0/ O.0 % ELECTRICAL (NI-7/NI-8) 0.0/ O.0 % BUS A/B NORM / NORM Core Thermocouple (HIGHEST) 380.8 "F BUS C1/C2 NORM / NORM BUS D1/D2 NORM / NORM MAKEUP AND ECCS EDG 1/2 OFF/OFF Kakeup Flow 19.1 gpm 480 VAC Distribution NOT NORM Makeup Tank Level / Press. 56.1 in/ 30.0 psig 250 VAC/125 VAC Dist. NORM CFT 51 Level / Press. 12.9 ft/ 641.9 psig Inst. AC NORM *-- CFT 82 Level / Press. 12.9 ft/ 642.0 psig Generator Wattmeter (Gross) 0.0 Mw $ HPI Line Flow (1-1) 198.0/(1-2) 253.4 w (2-1) 276.3/(2-2) 328.4 m LPI Line Flow (1-1) 0.0/(1-2) 0.0 gpm OTHER < DER Ex Inlet Temp. (1/2) 77.4/ 78.7 *F Instrument / Service Air NORM / NORM $ c CTNT Spray Flow (1/2) 0.0/ O.0 gpm Spent Fuel Pool Level / Temp. 23.5 ft/ 99.9 *F CCW Surge Tank Level (1/2) 49.0/ 50.0 in $ BWST Level 34.0 ft CCW Ex outlet Temp. 78.3/ 78.8 *F e a M e 2 e O - O . O _
( DAVIS-BESSE NUCLEAR POWER STATION PLANT PARAMETER SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 1245 To: Control Room Operators T: 04/45 THIS IS A DRILL DO NOT initiate actions affecting normal operations. REACTOR COOLANT CONTAINMENT
'RT5 Pressurn 324.1 poig CTMT Pressure 18.8 psia T Avg. 520.0 *F CTMT Temperature 143.8 "F T hot /T cold 383.9/ 358.6 *F CTMT Radiation (see separate RE Data Sheet) coron Concentration 727.3 gpm CTMT Sump Level 19.4 ft RCS Subcool. Marg. 45.0 F PER Temperature 386.8 *F STEAM GENERATORS PZR Level 320.0 in S/G 1 Level / Pressure 47.0 in/ 194.6 psig RCS Flcw (Loop 1/2) 0.0/ 0.0 Mpph S/G 2 Level / Pressure 48.0 in/ 191.9 psig PORV OPEN Block Valve OPEN S/G Shell Temp. (1/2) 483.1 *F/ 483.3 F Spray Valve AUTO Block Valve OPEN Turbine Edr. Pressure 2.0 psig Letdown Flow 0.6 gpm MSIV Position CLOSED 4 RCP Seal Flows 0.0 gpm (TOTAL) $
w 1-1 0.0 gpm 2-1 0.0 gpm FEED & CONDENSATE 1-2 0.0 gpm 2-2 0.0 gpm Main FN Flow (Loop 1/2) 0.0/ O.0 Mppm Quanch Tank Level / Pressure 12.5 ft/ 0.0 psig Hotwell Level / Press. 7.0 ft/ 10.0 in Hg CST Level (1/2) 0.6/ 0.6 ft REACTOR CORE Aux. Fleed Flow (1/2) 0.0/ 0.0 gpm Source Range Level (NI-1/NI-2) 3.1/ 3.0 cps Motor Driven Feed Pump Flow 0.0 gpm Intermediate Range (NI-3/NI-4)0.101E-10/0.100E-10 amps Power Range (NI-5/NI-6) 0.0/ O.0 % ELECTRICAL (NI-7/NI-8) 0.0/ *F O.0 % BUS A/B NORM / NORM Core Thermocouple (HIGHEST) 371.5 BUS C1/C2 NORM / NORM BUS D1/D2 NORM / NORM MAKEUP AND ECCS EDG 1/2 OFF/OFF H3keup Flow 19.5 gpm 480 VAC Distribution NOT NORM M2keup Tank Level / Press. 81.0 in/ 30.0 psig 250 VAC/125 VAC Dist. NORM CFT 31 Level / Press. 12.9 ft/ 646.3 psig Inst. AC NORM s CFT $2 Level / Press, 12.9 ft/ 646.4 sig Generator Wattmeter (Gross) 0.0 Mw HPI Line Flow (1-1) 197.3/(1-2) 253. (2-1) 276.0/(2-2) 328.1 n LPI Line Flow (1-1) 0.0/(1-2) 0.0 gpm OTHER DHR HE Inlet Temp. (1/2) 78.7/ 76.5 *F Instrument / Service Air NORM / NORM h CTMT Spray Flow (1/2) 0.0/ 0.0 gpm Spent Fuel Pool Level / Temp. 23.5 ft/ 99.9 *F c CCN Surge Tank Level (1/2) 49.0/ 50.0 in % BWST Level 33.3 ft CCW Ex Outlet Temp. 78.3/ 78.8 *F e
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e 2
DAVIS-BESSE NUCLEAR POWER STATION PLANT PARAMETER SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 1300 TO: Control Room Operators T: 05/00 THIS IS A DRILL DO NOT initiate actions affecting normal operations. . REACTOR COOIJLNT CONTAINMENT RCS Pressure 285.1 psig CTMT Pressure 19.0 psia T Avg. 520.0 'F CIwr Temperature 145.1 'F T hot /T cold 383.9/ 274.9 'F CTNT Radiation (see separate RE Data Sheet) Coron concentration 727.3 ppe CTMT Sump Level 20.9 ft RCS Subcool. Marg. 33.8 F PER Temperature 379.7 'F STEAM GENERATORS PZR Level 320.0 in S/G 1 Level / Pressure 46.3 in/ 186.9 psig RCS Flow (Loop 1/2) 0.0/ O.0 Mpph S/G 2 Level / Pressure 47.5 in/ 179.2 psig PORV OPEN Block Valve OPEN S/G Shell Temp. (1/2) 479.7 'F/ 479.9 'F Spray Valve AUTO Block Valve OPEN Turbine Hdr. Pressure 2.0 psig Letdown Flow 0.6 gpm MSIV Position CLOSED 4 RCP Seal Flows 0.0 gpm (TOTAL) 5 1-1 0.0 gpm 2-1 0.0 gpm FEED & CONDENSATE 6 1-2 0.0 gpm 2-2 0.0 cypm Main Fw Flow (Loop 1/2) 0.0/ 0.0 Mppm Qusach Tank Level / Pressure 12.5 ft/ O.0 psig Hotwell Level / Press. 7.0 ft/ 10.0 in Hg CST Level (1/2) 0.0/ 0.0 ft REACTOR CORE Aux. Fleed Flow (1/2) 0.0/ 0.0 gpm Source Range Level (NI-1/NI-2) 3.2/ 2.9 cps Motor Driven Feed Pump Flow 0.0 gpm Intermediate Range (NI-3/NI-4)0.101E-10/0.100E-10 amps Power Range (NI-5/NI-6) 0.0/ 0.0 % ELECTRICAL (NI-7/NI-8) 0.0/ 0.0 % BUS A/B NORM / NORM Core Thermocouple (HIGHEST) 364.1 'F BUS C1/C2 NORM / NORM BUS D1/D2 NORM / NORM MAKEUP AND ECCS EDG 1/2 OFF/OFF Makeup Flow 22.6 gpm 480 VAC Distribution NOT NORM Makeup Tank Level / Press. 76.9 in/ 30.0 psig 250 VAC/125 VAC Dist. NORM CFT 81 Level / Press. 12.9 ft/ 650.3 psig Inst. AC NORM +- CFT 82 Level / Press. 12.9 ft/ 650.3 psig Generator wattmeter (Gross) 0.0 Mw $ HPI Line Flow (1-1) 199.8/(1-2) 256.3 w (2-1) 227.4/(2-2) 273.2 p LPI Line Flow (1-1) 0.0/(1-2) 0.0 gpm OTHER < DHR Ex Inlet Temp. (1/2) 76.4/ 77.3 *F Instrument / Service Air NORM / NORM $ c CTMT Spray Flow (1/2) 0.0/ 0.0 gpm Spent Fuel Pool Level / Temp. 23.5 ft/ 100.0 *F CCW Surge Tank Level (1/2) 49.0/ 50.0 in $ LwST Level 32.5 ft CCW Hz Outlet Temp. 78.3/ 78.8 *F e
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M O m e O O O
DAVIS-BESSE NUCLEAR POWER STATION PLANT PARAMETER SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 1315 TO: Control Room Operators T: 05/15 THIS IS A DRILL DO NOT initiate actions affecting normal operations. REACTOR COOLANT CONTAINMENT MCS Pressure 238.5 psig CTMT Pressure 19.1 psia T Avg. 520.0 *F CTMT Teloperature 145.5 *F T hot /T cold 383.0/ 228.7 *F CTMT Radiation (see separate RE Data Sheet) Eoron Concentration 727.3 ppe CTMT Sump Level 21.8 ft RCS Subcool. Marg. 20.6 F PER Temperature 374.2 "F STEAM GENERATORS PER Level 320.0 in S/G 1 Level / Pressure 46.3 in/ 181.9 psig RCS Flow (Loop 1/2) 0.0/ 0.0 Mpph S/C 2 Level / Pressure 47.7 in/ 155.6 psig PORV OPEN Block Valve OPEN S/G Shell Temp. (1/2) 476.5 *F/ 476.7 F Spray Valve AUTO Block Valve OPEN Turbine Hdr. Pressure 2.1 psig Latdown Flow 0.5 gpm MSIV Position CLOSED 4 RCP Seal Flows 0.0 gym (TOTAL) $ 1-1 0.0 gpm 2-1 0.0 gpm FEED & CONDENSATE m 1-2 0.0 gpm 2-2 0.0 gpm Main FW Flow (Loop 1/2) 0.0/ 0.0 Mppm Quench Tank Level / Pressure 12.5 ft/ 0.0 psig Hotwell Level / Press. 7.0 ft/ 10.0 in Bg CST Level (1/2) 0.0/ 0.0 ft REACTOR CORE Aux. Fleed Flow (1/2) 0.0/ 0.0 gpm Source Range Level (NI-1/MI-2) 3.1/ 2.9 cps Motor Driven Feed Pump Flow O.0 gpm Intermediate Range (NI.-3/NI-4)0.101E-10/0.100E-10 amps Power Range (NI-5/NI-6) 0.0/ 0.0 % ELECTRICAL (NI-7/MI-8) 0.0/ 0.0 % BUS A/B NORM / NORM Core Thermocouple (HIGHEST) 361.1 *F BUS C1/C2 ' NORM / NORM BUS D1/D2 NORM / NORM MAKEUP AND ECCS EDG 1/2 OFF/OFF Makeup Flow 22.6 gpm 480 VAC Distribution NOT NORM Makeup Tank Level / Press. 80.5 in/ 30.0 psig 250 VAC/125 VAC Dist. NORM CFT 51 Level / Press. 12.9 ft/ 653.4 psig Inst. AC NORM N CFT 82 Level / Press. 12.9 ft/ 653.4 psig Generator Wattmeter (Gross) 0.0 Mw $ w HPI Line Flow (1-1) 202.9/(1-2) 260.2 (2-1) 175.0/(2-2) 142.2 m LPI Line Flow (1-1) 0.0/(1-2) 0.0 gpm OTHER DHR Hz Inlet Temp. (1/2) 79.3/ 78.0 *F Instrument / Service Air NORM / NORM $ c CTMT Spray Flow (1/2) 0.0/ 0.0 gpm Spent Fuel Pool Level / Temp. CCW Surge Tank Level (1/2) 23.5 ft/ 100.0 *F 49.0/ 50.0 in % BWST Level 31.9 ft CCW HE Outlet Temp. 78.3/ 78.8 *F e D-M M e Q O e
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DAVIS-BESSE NUCLEAR POWER STATION PLANT PARAMETER SHEET SCENARIO NO. 1993 Evaluated Exercice TIME: 1330 Tom Control Room Operators T: 05/30 THIS IS A DRII.L DO NOT initiate actions affecting normal operations. REACTOR COOLANT CONTAINMENT NCS Pressure 212.5 psig CTNT PresE re 19.1 psia T Avg. 520.0 *F CTMT Temperature 145.2 "P T hot /T cold 386.4/ 178.9 'F CTMT Radiation (see separate RE Data Sheet) Coron Concentration 727.3 ppm CTMT Sump Level 22.6 ft CCS Subcool. Marg. 16.8 F PZR Temperature 373.8 'F STEAM GENERATORS-PZR Level 320.0 in S/G 1 Level / Pressure 48.6 in/ 117.9 psig RCS Flow (Loop 1/2) 0.0/ O.0 Hpph S/G 2 Level / Pressure 49.4 in/ B3.8 psig . PORV OPEN Block Valve OPEN S/G Shell Temp. (1/2) 473.0 *F/ 472.6 F Spray Valve AUTO Block Valve OPEN Turbine Hdr. Pressure 1.7 psig Letdown Flow 0.5 gym MSIV Position CLOSED 4 RCP Seal Flows 0.0 gpm (TOTAL) $ 1-1 0.0 gpm 2-1 0.0 gpm FEED & CONDENSATE m 1-2 0.0 gpm 2-2 0.0 gpm Main FW Flow (Loop 1/2) 0.0/ 0.0 Mppm Qusnch Tank Level / Pressure 12.5 ft/ O.0 psig Hotwell Level / Press. 7.0 ft/ 10.0 in Hg CST Level (1/2) 0.0/ O.0 ft REACTOR CORE Aux. Fleed Flow (1/2) 0.0/ O.0 gym Source Range Level (NI-1/NI-2) 3.3/ 3.0 cps Motor Driven Feed Pump Flow 0.0 gpm Intermedialie Dange (NI-3/NI-4)O.101E-10/0.100E-10 amps Power Range (NI-5/NI-6) 0.0/ O.0 % ELECTRICAL (NI-7/NI-8) 0.0/ 0.0 % BUS A/B NORM / NORM Core Thermocouple (HIGHEST) 318.1 *F BUS C1/C2 NORM / NORM BUS D1/D2 NORM / NORM MAKEUP AND ECCS EDG 1/2 OFF/OFF M:keup Flow 18.7 gpm 480 VAC Distribution NOT NORM Mmkeup Tank Level / Press. 85.4 in/ 30.0 psig 250 VAC/125 VAC Dist. NORM CFT #1 Level / Press. 12.9 ft/ 655.8 psig Inst. AC NORM H CFT 82 Level / Press. 12.9 ft/ 655.9 psig Generator wattmeter (Gross) 0.0 Mw $ HPI Line Flow (1-1) 212.2/(1-2) 262.8 w (2-1) 165.7/(2-2) 134.6 m LPI Line Flow (1-1) 0.0/(1-2)3058.3 gpm OTHER < DER Ex Inlet Temp. (1/2) 78.4/ 229.5 *F Instrument / Service Air NORM / NORM $ CTNT Spray Flow (1/2) 0.0/ 0.0 gpm Spent Fuel Pool Level / Temp. 23.5 ft/ 100.0 *F c CCW Surge Tank Level (1/2) 49.0/ 50.0 in $ EwST Level 31.3 ft CCW Hz Outlet Temp. 78.4/ 105.8 'F e
. . . . . . . . . . . . . . . . . . . . . . . . . . . * * . . . . . . . . . * * . . * * * . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . * * . . . . . . . . * * . . . . . . . . D-M e
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O O DAVIS-BESSE NUCLEAR POWER STATION PLANT PARAMETER SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 1345 TO: Control Room Operators T: 05/45 THIS IS A DRILL DO NOT initiate actions affecting normal operations. REACTOR COOLANT CONTAINNENT EdS Pressure 197.7 psig CTMT Pressure 19.1 psia T Avg. 520.0 *r CTMT Temperature 144.3 'F T hot /T cold 369.1/ 162.7 *F CTMT Radiation (see separate RE Data Sheet) Eoron Concentration 727.3 ppe CTMT Sump Level 23.2 ft RCS Subcool. Marg. 18.9 F PZR Temperature 347.8 'F STEAM GENERATORS P2R Level 320.0 in S/G 1 Leve17 Pressure 51.6 in/ 41.9 psig RCS Flow (Loop 1/2) 0.0/ O.0 Mpph S/G 2 Level / Pressure 50.6 in/ 21.6 psig PORV OPEN Block Valve OPEN S/O Shell Temp. (1/2) 468.1 *F/ 467.3 F Spray Valve AUTO Block Valve OPEN Turbine Bdr. Pressure 1.7 psig Letdown Flow 0.6 gpm MSIV Position CLOSED -J RCP Seal Flows 0.0 gpm (TOTAL) $ 1-1 0.0 gpm 2-1 0.0 gpm FEED & CONDENSATE -J 1-2 0.0 gpm 2-2 0.0 gpm Main Fw Flow (Loop 1/2) 0.0/ O.O Mppm Quench Tank Level / Pressure 12.5 ft/ O.1 psig Hotwell Level / Press. 7.0 ft/ 10.0 in Hg CST Level (1/2) 0.0/ O.0 ft REACTOR CORE Aux. Fleed Flow (1/2) 0.0/ O.0 gpm Source Range Level (NI-1/NI-2) 3.3/ 3.1 cps Motor Driven Feed Pump Flow 0.0 gpm Intermediate Range (NI-3/NI-4)O.101E-10/O.100E-10 amps Power Range (NI-5/NI-6) 0.0/ O.0 % ELECTRICAL (NI-7/NI-8) 0.0/ O.0 % BUS A/B NORM / NORM Core Thermocouple (HIGHEST) 228.1 "F BUS C1/C2 NORM / NORM BUS D1/D2 NORM / NORM MAKEUP AND ECCS EDG 1/2 OFF/OFF M:keup Flow 19.0 gpm 480 VAC Distribution NOT NORM Makeup Tank Level / Press. 85.5 in/ 30.0 psig 250 VAC/125 VAC Dist. NORM CFT 81 Level / Press. 12.9 ft/ 657.8 psig Inst. AC NORM w CFT 82 Level / Press. 12.9 ft/ 657.8 psig Generator Wattmeter (Gross) 0.0 Mw $ HPI Line Flow (1-1) 0.0/ 1-2) 0.0 w (2-1) 0.0/ 2-2) 0.0 m LPI Line Flow (1-1) 0.0/ 1-2)3089.8 gym OTHER < DHR Hz Inlet Temp. (1/2) 79.8/ 176.1 *r Instrument / Service Air NORM / NORM $ CTMT Spray Flow (1/2) 0.0/ O.O gpm Spent Fuel Pool Level / Temp. 23.5 ft/ 100.1 *F c CCW Surge Tank Level (1/2) 48.0/ 49.0 in $ BNST Level 30.5 ft CCW Hz outlet Temp. 79.5/ 100.4 *F e
. . . . . . . . . . * * . . . . . . . . . . * * * * . . . . . . * . . . . . . . . . . . . . . . . * * * . * * . . * . . . . . . . . . . . . . * * . . . . . . * * . . . . . . * * * . . * * * . . * * * . . . . . . . O-M M
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DAVIS-BESSE NUCLEAR POWER STATION PLANT PARAMETER SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 1400 TO: Control Room Operators T: 06/00 THIS IS A DRILL DO NOT initiate actions affecting normal operations. REACTOR COOLANT CONTAINMENT RCS Pressure 141.8 psig CTMr Pressure 19.0 psia T Avg. 520.0 *F CTMT Temperature 144.0 *F T hot /T cold 357.4/ 152.2 'F CTNT Radiation (see separate RE Data Sheet) Coron Concentration 727.3 ppm CTNT Sump Level 18.9 ft RCS Subcool. Marg. 21.2 F PZR Temperature 321.1 'F STEAM GENERATORS Pzn Level 321.1 in S/G 1 Level / Pressure 51.9 in/ 23.9 psig ECS Flow (Loop 1/2) 0.0/ O.0 Mpph S/G 2 Level / Pressure 51.8 in/ 41.9 psig PORV OPEN Block Valve OPEN S/G Shell Temp. (1/2) 463.2 'F/ 461.7 F Spray Valve AUTO Block Valve OPEN Turbine Edr. Pressure 1.1 psig Iatdown Flow 0.5 gpm MSIV Position CLOSED 4 RCP Seal Flows 0.0 gpm (TOTAL) $ 1-1 0.0 gpm 2-1 0.0 gpm FEED & CONDENSATE m 1-2 0.0 gpm 2-2 0.0 gpm Main FW Flow (Loop 1/2) 0.0/ O.O Mppm Quench Tank Level / Pressure 12.5 ft/ O.2 psig Hotwell Level / Press. 7.0 ft/ 10.0 in Hg CST Level (1/2) 0.0/ O.0 ft REACTOR CORE Aur. Fleed Flow (1/2) 0.0/ O.0 gpm Source Range Level (NI-1/NI-2) 3.4/ 3.1 cps Motor Driven Feed Pump Flow 0.0 gpm Intermediate Range (NI-3/NI-4)O.101E-10/O.100E-10 amps Power Range (NI-5/NI-6) 0.0/ O.0 1 ELECTRICAL (NI-7/MI-S) 0.0/ O.0 % BUS A/B NORH/ NORM Core Thermocouple (HIGHEST) 217.2 'F BUS C1/C2 NORM / NORM BUS D1/D2 NORM / NORM MAKEUP AND ECCS EDG 1/2 OFF/OFF Malieup Flow 18.9 gpa 480 VAC Distribution NOT NORM Makeup Tank Level / Press. 85.7 in/ 30.0 psig 250 VAC/125 VAC Dist. NORM CFT $1 Level / Press. 12.9 ft/ 658.9 psig Inst. AC NORM w CFT $2 Level / Press. 12.9 ft/ 658.9 psig Generator Wattmeter (Gross) 0.0 Mw $ HPI Line Flow (1-1) 0.0/(1-2) 0.0 w (2-1) 0.0/(2-2) 0.0 m LPI Line Flow (1-1) 0.0/(1-2)3004.2 gpm OTHER 4 DHD Br Inlet Temp. (1/2) 77.7/ 170.2 *F Instrument / Service Air NORM / NORM $ c CTMT Spray Flow (1/2) 0.0/ O.0 gym Spent Fuel Pool Level / Temp. 23.5 ft/ 100.1 *F CCW Surge Tank Level (1/2) 48.0/. 49.0 in % EWST Level 30.3 ft CCW Hz outlet Temp. 79.7/ 95.8 *F e
.................................................**..........**.........***.................................. a M
e 2 7 e O O O
O DAVIS-BESSE NUCLEAR POWER STATION PLANT PARAMETER SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 1415 TO: Control Room Operators T: 06/15 THIS IS A DRILL DO NOT initiate actions affecting normal operations. REACTOR COOLANT CONTAINMENT RFS Pressure 122.1 psig CTMT Pressure 18.9 psia T Avg. 520.0 *F CTMT Temperature 143.7 *F T hot /T cold 364.1/ 167.5 "F CTMT Radiation (see separate RE Data Sheet) Eoron Concentration 727.3 ppm CTMT Sump Level 18.4 ft RCS Subcool. Marg. 28.9 F PZR Temperature 300.2 "F STEAM CENERATORS PZR Level 300.2 in S7G 1 Level / Pressure 52.1 in/ 24.4 psig RCS Flow (Loop 1/2) 0.0/ 0.0 Npph S/C 2 Level / Pressure 51.8 in/ 50.3 psig PORV OPEN Block Valve OPEN S/G Shell Temp. (1/2) 458.9 "F/ 456.5 F Spray Valve AUTO Block Valve OPEN Turbine Hdr. Pressure 1.7 psig Letdown Flow 0.6 gpm MSIV Position CLOSED -J F.CP Seal Flows 0.0 gpm (TOTAL) /,, 1-1 0.0 gpm 2-1 0.0 gpm FEED T. CONDENSATE w 1-2 0.0 pm 2-2 0.0 gpm Main Fw Flow (Loop 1/2) 0.0/ 0.0 Mppm ! Quench Tank Level / Pressure 1 .5 ft/ 0.0 psig Hotwell Level / Press. 7.0 ft/ 10.0 in Hg CST Level (1/2) 0.0/ 0.0 ft REACTOR CORE Aux. Fleed Flow (1/2) 0.0/ O.0 gpm Source Range Level (NI-1/NI-2) 3.3/ 3.2 eps Motor Driven Feed Pump Flow 0.0 gpm Intermediate Range (NI-3/MI-4)O.101E-10/O.100E-10 amps Power Range (NI-5/NI-6) 0.0/ O.0 % ELECTRICAL (NI-7/NI-8) 0.0/ O.0 % BUS A/B NORM / NORM Core Thermocouple (HIGHEST) 210.7 *F BUS C1/C2 NORM / NORM BUS D1/D2 NORM / NORM MAKEUP AND ECCS
~
EDG 1/2 OFF/OFF l Mmkeup Flow 20.9 gpm 480 VAC Distribution NOT NORM Makeup Tank Level / Press. 85.9 in/ 30.0 psig 250 VAC/125 VAC Dist. NORM CFT 91 Level / Press. 12.9 ft/ 659.4 psig Inst. AC NORM w CFT 82 Level / Press. 12.9 ft/ 659.4 psig Generator wattmeter (Gross) 0.0 Mw d: Line Flow (1-1) 0.0/(1-2) 0.0 w (2-1) 0.0/(2-2) 0.0 n, LPA Line Flow (1-1) 0.0/(1-2)3010.4 gpm OTHER' < DHR Ex Inlet Temp. (1/2) 75.9/ 163.8 *F Instrument / Service Air NORM / NORM $ CTMr Spray Flow (1/2) 0.0/ O.0 gpm Spent Fuel Pool Level / Temp. 23.5 ft/ 100.1 *F c CCW Surge Tank Level (1/2) 48.0/ 49.0 in % l CWST Level 30.3 ft CCN Ex Outlet Temp. 79.8/ 92.1 *F e
.......................................** ..........******* ..******....*..**.****....*****************...... 4 R
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DAVIS-BESSE NUCLEAR POWER STATION PLANT PARAMETER SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 1430 TO: Control Room Operators T 06/30 l l THIS IS A DRILL l DO NOT initiate actions affecting normal operations. REACTOR COOLANT CONTAINMENT RCS Pressure 106.3 psig CTMT Pressure 18.9 psia T Avg. 520.0 *F CTMT Temperature 143.2 'F T hot /T cold 362.1/ 175.0 *F CTMT Radiation (see separate RE Data Sheet) Coron Concentration 727.3 gpm CTMT Sump Level 17.6 ft ECS Subcool. Marg. 33.4 F PER Temperature 303.6 *F STEAM GENERATORS PZA Level 303.6 in S/G 1 Level / Pressure 52.0 in/ 24.4 psig RCS Flow (Loop 1/2) 0.0/ O.0 Mpph S/G 2 Level / Pressure 51.5 in/ 61.3 psig PORV OPEN Block Valve OPEN S/G Shell Temp. (1/2) 454.5 'F/ 451.0 F Spray Valve AUTO Block Valve OPEN Turbine Edr. Pressure 1.6 psig Lotdown Flow 0.6 gpm MSIV Position CLOSED 4 RCP Seal Flows 0.0 gpm (TOTAL) $ 1-1 0.0 gpm 2-1 0.0 gpm FEED & CONDENSATE o 1-2 0.0 gpm 2-2 0.0 9pm Main Fw Flow (Loop 1/2) 0.0/ O.0 Mppm Qusnch Tank Level / Pressure 12.5 ft/ O.0 psig Hotwell Level / Press. 7.0 ft/ 10.0 in Hg CST Level (1/2) 0.0/ O.0 ft REACTOR CORE Aux. Fleed Flow (1/2) 0.0/ O.0 gpm Source Range Level (NI-1/NI-2) 3.4/ 3.2 cps Motor Driven Feed Pump Flow 0.0 gpm Intermediate Range (NI-3/NI-4)O.101E-10/O.100E-10 amps Power Range (NI-5/NI-6) 0.0/ O.0 % ELECTRICAL (NI-7/NI-8) 0.0/ O.0 1 BUS A/B NORM / NORM Core Thermocouple (HIGHEST) 206.9 'F BUS C1/C2 NORM / NORM BUS D1/D2 NORM / NORM MAKEUP AND ECCS EDG 1/2 OFF/OFF MXkeup Flow 22.1 gpm 480 VAC Distribution NOT NORM Makeup Tank Level / Press. 86.8 in/ 30.0 psig 250 VAC/125 VAC Dist. NORM CPT fl Level / Press. 12.9 ft/ 659.1 psig Inst. AC NORM e CFT 82 Level / Press. 12.9 ft/ 659.1 psig Generator Wattmeter (Gross) 0.0 Mw $ HPI Line Flow (1-1) 0.0/(1-2) 0.0 w (2-1) 0.0/(2-2)3067.9 0.0 gpm m LPI Line ' low (1-1) 0.0/(1-2) OTHER 4 DHR Ex " !*t Temp. (1/2) 74.6/ 157.3 *F Instrument / Service Air NORM / NORM $ c CTMr Spt;j Flow (1/2) 0.0/ O.0 gpm Spent Fuel Pool Level / Temp. CCW Surge Tank Level (1/2) 23.5 ft/ 100.2 "F 40.0/ 49.0 in % e
.........................................................................................../........."F rwST Level 30.2 ft CCW Ex Outlet Temp. 79.9 88.4
......... D-M 2
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) O O DAVIS-BESSE NUCLEAR POWER STATION PLANT PARAMETER SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 1445 TO: Control Room Operators T: 06/45 THIS IS A DRILL DO NOT initiate actions affecting normal operations.
REACTOR COOLANT CONTAINMENT RCS Pressure 94.4 psig CTMT Pressure 18.7 psia T Avg. 520.0 *r CTMT Temperature 142.6 *F T hot /T cold 361.0/ 167.0 *F CTMT Radiation (see separate RE Data Sheet) Eoron Concentration 727.3 pom CTHT Sump Level 17.1 ft RCS Subcool. Marg. 37.6 F PZR Temperature 306.7 *F STEAM GENERATORS PZR Level 306.7 in 57G 1 Level / Pressure 52.0 in/ 24.5 psig RCS Flow (Loop 1/2) 0.0/ O.0 Mpph S/G 2 Level / Pressure 51.5 in/ 62.0 psig PORV OPEN Block Valve OPEN S/G Shell Temp. (1/2) 450.3 *F/ 445.7 F Spray Valve AUTO Block Valve OPEN Turbine Bdr. Pressure 1.6 psig Letdown Flow 0.6 gpm MSIV Position CLOSED -4 RCP Seal Flows 0.0 gpm (TOTAL) E 1-1 0.0 gpm 2-1 0.0 gpm FEED & CONDENSATE e 1-2 0.0 gpm 2-2 0.0 opa Main Fw Flow (Loop 1/2) 0.0/ O.0 Mppm quench Tank Level / Pressure 12.5 ft/ O.2 psIg Hotwell Level / Press. 7.0 ft/ 10.0 in Hg . CST Level (1/2) 0.0/ O.0 ft REACTOR CORE Aux. Fleed Flow (1/2) 0.0/ O.0 gpm Source Range Level (NI-1/NI-2) 3.4/ 3.2 cps Motor Driven Feed Pump Flow 0.0 gpm Intermediate Range (NI-3/NI-4)O.101E-10/O.100E-10 amps Power Range (NI-5/NI-6) 0.0/ O.0 % ELECTRICAL (NI-7/NI-8) 0.0/ O.0 % BUS A/B NORM / NORM Core Thermocouple (HIGHEST) 198.9 'F BUS C1/C2 NORM / NORM BUS D1/D2 NORH/ NORM MAKEUP AND ECCS EDG 1/2 OFF/OFF NiEup Flow 21.9 gpm 480 VAC Distribution NOT NORM Makeup Tank Level / Press. 87.2 in/ 30.0 psig 250 VAC/125 VAC Dist. NORM w CFT 51 Level / Press. 12.9 ft/ 658.8 psig Inst. AC NORM CFT 82 Level / Press. 12.9 ft/ 658.8 psig Generator Wattmeter (Gross) 0.0 Mw $ w HPI Line Flow (1-1) 0.0/(1-2) 0.0 (2-1 0.0/(2-2) 0.0 m LPI Line Flow (1-1)) 0.0/(1-2)3074.3 gpm OTHER DHR Ex Inlet Temp. (1/2) 72.3/ 153.4 *F Instrument / Service Air NORM / NORM $ c CTMT Spray Flow (1/2) 0.0/ O.0 gpm Spent Fuel Pool Level / Temp. 23.5 ft/ 100.2 'F CCW Surge Tank Level (1/2) 48.0/ 49.0 in I e BWST Level 30.2 ft
.................................. **...................**.........................................'F CCW Ex Outlet Temp. 79.9/ 86.3
.......... D-M m
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DAVIS-BESSE NUCLEAR POWER STATION PLANT PARAMETER SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 1500 TO: Control Room Operators T: 07/00 THIS IS A DRILL DO NOT initiate actions affecting normal operations. F.EACTOR COOLANT CONTAINMENT RCS Pressure 72.8 psig CTMT Pressure 18.4 psia T Avg. 520.0 *F CTwr Temperature 142.0 "F T hot /T cold 350.3/ 138.2 *F CTNT Radiation (see separate RE Data Sheet) Coron concentration 727.3 ppm CTMT Sump Level 16.7 ft RCS Subcool. Marg. 41.8 F PZR Temperature 301.0 *F STEAM GENERATORS PZR Level 301.0 in S/G 1 Level / Pressure 52.0 in/ 24.5 psig T.CS Flow (Loop 1/2) 0.0/ O.0 Mpph S/G 2 Level / Pressure 51.4 in/ 56.6 psig PORV OPEN Block Valve OPEN S/G Shell Temp. (1/2) 446.4 *F/ 440.6 F Spray Valve AUTO Block Valve OPEN Turbine Edr. Pressure 1.6 psig Letdown Flow 0.5 gpm MSIV Position CLOSED J RCP Seal Flows 0.0 gpm (TOTAL) i 1-1 0.0 gpm 2-1 0.0 gpm FEED & CONDENSATE N 1-2 0.0 gpm 2-2 0.0 gpm Main FW Flow (Loop 1/2) 0.0/ O.0 Mppm Qusnch Tank Level / Pressure 12.5 ft/ O.1 psig Hotwell Level / Press. 7.0 ft/ 10.0 in Hg CST Level (1/2) 0.0/ 0.0 ft REACTOR CORE Aux. Fleed Flow (1/2) 0.0/ 0.0 gpm Source Range Level (NI-1/NI-2) 3.4/ 3.2 cps Motor Driven Feed Pump Flow 0.0 gpm Intermediate Range (NI-3/NI-4)O.101E-10/O.100E-10 amps Power Range (NI-5/NI-6) 0.0/ 0.0 1 ELECTRICM. (NI-7/NI-8) G.0/ 0.0 % BUS A/B NORM / NORM Core Thermocouple (HIGHEST) 192.5 "F BUS C1/C2 NORM / NORM BUS D1/D2 NORM / NORM MAKEUP AND ECCS EDG 1/2 OFF/OFF Makeup Flow 21.0 gpm 480 VAC Distribution NOT NORM Makeup Tank Level / Press. 87.4 in/ 30.0 peig 250 VAC/125 VAC Dist. NORM CFT 81 Level / Press. 12.9 ft/ 658.2 psig Inst. AC NORM w CFT 82 Level / Press. 12.9 ft/ 658.2 psig Generator Wattmeter (Gross) 0.0 Mw $ w HPI Line Flow (1-1) 0.0/(1-2) 0.0 (2-1) 0.0/(2-2) 0.0 n LPI Line Flow (1-1) 0.0/(1-2)3065.4 gpm OTHER < DHR Hz Inlet Temp. (1/2) 70.6/ 149.6 "F Instrument / Service Air NORM / NORM $ CTNT Spray Flow (1/2) 0.0/ O.0 gpm Spent Fuel Pool Level / Temp. 23.5 ft/ 100.2 *F c CCW Surge Tank Level (1/2) 48.0/ 49.0 in $ LWST Level 30.2 ft CCW 8x Outlet Temp. 80.0/ 82.2 *F e
..................**..**......................................****..... .................**.................. D-M 2
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7-93 1993 Evaluated Exercise 7.4 CONTROL ROOM ALARM PANELS This section provides individual Control' Room annunciator alarm sheets to be passed out to Players in the event the Control Room Simulator-becomes unavailable to conduct'the Exercise. If the simulator is running, it will automatically provide all operational alarms as events progress, controllers should not provide hardcopy or verbal alarm data to the Players as.long as the simulator is running. Players should respond to the alarm conditions as they would normally. If the simulator should malfunction, however, during the course of the . Exercise, controllers are then permitted to release the data provided in this section. I i l 4 ~ . - - - - . _ _ - . _ _ . _ _ _ _ _ _ _ _ _ _ . - _ _-_ - - - .- _.. . . - _ . . . - _ . . . . . -- -. .
n Ala In Alarm SFAS \ CRD car u ARTS om
/ oeic RPS case cea cu.
nas u ,ess u res, u n2 m u SrxS SrAS SFAS Cno ,m3 s RPS ReS RPS neS CH4 O SPAS CTMTPRES RCPRESS RCPRESS CH1 CH2 CH3 C NTRAD LCO CHTR P TRP O 1 E!P TRP chm'P >18.4 PS!A CHTRP
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8-1 1993 Evaluated Exercise O 8.0 IN-PLANT RADIOLOGICAL, RADIOCHEMISTRY AND MEDICAL DATA f This section provides in-plant and site dose rate information, radiochemistry and post accident sampling-information, and medical information for Controller use during site emergency response team missions. 8.1 IN-PLANT RADIATION MONITORS
SUMMARY
This section provides radiation monitor indications in a tabular format for ease of review and for ease of locating a particular monitor's reading in a timely manner. 8.2 RADIATION ELEMENT (RE) DATA SHEETS This section provides individual radiation monitor
- data sheets to be passed out to Players on a 15 minute basis should the Control Room Simulator become unavailable to conduct the Exercise.
8.3 PLANT RADIATION MAPS This section provides controller guidance to any In-plant Controller who may be sent out with a Player during conduct of the Exercise. The maps display radiation levels based on time in the event for all locations within the plant. ( 8.4 RADIOCHEMISTRY DATA
SUMMARY
This section provides radiochemistry data in a tabular format for ease of review and for ease of evaluating the content assumed for a specific . radionuclide. 8.5 RADIOCHEMISTRY DATA SHEETS This section provides individual radiochemistry data sheets to be passed out to Players during predesignated time frames should the identified samples be taken during conduct of the Exercise. 8.6 POST ACCIDENT SAMPLING DATA This section provides information for Controllers to use who may be monitoring Player activities during Post Accident Sampling System (PASS) operations. (The PASS operations this year will be simulated.) i T n ,-
8-2 1993 Evaluated Exercise 8.7 MEDICAL DRILL DATA O This section provides information for controllers to use when monitoring Player activities during the medical emergency. 8.8 MEDICAL DRILL CUE CARDS This section provides cue cards that will be needed to provide medical information to Players who are responding to the medical emergency. O O\ i l
e 8-3 1993 Evaluated Exercise 7- .t 8.1 IN-PLANT RADIATION MONITORS
SUMMARY
This section provides values of the in-plant fixed radiation monitors for controller use when simulating accident radiation conditions. This information we.s developed in conjuction with the Plant Simulator for consistency of data. The containment radiation monitor values were selected in a manner to be consistent with an approximate 35% gap release into the reactor coolant indicated by RE 4596 A/B and RE 4597 AB/BB channel 1 and 2 as depicted on the Containment Radiation EAL Plots on pages 22 and 23 of procedure HS-EP-01500. Because the release path does not directly dump into the Containment annulus, the SFAS monitors RE 2004, 2005, 2006 and 2007, which are located in the annulus between the containment vessel and the shield building, are effected by shine only. Using a shielding software program, Microshield version 3.09, the amount of shine was determined to be approximately a factor of 6.0E-04 less than the values for the RE 4596 monitors. Shine outside the shield building was determined to be negligible and thus the only increase in area monitors as indicated is due to shine and postulated leaks from the primary coolant letdown line, primary sampling activities, and the Containment breach into the #3 Mechanical Penetration Room. O i i O
-6 8-4 1993 Evaluated Exercise IN-PLANT RAD MONITORS
SUMMARY
ryp.: are monitor. . . . . . . . . ....................................... 1.ocation: 1 2 3 4 5 6 7 8 8 , laumber t RZ 8400 M 8401 M 8402 M 8403 M 8404/05 M 8406 M 8407 M 8408 M 8409 Time fmR/ht) (mR/hr) (mR/hr) (mR/hr) (mR/hr) (mR/hrt (mR/hrt (mR/hrt (mR/hrt 0800 0.60 0.40 2.00 3.00 2.00 0.30 0.20 4.00 3.00 0815 0.60 0.40 2.00 3.00 2.00 0.30 0.20 4.00 3.00 0830 0.60 0.40 2.00 3.00 2.00 0.30 0.20 4.00 3.00 0845 0.60 0.40 2.00 3.00 2.00 0.30 0.20 4.00 3.00 [ 0900 0.60 0.40 2.00 3.00 2.00 0.30 0.20 4.00 3.00 0915 0.60 0.40 2.00 3.00 2.00 0.30 0.20 4.00 3.00 0930 0.60 0.40 2.00 3.00 2.00 0.30 0.20 4.00 3.00 0945 0.60 0.40 2.00 3.00 2.00 0.30 0.20 4.00 3.00 1000 0.60 1.60 2.00 3.00 2.00 0.30 0.20 4.00 3.00 E 1015 0.60 2.30 2.00 3.00 2.00 0.30 0.20 4.00 3.00 1030 0.60 3.50 2.00 3.00 2.00 0.30 0.20 4.00 3.00 1045 0.60 6.20 2.00 3.00 2.00 0.30 0.20 4.00 3.00 L 1100 0.60 6.00 2.00 3.00 2.00 0.30 0.20 4.00 3.00 1115 0.60 7.60 2.00 3.00 2.00 0.30 0.20 4.00 3.00 1130 0.60 4.10 2.00 3.00 2.00 0.30 0.20 4.00 3.00 1145 0.60 5.90 2.00 3.00 2.00 0.30 0.20 4.00 3.00 2200 0.60 5.60 2.00 3.00 2.00 0.30 0.20 4.00 3.00 1215 0.60 5.40 2.00 3.00 2.00 0.30 0.20 4.00 3.00 1230 0.60 S.20 2.00 3.00 2.00 0.30 0.20 4.00 3.00 1245 0.60 S.00 2.00 3.00 2.00 0.30 0.20 4.00 3.00 1300 0.60 4.70 168.00 180.00 150.50 0.30 0.20 4.00 33.00 1315 0.60 4.30 196.00 200.00 178.40 0.30 0.20 4.00 50.00 1330 0.60 4.10 225.00 238.00 206.20 0.30 0.20 4.00 845.00 - 1345 0.60 3.80 260.00 274.00 232.40 0.30 0.20 4.00 950.00 1400 0.60 3.40 282.00 294.00 253.00 0.30 0.20 4.00 1100.00 1415 0.60 3.20 297.00 311.00 264.10 0.30 0.20 4.00 1052.00 1430 0.60 3.10 290.00 290.00 255.00 0.30 0.20 4.00 344.00 , 1445 0.60 2.80 287.00 293.00 241.00 0.30 0.20 4.00 88.00
- 1500 0.40 2.50 285.00 290.00 238.30 0.30 0.20 4.00 46.00-i
..mmmmazmsnm.sm.mmmmm.mme==...mm..mmmmm.mmmm.mmm...mmmmmm..m.mmmmmm....m.amammes.m.m Location Legend:
1 - Maintenance Work Area, Room 109 2 - Primary Sample Hood Area, Room 106 3 - ECCS Pump Room #1 (West), Room 105 4 - ECCS Pump Room #2 (East), Room 115 5 - Decay Beat Exchanger Pit, Rcom 113 6 - Miscellaneous Waste Evaporator Room, Room 116 7 - Waste Gas Valve Access Room, Room 122 8 - Detergent Waste Drain and Pump Room, Room 125 9 - Mechanical Penetration Room #1 (West), Room 208
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8-5 1993 Evaluated Exercise IN-PLANT RAD MONITORS
SUMMARY
Typet Area Monitors . . . . . . . . .................. ................ . . Location: 1 2 3 4 5 6 7 e 9 Numbers RE 9410/11 RE B412 RE 0413 RE 8414/15 RE 8416 RE 0417 RE Seit RE 8419 RE 8420 Tire (mR/hr) ImW/hrt (mR/hrt (mR/br) (mR/hrt fmR/hrt imR/hrt imR/hrt imR/hrt 0800 0.32 20.0 1.50 0.15 0.20 0.40 0.30 0.90 0.20 0815 0.32 20.0 1.50 0.15 0.20 0.40 0.30 0.90 0.20 0930 0.32 20.0 1.50 0.15 0.20 0.40 0.30 0.90 0.20 0045 0.32 20.0 1.50 0.15 0.20 0.40 0.30 0.90 0.20 0900 0.32 20.0 1.50 0,15 0.20 0.40 0.30 0.90 0.20 0915 0.32 20.0 1.50 0.15 0.20 0.40 0.30 0.90 0.20 0930 0.32 20.0 1.50 0.15 0.20 0.40 0.30 0.90 0,20 0945 0.32 20.0 1.50 0.15 0.20 0.40 0.30 0.90 0.20 1000 0.32 20.0 1.50 0.15 0.20 0.40 0.30 0.90 0.20 1015 0.32 20.0 1.50 0.15 0.20 0.40 0.30 0.90 0.20 1030 0.32 20.0 1.50 0.15 0.20 0.40 0.30 0.90 0.20 1045 0.32 20.0 1.50 0.15 0.20 0.40 0.30 0.90 0.20 1100 0.32 20.0 1.50 0.15 0.20 0.40 0.30 0.90 0.20 1115 0.32 20.0 1.50 0.15 0.20 0.40 0.30 0.90 0.20 1130 0.32 20.0 1.50 0.15 0.20 0.40 0.30 0.90 0.20 1145 0.32 20.0 1.50 0.15 0.20 0.40 0.30 0.90 0.20 2200 0.32 20.0 1.50 0.15 0.20 0.40 0.30 0.90 0.20 1215 0.32 20.0 1.50 0.15 0.20 0.40 0.30 0.90 0.20 1230 0.32 41.0 1.50 0.15 0.20 0.40 0.30 0.90 0.20 1245 0.32 20.9 1.50 0.15 0.20 0.40 0.30 0.90 0.20 1300 0.32 20.0 20.0 0.15 0.20 0.40 0.30 0.90 0.20 1315 0.32 20.0 85.0 0.15 10.00 0.40 0.30 0.90 65.00 1330 0.32 20.0 110.0 0.15 24.00 0.40 0.30 0.90 2.50E+03 1345 0.32 20.0 240.0 0.15 46.00 0.40 0.30 0.90 2.85E404 1400 0.32 20.0 265.0 0.15 59.00 0.40 0.30 0.90 6.658+03 1415 0.32 20.L 280.0 0.15 34.00 0.4D 0.30 0.90 1.258+03 1430 0.32 10.0 270.0 0.25 27.00 b.40 0.30 0.90 410.00 1445 0.32 20.0 265.0 0.15 22.00 0.40 0.30 0.90 165.00 1500 0.32 20.0 260.0 0.15 18.00 0.40 0.30 0.90 58.00 ================================================================mammmmmmmmmmmmmmmmen Location Legends 1 - corridor to Hechanical Penetration Room #1 (West), Room 208 2 - Clean Waste Polish and Purification Demineralizers Valve Room, Room 212 3 - Makeup Pump Room Vestibule, Room 226 4 - Boric Acid Evaporator Passageway, Room 227 5 - Hechanical Penetration Room #2 (East), Room 236 6 - Fuel Bandling Truck Bay (middle of bay) 7 - Fuel Handling Truck Bay (West vall) 8 - Drumming Area, Room 302 ; 9 - Mechanical Penetration Room 43 (East), Room 303 ==================================================================================== l l 1 l 1 I I
1 8-6 1993 Evaluated Exarcise l IN-PLANT RAD MONITORS
SUMMARY
\ Types Area Monitors . .... . .. . ..................................... locations 1 2 3 4 5 6 7 8 9 Numbert RE $421 RE $422 M 8423 RE 9424 RE 8425 RE S428/29 M S430 RE 8431 RZ 8435 Time (mR/hrt inR/hrt (mR/hrt fmR/hrt (mR/hrt (mR/hr) (mR/hr) (mR/br) (mR/hrt 0800 0.40 0.60 0.20 0.20 1.50 0.20 0.15 0.10 0.10 0815 0.40 0.60 0.20 0.20 1.30 0.20 0.15 0.10 0.10 0830 0.40 0.60 0.20 0.20 1.50 0.20 0.15 0.10 0.10 0845 0.40 0.60 0.20 0.20 1.50 0.20 0.15 0.10 0.10 0900 0.40 0.60 0.20 0.20 1.50 0.20 0.15 0.10 0.10 0915 0.40 0.60 0.20 0.20 1.50 0.20 0.15 0.10 0.10 0930 0.40 0.60 0.20 0.20 1.50 0.20 0.15 0.10 0.10 0945 0.40 0.60 0.20 0.20 1.50 0.20 0.15 0.10 0.10 1000 0.40 0.60 0.20 0.20 1.50 0.20 0.15 0.10 0.10 i 1015 0.40 0.60 0.20 0.20 1.50 0.20 0.15 0.10 0.10 1030 0.40 0.60 0.20 0.20 1.50 0.20 0.15 0.10 0.10 1045 0.40 0.60 0.20 0.20 1.50 0.20 0.15 0.10 0.10 1100 0.40 0.60 0.20 0.20 1.50 0.20 0.15 0.10 0.10 1115 0.40 0.60 0.20 0.20 1.50 0.20 0.15 0.10 0.10 - 1130 0.40 0.60 0.20 0.20 1.50 0.20 0.15 0.10 0.10 1145 0.40 0.60 0.20 0.20 1.50 0.20 0.15 0.10 0.10 1200 0.40 0.60 0.20 0.20 1.50 0.20 0.15 0.10 0.10 1215 0.40 0.60 0.20 0.20 1.50 0.20 0.15 0.10 0.10 1230 0.40 0.60 0.20 0.20 1.50 0.20 0.15 0.10 0.10 1245 0.40 0.60 0.20 0.20 1.50 0.20 0.15 0.10 0.10 1300 0.40 0.60 0.20 0.20 1.50 0.20 0.15 0.10 0.10 1315 7.00 0.60 0.20 0.20 1.50 0.20 0.15 0.10 0.10 1330 10.00 0.60 0.20 0.20 1.50 0.20 0.15 0.10 0.10 134b 24.00 0.60 0.20 0.20 1.50 0.20 0.15 0.10 0.10 1400 33.00 0.60 0.20 0.20 1.50 0.20 0.15 0.10 0.10 1415 30.00 0.60 0.20 0.20 1.50 0.20 0.15 0.10 0.10 1430 27.00 0.60 0.20 0.20 1.50 0.20 0.15 0.10 0.10 1445 21.00 0.60 0.20 0.20 1.50 0.20 0.15 0.10 0.10 1500 9.00 0.60 0.20 0.20 1.50 0.20 0.15 0.10 0.10
===============================mmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmma Location Legend 1 - Mechanical Penetration Room 44 (East), Room 314 2 - Hot Instrument Shop, Room 406 3 - Hot Lab Room, Room 424B 4 - Personnel Local Area, Room 426 5 - Mix Tanks and Batch Area, Room 313 6 - Passage to Access Corridor, Room 411 7 - Control Room 8 - Control Cabinet Room 9 - Condensate Polishing Demineralizers 1 & 2 Area 432 maammmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmma
8-7 1993 Evaluated Exercise IN-PLANT RAD MONITORS
SUMMARY
Type Area Monitors . . . . . . . . . . . . . . . . . . . . . . . . . . . . Process Monitors . . . . . . . . . Locations 1 2 3 4 5 6 7 8 9 Numbers RE 8436 RE 0437 RE 8419 RE 2387/39 RE 5436/27 RE 8446/47 RE 8432 RB 8433 RE 8434 Time f atP / b r i fmR/hr) (mR/hr) (mR/hr1 (mR/hrt fmR/hrt f eral fepal f erm ) 0800 0.30 0.20 0.15 2.23 0.30 0.20 70.0 100.0 80.0 0015 0.30 0.20 0.15 2.23 0.30 0.20 70.0 100.0 50.0 0830 0.30 0.20 0.15 2.23 0.30 0.20 70.0 100.0 00.0 0945 0.30 0.20 0.15 2.23 0.30 0.20 70.0 100.0 83.0 0900 0.30 0.20 0.15 2.23 0.30 0.20 70.0 100.0 80.0 0915 0.30 0.20 0.15 2.23 0.30 0.20 7P.0 100.0 30.0 0930 0.30 0.20 0.15 2.23 0.30 0.20 70.0 100.0 80.0 0945 0.30 0.20 0.15 2.23 0.30 0.20 70.0 100.0 80.0 1000 0.30 0.20 0.15 2.23 0.30 0.20 70.0 100.0 80.0 1015 0.30 0.20 0.15 2.23 0.30 0.20 70.0 100.0 30.0 1030 0.30 0.20 0.15 2.23 0.30 0.20 70.0 100.0 80.0 1045 0.30 0.20 0.15 2.23 0.30 0.20 70.0 100.0 80.0 1100 0.30 0.20 0.15 2.23 0.30 0.20 70.0 100.0 90.0 1115 0.30 0.20 0.15 3.688+03 0.30 0.20 70.0 100.0 80.0 1130 0.30 0.20 0.15 5.69E+03 0.30 0.20 70.0 100.0 80.0 1145 0.30 0.20 0.15 2.30E+04 0.30 0.20 70.0 100.0 80.0 3200 0.30 0.20 0.15 5.62E+04 0.30 0.20 70.0 100.0 60.0 1215 0.30 0.20 0.15 9.788+04 0.30 0.20 70.0 100.0 80.0 1230 0.30 0.20 0.15 1.33E+05 0.30 0.20 70.0 100.0 80.0 1245 0.30 0.20 0.15 2.40E+05 0.30 0.20 70.0 100.0 50.0 1300 0.30 0.20 0.15 1.35E+05 0.30 0.20 70.0 100.0 80.0 1315 0.30 0.20 0.15 1.23E+05 0.30 0.20 70.0 100.0 80.0 1230 0.30 0.20 0.15 1.19E+05 0.30 0.20 70.0 100.0 00.0 1345 0.30 0.20 0.15 1.173+05 0.30 0.20 70.0 100.0 80.0 1400 0.30 0.20 0.15 1.14E+05 0.30 0.20 70.0 100.0 00.0 1415 0.30 0.20 0.15 1.13E+05 0.30 0.20 70.0 100.0 80.0 1030 0.30 0.20 0.15 1.093+05 0.30 0.20 70.0 100.0 80.0 1445 0.30 0.20 0.15 9.985+04 0.30 0.20 70.0 100.0 80.0 1500 0.3D 0.20 0.15 9.85E+04 0.30 0.20 70.0 100.0 80.0 Location Legend 1 1 - Condensate Polishing Demineralizers 3 & 4 Area 432 2 - condensate Polishing Demineralizers Holdup Tank, Room 248 3 - Backwash Receiving Tank Area, Room 334 4 - containment 5 - Spent ruel Area 224 6 - Spent ruel Fool vent Area 224 7 - service Water Discharge Header 8 - Station Effluent Collection Box 9 - station Inlet, Forebay i
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I 8-8 1993 Evaluated Exercist j IN-PLANT RAD MONITORS
SUMMARY
j Type: Procese Monitors . . .. . . . ............ ........................ Locations 1 2 3 4 5 6 7 8 9 Numbers RE 4606 RE 600 RE 609 RE 744 RE 1003A/S RE 1412 RE 1413 RE 1770A/8 RE 1822A/5 , l Time f cre l f eral tenet fermi fcDel tensi f er.1 f ernt fenm) ; 0000 100.0 10.0 15.0 N/A 40.0 1.30E+03 2.00E+03 300.0 2.50E+03 0915 100.0 10.0 15.0 N/A 40.0 1.30E+03 2.00E+03 300.0 2.50E+03 l 0830 100.0 10.0 15.0 N/A 40.0 1.30B+03 2.00E+03 300.0 2.50E+03 0845 200.0 10.0 15.0 N/A 40.0 1.30E+03 2.00E+03 300.0 2.50E+03 -l 0900 100.0 10.0 15.0 N/A 40.0 1.30E+03 - 2.00E+03 300.0 2.50E403 0915 200.0 10.0 15.0 N/A 40.0 1.30E+03 2.00E+03 300.0 2.50E+03 0930 100.0 10.0 15.0 N/A 40.0 1.30E+03 2.00E+03 300.0 2.50E+03 0945 100.0 10.0 15.0 N/A 40.0 1.30E+03 2.00E+03 300.0 2.50E+03 1000 100.0 10.0 15.0 N/A 40.0 1.30E+03 2.00E+03 300.0 2.50E+03 1015 200.0 10.0 15.0 N/A 40.0 1.30E+03 2.00E403 300.0 2.50E+03 1030 100.0 10.0 15.0 N/A 40.0 1.30E+03 2.00E+03 300.0 2.50E+03 , 1045 200.0 10.0 15.0 N/A 40.0 1.30E+03 2.00E+03 300.0 2.50E+03 , 1100 100.0 10.0 15.0 N/A 40.0 1.30E+03 2.00E+03 300.0 2.50E+03 1115 100.0 10.0 15.0 N/A 40.0 1.30E+03 2.00E+03 300.0 2.50E+03 1130 100.0 10.0 15.0 N/A 40.0 1.30E+03 2.00E+03 300.0 2.50B+03 1145 100.0 10.0 15.0 N/A 40.0 1.30E+03 2.00E+03 300.0 2.50E+03 1200 100.0 10.0 15.0 N/A 40.0 1.30B+03 2.00E+03 300.0 2.50E+03 1215 100.0 10.0 15.0 N/A 40.0 1.30E+03 2.00E+03 300.0 2.50E+03 1230 100.0 10.0 15.0 N/A 40.0 1.30E+03 2.00E+03 300.0 2.50E+03 1245 100.0 10.0 15.0 N/A 40.0 1.30E+03 2.00E+03 - 300.0 2.50E+03 \ 1300 100.0 10.0 15.0 N/A 40.0 1.30E+03 2.00E+03- 300.0 2.50B+03 1315 100.0 10.0 15.0 N/A 40.0 1.30E+03 2.00E+03 300.0 2.50E+03 1330 100.0 10.0 15.0 N/A 40.0 1.30E+03 2.00E+03 300.0 2.50E+03 7 1345 100.0 10.0 15.0 N/A 40.0 1.30E+03 2.00E+03 300.0 2.50E+03 , 1400 100.0 10.0 15.0 N/A 40.0 1.30E+03 2.L*JE+03 300.0 2.50E+03 1415 200.0 10.0 15.0 N/A 40.0 1.30E+03 2.00E+03 300.0 2.50E+03 1430 100.0 10.0 15.0 N/A 40.0 1.30B+03 2.00E+03 300.0 2.50E+03 1445 100.0 10.0 15.0 N/A 40.0 1.30E+03 2.00E403 300.0 2.50E+03 1500 100.0 10.0 15.0 N/A 40.0 1.30E+03 2.00E+03 300.0 2.50E+03
. . . . . . = . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . = = . . . = . . . . . = . . . . . . . . . . . . . . . . . . . . = . . . . . . . = . = = ,
Location Legendt i 1 - Unit Storm Sewer Outlet ! 2 - Main Steam Line #2 l 3 - Main Steam Line il 4 - Condensate Demin Backwash Pump Disch. - no longer in service , 5 - Vacuum System Non-condensable Vent ) 6 - Component Cooling Return Line #1 7 - Component Cooling Return Line #2 8 - Clean Waste System Outlet 9 - Waste Gas System Outlet
====.......==....=..=. .. .........======. .===.==.====......==..==.===.==.===.=...=
l 1
8-9 1993 Evaluated Exercise IN-PLANT RAD MONITORS
SUMMARY
Types Process Monitors . . . . . . . . ..................... . . CTMT El Range Monitors 1.ocations 1 2 3 4 5 6 7 8 9 Nusbars RE 1878A/B RE 199b RE SD52A-C RE 5327A C RE 3328A-C RE 5403A-C RE 5405A-C RE 4596A RE 45965 Time (epm) f ere) t ern t f ere t ferm) f ere) f ere) (R/hr) (R/hr} 0800 1.50E+04 1.20E+04 8.00E+02 30.0 40.0 2.00E+03 2.00E+03 1.00 1.00 0815 1.50E+04 1.20E+04 8.00E+02 30.0 40.0 2.00E+03 2.00E+03 1.00 1.00 0830 1.50E+04 1.20E+04 8.00E+02 30.0 40.0 2.00E+03 2.00E+03 1.00 1.00 0845 1.50E+04 1 20E+04 8.00E+02 30.0 40.0 2.00E+03 2.00E+03 1.00 1.00 0900 1.50E+04 6.85E+05 8.00E+02 30.0 40.0 2.00E+03 2.00E+03 1.00 1.00 0915 1.50E+04 1.00E+06 8.00E+02 30.0 40.0 2.00E+03 2.005403 1.00 1.00 0930 1.50E+04 1.00E+06 0.00E+02 30.0 40.0 2.00E+03 2.00E+03 1.00 1.00 0945 1.50E+04 1,00E+06 8.00E+02 30.0 40.0 2.00E+03 2.00E+03 1.00 1.00 1000 1.50E+04 1.00E+06 8.00E+02 30.0 40.0 2.00E+03 2.00E+03 1.00 1.00 1015 1.50E+04 1.005406 8.00E+02 30.0 40.0 2.00E+03 2.00E+03 1.00 1.00 1030 1.50E+04 1.00E+06 8.00E+02 30.0 40.0 2.00E+03 2.00E+03 1.00 1.00 1045 1.50E+04 1.00E+06 8.00E+02 30.0 40.0 2.00E+03 2.00E+03 1.00 1.00 1100 1.50E404 1.00E+06 8.00E+02 30.0 40.0 2.00E+03 2.00E+03 1.00 1.00 1115 1.50E+04 1.00E+06 8.00B+02 30.0 40.0 2.00E+03 2.00E+03 1.50 1.48 1130 1.50E+04 1.00E+06 0.00E+02 30.0 40.0 2.00E+03 2.00E+03 3.72 3.66 1145 1 50E+04 1.00E+0$ 8.00E+02 30.0 40.0 2.00E+03 2.00E+03 5.70 5.55 1200 1.50E+04 1.00E+06 d.00E+02 30.0 40.0 2.00E+03 2.00E+03 23.3 23.2 1215 1.50E+04 1.00E+06 0.00E402 30.0 40.0 2.00E+03 2.00E+03 56.4 55.0 1230 1.50E+04 1.00E+06 8.00E+02 30.0 40.0 2.00E+03 2.00E+03 98.2 97.6 1245 1.50E+04 1.00E+06 8.00E+02 30.0 40.0 2.00E+03 2.00E+03 1.45E+02 1.42E+02 1300 1.50E+04 1.00E+06 8.00E+02 30.0 40.0 2.00E+03 2.008+03 2.50E+02 2.47E+02 1315 1.50E+04 1.00E+06 8.00E+02 30.0 40.0 2.00E+03 2.00E+03 1.40E+02 1.38E+02 1330 1.50E+04 1.00E+06 6.00E+02 30.0 40.0 2.00E+03 2.00B403 1.38E+02 1.36E+02 1345 1.50E+04 1.00E+06 8.00E+02 30.0 40.0 2.00B+03 2.008+03 1.35E+02 1.33E+02 1400 1.50E+04 1.00E+06 8.00E402 30.0 40.0 2.00E+03 2.00E+03 1.33E+02 1.30E+02 1415 1.50E+04 1.00E+06 8.00E+02 30.0 40.0 2.00E+03 2.00E+03 1.30E+02 1.27E+02 1420 1.50E+04 1.00E+06 8.00E+02 30.0 40.0 2.00E+03 2.00E+03 1.2 0 E+02 1.25E+02 1d45 1.50E+04 1.00E+06 8.00E+02 30.0 40.0 2.00E+03 2.00E+03 1.25B+02 1.42 E SJ2 1500 1 50E+04 1.00E+06 8.00E+02 30.0 40.0 2.00E+03 2.00E+03 1.20E+02 1.18E+02 .................................................................a................... Location Legend: 1 - Misc. Waste System 2 - Failed Fuel Detector 3 - Containment Purge Exhaust 4 - Control Room Filter #1 Discharge 5 - Control Room Filter #2 Discharge 6 - Fuel Handling Area Exhaust 7 - Radwaste Area Exhaust 8 - Containment 9 - Containment e
, , -- - - --. -. . . ~ - . - - -- ~ . 8 -l'0 1993 Evaluated Exercise l IN-PLANT RAD MONITORS
SUMMARY
CTKr Air Normal Range Monitors . CTMT Air Accident Range Monitors ' Type: ........... . . .. .. . Location: 1 2 3 4 5 6 7 8 9' Numbers RE 4597AA RE 4597BA RE 4597AA RE 4597BA RE 4597AA RE 4597BA RE 4597AB RE 45978B RE 4597AB Ch. 1 Ch. 1 Ch. 2 Ch. 2 Ch. 3 Ch. 3 Ch. 1. Ch. 1- Ch. 2 Time fuci/cel fuci/ect fuci/cel fuci/eci fuci/ccl fuC1/ect fuC1/ect fuC1/cel (pC1/cel ; 0800 1.005-07 1.00E-07 2.00E-10 2.00&l0 1.00E-11 1.00E-11 0.00E+00 0.00E+00 0.00E+00 , 0815 1.00E-07 1.00E-07 2.00E-10 2.00E .0 1.00E-11 1.00E-11 d.00E+00 0.00E+00 0.00E+00 0830 1.008-07 1.00E-07 2.00E-10 2.00E-10 1.00E-11 1.00E-11 0.00E+00 0.00E+00 0.00E+00 0845 1.00E-07 1.00E-07 2.00E-10 2.00E-10 1.00E-11 1.00E-11 0.00E+00- 0.00E+00 0.00E400 0900 1.00E-07 1.00E-07 2.00E-10 2.00E-10 1.005-11 1.00E-11 0.00E+00 0.00E+00 0.00E+00 t 0915 1.0DE-07 1.00E-07 2.00E-10 2.00E-10 1.00E*11 1.00E-11 0.00E+00 0.00E+00 0.00E+00 0930 1.00r-17 1.00E-07 2.00E-10 2.00E-10 1.00E-11 1.00E-11 0.00E+00 0.00B+00 0.00E+00 0945 1.005-07 1.005-07 2.00E-10 2.00E-10 1.005-11 1.00E-11 0.00E+00 0.00E+00 0.00E+00 [ 1000 1.00E-07 1.00E-07 2.00E-10 2.00E-10 1.00E-11 1.00E-11 0.00E+00 0.00E+00 0.00E+00 1015 1.00E-07 1.00E-07 2.00E-10 2.00E-10 1.00E-11 1.00E-11 0.00E+00 0.00E+00- 0.00E+00 1030 1.00E-07 1.00E-07 2.00E-10 2.00E-10 1.00E-11 1.00E-11 0.00E+00 0.00B+00 0.00E+00 1045 1.00E-07 1.00E-07 2.00E-10 2.00E-10 1.003-11 1.00E-11 0.00E+00 0.00E+00 0.00E+00 1 1100 1.00E-07 1.00E-07 2.00E-10 2.00E-10 1.005-11 1.005-11 0.00E+00 0.00E+00 0.00E+00 1115 4.30E-06 5.80E-06 4.00E-09 4.00E-09 1.10E-11 1.10E-11 0.00E+00 0.00E+00 0.00E+00 r 1130 6.55E-02 8.70E-02 4.50E-08 4.50E-08 1.155-11 1.15E-11 6.76E-02 6.68E-02 1.00E+01 1145 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.60E+00 5.59E+00 1.00E+01 1200 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.30E+00 6.27E400 1.00E+01 1215 0,00E+00 0.00E+00 0.00E+00 0.00E+00 0.008400 0.00E+00 '1.10E+01 1.06E+01 1.12E+01 1230 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.2SE+01 3.22E+01 -3.27E+01 0 1245 1300 0.00E+00 0.00B+00 0.00E+00 0.00B+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.12E+01 4.368+01 4.082+01 4.33E+01 4.14E+01 4.3BE+01 1315 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.07E+01 3.985+01 4.093+01 1330 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.05E+01 3.975+01 4.07E+01 f 1345 0.00E+00 -0.00E+00 0.008400 0.00E+00 0.00E+00 0.00E+00 3.90E+01 3.89E+01 3.92E+01 b 1400 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E400 3.875+01 3.85E+01 3.89E401 1415 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.81E+01 3.79E+01. 3.83E+01 1430 0.00E+00 0.00E400 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.79E401 3.765+01 3.81E+01 1445 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.77E+01 3.74E+01 3.79E+01 1500 0.00E+00 0.00E+00 0.00E+00 0.00E400 0.00E400 0.00E+00 3.75B+01 3.72E+01 3.77E+01
==================================================================================== ,
Location Legend 1 - Noble Gas ; 2 - Noble Gas 3 - Particulate , 4 - Particulate 5 - Iodine 6 - Iodine 7 - Noble Gas 8 - Noble Gas 9 - Noble Gas
====================================================================================
B 1
8-11 1993 Evaluated Exercise IN-PLANT RAD MONITORS
SUMMARY
Type: CTMT Air Accident Range Monitoxe .. . . . . . . . . . . Station Vent Normal Range 7 8 9 Locations 1 2 3 5 6 Humbers RE 4597B9 RE 4597AB RE 4597BB RE 4597AD RE 4597BD RE 4597AD RE 4597BB RE 4598AA RE 4598BA Ch. 2 Ch. 3 Ch. 3 Ch. 4 Ch. 4 Ch. 5 Ch. 5 Ch. 1 Ch. 1 Time (pC1/cc) (mR/ht) (rR/hr) (mR/hr) (mR/hrt (mR/hr) (mR/hr) (pCl/ce) (pCi/cc) 0800 0.0DE+00 0.00E600 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00Ee00 1.00E-07 1.00E-07 0815 0.00E+00 0.00E+00 0.00E600 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.00E-07 1.00E-07 0830 0.00E600 0.00E+00 0.00E+00 0.00E400 0.00E+00 0.00E+00 0.00E+00 1.00E-07 1.00E-07 0045 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.00E-07 1.00E-07 0900 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E400 1.00E-07 1.00E-07 0915 0.00E400 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E400 0.00E+00 1.00E-07 1.00E-07 0930 0.00E+00 0.00E+00 0.00E400 0.00E400 0.0DE+00 0.00E+00 0.00E+00 1.00E-07 1.00E-07 0945 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.00E-07 1.00E-07 1000 0.00E+00 0.00E+00 0.00E400 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.00E-07 1.00E-07 1015 0.00E400 0.00E+00 0.00E+00 0.005400 0.00E+00 0.00E+00 0.008400 1.00E-07 1.00E-07 1030 0.00E+00 0.00E+00 0.00E400 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.00E-07 1.00E-07 1045 0.00E+00 0.00E+00 0.00E600 0.00E+00 0.00E+00 0.00E400 0.00E+00 1.00E-07 1.00E-07 1100 0.00E+00 0.00E400 0.00E+00 0.00E+00 0.00E+00 0.00E400 0.00E400 1.00E-07 1.00E-07 1115 0.00E400 0.00E*00 0.00E+00 0.00E400 0.00E+00 0.00E+00 0.00E+00 1.00E-07 1.00E-07 1130 1.00E401 1.00E-03 1.00E-03 1.00E-03 1.00E-03 1.00E-03 1.00E-03 1.00E-07 1.00E-07 1145 1.00E401 5.50E-03 5.50E-03 5.50E-03 5.50E-03 5.50E-03 5.50E-03 1.00E-07 1.00E-07 1200 1.00E+01 B.00E-03 9.00E-03 9.00E-03 8.00E-03 8.00E-03 B.00E-03 1.00E-07 1.00E-07 1215 1.16E+01 2.50E-02 2.5DE-02 2.50E-02 2.50E-02 2.50E-02 2.50E-02 1.00E-07 1.00E-07 1230 3.31E401 4.00E-02 4.00E-02 4.00E-02 4.00E-02 4.00E-02 4.00E-02 1.00E-07 1.00E-07 1245 4.1BE+01 5,50E-02 5.50E-02 5.50E-02 5.50E-02 5.50E-02 5.50E-02 1.00E-07 1.00E-07 1300 4.42E+01 7.00E-02 7.00E-02 7.00E-02 7.00E-02 7.00E-02 7.00E-02 1.00E-07 1.00E-07 1315 4.13E401 6.5CE-02 6.50E-02 6.50E-02 6.50E-02 6.50E-02 6.50E-02 6.50E-02 6.62E-02 1330 4.11E601 6.00E-02 6.00E-02 6.00E-02 6.00E-02 6.00E-02 6.00E-02 0.00E+00 0.00E+00 1345 3.96E+01 5.50E-02 5.50E-02 5.50E-02 5.50E-02 5.50E-02 5.50E-02 0.00E+00 0.005400 1400 3.9]E+01 5.00E-02 5.00E-02 5.00E-02 5.00E-02 5.00E-02 5.00E-02 0.00E+00 0.00E+00 1415 3.87E+01 4.50E-02 4.50E-02 4.5DE-02 4.50E-02 4.50E-02 4.50E-02 0.00E+00 0.00E+00 1430 3.95E401 4.00E-02 4.00E-02 4.00E-02 4. DOE-02 4.00E-02 4.00E-02 0.00E+00 0. DOE +00 1445 3.63E+01 3.50E-02 3.50E-02 3.50E-02 3.50E-02 3.50E-02 3.50E-02 4.B8E-03 4.82E-03 1500 3.E1E+01 3.00E-02 3.0CE-02 3.00E-02 3.002-02 3.00E-02 3.00E-02 3.92E-04 3.93E-04
=n=-a===============================================u==_===.=========
Location Legend: 1 - Noble Gas 2 - Particulate / Iodine 3 - Particulate /Iodino 4 - Particulate / Iodine 5 - Particulate / Iodine 6 - Particulate / Iodine 7 - Particulate / Iodine 0 - Noble Gas 9 - Noble Gas
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9
-. . - - . . - - ._ . .. _. - ~ --- .- - .- -. ... 8-12 1993 Evaluated Exercise IN-PLANT RAD MONITORS
SUMMARY
Types station Vent Normal Range Monitore . . . . . . Station Vant Accident Range Monitore . . . . . . . . . . . 1.ocations 1 2 3 4 5 6 7 8 9 Numbert RE 4598AA RE 4598DA RE 4598AA RE 4598BA RE 4598AB RE 459888 RE 4590AD RE 459888 RE 4598AB l Ch. 2 Ch. 2 Ch. 3 Ch. 3 Ch. 1 Ch. 1 Ch. 2 Ch. 2 Ch. 3 i Time iucl/cc) {pCl/cc1 f9C1/ec) fuCi/cc) fuCi/ecI fpCl/cc) fuCl/cci iDCl/cc) imR/hr1 0800 1.00E-10 1.00E-10 1.00E-10 1.00E-10 0.00E+00 0.00E+00 0.00E*00 0.00E+00 0.00E+00 0815 1.00E-10 1.00E-10 1.00E-10 1.00E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I 0810 1.00E-10 1.00E-10 1.00E-10 1.00E-10 0.00E+00 0.008400 0.00E+00 0.00E+00 0.00E+00 0845 1.00E-10 1.00E-10 1.00E-10 1.00E-10 0.00E+00 0.005600 0.00E+00 0.00E+00 0.00E+00 ,. 0900 1.00E-10 1.00E-10 1.005-10 1.00E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0915 1.00E-10 1.00E-10 1.00E-10 1.00E-10 0.00E+00 0.00E+00 0.00E400 0.00E+00 0.00E+00 0930 1.00E-10 1.00E-10 1.00E-10 1.00E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0945 1.00E-10 1.005 10 1.005-10 1.00E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1000 1.00E-10 1.00E-10 1.00E-10 1.00E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1015 1.00E-10 1.00E-10 1.005-10 1.00E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
-{
1010 1.00E-10 1.00E-10 1.00E-10 1.00E 10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1045 1.00E 10 1.002-10 1.005-10 1.00E-10 0.00E+00 0.00E400 0.00E400 0.00E+00 0.00E+00 l 1100 1.00E-10 1.00E-10 1.00E-10 1.00E-10 0.00E*00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1115 1.00E-10 1.00E-10 1.00E-10 1.00E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.005&00 1130 1.00E-10 1.005-10 1.00E-10 1.00E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ~ 0.00E+00 ! 1145 1.00E-10 1.005-10 1.00E-10 1.005-10 0.005600 0.00E+00 0.00E+00 0.00E400 0.00E+00 , 1200 1.00E-10 1.00E-10 1.00E-10 1.00E-10 0.00E+00 0.00E+00 0.008600 0.00E+00 0.00E+00 1215 1.00E-10 1.00E-10 1.00E 10 1.00E-10 0.00E+00 0.00E400 0.00E+00 0.00E+00 0.00E+00 1230 1.00E-10 1.00E-10 1.00E-10 1.00E-10 0.00E+00 0.00E+00 0.005400 0.00E+00 0.00E+00 . f 1245 1.00E-10 1.00E-10 1.00E-10 1.00E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00B+00 ! 1300 1.00E-10 1.005-10 1.00E-10 1.00E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1315 1.00E-10 1.00E-10 4.36E 10 4.40E-10 6.60E-02 6.62E-02 0.00E+00 0.00E+00 8.10E-01 i 1330 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.41E+00 2.45E+00 0. DOR +00 0.00E+00 5.10E+00 1345 0.00E+00 0.00E400 0.00B+00 0.00E+00 2.61E+01 2.71E+01 2.688+01 2.70E+01 '2.$0E+01 , 1400 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.395+00 6.41E+00 6.40E+00 6.40E+00 2.45E401 1415 0.00E+00 0.005600 0.00E+00 0.00E400 8.078-01 8.12E-01 8.11E-01 8.10E-01 2.40E+01 1430 0.00E+0D 0.00E+00 0.00E+00 0.00E+00 3.80E-02 3.868-01 3.775-01 3.788-01 2.35E+01 1445 3.40E-09 3.45E-09 6.75E-08 6.70E-08 0.00E+00 0.00E400 0.00E+00 0.00E400 0.00E+00 1500 6.05E-10 6.12E-10 7.32E-09 7.28E-09 0.00E+00 0.00Et00 0.00E+00 0.00E+00' '0.00E+00 ' i maammmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmme ? Location Legends 1 - Particulate 2 - Particulate 3 - Iodino , 4 - Iodine 5 - Noble Gas 6 - Noble Gas 7 - Noble Gas B - Noble Gas 9 - Particulate / Iodine mmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmm=mmmmmmmmmmmmmmmmmmmmmmme=mmmmmmmmmmmmmmmm=mmaz
?
f r 6
8-13 1993 Evaluated Exercise IN-PLANT RAD MONITORS
SUMMARY
Types Station Vent Accident Range Mosiltorm . ..... SFAS Monitose . . . . . . . . . . Locations 1 2 3 4 5 6 7 8 9 Humbers RE 459BBB RE 459BAB RE 4598BB RE 459 BAB RE 4598DB RE 2004 RE 2005 RE 2006 RE 2007 Ch. 3 Ch. 4 Ch. 4 Ch. 5 Ch. 5 Time (mR/hr) ( mR /h r ) (mR/hr) (mR/hr) (nP/hr) (mR/hr) (mR/hrt fmR/hr) (mR/hr) 0800 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.0 3.0 20.0 2.0 0915 0.00E+00 0.00K+00 0.00E400 0.00E+00 0.00E+00 9.0 3.0 20.0 2.0 0830 0.00E+00 0.00E400 0.00E+00 0.00E+00 0.00E+00 9.0 3.0 20.0 2.0 0045 0.0DE400 0.00E400 0.00E+00 0.00E400 0.00E+00 9.0 3.0 20.0 2.0 0900 0.0DE+00 0.00E+00 0.00E600 0.00E+00 0.00E+00 9.0 3.0 20.0 2.0 0915 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+DO 9.0 3.0 20.0 2.0 0930 0.00E+00 0.00E400 0.00E+00 0.00E+00 0.0DE+00 9.0 3.0 20.0 2.0 0945 0.00E+00 0.00E+00 0.00E400 0.00E+C0 0.00E+00 9.0 3.0 20.0 2.0 1000 0. DOE 400 0.00E+00 0.00E600 0.00E+00 0.00E+00 9.0 3.0 20.0 2.0 1015 0.00E+00 0.00E+00 0.00E+00 0.00E600 0.00E+00 9.0 3.0 20.0 2.0 1030 0.00E400 0.00E+00 0.0DE+00 0.00E+00 0.00E+00 9.0 3.0 20.0 2.0 1045 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 9.0 3.0 20.0 2.0 1100 0.00E+00 0.00E+00 0.00E400 0.00E+00 0.00E+00 9.0 3.0 20.0 2.0 1115 0.00E+00 0.00E&D0 0.00E+00 0.00E+00 0.00E+00 9.0 3.0 20.0 2.0 1130 0.00E+00 0.00E+00 0.00E+00 0.0DE+00 0.00E400 9.0 3.0 20.0 2.0 1145 0.00E+00 0.00E400 0.00E+00 0.00E600 0.00E400 9.0 B.7 20.0 B.5 1200 0.00E+00 0.00E+00 0.00E400 0.00E+00 0.00E+00 13.9 12.4 20.0 11.0 1215 0.00E+00 0.00E+00 0.00E+00 0.00E400 0.00E+00 33.8 31.7 35.8 30.2 1230 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 58.9 56.7 60.1 55.2 1245 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 87.0 05.2 89.3 04.4 1300 0.00E400 0.00E+00 0.00E+00 0.00E+00 0.00E+00 150.0 149.7 151.8 146.2 1315 8.00E-01 1.00E-03 1.00E-03 1.00E-03 1.00E-03 84.0 Bl.9 85.9 90.1 1330 5.05E+00 1.00E-03 1.00E-03 1.00E-03 1.00E-03 81.0 80.1 83.0 78.2 1345 2.45E+01 2.20E+02 2.25E+02 3.72E404 3.70E+04 79.9 78.0 91.2 76.0 1400 2.42E401 2.15E+02 2.20E+02 9.79E603 9.75E+03 77.5 76.4 79.0 74.5 1415 2.38E401 2.10E+02 2.15E+02 1.69E603 1.66E+03 75.2 74.5 77.0 72.1 1430 2.30E+01 2.05E402 2.10E+02 7.25E+02 7.22E402 74.4 72.9 76.6 71.8 1445 0.00E400 0.00E+00 0.00E+00 0.00E+00 0.00E+00 73.1 71.7 75.4 69.9 1500 0.0DE+00 0.00F+00 0.00E400 0.00E+00 0.00E+00 72.0 70.0 74.0 69.0
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Location Legend 1 1 - Particulate / Iodine i 2 - Particulate / Iodine ) 3 - Particulatc/Iodinc l 4 - Particulate / Iodine 5 - Particulate / Iodine 6 - SFAS Ch. 1 Cabinet l 7 - SFAS Ch. 2 Cabinet l 8 - SFAS Ch. 3 Cabinet 9 - SFAS Ch. 4 Cabinet = _ _ _ _ _ _ _ _ _ _ _ _ _ = _ _ _ _ _ _ _ _ _ _ _ === _ = 9
8-14 1993 Evaluated Exercise 8.2 RADIATION ELEMENT (RE) DATA SHEETS This section provides individual radiation monitor data sheets to be passed out to Players on a 15 minute basis should the Control Room simulator become unavailable to conduct the Exercise. These-data sheets should oniv be veed when directed to by the Lead Exercise Controller. 9 P 1 L-) i l l i
DAVIS-PESSE NUCLEAR POWER STATION RE DATA SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 0800 TO1 Player at the Control RooEl RE Panels T: 00/00 THIS IS A DRILL DO NOT initiate actions affecting normal o
........................................................................perations.
C5765-4 C5765-E RE4597BA RE1878A 1.50E+04 eps RE609 15.0 epe Ch 1 NG 1.00E-07 pCi/cc RE1770A 300.0 eps RE600 10.0 epn Ch 2 P 2.00E-10 pC1/cc RE1822A 2.50E+03 epe RE8427 0.30 mR/hr Ch 3 I 1.00E-11 pCi/cc RE5403A 2.00E+03 epe RE8403 3.00 mR/br RE4598BA RE5403B 30.0 epa RE8405 5.00 mR/hr Ch 1 NG 1.00E-07 pC1/ec RE5403C 40.0 epa RE8411 3.12 mR/br Ch 2 P 1.00E-10 pCi/ce C5765-8 RE8413 1.50 mR/hr Ch 3 I 1.002-10 pC1/cc RE1003A 40.0 eps RE8414 0.15 mR/hr RE4597BB RE5052A 8.00E+02 epe RE8416 0.20 mR/hr Ch 1 NG 0.00E+00 pCi/cc RE50529 50.0 eps RE8417 0.40 mR/br Ch 2 NG 0.00E+00 pC1/cc RE5052C 30.0 era RX8420 0.20 mR/hr Ch 3 PI 0.00E+00 mR/hr RE8432 70.0 epa RE8421 0.40 mR/hr Ch 4 PI O.00E+00 mR/hr m RE8434 70.0 eps RE8422 0.60 mR/hr Ch 5 PI 0.00E+00 mR/hr 8 RE8433 100.0 epa RE8423 0.20 mR/hr RE4598BB $ RE1998 1.20E+04 epe RE8424 0.20 mR/hr Ch 1 NG 0.00E+00 pCi/ce RE8425 1.50 mR/hr Ch 2 NG 0.00E+00 pCi/cc C5765-C RE8428 0.20 mR/br Ch 3 PI 0.00E+00 mR/hr RE18785 1.50E+04 epa RE8430 0.15 mR/hr Ch 4 PI 0.00E+00 mR/hr RE17705 250.0 epa Ch 5 PI 0.00E+00 mR/hr RE1822B 3.00E+03 epe C5765-F RE45968 1.00 R/hr RE5405A 2.00E+03 epa RE4686 100.0 epa RE4597AA RE54058 100.0 epm RE8436 0.30 mR/hr Ch 1 NG 1.00E-07 pCi/cc RZ5405C 150.0 epa RE8435 0.10 mR/hr Ch2P 2.00E 10 pC1/cc C5765-D RE8438 0.15 mR/br Ch 3 I 1.00E-11 pCi/ec RE1003B 40.0 epe RE8437 0.20 mR/hr RE4598AA RE8419 0.90 mR/hr Ch 1 NG 1.00E-07 pCi/cc RE8426 0.30 mR/hr C5755-8 Ch2P 1.00E-10 pCi/cc RE8400 0.60 mR/hr RES328A 40.0 epa Ch 3 1 1.005-10 pC1/cc g RE8401 0.40 mR/hr RES3288 12.0 cps RE4597AB W RE8402 2.00 mR/hr R25328C 22.0 cpm Ch 1 NG 0.00E+00 pCi/cc $ RR8404 2.00 mR/hr RE1413 2.00E+03 eps Ch 2 NG 0.00E+00 pCi/cc RE8406 0.30 mR/hr RS2389 2.43 mR/hr Ch 3 PI 0.00E+00 mR/hr RE8407 0.20 mR/hr RE8447 0.10 mR/br Ch 4 FI 0.00E+00 mR/hr D RE8408 4.00 mR/hr Ch 5 PI 0.00E+00 mR/hr [ RE8409 3.00 mR/hr C5762-8 RE4598AB D RE8410 0.32 mR/hr RE5327A 30.0 cpm Ch 1 NG 0.00E+00 pCi/ec g RE8412 20.0 mA/br RE53278 10.0 cpm Ch 2 NG 0.00E+00 pCi/cc D. RE8415 0.30 mR/hr RES327C 20.0 era Ch 3 FI 0.00E+00 mR/hr g RE8418 0.30 mR/hr RE1412 1.30E+03 epe Ch 4 PI 0.00E*'O mR/hr M RE8429 0.15 mR/hr RE2387 2.23 mR/hr Ch 5 PI O . 0 0E- 5 mR/hr h RE8431 0.10 mR/hr RE8446 0.20 mR/hr RE4596A 1.00 R/hr O G , 9 O O
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DAVIS-EE::SE NUCLEAR POWER STATION RE DATA SREET SCENARIO NO. 1993 Evaluated Exercise TIME: 0830 TO: Player at the Control Rocal R.E Panels T: 00/30 THIS IS A DRILI, DO NOT initiate actions af fecting norinal operations. C5165-4 c5765-E R24597BA R21879A 1.50E+04 ep R2609 15.0 ep Ch 1 BC 1.002-07 pCi/ce R21770A 200.0 era R2600 10.0 ep Ch 2 P 2.00E-10 pCi/cc R21922A 2.50E+03 eps R29427 0.30 mA/hr Ch 3 I 1.005-11 pC1/ce R25403A 2.00E+03 ep R29403 3.00 mR/hr R24599BA R25403B 30.0 era R39405 5.00 mR/hr Ch 1 NG 1.002-07 pC1/cc RE5403C 40.0 epe R28411 3.12 mR/hr Ch 2 P 1.00E-10 pC1/ec C5765-9 R29413 1.50 mR/hr Ch 3 I 1.00E-10 pCi/cc R21003A 40.0 epe R39414 0.15 mR/br R34597B9 R25052A 9.00E+02 ep R29416 0.20 mA/hr Ch 1 NG O.00E+00 pC1/ec RE30528 50.0 ep R39417 0.40 mR/hr Ch 2 NG 0.00E+00 pCi/ec R25052C 30.0 cym R29420 0.20 mR/br Ch 3 P1 0.00E+00 mR/br R29432 70.0 cyn R29421 0.40 mR/hr Ch 4 PI 0.00E+00 mA/hr e R!t434 70.0 epe RE9422 0.60 mR/hr Ch 5 PI 0.00E+00 mR/hr 8 RE9433 100.0 epe R29423 0.20 mA/hr R24598PB [ R21998 1.2CE+04 epa R29424 0.20 mAihr Ch 1 NG 0.00E+00 pCi/ec R29425 1.50 mA/hr Ch 2 NG 0.00E+00 pC1/ec C5765-C R28429 0.20 mR/hr Ch 3 PI 0.00E+00 mR/hr R21575E 1.50E+04 epa R29430 0.15 mA/hr Ch 4 FI 0. DOE 600 mR/hr R217705 250.0 epu Ch 5 FI 0.00E+00 mR/hr R21922S 3.00E+03 epe C5765-P RE45949 1.00 R/hr RE540$A 2.00E+03 eps RE4686 100.0 cym R34517AA R254055 100.0 epm R29436 0.30 mR/hr Ch 1 NG 1.00E-07 pC1/ec R25405C 150.0 epe R29435 0.10 mA/hr Ch2P 2.00E-10 pC1/ce C5765-D RE9439 0.15 mA/hr Ch 3 1 1.00E-11 pCi/ce RE10033 40.0 epe R39437 0.20 mR/hr F14599AA R29419 0.90 mA/hr Ch 1 NC 1.00E-07 pCi/ec R28426 0.30 mR/hr C5755-3 Ch 2 P 1.005-10 pC1/=c R39400 0.60 mR/hr R25328A 40.0 epe Ch 3 1 1.003-10 pCi/ce y RE8401 0.40 mR/hr RE532EB 12.0 eye RE4597AB e R28402 2.00 mA/hr R25320C 22.0 epe Ch 1 BG 0.00E+00 pC1/ec [ RE9404 2.00 mA/hr R21413 2.00E+03 epe Ch 2 NG 0.00E+00 #C1/cc RZ8406 0.30 mR/hr RE2399 2.43 mR/hr Ch 3 P1 0.00E+00 mA/hr R28407 0.20 mR/hr RZ8447 0.10 mR/hr Cb 4 FI 0.00E+00 mR/hr 98 R29408 4.00 mR/hr Ch 5 FI 0.00E+00 mR/hr [ R29409 3.00 mA/hr C5762-5 R34599AS De RE9410 0.32 mR/hr R25327A 20.0 era Ch 1 NG 0.00E+00 pCi/cc g R29412 20.0 mR/hr R253278 10.0 cye Ch 2 NG 0.00E+00 pC1/ec D. RE9415 0.30 mR/hr R2 5 32 7C 2 0.0 epa Ch 3 PI 0.00E+00 mR/hr g RZ9419 0.30 mR/hr R21412 1.30E+03 epa Ch 4 PI 0.00E+00 mA/hr M RES429 0.15 mR/hr R22387 2.23 mA/hr Ch 5 PI 0.00E+00 mR/hr k R29431 0.30 mR/hr R29446 0.20 mR/hr R24596A 1.00 R/hr O S O O O
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DAVIS-BESSE NUCLEAR POWER STATION RE DATA SHEET SCENARIO NO. 1993 Evaluated EEercise TIME: 0845 TO Player at the Control Roost RE Panela T: 00/45 THIS IS A DRILL DO NOT initiate actions affecting noZinal operations. C5765-4 c5765-E RE45973A RE1878A 1.50E+04 era RE609 15.0 eps Ch 1 NG 1.00E * #Ci/ec RE1770A 300.0 ep RE600 10.0 epen Ch2P 2.00E-10 pCi/cc RE1922A 2.50E403 ep RE8427 0.30 mR/hr Ch 3 I 1.00E-11 pCi/ce RE5403A 2.00E+03 esse RE8402 3.00 mR/hr RE4599BA RE54033 30.0 ep RE8405 5.00 mR/hr Ch 1 NG 1.00E-07 pC1/cc RE5403C 40.0 ep RE9411 3.12 mR/br Ch2P 1.00E 10 pC1/ce C5765 3 RE9413 1.50 mR/hr Ch 3 I 1.00E-10 pCi/cc RE1003A 40.0 etum RE9414 0.15 mR/hr RE4597BS RE5052A 8.00E+02 ep RE8416 0.20 mR/br Ch 1 NG 0.00E+00 pCi/cc RE50528 50.0 ep REsti? 0.40 mR/hr Ch 2 NG O.00E+00 pCi/cc RE5052C 30.0 epa RE8420 0.20 mR/hr Ch 3 PI 0.00E+00 mR/hr RE9432 70.0 epa RE8421 0.40 mR/hr Ch 4 PI 0.00E+00 mR/hr e RE8434 70.0 eTun RE9422 0.60 mR/hr Ch 5 PI 0.00E+00 mR/hr I RZ8433 100.0 epe RE9423 0.20 mR/hr RE4599BB $ RE1998 1.20E+04 epe RE8424 0.20 mR/br Cb 1 NG 0.00E+00 pC1/ec RE8425 1.50 mR/hr Ch 2 NG O.00E+00 pCi/cc C5765-C RE9429 0.20 mR/hr Ch 3 PI 0.00E+00 mR/hr RE18798 1.50E+04 esa RE8430 0.15 mR/hr Ch 4 PI 0.00E+00 mR/br RE17703 250.0 etum Ch 5 PI 0.00E+00 rR/hr RE18225 3.00E+03 cism C5765-F RE45968 1.00 PJhr RI5405A 2.00E+03 epe RE4696 100.0 epe RE4597AA RE54053 100.0 epa RE8436 0.30 mR/hr Ch 1 NG 1.003-07 pCi/ce RE5405C 150.0 egen RE8435 0.10 mR/hr Ch 2 P 2.00E-10 FCi/cc C5765-D RE8438 0.15 mR/hr Ch 3 I 1.00E-11 pCi/cc RE1003B 40.0 epe RE9437 0.20 mR/hr RE459ttAA RE9419 0.90 mR/hr Ch 1 NG 1.00E-07 pCi/cc RE9426 0.30 mR/hr C5755-3 Ch2P 1.00E-10 pC1/cc RE9400 0.60 mR/hr RE5324A 40.0 ep Ch 3 I 1.00E 10 pCi/ec w RE9401 0.40 mR/hr RES328B 12.0 epe RE4597AB W R20402 2.00 mR/hr RE5328C 22.0 epa Ch 1 NG 0.00E+00 pCi/cc (J RE9404 2.00 mR/hr RE1413 2.00E+03 epe Ch 2 NG 0.00E+00 pCi/ce RE8406 0.30 mR/br RZ2399 2.43 mR/hr Ch 3 PI 0.00E+00 mR/hr RE9407 0.20 mR/hr RE9447 0.10 mR/hr Ch 4 Pt 0.00E+00 mR/hr D RE9408 4.00 mR/Lr Ch 5 PI 0.00E400 mR/hr [ D RE9409 3.00 mR/br C5762-9 RE4599AB REB 410 0.32 mR/hr RE5327A 30.0 ep Ch 1 NG O.00E+00 pCi/cc h RE8412 20.0 mR/hr RES327B 10.0 eps Ch 2 NG 0.00E+00 pC1/ce D. RE9415 0.30 mR/hr RE5327C 20.0 epa Ch 3 PI 0.00E+00 mR/hr M RE9419 0.30 mR/hr RE1412 1.30E+03 epm Ch 4 PI 0.00E+00 mR/hr X RE8429 0.15 mR/hr RE2387 2.23 mp/hr Ch 5 PI 0.00E+00 mR/hr mR/hr RE8446 0.20 mR/hr RE4596A 1.00 R/hr O RE9431 0.10 e
DAVIC-FESPE NUCLEAR POWER STATION RE DATA SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 0900 TO: Player at the Control Roomt RE Panels T: 01/00 THIS IS A DRII.L DO NOT initiate actions affecting normal operations. C5765-A C5765-E PE4597BA l RE18784 1.50E+04 epa RE609 15.0 ep Ch 1 NG 1.00E-07 pCi/ce RE1770A 300.0 epe RE600 10.0 epe Ch2P 2.00E-10 pCi/cc RE1822A 2.50E+03 ep RE8427 0.30 mR/hr Ch 3 1 1.00E-11 pCi/cc RE5403A 2.00E+03 ep RE8403 3.00 mR/hr RE4598BA RE54038 30.0 epe RE8405 5.00 mR/hr Ch 1 NG 1.00E-07 pCi/cc RE5403C 40.0 ep RE8411 3.12 mR/hr Ch 2 P 1.00E-10 pCi/ce f C5765-B RE8413 1.50 mR/hr Ch 3 I 1.00E-10 pCi/ec RE1003A 40.0 era RE8414 0.15 mR/hr RE4597BS R25052A 8.00E+02 ep RE8416 0.20 mR/hr Ch 1 NG 0.00E+00 pCi/cc RE50529 50.0 ep RE8417 0.40 mR/hr Ch 2 NG 0.00E+00 pCi/ce RE5052C 30.0 epa RE8420 0.20 mR/hr Ch 3 PI 0.00E+00 mR/hr RE8432 70.0 epa RE8421 0.40 mR/hr Ch 4 PI 0.00E+00 mR/hr g RE8434 70.0 ep RE8422 0.60 mR/hr Ch 5 PI 0.00E+00 mR/hr I RE8433 100.0 ep RE8423 0.20 mR/hr RE4598BB U RE1998 6.85E+05 epe RE8424 0.20 mR/hr Ch 1 NG 0.00E+00 pC1/cc RE8425 1.50 mR/hr Ch 2 NG 0.00E+00 pci/ec C5765-C RE8428 0.20 mR/hr Ch 3 PI 0.00E+00 mR/hr RE18788 1.5CE+04 eps RE8430 0.15 mR/hr Ch 4 PI 0.00E+00 mR/hr RE17708 250.0 rpm Ch 5 PI 0.00E+00 mR/br RE18229 3.00E+03 epa C5765-F RE45965 1.00 R/hr RE5405A 2.00E+03 epe RE4686 100.0 epe RE4597AA RE54058 100.0 epe RE8436 0.30 mR/br ch 1 NG 1.00E-07 pCi/cc RE5405C 150.0 epe RE8435 0.10 mR/hr Ch 2 P 2.00E-10 pC1/ce C5765-D RE8438 0.15 mR/hr Ch 3 1 1.00E-11 pCi/ce RE10038 40.0 epe RE8437 0.20 mR/hr RE4598AA RE8419 0.90 mR/hr Ch 1 NG 1.00E-07 pCi/cc RE8426 0.30 mR/hr C5755-B Ch 2 P 1.03E-10 pCi/cc RZ8400 0.60 mR/hr RES328A 40.0 epa Ch 3 I 1.00E-10 pCi/cc p RE8401 0.40 mR/hr RE53285 12.0 eps RE4597AB W RE8402 2.00 mR/hr RE5328C 22.0 epa Ch 1 NG 0.00E+00 pC1/cc $ RE8404 2.00 mR/hr RE1413 2.00E+03 epe Ch 2 NG 0.00E+00 pCi/cc RE8406 0.30 mR/hr RE2389 2.43 mR/hr Ch 3 PI 0.00E+00 mR/hr RE8407 0.20 mR/hr RE8447 0.10 mR/hr Ch 4 PI 0.00E+00 mR/hr D RE8408 4.00 mR/hr Ch 5 PI 0.00E+00 4R/hr [ D RE8409 3.00 mR/hr C5762-3 RE4598AB RE8410 0.32 mR/hr RE5327A 30.0 eps Ch 1 NG 0.c0E+00 pCi/cc h RE8412 20.0 mR/hr RE5327B 10.0 epa Ch 2 NG 0.00E+00 pCi/ce D. RE8415 0.30 mR/hr RE5327C 20.0 era Ch 3 PI 0.00E+00 mR/hr y RE8418 0.30 mR/ha RE1412 1.30E+03 eps ch 4 PI 0.00E+00 mR/hr M RE8429 0.15 mR/hr RE2387 2.23 mR/hr Ch 5 PI 0.00E+00 mR/hr RE8431 0.10 mR/hr RE8446 0.20 mR/hr RE4596A 1.00 R/br G O O O
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( Q V DAVIS-BESSE NUCLEAR POWER STATION RE DATA SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 0915 TO: Player at the Control Room RE Panels T: 01/15 THIS IS A DRILL DO NOT initiate actions affecting normal operations. C5765-h C5765-E RE4597BA RE1878A 1.50E+04 epa R3609 15.0 epa Ch 1 NG 1.005-07 pC1/ec RE17704 300.0 ep RE600 10.0 epa Ch 2 P 2.00E-10 pci/ec RE1822A 2.50E+03 ep R28427 0.30 mR/hr Ch 3 1 1.00E-11 pCi/cc RE5403A 2.00E+03 c;n RE8403 3.00 mR/hr RE4598BA RE54038 30.0 epa RE8405 3.00 mR/hr Ch 1 NG 1.00E-07 pCi/cc RE5403C 40.0 cpm RE8411 3.12 mR/hr Ch 2 P 1.005-10 pCi/cc C5765-3 RE8413 1.50 mR/hr Ch 3 1 1.00E-10 pC1/cc RE1003A 40.0 cyn RI8414 0.15 mR/hr RE4597BS RE5052A 8.00E+02 cyn RE8416 0.20 mR/hr Ch 1 NG 0.00E+00 pCi/cc R250529 50.0 cTm R28417 0.40 mR/hr Ch 2 NG 0.00E+00 pCi/ce R25052C 30.0 cpm RE8420 0.20 mR/hr Ch 3 PI 0.00E+00 mR/hr R28432 10.0 cTm RE8421 0.40 mR/hr Ch 4 PI 0.00E+00 mR/hr m R28422 0.60 mR/hr Ch 5 PI 0.00E+00 mR/hr I RE8434 70.0 era RE8433 100.0 eTu RE8423 0.20 mR/hr RE4598BS $ R21998 1.00E+06 epm RE8424 0.20 mR/hr Ch 1 NG 0.00E+00 pC1/cc RE8425 1.50 mR/hr Ch 2 NG 0.00E+00 pCi/ec C5765-C RE8428 0.20 mR/hr Ch 3 PI 0.00E+00 mR/hr RE18788 1.50E+04 cyn REn430 0.15 mR/hr Ch 4 PI 0.00E+00 mR/hr RE17708 250.0 c;n Ch 5 PI 0.00E+00 mR/hr RE18228 3.00E+03 epa C5765-P RE45965 1.00 R/hr RE5405A 2.00E+03 ein RE4486 100.0 cpm RE4597AA RE54058 100.0 cyn RE8436 0.30 mR/hr Ch 1 NG 1.00E-07 pCi/ce RE5405C 150.0 RE8435 0.10 mR/hr Ch 2 P 2.005-10 pCi/ec esa C5765-D RE8438 0.15 mR/hr Ch 3 I 1.00E-11 pCi/cc RE10039 40.0 cru RE8437 0.20 mR/hr RE4598AA RE8419 0.90 mR/hr Ch 1 sc 1.005-07 pC1/cc RE8426 0.30 mR/hr C573 5-t1 Ch2P 1.00E-10 pCi/cc R28400 0.60 mR/hr RE5328A 40.0 epa Ch 3 1 1.00E-10 pCi/cc p RE532BB 12.0 cpm R24597AB W RE8401 0.40 mR/hr R28402 2.00 mR/hr RE5328C 22.0 cp Ch 1 NG O.00E+00 pCi/ec $ RE8404 2.00 mR/hr RE1413 2.00E+03 epe Ch 2 NG 0.00E+00 pCi/cc RE8406 0.30 mR/hr R22389 2.43 mR/hr Ch 3 PI 0.00E+00 mR/hr kD RE8407 0.20 mR/hr RE8447 0.10 mR/hr Ch 4 PI 0.00E+00 mR/hr RE8408 4.00 mR/hr Ch 5 PI 0.00E+00 mR/hr [ D RE8409 3.00 mR/hr C5762-9 RE4598AB RE8410 0.32 mR/hr RE5327A 30.0 era Ch 1 NG 0.00E+00 pC1/ec g RE8412 20.0 mR/hr RE53275 10.0 cTm Ch 2 NG 0.00E+00 pC1/cc Q. RE8415 0.30 mR/hr RE5327C 20.0 eps . Ch 3 P1 0.00E+00 mR/hr g mR/hr R21412 1.3CE+03 epa Ch 4 FI 0.00E+00 mR/hr M RE8418 0.30 R28429 0.15 mR/hr- RE2387 2.23 mR/hr Ch 5 PI 0.00E+00 mR/hr k RE8446 0.20 mR/hr RE45964 1.00 R/hr G RE8431 0.10 mR/hr
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DAVIS-BESSE NUCLEAR POWER STATION RE DATA SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 1000 TO! Player at the Control Room RE Panels T: 02/00
*............. .....................e....... ...*.......*.***.*........***...**.............*.**.... ..* ....
THIS IS A DRILL DO NOT initiate actions affecting normal operations. C5765-A C5765-E RE4597BA RE1970A 1.5CE+04 epe RE609 15.0 epa Ch 1 NG 1.00E-07 pC1/cc ep RE600 10.0 epe Ch2P 2.00E-10 pCi/cc RE1770A 300.0 RE8427 0.30 mR/hr Ch 3 I 1.00E-11 pC1/cc RE1822A 2.5CE+03 ep RE3403A 2.0CE+03 ep RE8403 3.00 mR/hr RE45998A RE54038 30.C epe RE8405 5.00 mR/hr Ch 1 NG 1.00E-07 pC1/cc RE5403C 40.C cp RE8411 3.12 mR/hr Ch 2 P 1.00E-10 pCi/ec REB 413 1.50 mR/hr Ch 3 I 1.00E-10 pCi/cc C5765-B l RE1003A 40.0 epa RE8414 0.15 mR/hr RE459788 RE8416 0.20 mR/hr Ch 1 NG 0.00E+00 pCi/ce RE5052A 8.0CE+02 ep ep RE8417 0.40 mR/hr Ch 2 NG 0.00E+00 pC1/ec RZ50525 50.C RE5052C 30.e ep RE8420 0.20 mR/hr Ch 3 PI 0.002400 mR/hr RE8432 70.C epe ret 421 0.40 mR/hr Ch 4 PI 0.00S+00 mR/hr m RE8434 70.C epa RE8422 0.60 mR/hr Ch 5 PI 0.00E+00 mR/hr I l RE8433 100.0 ep RE8423 0.20 mR/br RE4598BB U r RE1998 1.0CE+06 ep RE8424 0.20 mR/hr Ch 1 NG 0.00E+00 pC1/ce RE8425 1.50 mR/br Ch 2 NG C.00E+00 pCi/ce l RE8429 0.20 mR/hr Ch 3 PI 0.00E+00 mR/hr C576*-C RE18708 1.5CE+04 ep RE8430 0.15 mR/hr Ch 4 PI 0.00B+00 mR/hr l RE17708 250.0 epe Ch 5 PI 0.00E+00 mR/hr C5765-F RE4586B 1.00 R/hr RE18228 3.0CE+03 ep RE5405A 2.0CE+03 epm RE4486 100.0 ep RE4597AA RE5405B 100.0 ep RZ8436 0.30 mR/hr Ch 1 NG 1.00E-07 pCi/cc epa RE8435 0.10 mR/br Ch2P 2.00E-10 pC1/ce RE5405C 150.0 RE8438 0.15 mR/hr Ch 3 I 1.00E-11 pCi/cc C5765-D RE10039 40.0 epa RE8437 '3.20 mR/hr RE4598AA RE8419 0.90 mR/hr Ch 1 NG 1.00E-07 pC1/ec 0.30 mR/hr C5755-9 Ch 2 P 1.00E-10 pCi/cc I REB 426 mR/hr RE5328A 40.0 eps Ch 3 1 1.00E-10 pel/ec g RZ8400 0.60 to i RE8401 1.60 mR/hr RE53288 12.0 epa IL* 4 5 9 7 AB RE8402 2 . 0 81 mR/hr RE5328C 22.0 ep Ch 1 NG O.00E+00 pCi/cc [
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DAVIf3-BESSE NUCLEAR POWER STATION RE DATA SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 1030 TO1 Player at the Control Room RE Panels T: 02/30 THIS IS A DRILL DO NOT initiate actions affecting normal operations. C5765-A C5745-E RE4597BA RE1978A 1.5CE+04 epe RE609 15.0 epe Ch 1 NG 1.00E-07 pCi/ce. RE1770A 300.0 eps RE600 10.0 epe Ch2P 2.00E-10 pCi/cc RE1922A 2.50E+03 rpm RE8427 0.30 mR/hr Ch 3 I 1.00E-11 pCi/cc RE5403A 2.00E+03 epe RE8403 3.00 mR/hr RE4598BA RE54035 30.0 epe RE8405 5.00 mR/hr Ch 1 NG 1.005-07 pCi/cc RE5403C 40.0 epe RE8411 3.12 mR/hr Ch 2 P 1.00E-10 pCi/cc C5765-8 RE8413 1.50 mR/hr Ch 3 I 1.00E-10 pci/cc RE1003A 40.0 cpe RE8414 0.15 mR/hr RE4597BB RE5052A 8.00E+02 epe RE8416 0.20 mR/hr Ch 1 NG 0.00E+00 pCi/cc RE50528 50.0 epa RE8417 0.40 mR/hr Ch 2 NG 0.00E+00 pCi/ec RE5052C 30.0 epa RE8420 0.20 mR/hr Ch 3 PI 0.00E+00 mR/br RE8432 70.0 epe RE8421 0.40 mR/he Ch 4 FI 0.00E+00 mR/hr m RE8434 70.0 epm RE8422 0.60 mR/hr Ch 5 PI 0.00E+00 mR/hr i RE8433 100.0 epe RE8423 0.20 mR/br RE4598BB $ RE1998 1.00E+06 epe RE8424 0.20 mR/hr Ch 1 NG 0.00E+00 pC1/cc RE8425 1.50 mR/hr Ch 2 NG 0.008400 pC1/cc C5745-C RE8428 0.20 mR/hr Ch 3 PI 0.00E+C0 mR/hr RE18788 1.50E+04 era R28430 0.15 mR/br Ch 4 PI O.00E+00 mR/hr RE17709 250.0 cpm Ch 5 PI O.00E+00 mR/hr RE18229 3.00E+03 epe C5765-F RE45968 1.00 R/hr RE5405A 2.00E+03 epe RE4486 200.0 eps RE4597AA RE54058 100.0 cpe RE8436 0.30 mR/hr Ch 1 NG 1.00E-07 pCi/cc RE5405C 150.0 epa RE8435 0.10 mR/hr Ch2P 2.00E-10 pC1/ee C5765.D RE8438 0.15 mR/hr Ch 3 1 1.00E-11 pCi/cc RE10035 40.0 epe RE8437 0.20 mR/hr RE4598AA RE8419 0.90 mR/hr Ch 1 NG 1.00E-07 pC1/ee RE8426 0.30 mR/hr C5755-B Ch2P 1.00E+10 pC1/cc RE8400 0.60 mR/hr RE5328A 40.0 epe Ch 3 I 1.00E-10 pC1/ce p RE4597AB to RE8401 3.50 mR/br RE53283 12.0 eye RE8402 2.00 mR/hr RES328C 22.0 epe Ch 1 NG 0.00E+00 pCi/ec $ RE8404 2.00 mR/hr RE1413 2.00E+03 epe Ch 2 NG 0.00E+00 pCi/ec RE8406 0.30 mR'hr RE2389 2.43 mR/hr Ch 3 PI 0.00E+00 mR/hr mR/hr RE8447 0.10 mR/hr Ch 4 P1 0.00E+00 mR/hr D RE8407 0.20 RE8408 4.00 mR/hr Ch 5 FI 0.00E+00 mR/hr [ RE8409 3.00 mR/hr C5762-8 RE4598AB RE8410 0.32 mR/hr RE5327A 30.0 epa Ch 1 NG 0.00E+00 pCi/ce g RE3412 20.0 mR/hr RE5327B 10.0 era Ch 2 NG 0.00E+00 pCi/cc Q. RE8415 0.30 mR/hr RE5327C 20.0 epa Ch 3 PI 0.00E+00 mR/hr pg mR/hr RE1412 1.30E+03 epa Ch 4 PI 0.00E+00 mR/hr M RE8415 0.30 RE8429 0.15 mR/hr RE2387 2.23 mR/hr Ch 5 PI 0.00E+00 mR/hr mR/hr RE8446 0.20 mR/hr RE4596A 1.00 R/hr O RE8431 0.10 O O O
DAVIS-BESSE NUCLEAR POWER STATION RE DATA SHEET 1993 Evaluated Exercise TIME: 1045 SCENARIO NO. Player at the Control Room RE Panels T: 02/45 TO THIS IS A DRII.L DO NOT initiate actions affecting normal operations. C5765-E RE4597BA C5765-A 1.00E-07 pCi/cc RE1878A 1.50E+04 ep RE609 15.0 ep Ch 1 NG RE600 10.0 ep Ch2P 2 00E-10 pCi/ce RE1770A 300.0 epen RE1822A 2.50E+03 ep RE8427 0.30 mR/hr Ch 3 1 1.00E-11 pCi/ec RE8403 3.00 mR/hr RE4598BA RE5403A .2.00E+03 ep 1.00E-07 pCi/cc RE54035 30.0 cpm RE8405 5.00 mR/hr Ch 1 NG RE8411 3.12 mR/hr Ch 2 P 1 00E-10 pCi/ec R25403C- 40.0 ep RE8413 1.50 mR/hr Ch 3 1 1.00E-10 pCi/ce C5765-8 ep RE8414 0.15 mR/hr RE4597BB RE1003A 40.0 RE8416 0.20 mR/hr Ch 1 NG O.00E+00 pC1/cc RE5052A 8.00E402 epe RE8417 0.40 mR/hr Ch 2 NG 0.00E+00 pCi/cc RE50528 50.0 ep R25052C 30.0 epe RE8420 0.20 mR/hr Ch 3 PI 0.00E+00 mR/hr RE0432 70.0 ep RE8421 0.40 mR/hr Ch 4 PI 0.00E+00 mR/hr e. RE8434 70.0 ep RE8422 0.60 mR/hr Ch 5 PI 0.00E+00 mR/hr 8 RE0433 .100.0 epe RE8423 0.20 mR/hr RE4598BB $ RE8424 0.20 mR/hr Ch 1 NG 0.00E+00 pC1/cc RE1999 1.00E+06 epe RE8425 1.50 mR/hr Ch 2 NG 0.00E+00 pCi/cc RE8428 0.20 mR/hr Ch 3 FI 0.00E+00 mR/hr C5765-C RE18785 1.50E+04 ep RE8430 0.15 mR/hr Ch 4 PI 0.00E+00 mR/hr ep Ch 5 PI 0.00E+00 mR/hr RE17708 250.0 C5765-F RE45968 1.00 R/hr RE18228 3.00E+03 ep RE4686 100.0 epa RE4597AA RE5405A 2.0CE+03 ep 1.00E-07 pCi/cc ep RE8436 0.30 mR/hr Ch 1 NG RE54058 100.0 2.00E-10 pci/cc RE8435 0.10 ' mR/hr Ch 2 P RE5405C 150.0 ep 1.00E-11 pCi/cc C5765-D RE8439 0.15 mR/hr Ch 3 1 epe RE8437 0.20 mR/hr RE4598RA RE1003B 40.0 Ch 1 NG -1.00E-07 pC1/cc RE8419 0.90 mR/hr C5755-5 Ch 2 P 1 00E-10 pCi/cc RE8426 0.30 mR/hr RE5328A 40.0 epa Ch 3 2 1.00E-10.pCi/cc w RE8400 0.60 mR/br W mR/hr RE53288 12.0 epe RE4597AB RE8401 6.20 RE8402 2.00 mR/hr RE5320C 22 0 epe Ch 1 NG 0.00E+00 pCi/cc h mR/hr RE1413 2.00E+03 ep Ch 2 NG 0.00E+00 pCi/ee RE8404 2.00 RE8406 0.30 mR/hr RE2389 2.43 mR/hr' Ch 3 PI O.00E+00 mR/hr mR/hr Ch 4 PI 0.00E+00 mR/hr P RE8407 0.20 mR/hr RE8447- 0.10 RE8400 4.00 mR/hr Ch 5 PI 0.00E+00 mR/hr [ m mR/hr C5762-5 ~ RE4598A8 RE8409 3.00 mR/hr RE5327A 30.0 epm Ch 1 NG 0.00E+00 pC1/cc g RE8410 0.32 Ch 2 NG 0.00E+00 pCi/cc D. RE8412 20.0 mR/hr R253278 10.0 eps 0.30 mR/hr RE5327C 20.0 eps Ch 3 PI 0.00E+00 mR/hr p3 RE8415 RE8418 0.30 mR/hr RE1412 1.30E+03 eps Ch 4 PI 0.00E+00'mR/hr M mR/hr RE2387 2.23 mR/hr Ch 5 PI 0.00E400 mR/hr REB 429 0.15 O RE8446 0.20 mR/hr RE4596A 1.00 R/hr RE8431 0.10 mR/hr ;
DAVIS-BESSE NUCLEAR POWER STATION RE DATA SHEET SCENARIO NO. 1993 Evaluated EEercise TIME: 1100 To: Player at the Control RooE1 RE Panels T 03/00
.............................................******...***..******THIS IS A DRILL DO NOT initiate actions affecting normal operations.
C5765-A C5765-E RE4597sA RE1878A 1.50E+04 epe RE609 15.0 epe Ch 1 NG 1.00E-07 pCi/cc RZ600 10.0 epe Ch2P 2.00E-10 pCi/ec RE1770A 300.0 epe RE1822A 2.50E+03 epm RE8427 0.30 mR/hr Ch 3 I 1.00E-11 pCi/ec RE5403A 2.00E+03 epm RES403 3.00 mR/hr RE4598BA ep RE8405 5.00 mR/hr Ch 1 NG 1.005-07 pC1/cc RE54038 30.0 epe RE8411 3.12 mR/hr Ch 2 P 1.00E-10 pCi/cc RE5403C 40.0 RE9413 1.50 mR/hr Ch 3 1 1.005-10 pCi/cc C5765-5 epe RE8414 0.15 mR/hr RE4597BB RE1003A 40.0 RE3416 0.20 mR/hr Ch 1 NG 0.00E+00 pC1/ec RE5052A 9.00E+02 epe RE0417 0.40 mR/hr Ch 2 NG 0.00B+00 pC1/cc R250528 50.0 epe epe RE9420 0.20 mR/hr Ch 3 PI 0.00E+00 mR/hr RE5052C 30.0 RE9432 70.0 ep RE9421 0.40 mR/hr Ch 4 PI 0.00E+00 mR/br m RER434 70.0 epe RE8422 0.50 mR/hr Ch 5 PI 0.00E+00 mR/hr 8 RE9433 100.0 cpm RZ8423 0.20 mR/hr RE4596BB U 1.00E+06 ege R28424 0.20 mR/hr Ch 1 NG 0.00E+00 pC1/ec RE1998 REs425 1.50 mR/hr Ch 2 NG 0.00E400 pCi/ec RE9429 0.20 mR/hr Ch 3 PI 0.00E+00 mR/hr C5745-C RE19788 1.50E+04 epm RE8430 0.15 mR/br Ch 4 PI 0.00E400 mR/hr epa Ch 5 FI 0.00E+00 mR/hr RE17708 250.0 C5765-F RE45968 1.00 R/hr RE18225 3.00E+03 ep RE5405A 2.00E4 33 epe RE4686 100.0 cpm RE4597AA RE5405B 100.0 eps RE9436 0.30 mR/hr Ch 1 NG 1.00E-07 pCi/ec REB 435 0.10 mR/hr Ch2P 2.00E-10 pC1/ec RE5405C 150.0 epa RE9438 0.15 mR/hr Ch 3 1 1.00E-11 pC1/cc C5765-D epe RE8437 0.20 mR/hr RE4598RA RE1003B 40.0 mR/hr Ch 1 NG 1. 0 0 5-O'.* pCL/ec REB 419 0.90 Ch 2 P 1.005 13 pCi/ec RE8426 0.30 mR/hr C5755-B RE5328A 40.0 epa Ch 3 1 1.008-30 pC1/cc g RE8400 0.60 mR/hr W mR/hr RE5328B 12.0 cpm RE4597AB RE9401 6.80 RE9402 2.00 mR/hr RE5320C 22.0 era Ch 1 NG 0.00E MO pCi/ec [ RE1413 2.00E+03 epa Ch 2 NG 0.00E+JO pCi/ee RE9404 2.00 mR/hr RE8406 0.30 mR/hr RE2389 2.43 mR/hr Ch 3 PI O.00E430 mR/hr RE8447 0.10 mR/hr Ch 4 FI 0.00E+00 mR/hr W RE8407 0.20 mR/hr RE9409 4.00 mR/hr Ch 9 PT a "sE+0C mR/hr [ D mR/hr C5762-B RE4598AB REs409 3.00 RE5327A 30.0 epe Ch 1 NG 0.00E+00 pCi/cc g RE9410 0.32 mR/hr Q. mR/hr RE5327B 10.0 epa Ch 2 NG O.00E+00 pCi/cc ret 412 20.0 ret 415 0.30 mR/hr RE5327C 20.0 epa Ch 3 PI O.00E+00 mR/hr g 0.30 mR/hr RE1412 1.30E+03 epe Ch 4 PI 0.00E+00 mR/hr M RE9418 RE9429 0.15 mR/hr RE2397 2.23 mR/hr Ch 5 PI 0.00E+00 mR/hr k RE45964 R/hr G mR/hr RE9446 0.20 mR/hr 1.00 RE3431 0.10 O O O
DAVIS-BESSE NUCLEAR POWER STATION RE DATA SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 1115 TO: Player at the Control Room RE Panel.s T: 03/15 THIS IS A DRILL ! DO NOT initiate actions affecting normal operations.
................. 3 ..................***.........................................................-........**
C5765-E RE4597BA C5745-A pC1/ec RE1978A 1.50E+04 epa RE609 15.0 epa Ch 1 NG 5.80E-06 RE600 10.0 epe Ch2P 4.00E-09 pC1/cc RE1770f. 300.0 epa 1.102 11 pCi/cc RE18214 2.50E+03 eps RE8427 0.30 mR/hr Ch 3 1 R25403h 2.00E+03 epa RE8403 3.00 mR/hr R34598BA RE8405 5.00 mR/hr Ch 1 NG 1.00E-07 pCi/cc RE54038 30.0 epen RE5403C 40.0 ept RE8411 3.12 mR/hr Ch 2 P 1.00E-10 pCi/cc RE8413 1.50 mR/hr Ch 3 1 1.00E-10 pCi/cc C5765-5 RE8414 0.15 mR/hr RE4597BS RE1003R 40.0 ept RE8416 0.20 mR/hr Ch 1 NG 0.00E+00 pci/ce RE5052A 8.00E+02 eps RE8417 0.40 mR/hr Ch 2 NG 0.00E+00 pCi/cc R250523 50.0 eps RE5052C 30.0 epn RE8420 0.20 mR/hr Ch 3 PI O.00E+00 mR/hr RE8432 70.0 eps RE8421 0.40 mR/hr Ch 4 PI 0.00E+00 mR/hr m RE8434 70.0 eps RE8422 0.60 mR/hr Ch 5 PI 0.00E+00 mR/hr epn RE8423 0.20 mR/hr RE4599BB m RE8433 100.0 pC1/ec RE8424 0.20 mR/hr Ch 1 NG O.00E+00 RE1998 1.00E+06 epa RE8425 1.50 mR/hr ch 2 NG 0.00E+00 pCi/ec RE8428 0.20 mR/hr Ch 3 PI 0.002600 mR/hr C5765-C RE18788 1.5CE+04 epa RE8430 0.15 mR/hr Ch 4 PI 0.00E+00 mR/hr RE17708 250.0 epn Ch 5 PI 0.00E+00 mR/hr C5765-F RE459fB 1.48 R/hr RE1822B 3.00E+03 epm RE4685 100.0 epe RE4597AA RE5405A 2.00E+03 epa epa RE8436 0.30 mR/hr Ch 1 NG 4.30E-06 pCi/ce RE54055 100.0 RE8435 0.10 mR/hr Ch2P 4.00E-09 pCi/cc RE3405C 150.0 epa 1.10E-11 pCi/cc RE8438 0.15 mR/hr Ch 3 I C5765-D eps RE8437 0.20 mR/hr RE4598AA RE10038 40.0 mR/hr Ch 1 NG 1.00E-07 pCi/ee RE8419 0.90 1.00E-10 pCi/cc C5755-9 Ch 2 P RE8426 0.30 mR/hr RE5328A 40.0 epa Ch 3 1 1 00E 10 pCi/cc p RE8400 0.50 mR/hr W RE5328B 12.0 epe RE4597As RE8401 7.60 mR/hr RE8402 2.00 mR/hr RE5328C 22.0 epe Ch 1 NG 0.00E+00 pCi/cc h RE1413 2 00E+03 cra Ch 2 NC 0.00E+00 pCi/cc RE8404 2.00 mR/hr RE2389 3.72E+03 mR/hr Ch 3 FI 0.00E+00 mR/br RE8406 0.30 mR/hr D RE8447 0.10 mR/hr Ch 4 PI 0.00E+00 mR/hr RE8407 0.20 mR/hr RE8408 4.00 mR/hr Ch 5 PI 0.00E+00 mR/br [ RE4598A2 D RE8409 3.00 mR/hr C5762-3 RES327A 30.0 epa Ch 1 NG 0.00E+00 pCi/cc g RE8410 0.32 mR/hr pCi/ce D. RE5327B 10.0 epe Ch 2 NC 0.00E+00 RE8412 20.0 mR/hr RES327C 20.0 epa Ch 3 PI 0.00E+00 mR/hr g RE8415 0.30 mR/hr M RE1412 1 30E+03 epe Ch 4 PI 0.00E+00 mR/br RE8418 0.30 mR/hr RE2387 3.68E+03 mR/hr Ch 5 PI 0.00E+00 mR/hr RE8429 0.15 mR/hr R/hr O RE8446 0.20 mR/hr RE4596A 1.50 RE8433 0.10 mR/hr ;
DAVIS-BESSE NUCLEAR POWER STATION RE DATA SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 1130 TO Player at the Control Roo80 RE Panels T: 03/30 THIS IS A DRILL DO NOT initiate actions affecting normal operations C5765-A C5765-E RE4597BA RE1878A 1.50E+04 epe RZ609 15.0 eps Ch 1 NG 8.70E-02 pC1/cc RE1770A 300.0 cpm RE600 10.0 eps Ch2P 4.50E-08 pC1/cc RE1822A 2.50E+03 cpm RE8427 0.30 mR/hr Ch 3 I 1.15E-11 pci/ce RE5403A 2.00E+03 cpu RE8403 3.00 mR/hr RE4598BA RE54038 30.0 epa RE8405 5.00 mR/hr Ch 1 NG 1.00E-07 pCi/cc RE5403C 43.0 epa RE8411 3.12 mR/hr Ch2P 1.00E-10 pC1/cc C5765-B RE8413 1.50 mR/hr Ch 3 1 1.00E-10 pci/ce RE1003A 40.0 eps RE8414 0.15 mR/hr RE4597BB RE5052A 8.00E+02 eps RE8416 0.20 mR/hr Ch 1 NG 6.68E-02 pCi/cc RE50528 50.0 epe RE8417 0.40 mR/hr Ch 2 NG 1.00E+01 pCi/cc RE5052C 30.0 cpe RE8420 0.20 mR/hr Ch 3 PI 1.00E-03 mR/hr RE3432 70.0 eps RE8421 0.40 mR/hr Ch 4 PI 1.00E-03 mR/hr m RE8434 70.0 cpn RE8422 0.60 mR/hr Ch 5 PI 1.00E-03 mR/hr RE8433 100.0 epa RE8423 0.20 mR/hr RR4598BB w RE1998 1.00E+06 eps RE8424 0.20 mR/hr Ch 1 NG 0.00E+00 pCi/cc RE8425 1.50 mR/hr Ch 2 NG 0.00E+00 pC1/cc C5765-C RE8428 0.20 mR/hr Ch 3 PI 0.00E+00 mR/hr RE18788 1.50E+04 epa RE8430 0.15 mR/hr Ch 4 PI 0.00E+00 mR/hr RE17708 250.0 eps ch 5 PI 0.00E+00 mR/hr RE1822B 3.00E+03 eps C5765-F RE45968 3.66 R/hr R2540$A 2.00E+03 eps RE4686 100.0 eps PE4597AA RE3405B 100.0 cpm RE8436 0.30 mR/hr Ch 1 NG 6.55E-02 pCi/cc I RE5405C 150.0 epa RE8435 0.10 mR/hr Ch 2 P 4.50E-08 pCi/cc C5765-D RE8438 0.15 mR/hr Ch 3 I 1.155-11 pCi/cc RE10038 40.0 cpu RE8437 0.20 mR/hr RE4598AA RE8419 0.90 mR/hr Ch 1 NG 1.00E-07 pC1/ce RE3426 0.30 mR/hr C5755-5 Ch 2 P 1.00E-10 pC1/ce RE8400 0.60 mR/hr RE5328A 40.0 eps ch 3 1 1.00E-10 pCi/cc p mR/hr RE5328B 12.0 epa RE4597AB W RE8401 6.10 RE8402 2.00 mR/hr RE5328C 22.0 cpm Ch 1 NG 6.76E-02 pC1/cc h RE8404 2.00 mR/hr RE1413 2.005403 epa Ch 2 NG .1.00E+01 pC1/cc RE8406 0.30 mR/hr RE2389 5.73E+03 mR/br Ch 3 PI 1.00E-03 mR/hr RE8407 0.20 mR/hr RE8447 0.10 mR/hr Ch 4 PI 1.005-03 mR/hr D RE8408 4.00 mR/br Ch 5 P1 1.00E-03 mR/hr [ RE8409 3.00 mR/hr C5762-8 RE4598AB D RE8410 0.32 mR/hr RE5327A 30.0 cpe Ch 1 NG O.00E+00 pCi/cc h RE8412 20.0 mR/hr RE53278 10.0 epe Ch 2 NG 0.00E+00 pC1/cc D. RE8415 0.30 mR/hr RE5327C 20.0 cpn Ch 3 PI 0.00E+00 mR/hr pg RE8418 0.30 mR/hr RE1412 1.30E+03 eps Ch 4 PI 0.00E+00 mR/hr M RE8429 0.15 mR/hr RE2387 5.69E+03 mR/hr Ch 5 PI O.00E+00 mR/hr k mR/hr RE4596A 3.72 R/hr O RE8431 0.10 mR/hr RE8446 0.20
............................................................................................................. g e
O O O
N DAVIS-BESSE NUCLEAR POWER STATION RE DATA SHEET SCENARIO NO. 1993 Evaluated Exercise TIME 1 1145 TO: Player at the control Roo80 RE Panels T: 03/45 THIS IS A DRILL DO NOT initiate actions affecting normal operations. ee......................e..ee..* .*.......e....e.....*..*......*.............*.....e.....*....*..*..*.e...... C5745-A C5765-E RE4597R4 RE1878A 1.50E+04 ep RE609 15.0 eps Ch 1 NG 0.00E+00 pC1/cc RE1770A 300.0 epa RE600 10.0 epa Ch2P 0.00E400 pCi/cc RE1822A 2.50E+03 ept RE8427 0.30 mR/hr Ch 3 1 0.00E+00 pCi/cc RE3403A 2.00E+03 epe RE8403 3.00 mR/hr RE4598BA RE54039 30.0 cpm RE8405 5.00 mR/hr Ch 1 NG 1.00E-07 pC1/cc RE5403C 40.0 epu RE8411 3.12 mR/hr Ch 2 P 1.00E-10 pCi/cc C5765-9 RE8413 1.50 mR/hr Ch 3 1 1.005-10 pCi/cc RE1003A 40.0 epe RE8414 0.15 mR/hr RE459785 R25052A 8.00E+02 epe RE8416 0.20 mR/hr Ch 1 NG 5.59E+00 pCi/cc RE5052B 50.0 epa RE8417 0.40 mR/hr Ch 2 NG 1.00E+01 pCi/cc R25052C 30.0 eps RE8420 0.20 mR/hr Ch 3 PI 5.50E-03 mR/hr RE8432 70.0 epa RE8421 0.40 mR/hr Ch 4 PI 5.50E-03 mR/hr m RE8422 mR/hr Ch 5 PI 5.50E-03 mR/hr I RE8434 70.0 epe 0.60 RE8433 100.0 epa RE8423 0.20 mR/hr RE4598BB N RE1998 1.00E+06 epa RE8424 0.20 mR/hr Ch 1 NG 0.00E+00 pCi/cc RE8425 1.50 mR/hr Ch 2 NG 0.00E+00 pC1/cc C5765-C RE8428 0.20 mR/hr Ch 3 PI 0.00E+00 mR/hr RE18785 1.50E+04 epa R28420 0.15 mR/hr Ch 4 PI 0.00E+00 mR/br RE17708 250.0 epn Ch 5 PI 0.00E+00 mR/hr RE18229 3.00E+03 epa C5765-F RE4596B 5.55 R/hr RE5405A 2.00E+03 epa RE4696 100.0 epe RE4597AA RE54058 100.0 epa RE8436 0.30 mR/hr Ch 1 NG 0.00E+00 pCi/cc RE5405C 150.0 epa RE8435 0.10 mR/hr Ch 2 P 0.00E+00 pCi/cc C5765-D RE8438 0.15 mR/hr Ch 3 1 0.00E+00 pci/cc RE10035 40.0 epa RE8437 0.20 mR/hr RE4598AA RE8419 0.90 mR/hr Ch 1 NC 1.00E-07 pC1/cc RE8424 0.30 mR/hr C5755-9 Ch 2 P 1.00E-10 pC1/cc RE8400 0.60 mR/hr RE5328A 40.0 epn Ch 3 I 1.00E-10 pCi/cc p RE5328B 12.0 epa RE4597A3 W RE8401 5.90 mR/hr RE8402 2.00 mR/hr RE5328C 22.0 eps Ch 1 NG 5.60E+00 pC1/cc $ RE8404 2.00 mR/hr RE1413 2.00E+03 epu Ch 2 NG 1.00E+01 pCi/cc RE8406 0.30 mR/hr RE2389 2.40E+04 mR/hr Ch 3 PI 5.502-03 mR/hr RE8407 0.20 mR/hr RE8447 0.10- mR/hr Ch 4 PI 5.50E-03 mR/hr W RE8408 4.00 mR/hr Ch 5 PI 5.50E-03 mR/hr [ D RE8409 3.00 mR/br C5762-B RE4598AB RE8410 0.32 mR/hr RE5327A 30.0 epa Ch 1 NG O.00E+00 pCi/cc h RE8412 20.0 mR/hr- RE53278 10.0 epa Ch 2 NG 0.00E+00 pCi/cc D. RE8415 0.30 mR/hr RE5327C 20.0 epa Ch 3 PI 0.00E+00 mR/hr pg RE8418 0.30 mR/hr RE1412 1.30E+03 ept Ch 4 PI 0.00E+00 mR/hr M RE8429 0.15 mR/hr RE2387 2.30E+04 mR/hr Ch 5 PI 0.00E+00 mR/hr k mR/hr RE4596A 5.70 R/hr O RE8431 0.10 mR/hr RE8446 0.20
DAVIS-BESSE NUCLEAR POWER STATION RE DATA SHEET SCENARIO NO. 1993 Evaluated Exercise TINE: 1200 TO: Player at the control Room RE Panels T: 04/00 THIS IS A DRILL DO NOT initiate actions affecting normal operations. C5765-R C5765-E RE4597BA RE1878A 1.50E+04 ep RE609 15.0 ep Ch 1 NG 0.00E+00 pC1/cc RE1770A 300.0 ep RE600 10.0 epm Ch2P 0.00E+00 pCi/cc RE1822A 2.50E+03 ep RE8427 0.30 mR/hr Ch 3 I 0.00E+00 pCi/ec RE5403A 2.00E+03 ep RE8403 3.00 mR/hr RE4598BA 1.00E-07 R254018 30.0 epa RE8405 5.00 mR/hr Ch 1 NG pCi/ec R25403C 40.0 epa RE8411 3.12 mR/hr Ch2P 1.00E-10 pci/cc C5765-R RE8413 1.50 mR/hr Ch 3 I 1.00E-10 pCi/cc RE1003A 40.0 epa RE8414 0.15 mR/hr RE459798 RE5052A 8.00E+02 epe RE8416 0.20 mR/hr Ch 1 NG 6.275+00 pCi/cc RE50528 50.0 epa RE8417 0.40 mR/hr Ch 2 NG 1.00E+01 pC1/cc RE5052C 30.0 epa RE8420 0.20 mR/hr Ch 3 PI 8.00E-03 mR/hr RE8432 70.0 epe RE8421 0.40 mR/hr Ch 4 PI 8.005-03 mR/hr m RE8434 70.0 ep RE8422 0.60 mR/hr Ch 5 PI 8.00E-03 mR/hr I RE8433 100.0 epa RE8423 0.20 mR/br RE4598BB RE1998 1.00E+06 epe RE8424 0.20 mR/hr Ch 1 NG 0.00E+00 pC1/cc RE8425 1.50 mR/hr Ch 2 NG 0.00E+00 pci/cc C5765-C RE8428 0.20 mR/hr Ch 3 PI O.00E+00 mR/hr RE18798 1.50E+04 epa REB 430 0.15 mR/hr Ch 4 PI 0.00E+00 mR/hr RE17705 250.0 epa Ch 5 PI 0.00E+00 mR/hr RE19225 3.00E+03 ep C5765-F RE45968 23.2 R/hr RE5405A 2.00E403 epa RE4605 100.0 epa RE4597AA RE54058 100.0 epa RE8436 0.30 mR/hr Ch 1 NG 0.00E+00 pCi/cc RE5405C 150.0 epa RE8435 0.10 mR/hr Ch 2 P O.00E+00 pci/ce C5765-D RE8438 0.15 mR/hr Ch 3 1 0.00E+00 pCi/ce RE10035 40.0 epa RE0437 U.20 mR/hr RE4598AA RE8419 0.90 mR/hr Ch 1 NG 1.00E-07 pC1/cc RE8426 0.30 mR/hr C5755-5 Ch 2 P 1.00E-10 pC1/ec RE8400 0.60 mR/hr RE5320A 40.0 cpm Ch 3 1 1.00E-10 pCi/cc p epa RE4597AB 4D RE6401 5.40 mR/hr RE53285 12.0 RE8402 2.00 mR/hr RES328C 22.0 epe Ch 1 NG 6.30E+00 pCi/cc $ RE8404 2.00 mR/hr RE1413 2.00E+03 epa Ch 2 NG 1.005401 pC1/cc RE8406 0.30 mR/hr R22389 5.66E+04 mR/hr Ch 3 PI 8.00E-03 mR/hr RE8407 0.20 mR/hr RE8447 0.10 mR/hr Ch 4 PI 8.00E-03 mR/hr M RE8408 4.00 mR/hr Ch 5 PI 8.00E-03 mR/hr [ RE8409 3.00 mR/hr C5762-8 RE4590AB 2 RE8410 0.32 mR/hr RE5327A 30.0 epe Ch 1 NG G.00E+00 pCi/ce g RE8412 20.0 mR/br RZ53273 10.0 eps Ch 2 NG 0.00E+00 pCi/ec Q. RE8415 0.30 mR/hr R25327C 20.0 eps Ch 3 PI 0.00E+00 mR/hr g RE8418 0.30 mR/hr RE1412 1.30E+03 epe Ch 4 PI 0.00E+00 mR/br M RE8429 0.15 mR/hr RE2387 5.62E+04 mR/br Ch 5 PI 0.00E+00 mR/hr k RE8431 0.10 mR/hr RE0446 0.20 mR/hr RE4596A 23.3 R/hr f3 O O O
^
g ! t DAVIS-BESSE NUCLEAR POWER STATION RE DATA SHEET SCENARIO NO. 1993 Evaluated Exercise TIME 1 1215 ,, TO: Player at the Control Room RE Panels T: 04/15 THIS IS A DRILL DO NOT initiate actions affecting normal operations. C5765-A C5765-E RE4597BA RE1878A 1.50E+04 epa RE609 15.0 cpm Ch 1 NG 0.00E+00 pC1/cc RE1770A 200.0 epn RE600 10.0 cpm Ch2P 0.00E+00 pCi/ce RE1822A 2.50E+03 epe RE8427 0.30 mR/hr Ch 3 1 0.00E+00 pCi/ce RE5403A 2.00E603 eps REB 403 3.00 mR/hr RE4598BA RE54038 30.0 epn RE8405 5.00 mR/hr Ch 1 NG 1.00E-07 pCi/cc RE5403C 40.0 cpa RE8411 3.12 mR/hr Ch 2 P 1.00E-10 pCi/cc CS?65-B RE8413 1.50 mR/hr Ch3I 1.00E-10 pel/cc RE1003A 40.0 eps REB 414 0.15 mR/br RE4597BS RE5052A 8.00E*02 epa REB 416 0.20 mR/hr Ch 1 NG 1.06E+01 pCi/cc RE50528 50.0 epa RE8417 0.40 mR/hr Ch 2 NG 1.16E+01 pC1/ce RE5052C 30.0 epa RE8420 0.20 mR/hr Ch 3 PI 2.50E-02 mR/hr RE8432 70.0 epa RZ8421 0.40 mR/hr Ch 4 PI 2.50E-02 mR/hr m RE8434 70.0 epa REB 422 0.60 mR/hr Ch 5 PI 2.50E-02 mR/br 9 RE8433 100.0 epa RZ8423 0.20 mR/hr RE4598BB N RE1998 1.00E+06 epe RE8424 0.20 mR/hr Ch 1 NG 0.00E+00 pCi/cc RE8425 1.50 mR/hr Ch 2 NG 0.00E+00 pCi/ec C5765-C REB 428 0.20 mR/hr Ch 3 PI 0.00E+00 mR/hr RE18788 1.50E+04 cpu RZ8430 0.15 mR/hr Ch 4 PI 0.00E+00 mR/hr RE17705 250.0 epn Ch 5 PI 0.00E+00 mR/hr RE18225 3.00E+03 eps C5765-F RE45968 55.8 R/hr RZ5405A 2.00E+03 epa RE4686 100.0 epe RE4597AR RE34058 100.0 epa RE8436 0.30 mR/hr Ch 1 NG 0.00E+00 pC1/cc R25405C 150.0 epe RE8435 0.10 mR/hr Ch2P 0.00E+00 pCi/ec C5765-D RE8438 0.15 mR/hr Ch 3 I 0.00E+00 pCi/ce RE10038 40.0 epe RE8437 0.20 mR/hr RE4598AA RZ8419 0.90 mR/hr Ch 1 NG 1.00E-07 pCi/cc RE8426 0.30 mR/hr C5755-9 Ch2P 1.00E-10 pCi/ec RE8400 0.60 mR/hr RE5328A 40.0 eps Ch 3 1 1.00E-10 pCi/cc w RE8401 5.40 mR/hr RE53285 12.0 epe RE4597RB to RE8402 2.00 mR/hr RZ5328C 22.0 epa Ch 1 NG 1.10E+01 pCi/cc $ RE8404 2.00 mR/hr RE1413 2.00E+03 epa Ch 2 NG 1.12E+01 pCi/cc RE8406 0.30 mR/hr RE2389 9.80E+04 mR/hr Ch 3 PI 2.50E-02 mR/hr Q REB 407 0.20 mR/hr RE8447 0.10 mR/hr Ch 4 PI 2.50E-02 mR/br D RE8408 4.00 mR/hr Ch 5 PI 2.50E-02 mR/hr [ D RE8409 3.00 mR/hr C5762-8 RE4598RB RE8410 0.32 mR/hr RZ5327A 30.0 ep Ch 1 NG 0.00E+00 pCi/ce g RE8412 20.0 mR/hr RE53278 10.0 epa Ch 2 NG 0.00E+00 pCi/cc D. REB 415 0.30 mR/br RE5327C 20.0 epe Ch 3 P1 0.00E+00 mR/hr M RE8418 0.30 mR/hr RE1412 1.30E+03 epe Ch 4 PI 0.00E+00 mR/hr M RE8429 0.15 mR/hr RE2387 9.78E+04 mR/hr Ch 5 PI 0.00E+00 mR/hr k REB 431 0.10 mR/hr RE8446 0.20 mR/hr RE4594A 56.4 R/hr O e
i i DAVIS-BESSE NUCLEAR POWER STATION RE DATA SHEET l . SCENARIO NO. 1993 Evaluated Exercise TIME 1 1230 i l j Tol Player at the Control RooEl RE Panels T1 04/30 l l ..e......*.***.e.**.*.....e*...**.....*.........***.****....*..+..*....*.e..e**.*****...*******....*..***.*. l THIS IS A DRILL l DO NOT initiate actions af fecting nounal operations. i ...........................****..*****.***...................***...........**..........***......****.******** C5765-A C5755-E RE4597EA i RE18784 1.50E+04 ep RE609 15.0 cp Ch 1 NG 0.00E+00 pci/cc RE1770A 300.0 ep RE600 10.0 cp Ch 2 P O.00E+00 pcl/ec l RE1922A 2.50E+03 ep RE8427 0.30 mR/hr Ch 3 I 0.00E+00 pci/cc RE5403A 2.00E+03 ep RZ8403 3.00 mR/hr RE4598BA RZ54038 30.0 epa REB 405 5.00 mR/hr Ch 1 NG 1.00E-07 pCi/cc RE5403C 40.0 ep RE8411 3.12 mR/hr Ch 2 P 1.00E-10 pCi/ec C5765-8 RZ8413 1.50 mR/hr Ch 3 I 1.00E-10 pCi/cc RE1003A 40.0 ep RE8414 0.15 mR/hr RE4597B9 RE5052A 8 00E+02 ep RE8416 0.20 mR/hr Ch 1 NG 3.22E+01 pCi/cc RE50525 50.0 cpm RE8417 0.40 mR/hr Ch 2 NG 3.31E+01 pC1/cc RE5052C 30.0 ep RE8420 0.20 mR/hr Ch 3 PI 4.00E-02 mR/hr RE8432 70.0 ep RE8421 0.40 mR/hr Ch 4 P! 4.00E-02 mR/hr m RE8434 70.0 ep RZ8422 0.60 mR/hr Ch 5 PI 4.003-02 mR/hr I RZ8433 100.0 ep RE8423 0.20 mR/hr RE4598BB d RE1998 1.00E+06 ep RE8424 0.20 mR/hr Ch 1 NG 0.00E+00 pC1/cc RE8425 1.50 mR/hr Ch 2 NG 0.00E+00 pC1/cc C5765-C RE8428 0.20 mR/hr Ch 3 PI 0.00E+00 mR/hr RE18785 1.50E+04 ep RE0430 0.15 mR/hr Ch 4 PI 0.00E+00 mR/hr RE1770s 250.0 ep Ch 5 PI 0.00E+00 mR/hr RE18225 3.00E+03 eps C5765-F R345949 97.6 R/hr RE5405A 2.00E+03 ep RE4686 100.0 %d RE4597AA RE54058 100.0 cp RZ8436 0.30 mR/hr Ch 1 NG 0.00E+00 pCi/cc RE5405C 150.0 ep RE8435 0.10 mR/hr Ch 2 P 0.00E+00 pCi/cc C5765-D RZ8438 0.15 mR/hr Ch 3 2 0.00E+00 pC1/cc RE10035 40.0 ep RE8437 0.20 mR/hr R34598AA RE8419 0.90 mR/hr Ch 1 NG 1.00E-07 pci/cc RZ8426 0.30 mR/hr C5755-B Ch2P 1.002-10 pCi/cc RZ8400 0.60 mR/hr RE5328A 40.0 epm Ch 3 1 1.00E-10 pCi/cc p RE8401 5.20 mR/hr RE53285 12.0 epa RE4597AB to RE8402 2.00 mR/hr RE5328C 22.0 cp Ch 1 NG 3.25E+01 pCi/ec $ RE8404 2.00 mR/hr RE1413 2.00E+03 ep Ch 2 NG 3.27E+01 pCi/cc RE8406 0.30 mR/hr RE2389 1.42E405 mR/hr Ch 3 PI 4.00E-02 mR/hr RE8407 0.20 mR/hr RE8447 0.10 mR/hr Ch 4 P1 4.00E-02 mR/hr D RE8408 4.00 mR/hr Ch 5 PI 4.00E-02 mR/hr RE8409 3.00 mR/hr C5762-8 RE4598AB D RE8410 0.32 mR/hr RE5327A 30.0 cpm Ch 1 NG O.00E+00 pCi/cc h RE8412 20.0 mR/hr RE53275 10.0 cpm Ch 2 NG 0.00E+00 pCi/cc D. RE8415 0.30 mR/hr RE5327C 20.0 cpm Ch 3 PI 0.00E+00 mR/hr g RE8418 0.30 mR/hr RE1412 1.30E+03 epm Ch 4 PI 0.00E+00 mR/hr M RE8429 0.15 mR/hr RE2387 1.33E+05 mR/hr Ch 5 PI 0.00E+60 mR/hr k RE8431 0.10 mR/hr RE8446 0.20 mR/hr RE45964 98.2 R/hr O
......................................*....................**..........................................*...*. g O O O
DAVIS-BESSE NUCLEAR POWER STATION RE DATA SHEET ! SCENARIO NO. 1993 Evaluated Exercise TIME: 1245 TO: Player at the Control Room RE Panels T: 04/45 THIS IS A DRIII
**************************************************************g DO NOT initiate actions affectin normal operations.
C5765-A C5765-E RE4597BA RE1979A 1.50E+04 cpm RE609 15.0 cpm Ch 1 NG 0.00E,00 pci/cc RE1770A 200.0 epe RE600 10.0 cpm Ch2P 0.00E+00 pCi/cc RE1922A 2.50E+03 epm RZ9427 0.30 mR/hr Ch3I 0.00E+00 pci/cc RE5403A 2.00E+03 cpm RE9403 3.00 mR/hr RE4599BA RE54038 30.0 cpm RE9405 5.00 mR/hr Ch 1 NG 1.00E-07 pCi/ec RE5403C 40.0 cpm RE9411 3.12 mR/hr Ch 2 P 1.00E-10 pCi/cc C5765-B RE9413 1.50 mR/hr Ch 3 I 1.00E-10 pCi/cc RE1003A 40.0 cpm REB 414 0.15 mR/hr RE4597BB RE3052A 9.00E+02 cpm RE9416 0.20 mR/hr Ch 1 NG 4.09E+01 pCi/cc RE50529 50.0 cpm RE9417 0.40 mR/hr Ch 2 NG 4.18E+01 pCi/cc RE5052C 30.0 crea RE9420 0.20 mR/hr Ch 3 PI 5.50E-02 mR/hr RE9432 70.0 cpm RE9421 0.40 mR/hr Ch 4 PI 5.50E-02 mR/hr REB 434 70.0 m epa RE9422 0.60 mR/hr Ch 5 PI 5.50E-02 mR/br 1 RE9433 100.0 cpm RE9423 RE1999 1.00E+06 cpm RE9424 0.20 0.20 mR/hr mR/hr RE4599BB Ch 1 NG 0.00E+00 pCi/cc RE9425 1.50 mR/hr Ch 2 NG 0.00E+00 pCi/cc C5765-C RE9429 0.20 mR/hr Ch 3 PI 0.OCE+00 mR/hr RE19798 1.50E+04 cpm RE9430 0.15 mR/hr Ch 4 PI 0.00E+0D mR/hr RE17708 250.0 cpm Ch 5 PI 0.00E+00 mR/hr RE19228 3.00E+03 eps C5765-F RE45968 1.42E+02 R/hr RE5405A 2.00E+03 epm RE4696 100.0 cpm RE4597AA RE54058 100.0 cpm RE9436 0.30 mR/hr Ch 1 NG 0.00E+00 pCi/cc RE5405C 150.0 cpm RE9435 0.10 mR/hr Ch 2 P 0.00E+00 pC1/cc C5765-D RE9439 0.15 mR/hr Ch 3 1 0.00E+00 pCi/cc RE10035 40.0 cpm REB 437 0.20 mR/hr RE4599AA RE9419 0.90 mR/hr Ch 1 NG 1.00E-07 pCi/cc RE9426 0.30 mR/hr C5755-B Ch2P 1.00E-10 pci/cc RE9400 0.60 mR/hr RE5329A 40.0 cpm Ch 3 I 1.00E-10 pCi/cc g RE9401 5.00 mR/hr RE53298 12.0 cpm RE4597AB W RE9402 2.00 mR/hr RE5329C 22.0 cpm Ch 1 NG 4.12E+01 - pCi/cc $ RE9404 2.00 mR/hr RE1413 2.00E+03 epm Ch 2 NG 4.14E+01 pCi/ec RE94C6 0.30 mR/hr RE2399 2.45E+05 mR/hr Ch 3 PI 5.50E-02 mR/hr REB 407 0.20 mR/hr RE9447 0.10 mR/hr Ch 4 PI S.50E-02 mR/hr D RE9409 4.00 mR/hr Ch 5 PI S.50E-02 mR/hr RE9409 3.00 mR/hr C5762-B RE4599AB D RE9410 0.32 mR/hr RES327A 30.0 cpm Ch 1 NG 0.00E+00 pC1/cc h ! RE9412 20.0 mR/hr RE5327B 10.0 cpm Ch 2 NG 0.00E+00 pCi/cc Q. l RE9415 0.30 mR/hr RE5327C 20.0 cpm Ch 3 PI 0.00E+00 mR/hr g RE9419 0.30- mR/hr RE1412 1.30E+03 epm Ch 4 PI 0.00E+00 mR/hr M i REB 429 0.15 mR/hr RE2397 2.40E+05- mR/hr Ch 5 PI RE9431 0.10 mR/hr RE9446 mR/hr 0.00E+00 mR/hr k 0.20 RE4596A 1.45E+02 R/hr O ! e l l' i
DAVIS-BESSE NUCLEAR POWER STATION RE DATA SHEET SCENARIO NO, 1993 Evaluated Exercise TIME: 1300 TO: Player at the Control Room RE Panels T: 05/00 THIS IS A DRILL DO NOT initiate actions affecting noEmal operations. C5765-A C5765-E RE4597BA RE187BA 1.5CE+04 cpm RE609 15.0 cpm Ch 1 NG 0.00E+00 pCi/cc RE1770A 300.C epm RE600 10.0 epm Ch2P 0.00E+00 pCi/cc RE1822A 2.50E+03 cpm RE8427 0.30 mR/hr Ch 3 I 0.00E+00 pCi/cc RE5403A 2.00E+03 cpm RE8403 180.00 mR/hr RE459BBA RE5403B 30.0 epa RE8405 162.20 mR/hr Ch 1 NG 1.00E-07 pCi/cc RE5403C 40.0 epm RE8411 3.12 mR/hr Ch 2 P 1.00E-10 pCi/cc C5765-B RE8413 20.0 mR/hr Ch 31 1.00E-10 pci/cc RE1003A 40 0 cpm RE8414 0.15 mR/hr RE4597BB RE5052A 8.00E+02 epm RE8416 0.20 mR/hr Ch 1 NG 4.33E+01 pCi/cc RE50525 $0.0 cpm RZ8417 0.40 mR/hr Ch 2 NG 4.42E+01 pC1/ce RE5052C 30.0 cpe RE8420 0.20 mR/hr Ch 3 PI 7.00E-02 mR/hr RE8432 70.0 cpm RE8421 0.40 mR/hr Ch 4 PI 7.00E-02 mR/hr m RE8434 70.0 epm RE8422 0.60 mR/hr Ch 5 FI 7.00E-02 mR/hr i RE8433 100.0 epm RE8423 0.20 mR/hr RF4599BB RE1998 1.00E406 epm RE8424 0.20 mR/hr Ch 1 NG 0.00E+00 pC1/ec RE8425 1.50 mR/hr Ch 2 NG 0.00E+00 pCi/cc C5765-C RE8428 0.20 mR/hr Ch 3 PI Q.00E+00 mR/hr RE1878B 1.50E+04 cpm RE8430 0.15 mR/hr Ch 4 PI 0.00E+00 mR/hr RE1770B 250.0 cpm Ch 5 PI 0.CCE+00 mR/hr RE18228 3.00E+03 epm C5765-F RE45968 2.47E+02 R/br RE5405A 2.00E403 epm RE4686 100.0 cpm R'4597AA RE54053 100.0 epm RE9436 0.30 mR/hr Ch 1 NG 0.00E+00 pCi/cc RE5405C 150.0 cpm RE8435 0.10 mR/hr Ch2P 0.00E+00 pCi/cc C5765-D REB 438 0.15 mR/hr Ch 3 I 0.00E+00 pCi/cc RE10038 40.0 cpm RE8437 0.20 mR/hr RE4598AA RE8419 0.90 mR/hr Ch 1 NG 1.00E-07 pCi/cc RE8426 0.30 mR/hr C5755-B Ch2P 1.00E-10 pC1/cc RE8400 0.60 mR/hr RE5328A 40.0 cpm Ch3I 1.00E-10 pci/cc w l RE8401 4.70 mR/hr RE5328B 12.0 cpm RE4597AB W j RE8402 168.00 mR/hr RE5328C 22.0 epm Ch 1 NG 4.36E+01 pCi/cc [ j RE8404 150.50 mR/hr RE1413 2.00E+03 epm Ch 2 NG 4.38E+01 pC1/cc ( RE8406 0.30 mR/hr RE2389 1.37E+05 mR/hr Ch 3 PI 7.00E-02 mR/hr l RE8407 0.20 mR/br RE8447 0.10 mR/hr Ch 4 PI 7.00E-02 mR/hr 08 RE8408 4.00 mR/hr Ch 5 PI 7.00E-02 mR/hr [ l RE8409 33.00 mR/hr C5762-B RE4599AB D3 RE8410 0.32 mR/hr RE5327A 30.0 cpm Ch 1 NG 0.00E+00 pCi/cc h , RE8412 20.0 mR/hr RE53278 10.0 cpm Ch 2 NG Q.00E+00 pCi/cc D. RE8415 0.30 mR/hr RE5327C 20.0 cpm Ch 3 PI .0.00E+00 mR/hr M i RE8418 0.30 mR/hr RE1412 1.30E+03 cpa Ch 4 PI 0.00E+00 mR/hr M RE8429 0.15 mR/hr RE2387 1.35E+05 mR/hr Ch 5 PI 0.00E400 mR/hr RE8431 0.10 mR/hr RE8446 0.20 mR/hr RE4596A 2.50E+02 R/hr O
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O O O
DAVIS-BESSE NUCLEAR POWER STATION RE DATA SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 1315 TO: Player at the Control Room RE Panels T: 05/15 , THIS IS A DRILL DO NOT initiate actions affecting normal o
- perations.*************************e***********
C5765-A C5765-E- RE4597BA RE1878A 1.50E+04 epa RE609 15.0 cpm Ch 1 NG 0.00E+00 pCi/ce RE1770A 300.0 cpn RE600 10.0 cpm Ch 2 P 0.00E+00. pCi/cc REls22A 2.50E+03 epa RE8427 0.30 ER/hr Ch 3 I 0.00E+00 pCi/cc RE5403A 2.00E+03 eps RE8403 2C8.00 mR/hr RE4598BA RE54035 30.0 cpm RE8405 189.60 mR/hr Ch 1 NG 6.62E-02 pCi/cc FR*403C 40.0 cpm RE8411 3.12 mR/hr Ch2P 1.CCE-10 pCi/cc C5765-B RE8413 85.0 mR/hr Ch3I 4.40E-10 #Ci/cc RE1003A 40.0 cpm RE8414 0.15 mR/hr RE4597BB H5052A 8.00E+02 epn RE8416 10.00 mR/hr Ch 1 NG 3.98E+01 pC1/cc RE5052B 50.0 cpn RE8417 0.40 mR/hr Ch 2 NC 4.13E+01 pci/cc RE5052C 30.0 epm RE8420 65.00 mR/hr Ch 3 PI 6.5CE-02 mR/hr RE8432 70.0 cpm RE8421 7.00 mR/hr Ch 4 PI 6.50E-02 ER/hr m RE3434 70.0 cpn RE8422 0.60 mR/hr Ch 5 PI 6.50E-02 mR/hr i RE8433 RE1998 100.0 1.00E+06 epm epm RE8423 RE8424 0.20 0.20 mR/hr mR/hr RE4598BB Ch 1 NG 6.62E-02 pCi/cc RE8425 1.50 mR/hr Ch 2 NC 0.00E+00 pCi/ce ! C5765-C RE8428 0.20 mR/hr Ch 3 PI 8.08E-01 mR/hr RE1878B 1.50E+04 epm RE8430 0.15 mR/hr Ch 4 PI 1.00E-03 mR/hr RE17708 250.0 cpm Ch 5 PI 1.00E-03 mR/hr RE1822B 3.00E+03 cpra C5765-P RE45969 1.38E+02 R/hr RE5405A 2.00E+03 epm RE4686 100.0 cpm RF4597AA RE54058 100.0 epn RE8436 0.30 mR/hr Ch 1 NC 0.00E+00 pCi/ce' RE5405C 150.0 ' cpn RE8435 0.10 mR/hr Ch2P 0.00E+00 pCi/cc C5765-D RE8438 0.15 mR/hr Ch 3 1 0.00E+00 pCi/cc RE10038 40.0 epm RE8437 0.20 mR/hr RE4598AA RE8419 0.90 mR/hr Ch 1 NG 6.50E-02 sci /cc RE8426 0.30 mR/hr C5755-B Ch2P 1.00E-10 pCi/ee RE3400 0.60 mR/hr RE5328A 40.0 epm Ch 3 1 4.36E-10 pCi/ce. p RE8401 4.30 mR/br RE53288 12.0 epa RE4597AB W RE8402 196.00 mR/hr RE5328C 22.0 RE8404 178.40 mR/hr RE1413 2.00E+03 epa epm Ch 1 NC 4.07E+01 pCi/c= h Ch 2 NC 4.09E+01 pC1/ec RE8406 0.30 mR/hr RE2389 1.28E+05 mR/hr RE8407 0.20 mR/hr RE8447 0.10 mR/hr Ch 3 PI 6.50E-02 mR/hr Ch 4 PI 6.50E-02 mR/hr kD-RES408 4.00 mR/hr Ch 5 PI 6.5CE-02 mR/hr RE9409 50.00 mR/hr C5762-B RE4598AB D RE8410 0.32 mR/hr RE5327A 30.0 epe RE8412 20.0 mR/hr RE5327B 10.0 cpm Ch 1 NG 6.60E-02 pCi/cc h Ch 2 NG 0.00E+00 pCi/cc C. RE8415 0.30 mR/hr RE5327C 20.0 cpm- Ch 3 PI . 8.10E-01 mR/hr pj RE8418 0.30 mR/hr RE1412 1.30E+03 epm Ch 4 PI 1.00E-03 mR/hr M RE8429 0.15 mR/hr RE2387 1.23E+05 mR/hr Ch 5 PI mR/hr RE8431 mR/hr 1.00E-03 k 0.10 . RE8446 0.20 mR/hr RE4596A 1.40E+02 R/hr O
- +e*************************************************************************************** {
DAVIS-BESSE NUCLEAR POWER STATION RE DATA SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 1330 TO: Player at the control Room RE Panels T: 05/30 THIS IS A DRILL DO NOT initiate actions affecting normal operations.
- e**********************************************************************************************************
C5765-A C5765-E RE4597BA RE1879A 1.50E+04 cpm RE609 15.0 cpm Ch 1 NG 0.00E+00 pei/ce RE1770A 300.0 cpm RZ600 10.0 cpm Ch 2 P 0.00E+00 pei/c.:- RElt22A 2.50E+03 cpm RE8427 0.30 mR/hr Ch3I 0.00E+00 #Ci/ce RE5403A 2.00E+03 epm RE9403 238.00 mR/hr RE4599BA RE5403B 30.0 cpm RE8405 218.30 mR/hr Ch 1 NG 0.00E+00 pCi/cc RE5403C 40.0 cpm RES411 3.12 mR/hr Ch2P 0.00E+00 pel/cc C5765-B REB 413 110.0 mR/hr Ch 3 I 0.00E+00 pC1/cc RE1003A 40.0 cpm RE8414 0.15 mR/hr RE4597BB RZ5052A 8.00E+02 cpm RE9416 24.00 mR/hr Ch 1 NG 3.97E+01 pCi/cc RE5052B $0.0 cpm RZ8417 0.40 mR/hr Ch 2 NG 4.11E+01 pC1/cc RE5052C 30.0 cpm RES420 2.50E+03 mR/hr Ch 3 PI 6.00E-02 mR/hr RZ8432 70.0 cpm RZ8421 10.00 mR/hr Ch 4 PI 6.00E-02 mR/hr m RE8434 70.0 epm RE9422 0.60 mR/hr Ch 5 PI 6.00E-02 mR/br + RES433 100.0 cpm RE9423 0.20 mR/hr RE4599BB RE1998 1.0CE+06 cpm RE8424 0.20 mR/hr Ch 1 NG 2.45E+00 pCi/cc RE8425 1.50 mR/hr Ch 2 NG 0.00E+00 pCi/cc C5769-C RES428 0.20 mR/hr Ch 3 PI 5.0$E+00 mR/hr RE1879B 1.50E+04 cpm RE9430 0.15 mR/hr Ch 4 PI 1.00E-03 mR/hr RE17708 250.0 cpm Ch 5 PI 1.00E-03 mR/hr RE1822B 2.00E+03 cpm C5765-F RE45965 1.36E+02 R/hr RZ5435A 2.00E+03 cpm RE4686 100.0 cpm RE4597AA RE5405B 100.0 cpm RE8436 0.30 mR/hr Ch 1 NG 0.00E+00 pC1/cc RE5405C 150.0 epm RE8435 0.10 mR/br Ch 2 P 0.00E+00 pC1/c= C5765-0 RE9439 0.15 mR/hr Ch 3 I 0.00E+00 pCi/ec RE1003B 40.0 cpm RES437 0.20 mR/hr RE4599AA RZ9419 0.90 mR/hr Ch 1 NG 0.00E+00 pCi/cc RE8426 0.30 mR/hr C5755-B Ch 2 P 0.00E+00 pCi/cc RE9400 0.60 mR/hr RE5329A 40.0 cpm Ch 3 I 0.00E+00 pCi/cc RE9401 4.10 mR/hr RES329B 12.0 cpm RE4597AB W RE8402 225.00 mR/hr RE5329C 22.0 cpm Ch 1 NG 4.05E+01 pC1/cc $ RE9404 206.20 mR/hr RE1413 2.00E+03 epm Ch 2 NG 4.07E+01 uCi/cc RE8406 0.30 mR/hr RE2389 1.23E+05 mR/hr Ch 3 PI 6.00E-02 mR/hr h RE9407 0.20 mR/hr RES447 0.10 mR/hr Ch 4 PI 6.00E-02 mR/hr W RE8408 4.00 mR/hr Ch 5 PI 6.00E-02 mR/hr g RE8409 845.00 mR/hr C5762-B RE4599AB W REB 410 0.32 mR/hr RE5327A 30.0 cpm Ch 1 NG 2.41E+00 pCi/cc h RE9412 20.0 mR/hr RE53278 10.0 cpm Ch 2 NG 0.00E+00 pCi/cc Q. RE9415 0.30 mR/hr RE5327C 20.0 epa Ch 3 PT 5.10E+00 mR/hr M RZ9419 0.30 mR/hr RE1412 1.30E+03 cpm Ch 4 PI 1.00E-03 mPJhr M RE9429 0.15 mR/hr RE2387 1.19E+05 mR/hr Ch 5 PI 1.00E-03 mR/hr k RES.31 0.10 mR/hr RE8446 0.20 mR/hr RE4$96A 1.38E+02 R/hr O
************************************************************************************************************* y' O O O
DAVIS-BESSE NUCLEAR POWER STATION RE DATA SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 1345 TO: Player at the Control Room RE Panels T: 05/45 A THIS IS A DRILL
, Do NOT initiate actions affecting normal operations.
******************************+******************************************************************************
C5765-A C5765-E RZ4597BA ! RE1878A 1.50E+04 ep E.2609 15.0 cp Ch 1 NG 0.00E+00 pCi/ce RE1770A 300.0 cp R.E600 10.0 cp Ch2P 0.00E+00 pCi/cc RE1822A 2.50E+03 e;m RE8427 0.30 mR/hr Ch 3 I Q.00E+0D pCi/cc RE5403A 2.00E+03 epm RE8403 274.00 mR/hr RE4598BA RE54033 30.0 cp RE9405 244.70 mR/hr Ch 1 NG 0.00E+00 #Ci/ce RE5403C 40.0 cpm RE8411 3.12 mR/hr Ch 2 P 0.00E+00 pCi/cc C5765-3 RZ8413 240.0 mR/hr Ch 3 I 0.00E+00 pCi/ec RE1001A 40.0 cpm RE8414 0.15 mR/hr RE4597BB RE5052A 8.00E+02 cpm RE8416 46.00 mR/hr Ch 1 NG 3.89E+01 pCi/cc RE50523 50.0 cpm RE8417 0.40 mR/hr Ch 2 NG 3.96E+01 pCi/cc RE5052C 30.0 cpm RE9420 2.85E+04 mR/hr Ch 3 PI 5.5GE-02 mR/hr RE8432 70.0 cpm RZ8421 24.00 mR/hr Ch 4 PI 5.50E-02 mR/hr m RZ8434 70.0 cpm RE8422 0.60 mR/hr Ch 5 PI 5.50E-02 mR/hr i RE8433 RE1998 100.0 1.00E+06 epm epm RE8423 0.20 RE8424 0.20 mR/hr mR/hr RE4599BB Ch 1 NG 2.71E+01 pCi/cc RE9425 1.50 mR/hr Ch 2 NG 2.70E+01 pCi/cc C5765-C RZ6428 0.20 mR/hr Ch 3 PI 2.45E+01 mR/hr RE1878B 1.50E+04 cpm RE9430 0.15 mR/hr Ch 4 FI 2.25E+02 mR/hr RE17703 250.0 cpm Ch 5 PI 3.70E+04 mR/hr RE1822B 3.00E+03 epa C5765-F PE45968 1.33E+02 R/hr RE5405A 2.00E+03 cpm RE4686 100.0 cpm RE4597AA RE540$B 100.0 cpn RE8436 0.30 mR/hr Ch 1 NG 0.00E+00 pCi/cc RE5405C 150.0 cpm RE8435 0.10 mR/hr Ch 2 P 0.00E+00 pCi/cc C5765-D RE8439 0.15 mR/hr Ch 3 I 0.00E+00 pCi/cc RE10C3B 40.0 cpm RE8437 0.20 mR/hr RE4599AA RZ8419 0.90 mR/hr Ch 1 NG 0.00E+00 pC1/cc RES425 0.30 mR/hr C5755-B Ch2P 0.00E+00 pCi/cc RE8400 0.60 mR/hr RES328A 40.0 cpm Ch31 0.00E+00 pCi/cc p RE8401 3.90 mR/hr RE5329B 12.0 cpm RE4597AB W RZ8402 260.00 mR/hr RE5328C 22.0 cpm Ch 1 NG 3.90E+01 pCi/cc [ RE9404 232.40 mR/hr RE1413 2.00E+03 cpm Ch 2 NG 3.92E+01 pCi/cc RE8406 0.30 mR/hr 3E2389 1.21E+05 mR/hr Ch 3 PI 5.50E-02 mR/hr RE9407 0.20 mR/hr RE8447 0.10 mR/hr Ch 4 PI S.502-02 mR/hr D j RE8408 4.00 mR/hr Ch 5 PI 5.50E-02 mR/hr [ RE8409 950.00 mR/hr C5762-B RE4598AB A j RE8410 0.32 mR/hr RE5327A 30.0 cpm Ch 1 NG 2.623401 pCi/cc h RZ9412 20.0 mR/hr RE5327B 10.0 epa Ch 2 NG 2.68E+01 pCi/cc D. ( RE8415 0.30 mR/hr RE5327C 20.0 cpm Ch 3 PI 2.50E+01 mR/hr g l RE8418 0.30 mR/hr RE1412. 1.30E+03 cpm Ch 4 PI 2.20E+02 mR/br M RE9429 0.15 mR/hr RE2387 1.172+05 mR/hr Ch 5 PI 3.72E+04 mR/hr RZ8431 0.10 mR/hr RE8446 0.20 mR/hr RE4596A 1.35E+02 R/hr O
*****************************************************************************+++***************************** {
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DAVIS-BESSE NUCLEAR POWER STATION RE DATA SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 1400 TO: Player at the control Room RE Panels T1 06/00 THIS IS A DRILL DO NOT initiate actions affecting normal operations. C5765-A C5765-E RE4597BA RE1878A 1.50E+04 epn RZ609 15.0 cpm Ch 1 NG 0.00E+00 pCi/cc RE1770A 300.0 cpn RE600 10.0 eps Ch 2 P 0.00E+00 pC1/cc RE1822A 2.50E+03 cpm RE8427 0.30 mR/hr Ch3I 0.00E+00 pCi/cc RE5403A 2.00E+03 cpm RE8403 294.00 mR/hr RE4598PA RE5403B 30.0 cpm RE8405 268.00 mR/hr Ch 1 NG 0.00E+00 pCi/cc RE5403C 40.0 epm RZ8411 3.12 mR/hr Ch2P 0.00E+00 r.<Ci/cc C5765-B RE8413 265.0 mR/hr Ch 3 I O.00E+00 pCi/cc RE1003A 40.0 epm RZ8414 0.15 mR/hr RE4597BB RE5052A 8.00E+02 cpm RE8416 59.Q' mR/hr Ch 1 NG 3.85E+01 pci/cc RE5052B 50.0 cpm RE8417 0.40 mR/hr Ch 2 NG 3.93E+01 pCi/cc RE5052C 30.0 epm RE8420 6.65E+03 mR/hr Ch 3 PI 5.00E-02 mR/hr RE8432 70.0 cpn RE8421 33.00 mR/hr Ch 4 PI 5.00E-02 mR/hr m RE8434 70.0 epm RZ8422 0.60 mR/br Ch 5 PI 5.00E-02 mR/hr i RE8433 200.0 epm RE8423 0.20 mR/hr RE4599BB RE1998 1.00E+06 epe RE8424 0.20 mR/hr Ch 1 NG 6.41E+00 pCi/cc REB 425 1.50 mR/hr Ch 2 NG 6.40E+00 pCi/cc C5765-C RZ8428 0.20 nR/hr Ch 3 PI 2.42E+01 mR/hr RE18785 1.50E+04 cpm RE8430 0.15 mR/hr Ch 4 PI 2.20E+02 mR/hr RE17708 250.0 cpm Ch 5 PI 9.75E+03 mR/hr RE1822B 3.00E+03 cpm C5765-F RE4596B 1.30E+02 R/hr RE5405A 2.0CE+03 cpm RE4686 100.0 cpm RE4597AA RE54053 100.0 epm RE8436 0.30 mR/hr Ch 1 NG 0.00E+00 pC1/cc RE5405C 150.0 cpm RZ8435 0.10 mR/hr Ch 2 P 0.00E+00 pCi/ce C5765-D RE8438 0.15 mR/hr Ch3I 0.00E+00 pCi/cc RE1003B 40.0 cpm RZ8437 0.20 mR/hr RE459BAA RE8419 0.90 mR/hr Ch 1 NG 0.00E+00 pCi/cc RES426 0.30 mR/hr C5755-B Ch2P 0.00E+00 pC1/cc RE8400 0.60 mR/hr RE5328A 40.0 epm Ch3I 0.00E+00 pCi/cc p RE8401 3.40 mR/hr RE53289 12.0 epe RE4597AB W RE8402 282.00 mR/hr RE5328C 22.0 cpm Ch 1 NG 3.87t+01 pCi/cc [ RE8404 253.00 mR/hr RE1413 2.00E+03 epu Ch 2 NG 3.89E+01 pci/cc RE8406 0.30 mR/hr RE2389 1.182+05 mR/hr Ch 3 PI 5.00E-02 mR/hr RE8407 0.20 mR/hr RE8447 0.10 mR/hr Ch 4 PI 5.00E-02 mR/hr 9 RE8408 4.00 mR/hr Ch 5 PI 5.00E-02 mR/hr [ D RE8409 1100.00 mR/hr C5762-5 RE4598AB RE8410 0.32 mR/hr RE5327A 30.0 cpm Ch 1 NG 6.39E+00 pCi/cc h RE8412 20.0 mR/hr RE5327B 10.0 epm Ch 2 NG 6.40E+00 pCi/cc D. RE8415 0.30 mR/hr RE5327C 20.0 cpm Ch 3 PI 2.45E+01 mR/hr n RE8418 0.30 mR/hr RE1412 1.30E+03 cpm Ch 4 PI 2.15E+02 mR/hr M RE8429 0.15 mR/hr RE2387 1.16E+05 mR/hr Ch 5 PI 9.79E+03 mR/hr RE8431 0.10 mR/hr RE8446 0.20 mR/hr RE4596A 1.33E+02 R/hr o o O O O
DAVIS-BESSE NUCLEAR POWER STATION RE DATA SHEET SCENARIO NO. 1993 Evaluated Exercise TIME 1 1415 TO: Player at the Control Room RE Panels T: 06/15
.******************************+****************.*********.***********.e.**********.*********.***************
THIS IS A DRILL DO NOT initiate actions affecting normal operations. C5765-A C5765-E PJ45978A RE18781. 1.50E+04 ep RE609 15.0 ep Ch 1 NG 0.00E+00 pC1/cc RE1770A 300.0 cp RE600 10.0 epa Ch 2 P 0.00E+00 pC1/ce RE1822A 2.50E+03 epm REB 427 0.30 mR/hr Ch 3 I 0.00E+00 pC1/cc RE5403A 2.00E+03 epm RE8403 311.00 mR/hr RE4598BA RZ5403B 30.0 cp RE8405 272.30 mR/hr Ch 1 NG 0.00E+00 pCi/cc RI5403C 40.0 cpm RE8411 3.12 mR/hr Ch 2 P 0.00E+00 pCi/cc C5765-B RE8413 280.0 mR/hr Ch 3 I 0.00E+00 pC1/ce RE1003A 40.0 ep RE8414 0.15 mR/hr RE459 M RE5052A 8.00E+02 epm RE8416 34.00 mR/hr Ch 1 NG 3.79E+01 pC1/cc RE5052B $0.0 cpm RE8417 0.40 mR/hr Ch 2 NG 3.87E+01 pCi/cc RE5052C 30.0 epm RE8420 1.253+03 mR/hr Ch 3 PI 4.50E-02 mR/hr RE8432 70.0 cpm RE8421 30.00 mR/hr Ch 4 PI 4.50E-02 mR/hr m RE8434 70.0 ep RE8422 0.60 mR/hr Ch 5 PI 4.50E-02 mR/hr I RE8433 100.0 epm RZ8423 0.20 mR/hr RE45999B h RE1998 1.00E+06 eps RE8424 0.20 mR/hr Ch 1 NG 8.12E-01 pCi/cc RE8425 1.50 mR/hr Ch 2 NG 8.10E-01 pCi/cc C5765-C RE8428 0.20 mR/hr Ch 3 PI 2.38E+01 mR/hr RE18789 1.50E+04 epm RE8430 0.15 mR/hr Ch 4 PI 2.15E+02 mR/hr RE17708 250.0 epm Ch 5 PI 1.66E+03 mR/hr RE1822B 3.00E+03 cpm C5765-F RE45968 1.27E+02 R/hr RE5405A 2.00E+03 cpm RE4686 100.0 epm RE4597AA RE54058 100.0 epm RE8436 0.30 mR/hr Ch 1 NG 0.00E+00 pCi/cc RE5405C 150.0 cpm RE8435 0.10 mR/hr Ch2P 0.00E+00 pCi/cc ! C5765-D RE8438 0.15 mR/hr Ch 3 I 0.00E600 pCi/cc l RE1003B 40.0 cpm RE8437 0.20 mR/hr PE4598AA RE8419 0.90 mR/hr Ch 1 NG 0.00E+00 pCi/cc RE8426 0.30 mR/hr C5755-8 Ch 2 P 0.00E+00 pCi/cc l RIS400 0.60 mR/hr RE5328A 40.0 epm Ch3I 0.00E+00 pCi/cc w i RE8401 3.20 mR/hr RE53288 12.0 cpm RE4597AB W } RE8402 297.00 mR/hr RE5328C 22.0 cpm Ch 1 NG 3.81E+01 pC1/cc h
- RE8404 264.10 mR/hr RE1413 2.00E+03 cpm Ch 2 NG 3.83E+01 pCi/cc RZ8406 0.30 mR/hr RE2389 1.16E+05 mR/hr Ch 3 FI 4.503-02 mR/hr i RE8407 0.20 PR/hr RE8447 0.10 mR/hr Ch 4 PI 4.50E-02 mR/hr D a
RE8408 RE8409 4.00 1052.00 cR/hr mR/hr C5762-B RE4598AB Ch 5 PI 4.50E-02 mR/hr h D RIS410 0.32 mR/hr RE5327A 30.0 cpm Ch 1 NG 8.07E-01 pci/cc h l RE8412 20.0 mR/hr RE53278 10.0 cpm Ch 2 NG 8.11E-01 pCi/cc Q. , RE8415 0.30 mR/hr RE5327C 20.0 cpm Ch 3 PI 2.40E+01 mR/hr p)
; RE8418 0.30 mR/hr RE1412 1.30E+03 cpm Ch 4 PI 2.10E+02 mR/hr M RE8429 0.15 mR/hr RZ2387 1.13E+05 mR/hr Ch 5 PI 1.69E+03 mR/hr RE8431 0.10 mR/hr RE8446 0.20 mR/hr RE4596A 1.30E+02 R/hr O *.e.***.e......****...*.**.***.**.**......**.**...*...**...**..*...*****...*****.*.***********.**...*....**** ;
i a ? t __x -._ _ _ _ - _ . - _ - - _ _ _ - _ _ - _ - _ . - - . _ _ - - - - - - _ - _ _ - - _ _ . _ _ _ - _ - - - . - . - - - - - _ - - _ - _ _ - - - . _ _ _ _ . _ - - - - - . _ - _ . - _ _ _ _ - - _ - - - - - . _ - - - - - _ ___ ---- __ __J
DAVIS-BESSE NUCLEAR POWER STATION RE DATA SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 1430 TO: Player at the Control Room RE Panels T: 06/30
***********************************************************************************.*********************+***
THIS IS A DRILL DO NOT initiate actions affecting normal operations.
*****************+*******************************************************************************************
C5765-A C5765-E RE4597BA RE1979A 1.50E+04 cpu RE609 15.0 cpa Ch 1 NG 0.00E+00 pCi/cc RE1770A 300.0 cpn RE600 10.0 epa Ch2P 0.00E+00 pci/cc RE1922A 2.50E+03 cpn RES427 0.30 mR/hr Ch 3 I 0.00E+00 pci/cc RE5403A 2.00E+03 epa RE8403 299.00 mR/hr RE4599BA RE5403B 30.0 cpn RE9405 258.30 eR/br Ch 1 NG 0.00E+00 pCi/cc RE5403C 40.0 cpn RE9411 3.12 mR/hr Ch 2 P 0.00E+00 pCi/cc C5765-B RE8413 270.0 mR/hr Ch 3 1 0.00E+00 pC1/cc RE1003A 40.0 epm RE9414 0.15 mR/hr RE4597BB RE5052A 8.00E+02 cpm RE9416 27.00 mR/hr Ch 1 NG 3.76E+01 pCi/cc R25052B 50.0 cpn RE9417 0.40 mR/hr Ch 2 NC 3.85E+01 pC1/cc RE5052C 30.0 epm RE9420 410.00 mR/hr Ch 3 PI 4.00E-02 mR/hr RE9432 70.0 epm RE9421 27.00 mR/hr Ch 4 PI 4.00E-02 mR/hr c2 RE9434 70.0 cpm RES422 0.60 mR/hr Ch 5 PI 4.00E-02 mR/hr i RE9433 100.0 cpm RE9423 0.20 mR/hr RE4599BB h RE1999 1.00E+06 epm RE9424 0.20 mR/hr Ch 1 NG 3.06E-01 yCi/cc RE8425 1.50 mR/hr Ch 2 NG 3.78E-01 pCi/cc C5765-C RE8429 0.20 mR/hr Ch 3 PI 2.30E+01 mR/hr j RE18789 1.50E+04 cpm RE9430 0.15 mR/hr Ch 4 PI 2.10E+02 mR/hr RE1770B 250.0 cpm Ch 5 PI 7.22E+02 mR/hr RE1822B 3.00E+03 epm C5765-F RE4596B 1.25E+02 R/hr RE5405A 2.00E+03 cpm RE4686 100.0 ept RE4597AA RE5405B 100.0 cpm RE9436 0.30 mR/hr Ch 1 NG 0.00E+00 pC1/cc RE5405C 150.0 cpm RE8435 0.10 mR/hr Ch2P 0.00E+00 pCi/cc C5765-D RE8438 0.15 mR/hr Ch 3 I 0.00E+00 pCi/cc RE1003B 40.0 cpm RZ9437 0.20 mR/hr RZ4599AA RE9419 0.90 mR/hr Ch 1 NG 0.00E+00 pCi/cc i RE9426 0.30 mR/hr C5755-B Ch 2 P 0.00E+00 pci/cc RES400 0.60 mR/hr RE5328A 40.0 epm Ch3I 0.00E+00 pCi/c= p l RE9401 3.10 mR/hr RE5328B 12.0 epa RE4597AB W RE9402 290.00 mR/hr RE5329C 22.0 cpm Ch 1 NG 3.79E+01 pCi/cc [ RE9404 255.00 mR/hr RE1413 2.00E+03 cpm Ch 2 NG 3.91E+01 pCi/cc REB 406 0.30 mR/hr RE2389 1.11E+05 mR/hr Ch 3 PI 4.00E-02 mR/hr RE8407 0.20 mR/hr RE9447 0.10 mR/hr Ch 4 FI 4.00E-02 mR/hr Du RE8408 4.00 mR/hr Ch 5 FI 4.00E-02 mR/hr RE9409 344.00 mR/hr C5762-8 PE4599AB M RE8410 0.32 mR/hr RE5327A 30.0 cpm Ch 1 NG 3.E0E-02 pci/cc h RE2412 20.0 mR/hr RES327B 10.0 cpm Ch 2 NG 3.77E-01 pCi/ec Q. RE9415 0.30 mR/hr RE5327C 20.0 cpm Ch 3 PI 2.35E+01 mR/hr g RE9418 0.30 mR/hr RE1412 1.30E+03 epm Ch 4 PI 2.05E+02 mR/hr M RI9429 0.15 mR/hr RE2387 1.09E+05 mR/hr Ch 5 PI 7.25E+02 mR/hr k RE9431 0.10 mR/hr RES446 0.20 mR/hr RE4596A 1.283+02 R/hr G
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v O v J DAVIS-BESSE NUCLEAR POWER STATION RE DATA SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 1445 TO: Player at the control Room RE Panels T: 06/45
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.................*..........................RE9446.................................RE4596A 1.25E+02 R/hr G
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- B-44 1993 Evaluated Exercise t
8.3 PLANT RADIATION MAPS The radiation data sheets in Section 8.2 contain " fixed" monitor data relative to the radiation monitor display panels located at the plant Simulator. In this section, the fixed monitor readings are correlated to the " general area" readings which would be seen by emergency response team members with survey meters. The readings are presented on plant maps for ease of use by controllers, t A map is provided for each elevation where response teams may be dispatched. This includes:
- Auxiliary Building elevations 545', 565', 585', 603', 623' & 643'
= Turbine Building elevations 567', 585', 603', 623' e Protected Area ground elevation Data is presented in blocks of time corresponding to those times where plant changes do not affect the radiation levels (i.e., steady state conditions). Thus, a new block of data is provided whenever a plant event takes place that alters the general area radiation levels.
The radiation release path is not witnin " closed" systems since the Containment breach is through Penetration No. 59. This will result in several of the penetration rooms receiving various levels of airborne . contaminants due to dispersal by the plant ventilation system. s Thus, for the Mechanical Penetration Rooms, if Players go inside these areas of the plant, controllers should use the following guidelines e open and closed window readings will be different. The open window readings in these rooms should be given as a factor of 2 higher than the readings shown on the plant radiation maps in _' this section. e All collected and analyzed air samples taken within the , penetration rooms will have results consistent with data provided on the radiation maps. (containment air sample data is provided in the PASS results Section 8.6). ' e Results from contamination surveys (i.e., swipes) performed within the penetration rooms will also be consistent with the data provided on the radiation maps with some interpolation based on location using Controller judgement. ; For all other areas of the plant, controllers should use the following guidelines when transmitting radiological information to the Players: e All open and closed window readings will be the same. e All collected and analyzed air samples taken within the plant will have results of "as read". e All results from contamination surveys (i.e., swipes) performed within the plant (but outside the Mechanical Penetration Rooms) l will be *as read." ;
8-45 1993 Evaluated Exercise O Dosimeter readings can be extrapolated by taking the time an individual remains in an area, times the dose rate from the corresponding time block for the area, plus any additional exposure data if the individual was in any other area for approximately 15 minutes or greater. Controllers should not overload themselves with this calculation. If time does not permit a quick extrapolation to be performed, Controllers can simply raise the Player's dosimeter reading by a small amount over their previous reading (e.g., 10 mR) just for drill simulation purposes. O. O
8-46 1993 Evalucted ExSrciss V > AUXIWARY BUILDING - 545' ELEV.
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- 1. DOSE RATE INFORMATION Gempel Time Does Retse in mRom/h, ;
Notes Hours A B C D E F _ 0900-1100 As Reed As Reed As Reed As Reed As Reed As Reed 1. No red twel ehengse should enour until fuel 1100 1130 As Reed As Reed As Reed As Reed As Reed 7 is domeped et 0957. 1130-1200 As Reed As Reed ' As Reed As Reed As Reed 8 2. At 0915 hi red storm on letdown. 1200-1230 As Reed As Reed As Reed As Reed As Reed 5 3. At 0940 anoressing end in semp6e lab due to 1230 1300 As Reed As Reed As Reed As Reed As Reed 4 PASS eat 6vtties. 1300-1400 170-280 150 250 100 290 As Reed .:.s Reed 3 4. At 1300 red inoresees in Mech. Pen. Hms dus 1400-1500 295-285 250-240 310-290 As Reed As Reed 2 to the CTMT breech.
- 2. AIRDORNE CONCENTRATIONS AND CONTAMINATION LEVIIA Noble Gee ledinae Porto. Contenensten General Time '
Levole Notes Hours pCuae pC6/co pCL/co in epy _ 0900 1300 As Reed As Reed As Reed As Reed 1. Hi sirborno setsvtty does not ecour outside of 1300-1315 2.1 E44 As Reed As Reed As Reed CTMT untH efter the CTMT breech et 1300. 1315 1330 2.2E 04 As Reed As Reed As Reed 2. The breech le closed et 1402, et which time -
\ 1330-1345 24E44 As Reed As Reed As Reed airbome oathrity will begin te lower due to i 1345 1400 3.5E44 As Reed As Reed As Reed the TVS.
1400 1430 3 7E44 As Reed As Reed As Reed 1430-1500 36644 As Reed As Reed l As Reed
8-47 1993 Evalustcd Ex:rcies AUXILIARY BUILDING - 565' ELEV. x x x x x x x x x x m. xxxxx xxx x xxxx x x x xi D L_ , ; - D : s D
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- 1. DOSE RATE INFORMATION AUKILIARY BUIIJ)ING - 56 5 r ELEVATION G*'**l Time Dese Retes in enRernAt Notes A B C D E F Houre _
As Reed As Reed As Reed As Reed As Reed 1. No red level chenpee should oonur until fuel 0800-1100 As Reed As Reed As Reed As Reed As Reed 6e demaped et 0857. 11041130 As bed As bed 1130 1200 As Reed As Reed As Reed As bed As Reed As Reed 2. At 0915 hl red sistm on letdown. As bed As bed As Reed As bed As Bar 4 3. At 0940 inovesemp red 6n estrele lab due to 1200-1230 As bed 1230-1300 As Reed As Reed As bed As bed As Reed As Reed PASS actrvita. 1300-1400 30-1100 20-285 10-60 As bed As Reed As Reed 4. At 1300 red enoroeses in Mech. Pen. Rme due 1400-1500 1100-50 280-280 60-20 As Reed As Reed As Reed to the CTMT bresah.
- 2. AIRSORNE CONCENTRATIONS AND CONTAMINATION LEVELS Conterroneven Gerwel Time Noble Gee ledmes Porte.
Levele Notes Hours pCl/co pCitos pCi/ce in CPM - As Reed 1. Hi mirborno metrvlty dome twt noour outside of 0900 1300 As Reed As bed As bed 1300-1316 3.8E46 As Reed As bed As bed CTMT untit efter #w CTMT breech et 1300. 8.3E 45 As bed As Reed As bed 2. The breech to closed at 1402, et which vme 1315 1330 1.1 E43 As bed As bed Ae Reed airbome activity enit begin to lowet due to 1330-1345 1345-1400 1.3f 43 As Reed As bed As bed the EVS. 14D0~1430 B.8E44 As Reed As Reed As Reed 1430-1500 1.0144 As Reed As Reed As Reed
8-48 1993 Evaluated Ex2rcies
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- 1. DOSE RATE INFORMATION AUXILIARY BUILDING - 585* ELEVATION Time Does Retse in enRom/hr hel Notes Heure A B C D E F .,,,,,,_
0800 1100 As bed As Reed As Reed As Road As Reed As Reed 1. No red level changes should ocout until fuel 1100 1130 As bed As Reed As had As Reed As Reed As Reed 6e demeped at 0857. 1130-1200 As Reed As had As Reed As bed As Reed As had 2. At 0915 hi ved eierm on letdown. 1200 1230 As bad As bed As Rees! As Road As Reed As Reed 3. At 0940 moreesing rec
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1230-1300 As Reed As Reed As Reed As Reed As bed As had PASS actvities. 1300-1400 As Reed As Reed 857000* As Reed As Reed As bed 4. At 1300 red 6noroeses in Meah. Pen. Mme due 1400-1500 As Reed As Reed 7000-60
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#3. use 'A' values on pD. 847 for MPR #4.
- 2. AIRBORNE CONCENTRATIONS AND CONTAMINATION LEVELS Tsme Wble Gee tedines Partie. Contanntion General Levels Etes Hours pCi/cc pCl/ce pCi/cc gn epy _
0800 1300 As bed As Reed As bed As Reed 1. Hi airbeme activity does not ecour outside of 1300 1315 8.2F45 4.1 E47 1.0E-09 As Reed CTMT until etter the CTMT beoech at 1300. I 1315-1330 2.5E43 1.3E-05 3.3E 08 120 2. The breech k e6esed at 1402, et oddeh time 1330-1345 3.2E42 1.eE-04 4.0E 07 350 airhome netwity will begin to lower due to 1346-1400 1.0E 42 6.0E 45 1.3E-07 420 the EVS. 1400 1430 1DE43 6 OE-OS 1 SE49 430 mte . These values are for MPR #3. use attbome 1430-1500 2.5E-04 1.3E48 33E49 435 cone ve nues from og 847 for MPR $4
B-49 1993 Evalustsd Ex:rcies AUXILIARY BUILDING - 603' ELEV. .. l tv e tv 89CNER 85 , leCMGe se NO - A A { kj B \ g EttC
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- 1. DOSE RATE INFORMATION AUXILIARY BUILDING - 603* ELEVATION Gene'el Time Does Retse in mRom/hr Noten Hours A B C D E F _
As Reed As Reed As Reed As Reed As Reed As bed 1. No red level chenpas shodd enour until fusf 0800-1100 As Road As Reed As Reed As Reed As bed is demeped et 0957. 1100-1130 3E3-5 E 3 1130 1200 As Reed S ES-6E4 As had As bed As Reed As Reed 2. At 0915 hi end eierm en letdown. As Reed SE41 E5 As Reed As Reed As Reed As Reed 3. At 0940 incrossing red en semp4e tab due to 1200 1230 1230 1300 As Reed if5 As Reed As Reed As Reed As bad PASS setivit.es. 1300 1400 As Reed 1FB As bed As Reed As Reed As Reed 4. At 1300 red 6nerosese 6n Mech Pen. Rme dus 1400-1500 As Reed itS-9E4 As had As Reed As Reed As Reed to the CTMT breech.
- 2. AIR.BORIfE CONCENTRATIONS AND CONTAMINATION LEVELR Centem6netion General Time Noble Gas lodmes Partie.
Levole Notee Hours pCi/co pCi/co pCl/co in CPM - As Reed As Reed 1. Hi mirborne notivity does not occur outside of 0000-1300 As Reed As bed 1300-1315 As bed As Reed Ae Reed As bed CTMT until etter the CTMT breech et 1800. As Reed As bed As bed 2. The bemech le closed et 1402, et which teme 1315-1330 As bed As Reed airborno settwity will beam to lower due to 1330-1345 As Reed As bed As bed 1345 1400 As bed As Reed As bed As Reed the EVS. As Reed As Reed 3. CTMT (Aree B) setivtty 6e provided in the PASS 1400-1430 As bed As bed As Reed As Reed As bed As Reed date. 1430 'f 500
8-50 1993 Evaluntad ExarciD3 o AUXILIARY BUILDING - 623' ELEV. -
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- 1. DOSE RATE INFORMATION AUEILIARY BUILDING . 623' ELEVATION General Time Dose Retse in mRom/hr Notes Hours A B C D E F _
0800 1100 As Reed As Reed As R.eed As Reed As bed As Reed 1. No red level obenges should moeur until fuel 1100-1130 As bed As Reed As bed As Reed As Reed As bed le demeged et 0857. 1130-1200 As Reed As Reed As Reed As Reed As Reed As Reed 2. At 0915 N red eterm en letdown. _ 1200 1230 As Reed As Reed As had As Reed As Reed As Reed 3. At 0940 increasing red in esmole leb due to 1230-1300 As had As bed As Reed As Resd As Reed As Reed PASS eativities. 1300-1400 As Reed As Reed As Reed As bed 5-450 As bed 4. At 1300 red increeses near Station Vent from 1400-1600 As Reed As Reed As Reed As Reed 450-2 As Reed shine en release begme due to the CTMT breech.
- 2. AIRBORNE CONCENTRATIONS AND CONTAMINATION IElrELS Contamination General Tome Noble Gee lodmes Partic.
Notes l levels Hours pCUcc pCi/co pCiloc in CPM - 0800-1300 As Reed As Reed As Reed As Reed 1. Hi airborne sotMty does not occur outside of i 1300 1315 As Reed As Reed As Reed As had CTMT untit efter the CTMT breech et 1300. l As Reed As Reed 2. The breach is closed et 1402, et which time 1315 1330 An Reed As Reed 1330-1345 As Reed As Reed As Ned As Reed airborne actrv6ty will begin te lower due to 1345-1400 As Reed As Ned As Reed As Reed the D/S_ 1400 1430 As bed As Reed As Reed As Reed 1430 1500 As Reed As Ned As Reed As Reed
B-51 1993 Evalust2d Exarciso AUXILIARY BUILDING - 638' ELEV. D Il l I c __ J LJ i
% %8 Illl!lli D E
o u C A D B w J
-~
D D D D a D F O AUKILIARY BUILDING - 838' ELEVATION
- 1. Dose RATE INFORMATION General Time Does Retes in mrem /h, Notes A B C D E F _
Hours As bed As had As bed 1. No red level changes should enour until fuel 0800-1100 As bed As bed As Reed As bed As Reed As Reed As Reed 6e demoged et 0957. 1100 1130 As Reed As bed 1130-1200 As bed As Reed As Reed As Reed As Reed As bed 2. At 0915 N red eierm on letdown. As Reed As Reed As Reed As Reed 3. At 0940 6noresemg red in semple lab due to 1200 1230 As Reed As bed As Reed As Reed As had As Reed PASS activltion. 1230-1300 As bed As bed As Reed As Reed As bed As Reed As Reed As Reed 4. At 1300 red inoroesee in Mech. Pen. Rme dus 1300-1400 As Reed As bed As Reed As Reed As Reed As Reed to the CTMT breech. 1400 1500
- 2. AIRBORNB CONCENTRATIONS AND CONTAMINATION !EVELS Contownstion General Time Noble Gee lodines Partic.
Love 6e Notee Hours pCiloc pCi/co pCi/oc in CPM - As Reed 1. Hi mirborne activHy does not occur outside of 0800 1300 As Reed As Ned As Reed As bed As Reed As bed As Reed CTMT until ofter the CTMT breech et_i_300. 1300-1315 As Reed 2. The breach is elooed at 1402, et which time 1315-1330 As Reed As Reed As Reed As Road airborne sotwity will begin to lower due to 1330-1345 As Reed As Reed As Reed As Reed As Reed As Reed the EVS. 1345 1400 As bed 1400 1430 As Reed As bed As Reed As Reed As had As bed As Reed i 1430-1500 As bed
8-52 1993 Evalustad Exarciss AUXILIARY BUILDING - 643' ELEV. Ou ///<<</1 11sii, i
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- 1. DOSE RATE INFORMATION AUZILIART BUILDING - 643r ELEVATION Dose Retse en mRom/hr O*"*
Teme Notes Hours A B C D E F _ 0800-1100 As Reed As Reed As Reed As Reed As bed As Reed 1. No red level chenpee should occur until fuel 1100-1130 As Reed As Reed As bed As Road As Reed As Reed is demoped at 0867. 1130-1200 As Reed As Reed As Reed As Reed As Reed As Reed 2. At 0915 N red storm on 6etdown. 1200-1230 As Reed As Reed As bed As Bend As Reed As Reed 3. At 0940 inoreening red in osmole leta due to 1230 1300 As bed As Reed As bed As Reed As Reed As bed PASS motevities. 1300-1400 5-450 As Reed As Reed As Reed As Reed As Reed 4. At 1300 red enerosses near Station Vent from 1400 1500 450-2 As bed As bed As Reed As Reed As Reed eNne as solenes begins due to the CTMT breech.
- 2. AIRBORNE CDNCENTRATIONS AND CONTAMINATION LEVELS Contsmmet6on General T6me Noldo Gee todmes Portec.
Levels Notes Hours pCi/co pCitos pCi/oc in CPM - 0800 1300 As Reed As had As had As bed 1 Hi embome actevity does not occur outside of 1300-1316 As bed As bed As Reed As Reed CTMT until etter the CTMT breech at 1300. O 1316 1330 As bed As bed As Reed As bed 2. The breech is esosed et 1402. et which time 1330-1345 As bed As Reed As bed As Reed airbome activtty will begm to newer due to 1345-1400 As bed As Reed As Reed As Reed the EVS. 1400-1430 As Reed As had As Reed As Reed 1433-1500 As bed As Reed As bed As head
8-53 1993 Evolunted Ex;rcica O TURBINE BUILDING - 567 ELEV. V g =2" E ofe
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- 1. DOSE RATE INFORMATION STJRBINE BUI1. DING - S$7' E1EVATION 0*'*'*I Tmm Does Retse 6n mRom/hr Notes Hours A B C D E F _
0800-1100 As bed As bed As Reed As bed As Ned As Reed 1. b red 6evel obenges eteutd sockar en the 1100-1130 Ae Reed As bed As Reed As Reed As Reed As bed Turbine Bulleng. einos a Steam Generefor tube 1130 1200 As bed As bed As Reed As bed As bed As bed isok does not ecour end since the Turbine 1200-1230 As Reed As Reed As Reed As Reed As Reed As Reed Bulidng is umwend of the radiation release 1230-1300 As Reed As bed As bed As need As bed As bed point. 1300 1400 As Reed As Reed As Reed As Reed As had As Reed 1400-1500 As Reed As bed As Reed As Reed As bed As Reed
- 2. AIRBORNE CONCENTuTIONS AND CONTAMINATION 12VEIE Partin, Conterrunsten General T6me bble Gee teense Levese Notes Hours pC6/co pCi/co pCi/co in CPM -
0800-1300 As Reed As bed As bed As bed 1. M eirborne activity does ret secur in tow 1300 1316 As bed As bed As bed As bed Turbire Build no due to the reaeene stated 1315 1330 As bed As Reed As Reed As Ned above. 1330 1345 As had As Road As bed As Reed 2. Be en the leekeut for the eseems of conterrone. 1345-1400 As bed As bed As Reed As Reed tion from the Mecherweef Penetration home dte 1400-1430 As bed As bed As Reed As bed to 6nsperoonste metene er precautions teken As Reed As Reed As Reed by the Pievers.
} 1430 1500 l As bed
8-54 1993 Evaluated Exarcise A TURBINE BUILDING - 585' ELEV. U E r N D mEl B
,=
l l 1 1I I E B y e t_; r G F l " Ia
.m.
i P m , - A ,l C = A g a e . sua eas ses qD asa ass atasses & . tentss seis I. DOSE RATE INFORMATION TURBINE BUILDING = 585r ELEVATION Time Dose btse in mnem/br G*n*'ai Notes Hours A D C D E F _ 0800-1100 As had As Reed As had As Reed As Reed As Reed 1. No red level changes should occur en the 1100-1130 As bed As Reed As Reed As bed As had As Reed Turbine Buildmp since a Steam Generator tube 1130 1200 As Reed As bed As Reed As Reed As Reed As bed leek does not ooour and eence the Turbino 1200-1230 As Reed As Reed As Reed As Reed As Road As Reed Buildmg 6e upwmd of the radiation release 1230-1300 As Reed As Reed As Reed As bad As Reed As Reed point. 1300 1400 As Reed As bed As bed As Reed As bed As Reed 1400-1600 As Reed As had Am Reed Ae Reed As Reed As Reed
- 2. AIRBORNE CONCENTRATIONS AND CONTAMINATION LEVEIA Time Noble Gee loihnee Parbo. Conterrunshon General Levein Notes Hours pC1/no pCl/co pCiton in CPM -
0800-1300 As bed As Reed As bed As Reed 1. He airbome entivity does not occur in the 1300 1316 As Reed As Reed As bed As bed Turbme Building due to the reasono stated 1316-1330 As Reed As bed As bad As bed shove. 1330 1345 As Reed As bed As Reed As bar' 2. Be on the lookout for the moreed of conterrwne. 1345-1400 As had As Reed As Reed As Reed tson from the SAschenecal Penetretion bome due 1400 1430 As Reed As Reed As bed As bed to ineooropriate acteone or orecautsons tenen 1430 1500 As bed As bed As bed As Reed by me Psevere
8-55 1993 Evalunted Exarcica TURBINE BUIL. DING - 603' ELEV. B Nh t'<' ls A are ya p 9 C I} E ' eF
- Aete one Rt g , gag g&8 MAHet
- 1. DORE RATE INFORMATION TURBINE BUILDING - 603r ELEVATION Time Dose Rates in mBom/hr G8"*'el btes Hours A B C D E F _
0800-1100 As bed As Reed As Reed As had As bed As Reed 1. No red level chenpes should occur m the 1100-1130 As bad As Reed As bed As Reed As had As Reed Turbine Building einee a Steem Generater tube 1130-1200 As bed As bed As bed As Reed As Reed Ae Reed leek does not enour and e6 nom the Turbane 1200-1230 As bed Ao Reed As bed As Reed As bed As bed Bunding 6e upw6nd of the radiateen redesse 1230-1300 As bed As Reed As Reed As Reed As Reed As Reed poirtt. 1300-1400 As bed As bed As Reed As Reed As bed As bed 1400-1500 As bed As Read As bed As Reed As had As Reed
- 2. AIR. BORNE CONCENTRATIONS AND CONTAMINATION !EVEIA bb6 Gee todmes Partic. Conternineteen Ge'wat Time Levels blee Hours pCi/cm pC6/co ph in CPM -
0900-1300 As had As Reed As Reed As Reed 1. H serborne setivtty does not enour in the 1300-1315 As bed As Ned As bed As Reed Turbine Buhding due to the sweeene eteted 1315 1330 As bed As Reed As Reed As bed above. I 1830 1345 As had As bed As Reed As heed 2. Be on the lookout for the spread of contamine. 1 13401400 As Reed As bed As bed As Reed teen from the Mooherwool Penetrot en borre due l 1400-1430 Ae Reed As bed As bed As bed to knoppropr6ste actions or preneutions taken j As bed As Reed As Reed As Reed by the Plovers.
, 1430 1500
4 0-56 1993 Evaluated Exercise s i l' 'k TURBINE BUILDING - 623' ELEV. i Q GELD c.j ;. L N >~
.p ~ .
S F D A II I I E - . /~T ~ll U l I L B h I. DOSE RATE INFORMATION TURBINE BUILDING . 623 ELEVATION ; Tune Dose Rates in mRom/hr Gerwsel Notes Hours A B C I D E F _ 0800 1100 As Reed As Road ' As Read As Reed As Reed As Ned 1. No red leved changes should occur in the 1100-1130 As had As had As Reed As Reed As Reed As had Turbine Building, since a Steam Generator tube
.1130-1200 As fleed As Reed As had As Reed As Reed As had leek does not occur and sinos the Turbine 1200 1230 As Reed As Reed As Reed As Reed As had As Reed Building is upwind of L% radiation release 1230-1300 As had As Reed As Reed As Reed As bed As Ned point.
1300-1400 AsRned As Reed 6 250 As Read As Reed As Reed 2. The 'C' readmps ese due to shine irom the 1400-1500 AsRead As Reed 250-20 As Reed As Reed As had Station Vent Keman skids located in thes erse.
- 2. AIRBORKI. CONCENTRATIONS AND CONTAMINATION IEVELS Time Nuble Gas lodines Partio. Contorninetion General Levels Notes ,
Hours pCi/co pCi/co pCi/co in CPM - 0800-1300 As had As bed As Reed As had 1. Hi airborne activity does not occur in the 1300-1315 As Reed As Reed As Reed As Reed Turbine Building due to the reasons stated , 1315 1330 As Reed As bed As Reed As bed above 1330-1345 As Reed As had As had As Reed 2. Be on the lookout for the spread of contamirw-1345-1400 As Reed As Reed As Reed As bed tien froan the Moohenical Penetretion Rooms due 1400-1430 As Reed As Reed As bed As Reed to inappropriate actions or precautions taken 1430-1500 As h ad As Ned As Road As Reed by the Plovers.
8-57 1993 Evaluated Exercise PROTECTED AREA O 585' ELEV. (Grade Level) N F at N' ' s % Nh 6"m ' D e- ]h ' - se. - Q ar. - ot-- :: . L L. _+s m E - as S L w een ,q PJ, i **** F , at eue 2 w " j u ar 3 e= e. 3
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- 1. DrW,E RATE INFORMATION PROTECTED AREA - $85* ELEVATION (GRADE LEVEL)
(kese Rates in mrem /h, General Time Notes Hours A B C D E F _ 0800 1100 As Reed As Road As Reed As bed As Ned As Ned 1. No red level changes should poeur in the 1100 1130 As had As fiend Asfked As fload As flood As had Turbine Ikdidmg, sieme a Steam Generetnr tube 1130 1200 As bed As Rond As Reed As bed As flood As Ned leek does not occur and sieme the Turbine 1200-1230 As Reed As Ned As Head As Reed As Reed As Road Nilding 6e upwind of Dus radiation release 1230-1300 As Ned As fload be Note 2 As Read As Reed As bed pr, int. 1300-1400 As Ned As R:ed be Nte 2 As Ned As flood As fload 2. Refer to Onstte Plume Map for redieten leve6s 1400 1500 As fiend As Ned See Nte 2 Asfiend As Ned As Nnd in this evea due to Stetsen Vent relense.
- 2. AIRBORNE CONCEFrTRATIONS AND CONTAMINATION LEVELS 1 Time Noble Gas lederme Partie. Contaminstrun Germare!
Levels Notes Hours pCuce pCi/oc pCiloe , cpgj _ 0800-1300 As had As bed As flood As bed 1. H mirhorno motivity does not occur in We 1300131b As Ned As Reed As bad As bad Tvebme Building due to the receans stated 1315 1330 As beJ As Ned As Ned As Road above. 1330-1346 Asfend As had As Road As Ned 2. He on the lookout for the spread of contamina-1345 1400 As Head As Nad As Reed As Reed tion from the Mechenecel Penettsteon Noms due 1400-1430 As Ned As Ned As fiend As Ned to inapper,priets acticeve or precautione taken 1430 1500 As bed As Road As Ned As Nad by the Pteyess. I 1
B-58 1993 Evaluated Exercise ONSITE PLUME TRAVEL MAP O w e ri l
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r.et ul,<.. Tll .- s v........, < Note: The plume does not touch ground until Location 3.
- survey Meter in mrem /hr Air Samples in cpe Smears in cpm Window open Window Closed Cartridge Filter s' 's' swipe d
1/1300-1307 s s As Read As Read A. Road 2/1300-1307 As Road As Read As Road As Dead As Read j 1/1307 1330 a e A. R ad A. Reed As Read 2/1307-1330 s s As Read A. Re.d A. Road 4 1/1330-1405 15 15 As Read As Read An Read i 2/1330-1405 12 12 A Read A. Read as Read 1/atter 1405 As Read As Read As Reed As Read As Read 2iafter 1405 As Reed As Road As Read As Read As Read 3 d aef er to of f site maps in section 9.4i
O O 1 1 0
8-59 1993 Evaluated Exercise 8.4 RADIOCHEMISTRY DATA
SUMMARY
Thirty-five minutes into the start of the Exercise, the 2-1 Reactor Coolant Pump undergoes severe vibrational stress which damages the impeller. Metal fragments from the damaged impeller then pass through the Reactor Coolant System it.to the core. Approximately. twenty-two minutes later, the abrasive action of the metal against the fuel rods causes approximately 35% gap activity to be released from the fuel. Up until this time (0857), sample analysis on either the primary or secondary plant can be performed using the normal sampling. systems. This data can be found in section 6.3 of this manual. After 0857, samples will have to be taken using the Post Accident Sampling System (PASS). A summary of the date for PASS samples are , provided on the following pages. Data is furnished for the following sample points: ; e Reactor Coolant System e Containment Building Sump e containment Building Atmosphere e Station Vent t l l l
60 1993 Evaluttsd.Exarcies
' A RADIOCHEMISTRY DATA
SUMMARY
REACTOR COOLANT AND PRESSURIZER SAMPLE ACTIVITY CONCENTRATION (uCi/g) AT INDICATED TIME Sample 1 Sample 2 Sample 3 Isotope 0900-1100 1100-1300 After 1300 Kr-85m 2.46E+01 7.03E+01 5.9BE+01 Kr-85 2.40E+02 6.88E+02 5.84E+02 Kr-87 1.35E+01 3.85E+01 3.27E+01 Kr-88 4.33E+01 1.23E+02 1.05E+02 Xe-133 4.14E+03 1.18E+04 1.00E+04 Xe-135 4.28E+01 1.22E+02 1.04E+02 I-131 6.47E+02 1.85E+03 1.57E+03 I-132 4.15E+01 1.18E+02 1.00E+02 I-133 1.35E+02 3.87E+02 3.29E+02 I-134 7.73E+00 2.21E+01 1.87E+01 I-135 4.28E+01 1.22E+02 1.04E+02 Cs-134 6.64E+02 1.89E+D3 1.61E+03 Cs-137 9.22E+02 2.63E+03 2.24E+03 Cs-138 1.18E+01 3.39E+01 2.88E+01 Te-132 7.73E+00 1.87E+01 1.43E+01 Mo-99 6.75E+01 1.64E+02 1.25E+02 Ru-103 7.12E+00 1.73E+01 1.32E+01 Sr-91 7.32E-01 1.77E+00 1.36E+00 Sr-92 1.62E-01 3.95E-01 3.02E-01 Ba-140 1.30E-08 1.30E-08 1.30E-08 Y-91 1.51E+00 3.69E+00 2.82E+00 La-140 1.7BE+00 4.33E+00 3.31E+00 s_ ,/ Ce-144 1.82E+00 4.43E+00 3.38E+00 Gross Noble Gas 4.50E+03 1.28E+04 1.00E+04 ' Gross Iodines B.74E+02 2.49E+03 2.12E+03 Gross Particulates 1.68E+03 4.76E+03~ 4.04E+03 , Dose Equivalent I-131 6.88E+02 1.96E+03 1.67E+03 ; Sample Pressure (PSIA) 2143 671 280 Temperature (*F) 115.0 110.0 105.0 RCS Pressure (PSIA) 2148 676 285 Temperature (*F) 549 520 520 1 PZR Temperature (*F) 648 493 380 Boron (PPM) 672 727 727 l l J 1 l
8-61 1993 Evaluated Ex3rcico RADIOCHEMISTRY DATA
SUMMARY
CONTAINMENT ATMOSPHERE SAMPLE ACTIVITY CONCENTRATION (uci/cc) AT INDICATED TIME sample 1 sample 2 sample 3 Isotope 0900-1100 1100-1300 After 1300 Kr-85m 0.00E+00 2.00E-01 8.50E-02 Kr-85 0.00E+00 9.78E-01 8.31E-01 Kr-87 0.00E+00 5.48E-02 4.66E-02 Kr-88 0.00E+00 1.76E-01 1.49E-01 , Xe-133 0.00E+00 1.68E+01 1.43E+01 Xe-135 0.00E+00 1.74E-01 1.48E-01 I-131 0.00E+00 9.07E-03 7.71E-03 I-132 0.00E+00 5.81E-04 4.94E-04 I-133 0.00E+00 1.90E-03 1.61E-03 I-134 0.00E+00 1.0BE-04 9.20E-05 I-135 0.00E+00 6.00E-04 5.10E-04 Cs-134 0.00E+00 1.86E+00 1.58E+00 Ca-137 0.00E+00 2.58E+00 2.19E+00 Cs-138 0.00E+00 3.32E-02 2.82E-02 Te-132 0.00E+00 1.84E-02 1.40E-02 Mo-99 0.00E+00 1.60E-01 1.23E-01 Ru-103 0.00E+00 1.69E-02 1.29E-02 Sr-91 0.00E+00 1.74E-03 1.33E-03 Sr-92 0.00E+00 3.87E-04 2.96E-04 Ba-140 0.00E+00 1.27E-11 1.27E-11 Y-91 0.00E+00 3.61E-03 2.76E-03 La-140 0.00E+00 4.24E-03 3.24E-03 Ce-144 0.00E+00 4.34E-03 3.32E-03
======== ======== ========
Gross Noble Gas 0.00E+00 1.82E+01 1.55E+01 Gross Iodines 0.00E+00 1.22E-02 1.04E-02 Gross Particulates 0.00E+00 4.6BE+00 3.95E+00 Sample Pressur' (PSIA) 13 13 17 Temperature (*F) 74 75 130 15 15 19 CTMTPressure(PSIAg) Temperature (F 89 90 145 l i 1 0 !
I 8-62 1993 Evaluttcd Ex2rcice -j RADIOCHEMISTRY DATA
SUMMARY
CONTAINMENT SUMP , ACTIVITY CONCENTRATION (uCi/g) AT INDICATED TIME Sample 1 Sample 2 Sample 3 Isotope 0900-1100 1100-1300 After 1300 Kr-85m 0.00E+00 2.90E+01 2.47E+01 Kr-85 0.00E+00 2.84E+02 2.41E+02 Kr-87 0.00E+00 1.5PE+01 1.35E+01 Kr-88 0.00E+00 5.11E+01 4.35E+01 Xe-133 0.00E+00 4.89E+03 4.16E+03 4.30E+01 Xe-135 0.00E+00 5.06E+01 I-131 0.00E+00 6.12E+02 4.97E+02 I-132 0.00E+00 3.92E+01 3.18E+01 I-133 0.00E+00 1.28E+02 1.04E+02 I-134 0.00E+00 7.30E+00 5.93E+00 I-135 0.00E+00 4.05E+01 3.29E+01 cs-134 0.00E+00 7.84E+02 6.66E+02 Cs-137 0.00E+00 1.0BE+03 9.26E+02 Cs-138 0.00E+00 1.40E+01 1.19E+01 Te-132 0.00E+00 7.76E+00 5.93E+00 Mo-99 0.00E+00 6.78E+01 5.18E+01 5.46E+00 Ru-103 0.00E+00 7.15E+00 Sr-91 0.00E+00 7.35E-01 5.62E-01 Sr-92 0.00E+00 1.63E-01 1.24E-01 Ba-140 0.00E+00 5.37E-09 5.37E-09 Y-91 0.00E+00 1.52E+00 1.16E+00 La-140 0.00E+00 1.79E+00 1.36E+00 Co-144 0.00E+00 1.83E+00 1.40E+00
........ ======.. ........ /' Gross Noble Gas 0.00E+00 5.32E+03 4.52E+03 Gross Iodines 0.00E+00 8.27E+02 6.71E+02
( Gross Particulates 0.00E+00 1.96E+03 1.67E+03 Sample Pressure (PSIA) 12 12 16 Temperature (*F) 74 75 130 Building Pressure (PSIA) 17 17 21 Temperature ('T) 91 92 147
8-63 1993 Evalu2tGd ExOrcico RADIOCHEMISTRY DATA
SUMMARY
STATION VENT ; ACTIVITY CONCENTRATION (uci/cc) AT INDICATEL TIME sample 1 sample 2 sample 3 Isotope 0900-1300 1300-1400 1400-1415 Kr-85m 0.00E+00 5.48E-02 3.29E-02 Kr-85 0.00E+00 5.36E-01 3.21E-01
, Kr-87 0.00E+00 3.00E-02 1.80E-02 Kr-88 0.00E+00 9.65E-02 5.79E-02 Xe-133 0.00E+00 9.23E+00 5.54E+00 xe-135 0.00E+00 9.55E-02 5.73E-02 I-131 0.00E+00 2.4BE-04 1.49E-04 I-132 0.00E+00 1.59E-05 9.57E-06 I-133 0.00E+00 5.21E-05 3.12E-05 I-134 0.00E+00 2.97E-06 1.78E-06 I-135 0.00E+00 1.64E-05 9.88E-06 Cs-134 0.00E+00 5.10E-02 3.06E-02 Cs-137 0.00E+00 7.08E-02 4.25E-02 Cs-138 0.00E+00 9.12E-04 5.47E-04 Te-132 0.00E+00 5.54E-04 3.16E-04 Ho-99 0.00E+00 4.84E-03 2.76E-03 Ru-103 0.00E+00 5.10E-04 2.91E-04 sr-91 0.00E+00 5.25E-05 3.00E-05 Sr-92 0.00E+00 1.16E-0. 6.67E-06 Ba-140 0.00E+00 0.00E+00 0.00E+00 Y-91 0.00E+00 1.08E-04 6.22E-05 La-140 0.00E+00 1.27E-04 7.31E-05 Ce-144 0.00E+00 1.30E-04 7.47E-05 Gross Noble Gas 0.00E+00 1.00E+01 6.02E+00 Gross Iodines 0.00E+00 3.35E-04 2.01E-04 Gross Particulates 0.00E+00 1.29E-01 7.72E-02
. .. . - = .
)
'l 8-64 1993 Evaluated. Exercise I
l i ~
^
8.5 RADIOCHEMISTRY DATA SHEETS This section provides individual radiochemistry data sheets to be passed ) out to Players during predesignated time frames should the - identified samples be taken during conduct of the Exercise. ! A
)
i 4 l l l l i l I 1 i I l I I
8-65 1993 Evaluttsd Ex3rcise
/\' RADIOCHEMISTRY DATA SHEET V
r
********************************** THIS IS A DRILL **************************
REACTOR COOLANT / PRESSURIZER SAMPLE 1 Activity- -i Isotope concentration (uci/g) Kr-85m 2.46E+01 Kr-85 2.40E+02 Kr-87 1.35E+01 Kr-88 4.33E+01 Xe-133 4.14E+03 re-135 4.28E+01 I-131 6.47E+02 I-132 4.15E+01 I-133 1.35E+02 I-134 7.73E+00 I-135 4.28E+01 cs-134 6.64E+02 ca-137 9.22E+02
-("')
( ,/ co-138 1.18E+01 Te-132 7.73E+00-Mo-95 6.75E+01 Ru-103 7.12E+00 Sr-91 7.32E-01 Sr-92 1.62E-01 Ba-140 1.30E-08 Y-91 1.51E+00 La-140 1.78E+00 ce-144 1.82E+00
********************************** THIS IS A DRILL **************************
O
B-66 1993 Evaluated Exercise RADIOCHEMISTRY DATA SHEET ................................
- THIS IS A DRILL *******************. .....
REACTOR COOLANT / PRESSURIZER SAMPLE 2 Activity Isotope concentration (uci/g) Kr-85m 7.03E+01 Kr-85 6.88E+02 Kr-87 3.85E+01 Kr-88 1.23E+02 Xe-133 1.18E+04 xe-135 1.22E+02 I-131 1.85E+03 I-132 1.18E+02 I-133 3.87E+02 1-134 2.21E+01 I-135 1.22E+02 ca-134 1.89E+03 cs-137 2.63E+03 Cs-138 3.39E+01 Te-132 1.87E+01 Mo-99 1.64E+02 Ru-103 1.73E+01 Sr-91 1.77E+00 Sr-92 3.95E-01 Ba-140 1.30E-08 Y-91 3.69E+00 La-140 4.33E+00 co-144 4.43E+00
- THIS IS A DRILL **************************
O
s-67 1993 Evaluated Exercise [J -s RADIOCHEMISTRY DATA SHEET
********************************** THIS IS A DRILL ************************** g.
REACTOR COOLANT / PRESSURIZER SAMPLE 3 Activity Isotope Concentration (uCi/g) Kr-85m 5.98E+01 Kr-85 5.84E+02 Kr-87 3.27E+01 Kr-88 1.05E+02 Xe-133 1.00E+04 Xe-135 1.04E+02 I-131 1.57E+03 I-132 1.00E+02 I-133 3.29E+02 I-134 1.87E+01 I-135 1.04E+02 /~"' Cs-134 1.61E+03 k-s Cs-137 2.24E+03 2.88E+01 Ca-13B Te-132 1.43E+01 Mo-99 1.25E+02 Ru-103 1.32E+01 Sr-91 1.36E+00 Sr-92 3.02E-01 Ba-140 1.30E-08 Y-91 2.82E+00 La-140 3.31E+00 Ce-144 3.38E+00
********************************** THIS IS A DRILL **************************
\
8-68 1993 Evalu3tsd Exarcica RADIOCHEMISTRY DATA SHEET
********************************** THIS IS A DRILL **************************
CONTAINMENT ATMOSPHERE SAMPLE 1 Activity i Isotope Concentration (uci/cc) Kr-85m 0.00E+00 Kr-85 0.00E+00 Kr-87 0.00E+00 Kr-BB 0.00E+00 Xe-133 0.00E+00 Xe-135 0.00E+00 I-131 0.00E+00 I-132 0.00E+00 I-133 0.00E+00 I-134 0.00E+00 I-135 0.00E+00 cs-134 0.00E+00 Cs-137 0.00E+00 Cs-130 0.00E+00 Te-132 0.00E+00 Mo-99 0.00E+00 Ru-103 0.00E+00 Gr-91 0.00E+00 Sr-92 0.00E+00 Ba-140 0.00E+00 Y-91 0.00E+00 La-140 0.00E+00 co-144 0.00E+00
********************************** THIS IS A DRILL **************************
O
( . .: 8-69 '1993 Evalustsd Ex3rcice RADIOCHEMISTRY DATA SHEET
********************************** THIS IS A DRILL **************************
CONTAINMENT ATMOSPHERE SAMPLE 2 Activity Isotope concentration (uci/cc) Kr-85m 1.00E-01 Kr-85 9.78E-01 Kr-87 5.48E-02 Kr-88 1.76E-01 Xe-133 1.6BE+01 Xe-135 1.74E-01 I-131 9.07E-03 I-132 5.81E-04 I-133 1.90E-03 I-134 1.08E-04 'i I-135 6.00E-04 cs-134 1.86E+00 ' Os cs-137 Cs-138 2.5BE+00 3.32E-02 Te-132 1.84E-02 Mo-99 1.60E-01 Ru-103 1.69E-02 , Sr-91 1.74E-03 Sr-92 3.87E-04 Ba-140 1.27E-11 Y-91 3.61E-03 La-140 4.24E-03 co-144 4.34E-03 i
********************************** THIS IS A DRILL **************************
l j (1 s_ - i
8-70 1993 Evaluatcd ExLrcics RADIOCHEMISTRY DATA SHEET
********************************** THIS IS A DRILL **************************
l CONTAINMENT ATMOSPHERE SAMPLE 3 Activity Isotope concentration (uci/cc) l Kr-85m 8.50E-02 ! Kr-85 8.31E-01 I Kr-87 4.66E-02 Kr-88 1.49E-01 Xe-133 1.43E+01
- j. Xe-135 1.48E-01 I-131 7.71E-03 I-132 4.94E-04 I-133 1.61E-03 I-134 9.20E-05 I-135 5.10E-04 co-134 1.5BE+00 l Cs-137 2.19E+00 i
} co-138 2.82E-02 l Te-132 1.40E-02 f Mo-99 1.23E-01 Ru-103 1.29E-02 Sr-91 1.33E-03 ,. Sr-92 2.96E-04 Ba-140 1.27E-11 Y-91 2.76E-03 La-140 3.24E-03 co-144 3.32E-03
********************************** THIS IS A DRILL **************************
O
8-71 1993 Evaluated Exarcias n RADI0 CHEMISTRY DATA SHEET ( J .
- ********************************** THIS IS A DRILL ************************** ,
CONTAINMENT SUMP SAMPLE 1 Activity Isotope Concentration (uCi/g) I-131 0.00E+00 I-132 0.00E+00 I-133 0.00E+00 I-134 0.00E+00 , I-135 0.00E+00 , Cs-134 0.00E+00 i Cs-137 0.00E+00 Co-138 0.00E+00 Te-132 0.00E+00 Mo-99 0.00E+00 Ru-103 0.00E+00 Sr-91 0.00E+00 Sr-92 0.00E+00 Ba-140 0.00E+00 : Y-91 0.00E+00 La-140 0.00E+00 ' Co-144 0.00E+00 f
********************************** THIS IS A DRILL **************************
f l n - - - -, -
1 8-72 1993 Evaluated Exerciser i RADIOCHEMISTRY DATA SHEET .
- THIS IS A DRILL **************************
CONTAINMENT SUMP SAMPLE 2 Activity Isotope Concentration (uCi/g) I-131 2.90E+01 I-132 2.84E+02 I-133 1.59E+01 I-134 5.11E+01 I-135 4.89E+03 Cs-134 5.06E+01 ca-137 6.12E+02 cs-138 3.92E+01 Te-132 1.28E+02 Mo-99 7.30E+00 Ru-103 4.05E+01 Sr-91 7.84E+02 Sr-92 1.08E+03 - Ba-140 1.40E+01 Y-91 7.76E+00 La-140 6.7BE+01 co-144 7.15E+00
- THIS IS A DRILL **************************
O
. _ _~ .. .
8-73 1993 Evaluated Exercise t RADIOCHEMISTRY DATA SHEET
********************************** THIS IS A DRILL ************************** l 1
CONTAINMENT SUMP SAMPLE 3 , t Activity Isotope concentration (uci/g) , I-131 2.47E+01 I-132 2.41E+02 I-133 1.35E+01 I-134 4.35E+01 ! I-135 4.16E+03 co-134 4.30E+01 co-137 4.97E+02 l ca-138 3.18.e01 Te-132 1.04E+02 Ho-99 5.93E+00 Ru-103 3.29E+01
/~' Sr-91 6.66E+02 Sr-92 9.26E+02 i Ba-140 1.19E+01 Y-91 5.93E+00 La-140 5.18E+01 co-144 5.46E+00 >
1
********************************** THIS IS A DRILL ************************** j
{s
8-74 1993 Evalunted Ex!rcisa RADIOCEEMISTRY DATA SHEET
- THIS IS A DRILL **************************
STATION VENT SAMPLE 1 Activity Isotope Concentration (uCi/cc) Kr-85m 0.00E+00 Kr-85 0.00E+00 Kr-87 0.00E+00 Kr-88 0.00E+00 Xe-133 0.00E+00 xe-135 0.00E+00 I-131 0.00E+00 I-132 0.00E+00 I-133 0.00E+00 I-134 0.00E+00 I-135 0.00E+00 Cs-134 0.00E+00 Cs-137 0.00E+00 Cs-138 0.00E+00 Te-132 0.00E+00 Mo-99 0.00E+00 Ru-103 0.00E+00 Sr-91 0.00E+00 Sr-92 0.00E+00 Ba-140 0.00E+00 Y-91 0.00E+00 La-140 0.00E+00 Ce-144 0.00E+00
- THIS IS A DRILL **************************
O
1
-1 I
J 8-75 1993 Evaluated Exercise l s RADIOCHEMISTRY DATA SHEET l
********************************** THIS IS A DRILL **************************
I STATION VENT SAMPLE 2 Activity Isotope Concentration (uci/cc) ; Kr-85m 5.48E-02 Kr-85 5.36E-01 Kr-87 3.00E-02 Kr-88 9.65E-02 Xe-133 9.23E+00 xe-135 9.55E-02 I-131 2.48E-04 I-132 1.59E-05 ' I-133 5.21E-05 I-134 2.97E-06 I-135 1.64E-05 cs-134 5.10E-02 .O Co-137 cs-138 7.08E-02 9.12E-04 Te-132' 5.54E-04 Mo-99 4.84E-03 Ru-103 5.10E-04 Sr-91 5.25E-05 Sr-92 1.16E-05 Ba-140 0.00E+00 Y-91 1.08E-04 La-140 1.27E-04 ce-144 1.30E-04 '
*****************'***************** THIS IS A DRILL **************************
l 8-76 1993 Evaluated Exercise RADIOCHEMISTRY DATA SHEET
********************************** THIS IS A DRILL ************ee............
STATION VENT SAMPLE 3 Activity Isotope Concentration (uCi/cc) Kr-85m 3.29E-02 Kr-85 3.21E-01 Kr-87 1.80E-02 Kr-88 5.79E-02 Xe-133 5.54E+00 xe-135 5.73E-02 I-131 1.49E-04 I-132 9.57E-06 I-133 3.12E-05 I-134 1.78E-06 I-135 9.8BE-06 cs-134 3.06E-02 co-137 4.25E-02 cs-138 5.47E-04 Te-132 3.16E-04 Mo-99 2.76E-03 Ru-103 2.91E-04 Sr-91 3.00E-05 Sr-92 6.67E-06 Ba-140 0.00E+00 Y-91 6.22E-05 La-140 7.31E-05 co-144 7.47E-05 l l l l t I
********************************** THIS IS A DRILL **************************
O 1 l 1
i 8-77 1993 Evaluated Exercise 8.6 POST ACCIDENT SAMPLING DATA The scenario postulates up to 35% gap activity released into the primary coolant following damage to the fuel rods from the Reactor Coolant Pump impeller fragments. . Prior to this event all chamistry samples (if any are taken) could be via the normal sampling methods and equipment. Data ! for this early period in the scenario can be found in Section 6.3. Once , the gap activity has been released into the coolant, however, sampling ; will have to be performed using the Post Accident Sampling System (PASS) I due to the high radiation levels incurred while taking the sample. ; Following the gap activity release, the plant indications provided by-the Simulator will prompt the Players to be concerned about what is happening and to determine the source term that exists inside the ! Containment building. The PASS can be used to obtain this type of information and thus PASS sample guAdance and information is provided. l In this section, controllers are provided representative radiological j survey forms applicable to PASS activities. Although an " actual" PASS ; sample is not required to be performed as part of this year's Exercise j scope, Players should still simulate the steps they would take to draw a ' sample, of concern to the Players who may be taking the sample, is the area ! radiation levels before (refer to Figure 8.6-1), during (Figure.8.6-2), and after (Figure 8.6-3) the sample is drawn. The PASS Controller , should release this information as appropriate to the steps the Player is simulating. A liquid PASS sample is the most likely to be performed and should be ; reviewed by the Technical Support center to determine the radiological hazards involved (refer to Figure 8.6-4). However, if a Containment { atmosphere sample is taken, the radiation levels at the area can be { given as being 150 mrem /hr during recirc. The general area radiation levels at all other times can be given as being background since the r sample skid is located in the Auxiliary Building Elevation 585', Fuel I Handling Area, Room 300. A PASS sample of the Station Vent may not be taken by Players since the i high range noble gas process monitors for this function will remain in i service throughout the duration of the Exercise. Players should know that because of ALARA concerns, a post accident Station Vent sample ! should not be drawn as long as the monitors are working. For radicio- ! dine and particulate information, Players may decide to pull one or more j of the Station vent accident range sample cartridges (refer to RP/chom-istry Supplemental Information on page 8-77a). After a sample is simulated to be taken, the PASS sample results that ; are available in Section 8.5 of this manual can be provided to the i Players. 1 4 O ! , j i
+
\
8-77a 1993 Evaluated Exercise RP/CHEFISTRY SUPPLEMENTAL INFORMATION _ This information is being provided in the event personnel are dispatched to the RAMAN skids to retrievs the station Vent cartridges during the offsite release (IAW DB-CH-06012, Accident Range Station Vent Monitor operation). Radiciodine release concentrations do not directly readout from the accident range monitors and an iodine to noble gas ratio will be used to initially determine radioiodine concentrations. However, should the ECC dose assessment personnel deem it necessary to verify thyroid dose projections the station vent cartridges will have to be pulled and read (IAW DB-CH-01801, Radiochem-istry Gamma spectral Analysis) to determine the concentration of radiciodines released. (The ECC personnel could also back-calculate using readings from the field monitoring teams, however, they still may want to use the station Vent cartridges for verification of any calculated values.) It is assumed that the noble gas release rates cause the station vent radia-tion monitoring system to transfer from the normal range to the accident range skids before radiciodine activity builds up on the normal range cartridges, so if the Players pull the normal range cartridge, Controllers can indicate that it is reading background. For purposes of the Exercise, Controllers can assume and convey to the Players that the indications at the accident range skid are as follows: Dose Rates in mrem /hr Times Ch. 3 Ch. 4 Ch. 5 , 1300-1315 Background Background Background 1316-1330 5.0 Background Background 1331-1345 25.0 220.0 7,000.0 1346-1400 25.0 220.0 9,000.0 1401-1500 (Dose rates remain the same until cartridge is pulled. After 1415, any new cartridges that are installed will not have increasing dose rates and should be indicated as background.) Red Light Indications on skid Times Ch. 3 Ch. 4 Ch. 5 1300-1330 off off off 1331-1335 on off off 1336-1340 on on off 1341-1400 on on on 1400-1500 (Red lights remain on until cartridge is replaced and channel is reset.) They should not pull a cartridge until after the red light is on (indicating that the sample collection process has been completed). Thus, the following readings are based on whether the channel has been on-line prior to when they pull the cartridge. Radionuclide Concentrations Based on When Cartridge Is Pulled Times Ch. 3 Ch. 4 Ch. 5 1315-1331 As Read As Read As Read 1331-1345 sample 2 As Read As Read 1346-1400 sample 2 sample 2 As Read 1401-1500 sample 2 sample 2 sample 2 " sample 2" is referring to the Pass station Vent sample data provided on page 8-75. The sample 2 data should not be provided to the Players until they have simulated taking the cartridge (s) to the Lab and stepping through the use of the gamma spectroscopy system per DB-CH-01801.
P-78 1993 Evaluated Exercise PASS AREA DOSE RATES - BEFORE SAMPLE FIGURE 8.6-1 RA OLOGICALSt.!RVEY FORM Duuusen i-i ximi m 'h.,% a-ixi xix, x _,, EttvatoN Aat'epoouism u NA $$ $$ $A) M f0 Q&
~
]4dZuyp~ "Oh" PASS Smls ,
aa an e as== maamgi e,e sa min ma mee nowe O .suun A .uturnow p.scTa 0-amsauett . * .co.nact RA . mar 4ATioN AREA HRA.eeGMRADATioN AMEA CA . cont Amtf.D AREA HCA..eGu coNTANTCN ARCA l Dose Rates s% ore in manir. sw , O C
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On *
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@ ~26 27.W3 c2. 2. / 5SC 10-10 73 9-n <13 lAM a'*$j" c3L%Yf
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8-79 1993 Evaluated Exercise PASS AREA DOSE RATES - DURING SAMPLE FIGURE B.6-2 RADIOLOGICALSURVEY FORM <t v wuuaca n w e eeuwatn
'*'"' 5$\3n1xs1sx,nsx
= - _h31-1 y, v , v, y:.
%**<a EltYATON
_sy3' Mssr'MM jfLSQ' 1gks/R5 AREAIROOursysTEM DATE Tiub?V6+ Id Savau %;s" Pass %,/,h, ~ " "8 acaso % % ~ d As eas=m m ags we .n .nnen ,me om ao.a O . suren A .wrutaow ti. acta O . Am sAuau * .coutAct RA . nanAton AntA HRA .eeGH nAotAtioN AarA CA -coutAue.AYto AntA HCA . **GM CONTAuedAfsDN ARLA Dose Rates O =,. in mn/hr. O C [ 200-
.=
m M 9
% 4 i h o, R '* 1 g
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_ . - . - ~ . - . _ _ . , . _ - - _ . - - - - . - . _ . . . _ - B-80 1993 Evaluated Exercise PASS AREA DOSE RATES - AFTER SAMPLE FIGURE 0.6-3 RADIOLOGICAL SURVEY FORM P'AM80R
'a '*
h'RVEY NUWeER32--a.i jPa3 -ixi mex. v.i xi w_ (LEvataON ARCA,R00u,5 Oatt Tet Tw:. SS!5' inssiAv5TEsAmild{a . 5. /200 + '
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= -. a mau.
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= .
1 y =- : Gas & Liquid PASS Sample . Dose Rates (mR/hr) 2:s i feet Contact Skin Of CW OR CW ' S 3 /400 II00 =?,500 i
I'*"EO *Y - M -
etSTRuutut$ USED jern $7 * /3 O Na[a I zomna z v.is 3 , ors-73 A - .- m - < b-M 2. ?, /3y 7-O-93 2DQ),'T]WQ
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8-81 1993 Evaluated ExSrcise j t TECHNICAL SUPPORT CENTER PASS ANALYSIS SHEET I FIGURE 0.6-4 PROCEtpuRE CONTINUATION SHEET so vma 8"'CT've cava esoe o. avsetRERCENCY RAD 10t4GICAL CONTROL ORGANIZATION ACTIVATION AND RESPONSE D 26 @ 16 ,, 20 HS-EP-02610 R3 ATTACHMENT 2: PASS CHECY1IST CEECKLIST POR PASS LIOUID SAMPLE 1 NOTE I I Refer to ES-EP-02620, Energency Exposure Control and KI Distribution, if the decision to take the sample results in operator exposure >1250 mRes. The TSC shall determine the radiological hasards associated with obtaining a PASS liquid sample in accordance with DB-CH-06000, Post Accident Radiological sampling and Analysis and DB-CH-00007, Post Accident Radiological Sampling and Analysis, by
- 1. Requesting the OSC to obtain current radiological conditions in appropriate areas.
- 2. Performing an evaluation based on projected dose rates af ter sampling.
- 3. Determination of operator dose shall be made as follows:
Area Dose Rate Time Calc. Do'e. Activity (area /hr) (hrs) (area)
- a. Dress out in preparation for Oe/(x) 0.5 C. 07 obtaining the liquid PASS samples, inc.luding briefing.
- b. Transit to PASS skid free / O (x) 0.04 O.
Chem. Lab.
- c. Initial PASS system checkout 2 0 (x) 0.57 /
and lineup.
- d. PASS systen sample purge up to sample cave isolation.
550(x) 0.17 d5
- e. Degas sample, collect gaseous 2 8 (x) 0.17 4{23 and liquid samples in vials and put vials in transport containers. *
- f. Deminerallred water flush of /OO(x) 0.20 N *O .
sample cave and sample needles. O ATTACHMENT 2 Pare 1 nf &
8-82 1993 Evaluatsd Ex3rcica TECHNICAL SUPPORT CENTER PASS ANALYSIS Sf1EET . FIGURE 8.6-4 iCont'd) PROCEDURE CONTINUATION SHEET eo vma o. peacviva cava emos
*d 1RERGENCY RADIOLOGICAL CONTROL ORGANIZATION ACTIVATION AND RESPONSE NOV 2 8 g 17 o, 20 as-EP-02610 R3 ATTACRMENT 2: PASS CHECKLIST (Continued)
CHECKLIST FOR PASS LIOUID SAMPLE (Continued) Area Dose Rate Time Calc. Dos,e Activity (mRea/hr) (hrs) (mrem)
- g. PASS skid and simic board /d D (x) 0.03 3.O sample valve lineup check.
- h. Transit to lab with transport / 8 d (x) 0.07 /d8 container.
- 1. Preparation of liquid and gaseous gamma spectroscopy
/2 [ (x) 0.07 M[
samples. J. Camma spectroscopy samples /[8(x) 0.17 3 d.b analysis.
- k. Boron analysis. f (x) 0.83
- 1. Store remaining samples and fO(x) 0.03 Ee7 waste.
Total M b. W mRea If the total projected calculated dose to the operator from area dose rates is less than 1250 mRea, recommend a sample be taken and obtain the Emer-gency Plant Manager's approval to draw the sample. If the projected calculated dose exceeds 1250 area, recommend a sample not be taken until the dose rates are reduced.
~
ATTACHMDrT 2 G 5 c... ? or 1 l 1 5
8-83 1993 Evaluated Exercise 8.7 MEDICAL DRILL DATA In order to satisfy the annual MS-1 Medical Drill requirements, this section of the Exercise Manual has been developed to test the coordinated response capabilities of the onsite medical organization, a local EMS group, and a local support hospital in the handling and treatment of a contaminated injured individual. The event begins at time 0905 in the Auxiliary Building where a Maintenance individual vill be pre-staged and simulating work on a Containment Spray pressure instrument. (refer to Figure 8.7-1). It is assumed that a chain hoist is being used to lift some heavy equipment when the hoist breaks loose, knocking the individual performing the maintenance to the floor. He suffers contaminated injuries, including a broken vrist, twisted knee, and abrasions of the forearm and right thigh area (refer to Figures 8.7-2 thru 8.7-4). Because of the area radiation / contamination levels, an area survey map is provided (refer to Figure 8.7-5). A roving Equipment Operator comes upon the scene and notifies the Control Room (Simulator). The Station First Aid Team responds. The Controller at the scene should issue vital signs and radiation survey information per the medical cue cards in Section 8.8. Security (CAS/SAS) vill notify the Ottava County Sheriff's Office who vill ' in turn notify the Mid-County EMS (refer to Figure 8.7-6), since it will be' simulated that Carroll Township EMS is on another call or is otherwise unavailable. NOTE: Normally 911 would be used, however, a non-emergency telephone number vill be used for this Exercise. 911 service at the Sheriff's Office must remain open in the event of any real emergencies that may occur the day of the Exercise. Following pickup of the injured worker by the Mid-County EMS, the ambulance vill be directed to Fremont for a demonstration by Fremont Memorial Hospital (refer to Figures 8.7-7 and 8.7-8). Again, normally Magruder Hospital vould be used to treat the victim. However, for the purpose of this Exercise to demonstrate the capabilities of the Fremont Memorial Hospital, it is simulated that the victim has requested the change. Frior to release of the ambulance, the ENT's, their vehicle and equipment should be surveyed for contamination. The stretcher / backboard (used to carry the victim) vill be simulated to be contaminated (refer to Figure 8.7-9). A brief decon demonstration should be performed before releasing , the ambulance. Refer to Table 8.7-1 for a timeline of the above events. O
8-04 1993 Evaluated Exercise < SCENE OF MEDICAL EMERGENCY FIGURE 8.7-1 Penetration No. 59
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e Pressure Instrument PI-1559 Victim falls into contaminated area I f t 4
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8-85 1993 Evaluated Exercise ( VICTIM'S INJURIES FIGURE 8.7-2 RIGHT BACK Sp FRONT
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i 8-86 1993 Evaluated Exercise VICTIM'S C0!TTAMINATION - CLOTilES ON FIGURE 8.7-3 LEfi RIGHT BACK 9 p FRONT
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8-87 1993 Evaluated Exercise [(y) VICTIH'S CONTAMINATION - CLOTHES REMOVED FIGURE 8.7 4 LEFT RIGHT I M l
" FRONT
@ p BACK
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' v.
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)
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8-88 1993 Evaluated Exercise AREA RADIATION SURVEY MAP FIGURE 8.7-5 RADIOLOGICAL SURVEY FORM avtvNuusta nwe uumui bf-lXiKl%I$1_% k hl-lY VIXIX l N:lk WS ' " ATE 2 .,1 AuL A f*3 *)'h)s/}3 "o?oo . Ex -d 'sM eSwel ou C7MTSAe4 /%ge. Esk Too
< i awa As redemon eenmaps are sa mm/h oness eewrwies acted O .suom A .wournos p-noA O . AsisAupa * .co.nAci ,
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~1 8-89 1993 Evaluated Exercise l MID-COUNTY EMS FIGURE 8.7-6 Maumes Bay lake Erie Turtle Creek 51 Williston e_ _
g h s DAVIS-Besse Toussaint River /~ i .. .. . ., e .. . n..e , j Lt Iwm i
-. A163 EMSrf[f _ \ V Dak HarIor -- I Ohio Turnpike W~ Portage River i
N i g 9 , k EWS = Mid-County Ernergency Medical Services p.w e s. w a %
8-90 1993 Evaluated Exercise FREMONT MEMORIJL HOSPITAL LOCATION ZIGURE 8.7-7 Maumee Bay lake Erie Turtle Creek Williston t_ 51 Davis-Besse i g Toussaint River x @ >
- - e N Qak Herber -
W-- Ohio Portage River Turnpike f N . a E H0S = Fremont Memorial
- 53 Hospital 20 in. i.eu... i. r, ..o ,,
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N 0-91 1993 Evaluated Exorcise FREMONT MEMORIAL HOSPITAL RADIATION EMERGENCY AREA FIGURE 8.7-8 NURSES STATION -
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sih :{:{$:{'{ {:{:{:{:{'i$!j!!!{,$.:{, SMG. ':ss9:'sssp:9[Q1 (~ ' ucirwn [D /. - N %g e Yellow licrcuhte g Green llerculite WE k-O
i i 1 8-92 1993 Evaluated Exercise l STRETCIIER/ BACKBOARD CONTAMINATION FIGURE 8..-9 IlEAD I I I I l Initial Readings: l 0.3 mR/hr Survey l 9500 dpm Svipe l l l l Follov-up readings should l Xl be given "as read" once j Xl decon measures are l Xl performed. I I I I l l l l 1 I I i 1: lX l l 9 ! I I l 1 I l FOOT XXXX l XXXX = Area of contamination on backboard. Should be noted by Rad Tech " clearing" equipment for return to EMS. l l
l 8-93 1993 Evaluated Exercise () MEDICAL EVENTS TIMELINE TABLE 8.7-1 .l l T-Time Real Time 0000 0905 Maintenance worker is injured. 0001 0906 Roving Equipment Operator notifies Control Room (Simulator). 0002 0907 Control Room sounds the Initiate Emergency Procedures alarm. , 0015 0915 First Aid Team and Radiation Protection personnel arrive on scene and commence patient assessment and treatment. 0020 0920 First Aid Team Leader requests offsite medical assistance, also advises the Control Room the injured victim is-contaminated and provides a brief assessment of injuries, injured's name and employer. 0025 0925 SAS notifies Ottava County Sheriff's Office of need to dispatch ambulance to respond to contaminated injury at Davis-Besse. SAS also notifies Fremont Memorial Hospital of impending arrival of contaminated injured victim. . .O 0026 0926 The Sheriff's Office tones out Mid-County EMS since Carroll Township EMS is (simulated) to be out on another call. L 0030 0930 Fremont Memorial Hospital personnel begin setting up the Radiation Emergency Area for receipt of the contaminated victim. 0045 0945 Mid-County EMS arrives onsite, picks up security escort and contamination control kit at the Personnel Processing-Facility. ; 0050 0950 Mid-County EMS arrives at injury scene. First Aid Team ; turns over victim (i.e., patient) for EMS assessment and treatment. 0110 1010 Mid-County EMS leaves scene with patient. 0115 1015 Mid-County EMS leaves site boundary for Fremont Memorial Hospital. 0140 1040 Mid-County EMS arrives at Fremont Memorial Hospital. 0145 1045 Patient is taken to Hospital Radiation Emergency Area for treatment and decontamination. (/ 0150 1050 Patient in Radiation Emergency Area. Stabilization and decontamination begins.
, . - . - - - - - - - - - ,n.. . ,., ---
8-94 1993 Evaluated Exercise HEDICAL EVENTS TIMELINE TABLE 8.7-1 (Continued) T-Time Real Time 0210 1110 Mid-County EMS personnel and equipment (including the ambulance) are monitored, deconned and released. 0220 1120 Patient decontamination is completed. 0225 1125 Patient is transported to Emergency Room Area for final treatment and hospital admittance. 0245 1145 flospital personnel exit Radiation Emergency Area. 0250 1150 Medical Drill is terminated at the hospital. O O
B-95 1993 Evaluated Exercise I O ; 8.8 MEDICAL DRILL CUE CARDS This section provides cue cards that vill be'needed to relay injured. Victim data to Players who are responding to the medical emergency. b O f r O l
8-96 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. MD-1 TO: First Aid Team TIME: 09:05 T: 00/05 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. INFORMATION: Initial medical data: RESP - 18 PULSE - 100, Regular / Strong SKIN - Normal B/P - 138/78 PUPILS - Equal / Reactive O THIS IS A DRILL 4
8-97 1993 Evaluated Exercise -' DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) CUE CARD NO. HD-1 TO: FAT Controller . TIME: 09:05 , T: 00/05 , ANTICIPATED RESPONSE: Treatment provided to victim. l l INSTRUCTIONS: Initially have victim in #3 Hechanical Penetration Room of Aux. Bldg., Elevation 585' (refer to Figure 8.7-1) Provide the information from this cue card after the team arrives and begins to assess victim's vital signs. j
) The victim should be dressed out with moulage that indicates (refer to figure 8.7-2):
- 1. A sprained right knee. l
- 2. Abrasions to right forearm and thigh.- l
- 3. A broken right vrist. .l The individual playing the part of the victim should indicate being conscious, :
j but irritated. i Injury summary: Chief complaint - pain in right vrist, some bruising noted, some deformation and svelling, probable fracture i but NOT compound (not through the skin). Additional injuries: slight abrasions to right forearm ) and right thigh (no bleeding); pain (sprain) right knee. ! No physical indication of neck or back injury. THIS IS A DRILL () ****************************************************************************** 1
8-98 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO No. 1993 Evaluated Exercise CUE CARD NO. MD-2 TO: Rad Protection Technician TIME: 09:05 T: 00/05
- +**********************************************
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
- f********************
INFORMATION: , Initial radiological data (in epm): FACE - BKGD HAIR - BKGD. CHEST - BKGD BACK - BKGD. R ARM - 30K L ARM - BKGD. R LEG - 40K L LEG - BKGD. HAND - 50K
- 6*
THIS IS A DRILL
B-99 1993 Evaluated Exercise i DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) CUE CARD NO. HD-2 TO: RP Controller TIME: 09:05 1 T: 00/05 i ANTICIPATED RESPONSE: , i Surveys and determines victim to be contaminated. s t INSTRUCTIONS: , Provide cue card information after the RP Tech arrives and begins to survey the victim. The cue card itself should not be handed to the RP Tech, instead provide the readings as the survey meter is passed over the contaminated areas of the victim's body (refer to Figure 8.7-3). These areas include the upper right forearem, the thigh and knee of the right leg, and the palm and wrist of ' the right hand. If the RP Tech requests the area survey map, provide Figure 8.7-5. f
?
l t l THIS IS A DRILL
\ ******************************************************************************
l l
)
l 8-100 1993 Evaluated Exercis ) i DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. MD-3 T0: First Aid Team TIME: 09:20 l T: 00/20 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. INFORMATION: Medical data after treatment: RESP - 16 PULSE - 92, Regular / Strong SKIN - Normal B/P - 136/78 PUPILS - Equal Reactive d 1 Q***************************************************************************** THIS IS A DRILL Q*****************************************************************************
1 I 8-101 -1993 Evaluated Exercis-DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) CUE CARD NO. MD-3 TO: FAT Controller TIME: 09:20 ! T: 00/20 ANTICIPATED RESPONSE: Victim prepared for transport out of Auxiliary Building. INSTRUCTIONS: Provide information after initial treatment is performed. The victim should simulate being conscious and alert, suffering severe pain from abrasions, sprained knee and broken vrist. n 9 9 I THIS IS A DRILL
****************************************************************************** l 1)
)
8-102 1993 Evaluated Exercis DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO, 1993 Evaluated Exercise CUE CARD NO. MD-4 TO: Rad Protection Technician TIME: 09:20 T: 00/20 o***************************************************************************** THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
~
INFORMATION: Radiological data in cpm (if clothes removed): FACE - BKGD. HAIR - BKGD. CHEST - BKGD. BACK - BKGD. R ARM - 20K L ARM - BKGD. R LEG - 35K L LEG - BKGD. HAND - 50K THIS IS A DRILL
****************************************************************************** {
1
.! 1 8-103 1993 Evalunted Exercis \
DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd)- O
-/ CUE-CARD NO. HD 4 TO: RP Controller TIME: 09:20 T: 00/20 4
ANTICIPATED RESPONSE: 4 Precautions should be taken to prevent the spread of contamination to the First Aid Team members. INSTRUCTIONS: If the victim's clothes have not been removed, continue to provide contamination levels as specified on Cue Card No. MD-2. Provide these new readings only after the victim's clothes are removed (refer to Figure 8.7-4). Injury Summary: Patient is alert and oriented. Chief complaint continues to be pain in right vrist. I i 1 4 THIS IS A DRILL j () ****************************************************************************** l
8-104 1993 Evaluated Exercis DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. MD-5 TO: Mid-County EMS TIME: 09:50 T: 00/50 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. o***************************************************************************** INFORMATION: Initial medical data for Mid-County EMS: RESP - 16 PULSE - 90, Regular / Strong SKIN - Normal B/P - 136/78 PUPILS - Equal / Reactive O THIS IS A DRILL o*****************************************************************************
8-105 1993 Evaluated Exercis
,s . DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd)
CUE CARD NO. HD-5 T0: EMT Controller TIME: 09:50 T: 00/50 ANTICIPATED RESPONSE: Victim (patient) is stabilized and immobilized, i.e., readied for transport.
- INSTRUCTIONS:
Provide information after EMT's from Mid-County begin examining victim. The victim should indicate being conscious and alert, as well as suffering pain from the abrasions, tvisted knee and broken vrist. Injury Summary: Patient is alert and oriented. Chief complaint continues to be pain in the right vrist. Patient is stable and immobilized; ready for transport. 5 A THIS IS A DRILL () ******************************************************************************
8-106 1993 Evaluated Exercis DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. MD-6 TO: Rad Protection Technician TIME: 09:50 T: 00/50
- /,-**************************************************************************
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
- kA*************************************
INFORMATION: Radiological data in cpm (with clothes on): FACE - BKGD. HAIR - BKGD. CHEST - BKGD. BACK - BKGD. R ARM - 30K L ARM - BKGD. R LEG - 40K L LEG - BKGD. HAND - 50K Radiological data in epm (if clothes removed): FACE - BKGD. HAIR - BKGD. CHEST - BKGD. BACK - BKGD. R ARM - 20K L ARM - BKGD. R LEG - 35K L LEG - BKGD. HAND - 50K o***************************************************************************** THIS IS A DRILL o*****************************************************************************
'I l
.i 8-107 1993 Evaluated Exercis DBNPS EMERGENCY PREPAREDNESS CUE CARD.(Cont'd)
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CUE. CARD NO. HD-6 TO: RP Controller TIHE: 09:50 T: 00/50 J ANTICIPATED RESPONSE: Victim is readied for " clean" transfer to ambulance. INSTRUCTIONS: Provide information as appropriate to the victim's condition, i.e., with clothes on or if outer clothes have been removed.
\
r i i THIS IS A DRILL
\. l
8-108 1993 Evaluated Exercis DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD No. MD-7 TO: Mid-County EMS TIME: 10:15 T: 01/15 o***************************************************************************** THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. o*********************************.x****************************************** INFORMATION: Medical data while in transit to hospital: RESP - 16 PULSE - 80, Regular / Strong SKIN - Normal B/P - 128/76 PUPILS - Equal / Reactive 0 c............................................................................. THIS IS A DRILL
- +*************.*
8-109 1993 Evaluated Exercis DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) O
. CUE CARD NO. HD-7 j TO: EMT Controller TIME: 10:15 f j
T: 01/15 ANTICTPATED RESPONSE: Patient is maintained stablt. and vital signs are monitored during transport to Premont Memorial Hospital. INSTRUCTIONS: Provide information as necessary during drive to Premont Memorial Hospital. The patient should indicate remaining conscious and alert; pain also remains from the injuries. Note: Radiological data is provided on cue card MD-6. Injury Summary: Patient is alert and oriented. Pain continues in the right vrist. Patient has motor and sensory ability in the right hand, capillary refill delayed due to swelling and bruising in vrist but is present. Paln in right knee is minor. Patient has motor and sensory ability in both extremities. Distal pulse is present, capillary refill is immediate. Patient is stable during transport to Premont. THIS IS A DRILL i
8-110 1993 Evaluated Exercis DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. MD-8 TO: Hospital Staff TIME: 10:45 T: 01/45 o***************************************************************************** THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. INFORMATION: Initial medical data at Fremont Memorial Hospital: RESP - 16 PULSE - 88, Regular / Strong SKIN - Normal B/P - 130/80 PUPILS - Equal / Reactive O THIS IS A DRILL
8-111 1993 Evaluated-Exercis. DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) ' CUE CARD NO. HD-8 TO: Hospital Contoller TIME: 10:45 T: 01/45 _ ANTICIPATED RESPONSE: A " clean transfer" should occur from the ambulance to the REA. Vital signs are checked and initial treatment provided. i c INSTRUCTIONS: . Provide this information after the hospital' staff begins examining patient. Note: Radiological data should be provided as on cue card HD-6. Prior to release of the Mid-County EMS, the ambulance backboard should be simulated being contaminated as per Figure 8.7-9. , Inj ury . Summary: Patient remains alert and oriented. Pain continues in right vrist. Patient is properly assessed, treated and stabilized for decon. THIS IS A DRILL l 1 I
8-112 1993 Evaluated Exercis DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. HD-9 TO: Hospital Staff TIME: 10:50+ T: 01/50+ o***************************************************************************** THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. o***************************************************************************** INFORMATION: Medical data: RESP - 16 PULSE - 88, Regular / Strong SKIN - Normal B/P - 130/80 PUPILS - Equal / Reactive Radiological data in cpm after first decon attempt: FACE - BKGD. HAIR- BKGD. CHEST - BKGD. BACK - BKGD. R ARM - 10K L ARM - BKGD. R LEG - 10K L LEG - BKGD. H/ND -20K General contamination is removed; hot spots remain, o***************************************************************************** THIS IS A DRILL o***************************************************************************** l
8-113 1993 Evaluated Exercis
,g DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd)
\' CUE CARD NO. MD-9 TO: Hospital Controller TIME: 10:50+ T: 01/50+ ANTICIPATED RESPONSE: Patient is properly treated and stabilized during decon. INSTRUCTIONS: Provide information following first decon. Patient should continue to indicate being conscious and alert; experiences pain from the decon methods used on the contusions and broken arm. A THIS IS A DRILL I ) ***<**************************************************************************
8-114 1993 Evaluated Exercis DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. MD-10 O. To: Hospital Staff TIME: 11:00 - 11:20 T: 02/00 - 02/20 o***************************************************************************** THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. o***************************************************************************** INFORMATION: Medical data: RESP - 18 PULSE - 80, Regular / Strong SKIN - Normal B/P - 130/80 PUPILS - Equal / Reactive Radiological data in epm afer final decon: FACE - BKGD. HAIR - BKGD. CHEST - BKGD. BACK - BKGD. R ARM - BKGD. L ARM - BKGD. R LEG - BKGD. L LEG - BKGD. Patient successfully deconned to satisfactory levels; is successfully removed from the REA. o******************************************+********************************** THIS IS A DRILL o***************************************************************************** g'
B-115 '1993 Evaluated Exercis - DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd)- CUE CARD NO. HD-10' T0: Hospital Controller TIME: 11:00 - 11:20 : T: 02/00 - 02/20 ANTICIPATED RESPONSE: Patient treated, stabilized and deconnned ready to admit as a normal patient. t INSTRUCTIONS: Provide this information following the final decon. - Patient should continue to indicate being conscious and alert requiring standard medical treatment. I THIS IS A DRILL l
9-1 1993 Evaluated Exercise. O 9.0 OFFSITE DOSE ASSESSMENT DATA. PLUME MAPS AND PUBLIC INFORMATION CUE CARDS This section provides meteorological, offsite dose assessment data, and field monitoring response conditions. 9.1 METEOROLOGICAL FORECAST DATA This section provides a general' overview of meteorological conditions postulated for the day of the Exercise. 9.2 METEOROLOGICAL DATA
SUMMARY
This section provides meteorological data in a tabular format for ease of review and for ease of locating a particular data point over an extended period of time. 9.3 ECC DOSE ASSESSMENT CENTER CUE CARDS This section provides individual data sheets of meteorological (and other dose assessment parameters) data which can be passed out to Players on a 15 minute basis should the Control Room Simulator become unavailable to conduct the Exercise. 9.4 RADIATION PLUME HAPS This section provides controller guidance to any field O
~
team controller who may be sent offsite with Radiation Monitoring Team Players during conduct of the Exercise. The maps display radiation levels based on time in the event for all locations downwind of the plant. 9.5 PUBLIC INFORMATION CUE CARDS This section provides individual messages pertaining to the Toledo Edison public relations response and can be used to initiate and document actions taken by Players at the Joint Public Information Center. O
-)
9-2 1993 Fraluated Exercise 9.1 [1ETEOROLOGICAL FORECAST DATA Thio: section provides a general overview of meteorological conditions postulated for the day of the Exercise. This information plays an important role in the scenario for the following reasons: , o A lightning strike initiates the plant transient, e wind conditions affect the dispersion of radionuclides to the environment when the radiation release occurs. e overall weather conditions must be factored into the public protective action decision-making process. The control cell, representing the National Weather service, can provide meteorological forecast data to Players as needed. Refer to Table 9.1-1. O l l O 1
9-3 1993 Evaluated Exercise METEOROLOGICAL OVERVIEW AND FORECAST INFORMATION Overviews e A nevere thunderstorm occurs in the first hour of the Exercise, however, conditions rapidly improve to normal temperatures, barometric pressures and cloud cover for an October time period. e Some precipitation occurs in the first hour only. e The control Room Simulator will display meteorological data based on pre-selected parameters. Thu data will be provided to other onsite emergency facilities by the Simulator via the Data Acquisition and Display System (DADS) terminals. Data will be provided to the State Dose Assessment Center in Columbus by the use of hard-copy data sheets provided by controllers every 15 minutes. Forecasts e Wind direction will begin from the North at seasonal wind speeds (approximately 8 MPH). e From 0700 AM until 1000 AM, the wind will slowly change direction and speed to become Northeasterly at approximately 5 MPH. e From 1000 AM until 1100 AM, the wind will continue to shift until at 1100 AM it holds relatively steady until arour.4 0200 PM with winds from the East at approximately 2 MPH.
- From 0200 PM until the end of the day, the wind shifts slightly until it is coming from the Southeast at approximately 3 to 4 MPH.
O
9-4 1993 Evaluated Exercise CONTR>L CELL GUIDANCE FOR PROVIDING NWS INFORMATION j TABLE 9.1-1 Instructions: l l The Control Cell can release the following information when contacted by l Players who need information from the National Weather Service (NWS). This information is normally provided by a telephone answering device at the Toledo Express Airport, however, for the purposes of the Exercise the Control cell can just read the following information when contacted:
. If a call for the NWS is received in the morning (08:00 AM to 12:00 PM) hours, read the following:
"THIS IS A DRILL. WEATHER CONDITIONS FOR WEDNESDAY MORNING, OCTOBER 13TH... NORTHERLY WINDS ARE EXPECTED FROM 12 TO 15 KNOTS, WAVES AROUND 4 FEET. THURSDAY, WINDS FROM 5 TO 7 KNOTS, CREATING WAVES FROM THE SOUTHEAST AT 1 TO 2 FEET....FOR THE TOLEDO AREA, WE ARE CURRENTLY UNDER A SEVERE THUNDERSTORM WATCH, CLOUDY CONDITIONS, AT 60 DEGREES, WITH RELATIVE HUMIDITY AT 73%, BAROMETRIC PRESSURE AT 31.4 INCHES AND RISING.
FOR THE AFTERNOON, THE STORM FRONT IS EXPECTED TO MOVE OUT, TEMPERATURES SHOULD REACH 71 DEGREES WITH THE WINDS COMING FROM THE EAST AT 3 KNOTS... THIS IS THE NATIONAL WEATHER SERVICE AT TE!E TOLEDO EXPRESS AIRPORT. HAVE A COOD DAY. THIS IS A DRILL."
. If a call for the NWS is received in the afternoon (12:00 PM to 3:00 PM) hours, read the following:
(
"THIS IS A DRILL. WEATHER CONDITIONS FOR WEDNESDAY AFTERNOON, OCTOBER 13TH... EASTERLY WINDS AT 2 TO 3 KNOTS, WAVES AROUND 1 FOOT. THURSDAY, WINDS FROM 5 TO 7 KNOTS, CREATING WAVES FROM THE SOUTHEAST AT 1 TO 2 FEET....FOR THE TOLEDO AREA, WE ARE CURRENTLY UNDER CLEARING SKIES, AT 70 DEGREES, WITH RELATIVE HUMIDITY AT 64%, BAROMETRIC PRESSURE AT 30 INCHES AND STEADY. THIS IS THE NATIONAL WEATHER SERVICE AT THE TOLEDO EXPRESS AIRPORT. HAVE A CDOD DAY. THIS IS A DRILL."
O P
9-5 1993 Evaluated Exercise 9.2 METEOROLOGICAL DATA
SUMMARY
This section contains the meteorological parameters modeled to coincide with the scenario sequence of events. It has been built into the simulator data files in order to disseminate it over the Data Acquistion and Displa:'* System (DADS) during the Exercise." Controllers should not pro %.de hardcopy or verbal meteorological data to the Players as long as the Simulator is running.
- Players should obtain meteorological data from DADS as they would normally.
If the Simulator should malfunction, however, during the course of the Exercise, Controllers are then permitted to release the data provided in this section. This is at onsite emergency facilities only. The State of Ohio will receive this information on cue cards representing the data they would normally be able to access over the Nuclear Data System (NDS). Controllers at the State EOC in Columbus will issue NDS Cue Cards every 15 minutes. O O
9-6 1993 Evaluated Exercise METEOROLOGICAL CONDITIONS DATA
SUMMARY
100-m 75-m 10-m 100-m 75-m 10-m 100-m 75-m 10-m ; TITime Time WD WD WD WS WS WS SD SD SD 00 00 0800 52.0 52.0 52.0 9.2 9.2 8.9 20.2 20.2 19.9 ! 00 15 0815 53.0 53.0 52.0 9.1 9.1 8.8 20.1 20.1- 19.6 ! 00 30 0830 55.0 55.0 53.0 9.3 9.3 9.0 19.2 19.2 19.0 00/45 0845 56.0 56.0 55.0 9.3 9.3 9.1 18.3 18.3 17.6 01 00 0900 58.0 58.0 57.0 9.2 9.2 9.0 17.6 17.6 17.3 l 01 15 0915 57.0 57.0 57.0 8.8 8.8 8.7 17.2 17.2 17.0 ! 01 30 0930 60.0 60.0 59.0 8.7 8.7 8.5 17.0 17.0 16.6 l 01/45 0945 62.0 62.0 60.0 8.2 8.2 7.9 16.8 16.8 16.4 02/00 1000 62.0 62.0 61.0 8.0 8.0 7.8 16.7 16.7 16.2 02/15 1015 64.0 64.0 63.0 7.7 7.7 7.5 16.3 16.3 16.1 02/30 1030 65.0 65.0 65.0 7.2 7.2 6.9 16.2 16.2 16.0 02/45 1045 66.0 66.0 65.0 6.8 6.8 6.5 16.0 16.0 15.9 03/00 1100 71.0 71.0 69.0 6.1 6.1 5.8 15.8 15.8 15.6 03/15 1115 72.0 72.0 71.0 5.5 5.5 5.2 15.6 15.6 15.4 03/30 1130 75.0 75.0 74.0 4.2 4.2 4.0' 15.5 15.5 15.4 03/45 1145 74.0 74.0 74.0 3.4 3.4 3.2 15.1 15.1 15.2 04/00 1200 76.0 76.0 75.0 2.9 2.9 2.8 14.8 14.8 14.6 04/15 1215 78.0 78.0 77.0 2.6 2.6 2.5 14.6 14.6 14.6 04/30 1230 81.0 81.0 80.0 2.2 2.2 2.0 14.4 14.4 14.3 04/45 1245 80.0 80.0 80.0 2.0 2.0 1.9 14.2 14.2 14.1 05/00 1300 79.0 79.0 79.0 2.1 2.1 2.0 14.0 14.0 13.9 05/15 1315 80.0 80.0 79.0 2.0 2.0 2.0 13.8 13.8 13.6 05/30 1330 80.0 80.0 80.0 2.2 2.2 2.1 13.7 13.7 13.6 i 05/45 1345 81.0 81.0 80.0 2.0 2.0 1.9 13.7 13.7 13.5 1 06/00 1400 82.0 82.0 81.0 2.1 2.1 2.0 13.5 13.5 13.4 , 06/15 1415 83.0 83.0 82.0 2.0 2.0 1.9 13.3 13.3 13.2 i 06/30 1430 85.0 85.0 83.0 1.9 1.9 1.8 13.2 13.2 13.1 i 06/45 1445 86.0 86.0 85.0 2.1 2.1 2.0 13.1 13.1 13.1 07/00 1500 88.0 88.0 87.0 2.2 2.2 2.1 13.2 13.2 12.9 100-10m 75-10m Amb 100-m 10-m Time Delta T Delta T Temo Dew Pt Dew Pt Precio 0800 -3.0 -2.2 51.3 45.2 45.2 0.0 0815 -3.0 -2.2 55.7 49.6 49.6 0.1 0830 -3.0 -2.1 57.4 51.3 51.3 0.1 0845 -2.9 -2.1 61.8 55.7 5S.7 0.1 0900 -2.9 -2.1 62.9 56.8 56.8 0.1 0915 -2.9 -2.1 63.4 57.3 57.3 0.0 0930 -2.9 -2.1 66.3 60.2 60.2 0.1 0945 -2.9 -2.1 67.7 61.6 61.6 0.1 1000 -2.9 -2.1 68.5 62.4 62.4 0.0 1015 -2.8 -2.0 69.6 63.5 63.5 0.0 1030 -2.8 -2.0 70.8 64.7 64.7 0.0 1045 -2.8 -2.0 71.1 65.0 65.0 0.0 1100 -2.8 -2.0 71.2 65.1 65.1 0.0 1115 -2.8 -2.0 71.3 65.2 65.2 0.0 1130 -2.8 -2.0 71.2 65.1 65.1 0.0 1145 -2.8 -2.0 71.3 65.2 65.2 0.0 1200 -2.7 -1.9 71.3 65.2 65.2 0.0 1215 -2.7 -1.9 71.5 65.4 65.4 0.0 1230 -2.7 -1.9 71.7 65.6 65.6 0.0 1245 -2.7 -1.9 72.3 66.2 66.2 0.0 1300 -2.7 -1.9 72.6 66.5 66.5 0.0 1315 -2.6 -1.9 72.7 66.6 66.6 0.0 1330 -2.6 -1.8 72.8 66.7 66.7 0.0 1345 -2.6 -1.8 72.8 66.7 66.7 0.0 1400 -2.5 -1.8 72.8 66.7 66.7 0.0 1415 -2.5 -1.8 72.9 66.8 66.8 0.0 1430 -2.5 -1.7 72.7 66.6 66.6 0.0 1445 -2.4 -1.7 72.5 66.4 66.4 0.0 1500 -2.4 -1.6 72.3 66.2 66.2 0.0
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k 9-7 1993 Evaluated Exercise 9.3 _ECC DOSE ASSESSMENT CENTER CUE CARDS This section prerides individual data sheets of meteorological (and other dose assessment parameters) data which can be passed out to Players on a 15 minute basis should the Control Room Simulator become unavailable to conduct the Exercise. o V
9-8 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. DAC-1 TO: ECC Done Assessment Personnel TIME: 08:00 T a' 00/00 .......r.................................................**.....**........... THIS IS A DRILL DO NOT initiate actions affecting normal operations. INFORMATION: Davio-Besse Dose Assessment Center (DAC) Sheets DAVIS-BESSE SCAN TIME --- 13-October-93 08:00:00 13-October-93 08:05:02 ID DESCRIPTION VALUE UNITS M003 WIND DIRECTION 52.0 DEG M006 WIND SPEED 8.9 MPH M009 WIND DIRECTION STDV 19.9 DEG M011 TEMPERATURE DIFFER. -2.2 DEG F P305 CONTAINMENT PRESSURE 15.2 PSIA R299 CONTAINMENT RADIATION 1.00 R/HR RB45 UNIT VENT I-131 1.00E-10 UCI/CC RB47 UNIT VENT XE-133 0.00E+00 UCI/CC F883 UNIT VENT STACK FLOW 121.5 KCFM .................................................................a........... THIS IS A DRILL
J a 1 1 i 9-9 1993"Evaluttsd Ex2rcice ] i [ DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD N~ ' l
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1 SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. DAC-2 To: ECC Dose Assessment Personnel TIME: 08: 15 j T: 00/15 i
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9-10 1993 Evalusted Ex rcico DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. DAC-3 TO: ECC Dose Assssament Personnel TIME: 08:30 T: 00/30 THIS IS A DRILL DO NOT initiate actions affecting normal operations. INFORMATION: Davis-Besse Dose Assessment Center (DAC) Sheets DAVIS-BESSE SCAN TIME --- 13-October-93 08:30:00 13-October-93 08:35:14 ID DESCRIPTION VALUE UNITS M003 WIND DIRECTION 53.0 DEG M006 WIND SPEED 9.0 MPH M009 WIND DIRECTION STDV 19.0 DEG M011 TEMPERATURE DIFFER. -2.1 DEG F P305 CONTAINMENT PRESSURE 14.9 PSIA R299 CONTAINHENT RADIATION 1.00 R/ER R845 UNIT VENT I-131 1.00E-10 UCI/Cd RB47 UNIT VENT XE-133 0.00E+00 UCI/CC l FBB3 UNIT VENT STACK FLOW 121.2 KCFM THIS IS A DRILL l l
9-11 1993 Evalustcd Ex rciCO DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD No. DAC-4 5 TO: ECC Dose Assessment Personnel TIME: 08:45-T: 00/45 THIS IS A DRILL DO NOT initiate actions affecting normal operations. t INFORMATION: Davis-Besse Dose Assessment Center (DAC) Sheets DAVIS -BESSE , SCAN TIME --- 13-October-93 08:45:00 13-October-93 08:50:21 ID DESCRIPTION VALUE UNITS , M003 WIND DIRECTION 55.0 DEG M006 WIND SPEED 9.1 MPH M009 WIND DIRECTION STDV 17.6 DEG M011 TEMPERATURE DIFFER. -2.1 DEG F P305 CONTAINMENT PRESSURE 14.9 PSIA R299 CONTAINKENT RADIATION 1.00 R/HR R845 UNIT VENT I-131 1.00E-10 UCI/CC . R847 UNIT VENT XE-133 0.00E+00 UCI/CC l 1 F883 UNIT VENT STACK FLOW 92.6 KCFM i l l i 1
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a-9-12 1993 Evaluated Exarcico DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD . SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. DAC-5 TO: ECC Dose Assessment Personnel TIME: 09:00 T: 01/00 THIS IS A DRILL DO NOT initiate actions affecting normal operations. INFORMATION: Davis-Besse Dose Assessment Center (DAC) Sheets DAVIS-BESSE SCAN TIME --- 13-October-93 09:00:00 13-October-93 09:05:28 ID DESCRIPTION VALUE UNITS M003 WIND DIRECTION 57.0 DEG M006 WIND SPEED 9.0 MPH M009 WIND DIRECTION STDV 17.3 DEG M011 TEMPERATURE DIFFER. -2.1 DEG F P305 CONTAINMENT PRESSURE 14.9 PSIA R299 CONTAINMENT RADIATION 1.00 R/HR R845 UNIT VENT I-131 1.00E-10 UCI/CC RB47 UNIT VENT XE-133 0.00E+00 UCI/CC F803 UNIT VENT STACK FLOW 92.7 KCFM THIS IS A DRILL l l 1
I l i 9-13 1993 Evaluated Ex2rcios . l I DBNPS EMERGENCY PREPAREDNESS EKERCISE CUE CARD \
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SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. DAC-6 i TO: ECC Dose Assessment Personnel TIME: 09:15 T: 01/15 s THIS IS A DRILL DO NOT initiate actions affecting normal operations. INFORMATION: Davis-Besse Dose Assessment Center (DAC) Sheets DAVIS -BESSE O SCAN TIME --- 13-October-93 09:15:00 13-October-93 09:20:35 , ID DESCRIPTION VALUE UNITS M003 WIND DIRECTION 57.0 DEG M006 WIND SPEED 8.7 MPH M009 WIND DIRECTION STDV 17.0 DEG M011 TEMFERATURE DIFFER. -2.1 DEG F ,. P305 CONTAINMENT PRESSURE 14.9 PSIA R299 CONTAINMENT RADIATION 1.00 R/HR R845 UNIT VENT I-131 1.00E-10 UCI/CC RB47 UNIT VENT XE-133 0.00E+00 UCI/CC F883 UNIT VENT STACK FLOW 92.3 KCFM THIS IS A DRILL
9-14 1993 EvaluOted Ex0rciCo DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. _DAC-7 TO: ECC Dose Assessment Personnel TIME: 09:30 T: 01/30 THIS IS A DRILL DO NOT initiate actions affecting normal operations. INFORMATION: i. Davis-Besse Dose Assessment Center (DAC) Sheets DAVIS -BESSE SCAN TINI --- 13-October-93 09:30:00 13-october-93 09:35:42 ID DESCRIPTION VALUE UNITS M003 WIND DIRECTION 59.0 DEG H006 WIND SPEED 8.5 12H H009 WIND DIRECTION STDV 16.6 DEG H011 TEMPERATURE DIFFER. -2.1 DEG F P305 CONTAINMENT PRESSURE 14.9 PSIA R299 CONTAINMENT RADIATION 1.00 R/HR R845 UNIT VENT I-131 1.00E-10 UCI/CC R847 UNIT VENT XE-133 0.00E+00 UCI/CC TBB3 UNIT VENT STACK FLOW 92.0 KCFM .......................s......**.e............................. ***.......a** THIS IS A DRILL
9-15 1993 Evaluated Exercico
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DBNPS EMERGENCY PR5;PAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. DAC-8 TO: ECC Dose Assessment Personnel TIME: 09:45 T: 01/45
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INFORMATION: Davis-Desse Dose Assessment Center (DAC) Sheets DAVIS-BESSE O SCAN TIME --- 13-October-93 09:45:00 13-october-93 09:50:49 i' ID DESCRIPTION VALUE UNITS M003 WIND DIRECTION 60.0 DEG M006 WIND SPEED 7.9 MPH M009 WIND DIRECTION STDV 16.4 DEG M011 TEMPERATURE DIFFER. -2.1 DEG F P305 CONTAINMENT PRESSURE 14.9 PSIA R299 CONTAINMENT RADIATION 1.00 R/HR R845 UNIT VENT I-131 1.00E-10 UCI/CC R847 UNIT VENT XE-133 0.00E+00 UCI/CC F883 UNIT VENT STACK FLOW 92.1 KCFM e.................................... ................... ** e* ......... ** THIS IS A DRILL
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9-16 1993 Evclu ted Ex0rcica DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD HO. DAC-9 TO: ECC Dose Assessment Personnel TIME: 10:00 T: 02/00 . .............................e**e e=*ee**emen*******e...eeeeeeeene.eeeeemen THIS IS A DRILL DO NOT initiate actions affecting normal operations. INFORMATION: Davis-Besse Done Assessment Center (DAC) Sheets DAVIS-BESSE SCAN TIME --- 13-October-93 10:00:00 13-October-93 10:05:56 ID DESCRIPTION VALUE UNITS H003 WIND DIRECTION 61.0 DEG M006 WIND SPEED 7.8 MPH M009 WIND DIRECTION STDV 16.2 DEG N011 TEMPERATURE DIFFER. -2.1 DEG F P305 CONTAINMENT PRESSURE 14.9 PSIA R299 CONTAINMENT RADIATION 1.00 R/HR R845 UNIT VENT I-131 1.00E-10 UCI/CC R847 UNIT VENT KE-133 0.00E+00 UCI/CC F883 UNIT VENT STACK FLOW 92.2 KCFM
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9-17 1993 Evaluntsd Ex:rcies DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD G SCENARIO No. 1993 Evaluated Exercice CUE CARD NO. DAC-10 TO: ECC Dose Assessment Personnel TIME: 10:15 T: 02/15 .
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INFORMATION: i Davis-Besse Dos 3 Assessment Center (DAC) Sheets DAVIS-BESSE SCAN TIME --- 13-October-93 10:15:00 13-october-93 10:20:09 ID DESCRIPTION VALUE UNITS M003 WIND DIRECTION 63.0 DEG M006 WIND SPEED 7.5 MPH M009 WIND DIRECTION STDV 16.1 DEG M011 TEMPERATURE DIFFER. -2.0 DEG F. P305 CONTAINMENT PRESSURE 14.9 PSIA R299 CONTAINMENT RADIATION 1.00 R/HR , R845 UNIT VENT I-131 1.00E-10 UCI/CC RB47 UNIT VENT KE-133 0.00E+00 UCI/CC F883 UNIT VENT STACK TLOW 92.3 KCFM I
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9-18 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. DAC-11 TO: ECC Dose Assessment Personnel TIME: 10:30 T: 02/30 .ee.......e**.....................e****ee.........e******ee . eeeee******.*** THIS IS A DRILL DO NOT initiate actions affecting normal operations. ...................................... e***.eeesnemenee********** .**e***ewen INFORMATION: Davis-Besse Dose Assessment Center (DAC) Sheets DAVIS -BESSE SCAN TIME --- 13-October-93 10:30:00 13-october-93 10:35:16 ID DESCRIPTION VALUE UNITS M003 WIND DIRECTION 65.0 DEG M006 WIND SPEED 6.9 MPH M009 WIND DIRECTION STDV 16.0 DEG M011 TEMPERATURE DIFFER. -2.0 DEG F P305 CONTAINMENT PRESSURE 14.9 PSIA R299 CONTAINHENT RADIATION 1.00 R/HR RB45 UNIT VENT I-131 1.00E-10 UCI/CC RB47 UNIT VENT XE-133 0.00E+00 UCI/CC FB83 UNIT VENT STACK FLOW 92.2 KCFM .............................................................e**ene ***eeee** THIS IS A DRILL
s 9-19 1993 Evaluatsd Ex3rcios DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD k SCENARIO No. 1993 Evaluated Exercise TH: CARD NO. DAC-12 TO: ECC Dose Assessment Personnel TIME: 10:45-T: 02/45 ese*ne.**enee.........eeee**** .....e****eeeeeeeee**ee .. ********e********
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DAVIS-BESSE \ SCAN TIME --- 13-October-93 10:45:00 13-October-93 10:50:23 ID DESCRIPTION VALUE UNITS M003 WIND DIRECTION 65.0 DEG M006 WIND SPEED 6.5 MPH M009 WIND DIRECTION STDV 15.9 DEG M011 TEMPERATURE DIFTER. -2.0 DEG F P305 CONTAINMENT PRESSURE 14.9 PSIA R299 CONTAINMENT RADIATION 1.00 R/HR R845 UNIT VENT I-131 1.00E-10 UCI/CC RB47 UNIT VENT XE-133 0.00E+00 UCI/CC F883 UNIT VENT STACK FLOW 92.2 KCFM
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9-20 1993 Evaluated Exarcios DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. DAC-13 To ECC Dose Assessment Personnel TIME: 11:00 1 T: 03/00
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INFORMATION: Davls-Besse Dose Assessment Center (DAC) Sheets DAVIS -BESSE SCAN TlME --- 13-October-93 , 11:00:00 13-October-93 11:05:30 ID DESCRIPTION VALUE UNITS M003 WIND DIRECTION 69.0 DEG M006 WIND SPEED 5.8 MPH M009 WIND DIRECTION STDV 15.6 DEG M011 TEMPERATURE DIFFER. -2.0 DEG F P305 CONTAINMENT PRESSURE 14.9 PSIA R299 CONTAINMENT RADIATION 1.00 R/HR R845 UNIT VENT I-131 1.00E-10 UCI/CC R847 UNIT VENT KE-133 0.00E+00 UCI/CC F883 UNIT VENT STACK FLOW 92.2 KCFM e...............e.................................................ee.een. .ee THIS IS A DRILL i
( 9-21 1993 Evaluated Exorcies ! DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD .{ SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. DAC-14 TO: ECC Dose Assessment Persennel TIME: 11:15 T: 03/15 THIS IS A DRILL DO NOT initiate actions affecting normal operations. INFORMATION: Davis-Besse Done Assessment Center-(DAC) Sheets DAVIS-BESSE - 5 l SCAN TIME --- 13-October-93 11:15:00 13-October-93 11:20:37 t ID DESCRIPTION VALUE UNITS M003 WIND DIRECTION 71.0 DEG ! M006 WIND SPEED 5.2 ~ MPH M009 WIND DIRECTION STDV 16.4 DEG M011 TEMPERATURE DIFFER. -2.0 DEG F , P305 CONTAINMENT PRESSURE 15.7 PSIA R299 CONTAINMENT RADIATION 1.50 R/HR RB45 UNIT VENT I-131 1.00E-10 UCI/CC , RB47 UNIT VENT KE-133 0.00E+00 UCI/CC F883 UNIT VENT STACK FLOW 92.3 KCFM r t 7 THIS IS A DRILL 4 6
9-22 1993 Evalustsd Exercics DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. DAC-15 TO: ECC Dose Assessment Personnel TIME: 11:30 T: 03/30 ...................i .......................*.....** .....*.......... ....... THIS IS A DRILL DO NOT initiate actions affecting normal operations. INFORMATION: Davis-Besse Dose Assessment Center (DAC) Sheets DAVIS -BESSE SCAN TIME --- 13-October-93 11:30:00 13-October-93 11:35:44 ID DESCRIPTION VALUE UNITS M003 WIND DIRECTION 74.0 DEG M006 WIND SPEED 4.0 MPH M009 WIND DIRECTION STDV 15.4 DEG M011 TEMPERATURE DIFFER. -2.0 DEG F P305 CONTAINMENT PRESSURE 16.5 PSIA R299 CONTAINKENT RADIATION 3.72 R/HR RB45 UNIT VENT I-131 1.00E-10 UCI/CC RB47 UNIT VENT XE-133 0.00E+0;: UCI/CC F883 UNIT VENT STACK FLOW 92.4 KCFM THIS IS A DRILL
k 9-23 1993 Evaluated Excrcios DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. DAC-16 TOs ECC Dose Assessment Personnel TIME: 11:45 T: 03/45 4
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9-24 1993 Evaluated Exarcica DBNPS EMERGENCY PREPAREDNESS EKERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. DAC-17 TO: ECC Dose Assessment Personnel TIME: 12:00 T: 04/00 emme eetienewee.***= ...ee===e***eme**ee e**ee*=*ene****=*eemme**eeeee***eeen t THIS IS A DRILL DO NOT initiate actions affecting normal operations. . ***eseeen....e.eeemente e ent ..e****emeenemenenemeneseeemeneeeeeeeeee***=* INFORMATION: Davis-Besse Dose Assessment Center (DAC) Sheets DAVIS-BESSE SCAR TIME --- 13-October-93 12:00:00 13-October-93 12:05:58 ID DESCRIPTION VALUE UNITS N003 WIND DIRECTION 75.0 DEG M006 WIND SPEED 2.8 MPH M009 WIND DIRECTION STDV 14.6 DEG M011 TEMPERATURE DIFFER. -1.9 DEG F P305 CONTAINMENT PRESSURE 17.8 PSIA l R299 CONTAINMENT RADIATION 23.3 R/HR l R845 UNIT VENT I-131 1.00E-10 UCI/CC j RB47 UNIT VENT XE-133 0.00E+00 UCI/CC l FBB3 UNIT VENT STACK FLOW 92.2 KCFM .j
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9-25 1993 Evaluated Exercise - DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. DAC-18 TO: ECC Dose Assessment Personnel TIME: 12:15 T: 04/15 t ee***eeeeee*******menemee*****eeeeeeme*eeeee,*weneme* emmenenee.***ene.****ee THIS IS A DRILL DO NOT initiate actions affecting normal operations.
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i INFORMATION: Davis-Besse Dose Assessment Center (DAC) Sheets DAVIS -BESSE SCAN TIME --- 13-October-93 12:15:00 13-October-93 12:20:09 ID DESCRIPTION VALUE UNITS M003 WIND DIRECTION 77.0 DEG M006 WIND SPEED 2.5 MPH M009 WIND DIRECTION STDV 14.6 .DEG M011 TEMPERATURE DIFFER. -1.9 DEG F , P305 CONTAINKENT PRESSURE 18.2 PSIA R299 CONTAINKENT RADIATION 56.4 R/BR R845 UNIT VENT I-131 1.00E-10 UCI/CC R847 UNIT VENT KE-133 0.00E+00 UCI/CC
- FB83 UNIT VENT STACK FLOW 92.2 KCFM L
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9-26 1993 Evaluated Exercise e DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. DAC-19 TO: ECC Dose Assessment Personnel TIME: 12:30 T: 04/30 emeeneen.. ***e eesseeeeeeeeeeeme==*eeeeeeeeeee***ee********* eeee*****ee**e* THIS IS A DRILL DO NOT initiate actions affecting normal operations. ee mene.. ee......e****emene..... ewe ********ee******ee**me**=***eeeeme******* INFORAATION: Davis-Besse Dose Assessment Center (DAC) Sheets DAVIS-BESSE SCAN TIME --- 13-October-93 12:30:00 13-October-93 12:35:16 ID DESCRIPTION VALUE UNITS M003 WIND DIRECTION 80.0 DEG M006 WIND SPEED 2.0 MPH M009 WIND DIRECTION STDV 14.3 DEG
-1.9 '
M011 TEMPERATURE DIFTER. P305 CONTAINMENT PRESSURE 18.6 ruin R299 CONTAINKENT RADIATION 98.2 R/ER RB45 UNIT VENT I-131 1.00E-10 UCI/CC R847 UNIT VENT XE-133 0.00E+00 UCI/CC F883 UNIT VENT STACK TLOW 92.2 KCFM menesoneeeeeeeeeeeeeeeeeee***e**eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeemme**ee THIS IS A DRILL .......e. ....................e.e.e...................... ...e... ....e...e.e
9-27 1993 Evaluated Exarcise LBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. DAC-20 TO: ECC Dose Assessment Personnel TIME: 12:45 T: 04/45 THIS IS A DRILL DO NOT initiate actions affecting normal operations. INFORMATION: Davis-Besse Dose Assessment Center (DAC) Sheets OAVIS-BESSE SCAN TIME --- 13-October-93 12:45:00 13-October-93 12:50:23 ID DESCRIPTION VALUE UNITS M003 WIND DIRECTION 80.0 DEG M006 WIND SPEED 1.9 MPH M009 WIND DIRECTION STDV 14.1 DEG M011 TEMPERATURE DIFFER. -1.9 DEG F P305 CONTAINMENT PRESSURZ 18.8 PSIA R299 CONTAINMENT RADIATION 1.45E+02 R/HR R845 UNIT VENT I-131 1.00E-10 UCI/CC R847 UNIT VENT KE-133 0.00E+00 UCI/CC F883 UNIT VENT STACK FLOW 92.1 KCFM THIS IS A DRILL
1 9-28 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCEdARIO NO. 1993 Evaluated Exercise CUE CARD NO. DAC-21 TO: ECC Dose Assessment Personnel TIME: 13:00 T: 05/00 THIS IS A DRILL DO NOT initiate actions affecting normal operations. ..............................................=*............................. INFORMATION: Davis-Besse Dose Assessment Center (DAC) Sheets DAVIS -BESSE SCAN TIME --- 13-October-93 13:00:00 13-October-93 13:05:30 ID DESCRIPTION VALUE UNITS M003 WIND DIRECTION 79.0 DEG M006 WIND SPEED 2.0 MPH N009 WIND DIRECTION STDV 13.9 DEG N011 TEMPERATURE DIFFER. -1.9 DEG F P305 CONTAINMENT PRESSURE 19.0 PSIA R299 CONTAINMENT RADIATION 2.50E+02 R/ER RB45 UNIT VENT I-131 1.00E-10 UCI/CC R847 UNIT VENT XE-133 0.00E+00 UCI/CC FB83 UNIT VENT STACE FLOW 92.2 KCFM THIS IS A DRILL
9-29 1993 Evaluated Ex2rcise t Oi DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD I V SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. DAC-22 TO: ECC Dose Assessment Personnel TIME: 13:15 T: 05/15 enee**eeeeeeeeeeen****e**** eeeeeee*e ****e***ese eene ..eeeeeeeeeeeeeeeeee
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I INFORMATION: Davis-Besse Dose Assessment Center (DAC) Sheets DAVIS-BESSE s SCAN TIME --- 13-October-93 13:15:00 13-October-93 13:20:37 ID DESCRIPTION VALUE UNITS M003 WIND DIRECTION 79.0 DEG M006 WIND SPEED 2.0 MPH M009 WIND DIRECTION STDV 13.6 DEG M011 TEMPERATURE DIFFER. -1.9 DEG F P305 CONTAINMENT PRESSURE 19.1 PSIA R299 CONTAINMENT RADIATION 1.40E+02 R/HR R845 UNIT VENT I-131 1.00E-10 UCI/CC R847 UNIT VENT XE-133 6.60E-02 UCI/CC F883 UNIT VENT STACK FLOW 92.2 KCFM
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q 9-30 1993 Evaluated Ex0rcico DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. DAC-23 TO: ECC Dose Assessment Personnel TIME: 13:30 T: 05/30 ................................. aeeeee**eneeseeeee==e** es......e***e...... THIS IS A DRILL DO NOT initiate actions affecting normal operations. e....neeeeeeeme***eeeeeeeeeeeeeeeee*** e**e,***eeeeeeee**eneeeen***********
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Davis-Besse Dose Assessment Center (DAC) Sheets DAVIS-DESSE SCAN TIME --- 13-October-93 13:30:00 13-October-93 13:35:44 O ID DESCRIPTION VALUE UNITS M003 WIND DIRECTION 80.0 DEG M006 WIND SPEED 2.1 MPH M009 WIND DIRECTION STDV 13.6 DEG M011 TEMPERATURE DIFFER. -1.8 DEG F P305 CONTAINMENT PRESSURE 19.1 PSIA R299 CONTAINMENT RADIATION 1.38E+02 R/BR R845 UNIT VENT I-131 0.00E+00 UCI/CC RB47 UNIT VENT KE-133 2.41E+00 UCI/CC F883 UNIT VENT STACK FLOW 92.3 KCFM ene**emeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeneseeeeeee menesee***ene THIS IS A DRILL .....................................ee..............,................**.....
I 9-31 1993 Evaluated Exercise I ( DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. DAC-24 TO: ECC Dose Assessment Personnel TIME: 13:45 T: 05/45 t
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THIS IS A DRILL DO NOT initiate actions affecting normal operations. eeeeeeeeeeeeeeeeeee...**eeeeeeee *ee *** ... ***=e ..... eee*ene.........e*=* INFORMATION: Davis-Besse Dose Assessment Center (DAC) Sheets DAVIS-DESSE SCAN TIME --- 13-October-93 13:45:00 13-October-93 13:50:51 ID DESCRIPTION VALUE UNITS M003 WIND DIRECTION 80.0 DEG N006 WIND SPEED 1.9 MPH M009 WJ ND DIREC'.7 ION STDV 13.5 DEG M011 TEMPERATURE DIFFER. -1.8 DEG F P305 CONTAINMENT PRESSURE 19.1 PSIA R299 CONTAINMENT RADIATION 1.35E+02 R/BR R845 UNIT VENT I-131 0.00E+00 UCI/CC R847 UNIT VENT XE-133 2.62E+01 UCI/CC F883 UNIT VENT STACK FLOW 92.3 KCFM i seeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeaesseeeweseeeeeeeeeeeee***** THIS IS A DRILL emee ...eeseeeeeeeee.........me ..ee.....eeeeee e eeeeee.*eeeeeeene..... een
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9-32 1993 Evaluttsd Exarci23 DBNPS EMERGENCY PI2PAREDNESS EXERCISE CUE CARD SCENARIO No. 1993 Evaluated Exercise CUE CARD NO. DAC-25
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To: ECC Dose Assessment Personnel TIME: 14:00 T: 06/00 THIS IS A DRILL DO NOT initiate actions affecting normal operations. INFORMATION: Davis-Besse Dose Assessment Center (DAC) Sheets DAVIS-BESSE SCAN TIME --- 13-October-93 14:00:00 13-October-93 14:05:58 O ID DESCRIPTION VALUE UNITS M003 WIND DIRECTION 81.0 DEG N006 WIND SPEED 2.0 HPH N009 WIND DIRECTION STDV 13.4 DEG H011 TEMPERATURE DIFFER. -1.8 DEG F P305 CONTAINMENT PRESSURE 19.0 PSIA R299 CONTAINMENT RADIATION 1.33E+02 R/HR RB45 UNIT VENT I-131 0.00E+00 UCI/CC R847 UNIT VENT XE-133 6.39E+00 UCI/CC F003 UNIT VENT STACK FLOW 92.2 KCFM THIS IS A DRILL j
r 9-33 1993 Evaluated Exarcios
- DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD \
CUE CARD NO. DAC-26 SCENARIO NO. 1993 Evaluated Exercise TIME: 14:15 TO: ECC Dose Assessment Personnel T: 06/15 see.*****eeeeee*****ene***********e**ee***************enen************ene**ee THIS IS A DRILL DO NOT initiate actions affecting normal operations. eeme**ee.**emee*****e***e e** ....e** **eeee********ene***en*ee************ee INFORMATION: Davis-Besse Dose Assessment Center (DAC) Sheets DAVIS-BESOE
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SCAN TIME --- 13-October-93 14:15:00 13-October-93 14:20:09 DESCRIPTION VALUE UNITS ID M003 WIND DIRECTION 82.0 DEG M005 WIND SPEED 1.9 MPH M009 WIND DIRECTION STDV 13.2 DEG TEMPERATURE DIFFER. -1.8 DEG F M011 P305 CONTAINMENT PRESSURE 18.9 PSIA R299 CONTAINHENT RADIATION 1.30E+02 R/HR UNIT VENT I-131 0.00E+00 UCI/CC R845 R847 UNIT VENT KE-133 1.07E+00 UCI/CC F883 UNIT VENT STACK FLOW 92.2 KCFM e...........e***** ...............e**s........ **e..e**e...........e*****ene. THIS IS A DRILL e ......eeeee.*******eeeeeeee*** ee......ee......................me***e***e** m ___,
m 9-34 1993 Evalustsd Excrcica l DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD , I l 1993 Evaluated Exercise CUE CARD NO. DAC-27 SCENARIO NO. i TO: ECC Dose Assessment Personnel TIME: 14:30 T: 06/30 e.e.eeeeeeee............e..........**.................*.......***....***.. THIS IS A DRILL DO NOT initiate actions affecting normal operations.
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INFORMATION: Davis-Besse Dose Assessment Center (DAC) Sheets DAVIS -BESSE SCAN TIME --- 13-October-93 14:30:00 13-October-93 14:35:16 ID DESCRIPTION VALUE UNITS H003 WIND DIRECTION B3.0 DEG M006 WIND SPEED 1.8 MPH M009 WIND DIRECTION STDV 13.1 DEG H011 TEMPERATURE DIFFER. -1.7 DEG F P305 CONTAINHENT PRESSURE 18.9 PSIA R299 CONTAINMENT RADIATION 1.28E&O2 R/HR R845 UNIT VENT I-131 0.00E+00 UCI/CC R847 UNIT VENT XE-133 3.80E-01 UCI/CC FB83 UNIT VENT STACK FLOW 92.1 KCFM
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9-35 1993 Evaluntsd Ex3rcise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD , 1993 Evaluated Exercise CUE CARD NO. DAC-28 SCENARIO NO. TO: ECC Dose Assessment Personnel TIME: 14:45 T: 06/45 THIS IS A DRILL DO NOT initiate actions affecting normal operations. INFORMATION: , Davis-Besse Dose Assessment Center (DAC) Sheets DAVIS -BESSE
,y SCAN TIME --- 13-October-93 14:45:00- 13-October-93 14:50:23 ID DESCRIPTION VALUE UNITS WIND DIRECTION 85.0 DEG -
H003 H006 WIND SPEED 2.0 MPH H009 WIND DIRECTION STDV 13.1 DEG M0ll TEMPERATURE DIFFER. -1.7 DEG F P305 CONTAINMENT PRESSURE 18.7 PSIA R299 CONTAINMENT RADIATION 1.25E+02 R/HR RB45 UNIT VENT I-131 1.00E-10 UCI/CC l l R847 UNIT VENT XE-133 0.00E+00 UCI/CC FBB3 UNIT VENT STACK FLOW 92.3 KCFM i l THIS'IS A DRILL
9-36 1993 Evolunted Ex3rcice DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. DAC-29 TO: ECC Dose Assessment Personnel TIME: 15:00 T: 07/00 THIS IS A DRILL DO NOT initiate actions affecting normal operations. INFORMATION: Davis-Besse Dose Assessment Center (DAC) Sheets DAVIS -BESSE SCAN TIME --- 13-October-93 15:00:00 13-October-93 15:05:30 O ID DESCRIPTION VALUE UNITS H003 WIND DIRECTION 87.0 DEG H006 WIND SPEED 2.1 MPH H009 WIND DIRECTION STDV 12.9 DEG H011 TEMPERATURE DIFFER. -1.6 DEG F P305 CONTAINMENT PRESSURE 18.4 PSIA R299 CONTAINMENT RADIATION 1.20E+02 R/HR R845 UNIT VENT I-131 1.00E-10 UCI/CC R847 UNIT VENT XE-133 0.00E+00 UCI/CC F883 UNIT VENT STACK FLOW 92.2 KCFM THIS IS A DRILL I 1 i I
9-37 1993 Evaluated Exercise 9.4 RADIATION PLUME MAPS This section of the manual provides information needed by controllers to simulate offsite radiation levels due to the radioactive plume that is released during the course of the Exercise. The release path is: 1) 35% gap activity is released into the primary coolant at 0915, 2) coolant activity is released into the containment atmosphere due to the loss of secondary plant heat removal capability, which requires reactor cooling to be provided by Makeup /High Pressure Injection flow vented out of a Pressurizer relief valve into containment at around 1100, 3) at time 1300, a-containment piping penetration (No. 59) failure caused by maintenance activities providos a path for the activity to flow into Mechanical Penetration Room #3 outside of containment, and finally 4) the Emergency Ventilation system (EVs) takes a suction on the penetration room and exhausts the radioactivity (i.e., noble gases) out the Plant Vent. The release continues until Maintenance personnel cap the broken pipe at time 1400. (Residual activity continues to be discharged by EVS until 1415. Thus, release duration can be considered to be 1.2 hours.) It is assumed that less than 0.5% of the radiciodines in the primary coolant are dispersed from the coolant into the containment atmosphere and thus only a small fraction is potentially available for release to the environment. And, because the release is out the station Vent, the vent HEPA and charcoal filters play an important role in reducing the radioactive elements that are ultimately released from the plant. For this Exercise, the station vent filter efficiency is assumed to be 95%. Thus any particulates that may have O been passed from the containment building into the penetration rooms are essentially filtered out by the Evs. The meteorological conditions which form the basis for plume dispersion characteristics during the release time frame are as follows: Wind speed. . . . . . . . 2 MPH Wind direction (from) . . 80 Degrees stability class . . . . . c (slightly Unstable) The caussian plume dispersion method was used to plot radioactivity concentra-tions downwind of the station Vent. Using the vertical diffusion factor (o,), a 50s plume width concentration, and the vent height-of 83 meters, it can be determined that the plume touches ground at approximately 400 meters (or 2/10's of a mile) downwind. However, for the purposes of this Exercise it is assumed the plume does not touch ground until 7/10's of a mile downwind (i.e., across Route 2). Using the lateral dif fusion f actor (o,) and a 1% plume concentration, the plume width can be determined at a distance of 5 miles downwind as being 3,200 meters on either side of plume centerline or a total of 6,400 meters (approximately 3.6 miles) wide. These factors determined the size and position of the plume on the maps that follow in this section. Because of the relative short vent height and the potential for building wake effect, . downwind dose projections made by the Players will be based on ground-level release formulae. Thus, some differences can be expected between dose
-projected values and the values obtained by the field monitoring teams.
With the release containing primarily noble gases, all readings for par-ticulates will be "as read" and values Iw r radiciodines will be below O protective action levels using a PRM-6 or SAM-2 meter in CPM. Controllers should indicate whole body readings on the RSO-5 survey meter per the
I l 9-38 1993 Evaluated Exercise indicated vslues on the " Radioactivity Plume Travel Maps" provided on the e ) following pages. A map is provided for times 1305-1315, 1315-1330, 1330-1345, i 1345-1400, 1400-1415, 1415-1430, 1430-1445, and 1445-1500. The air sample values (shown in cpm on the Radioactivity Plume Travel Maps) are based on a ten minute air sample, a standard sample taken by the RMT's, and should be relayed to the Players after they leave the plume and count the sample. If Players are directed to take a five minute sample, Controllers should divide the cpm values shown on the maps in half. In the Radiological Testing Laboratory, when a sample is counted on a SAM-2, the controller must take the field reading for the sample and multiply it by 4.73 to come up with the new countrate for the SAM-2. As has been the practice and training in the past, controllers must interpolate the readings on the maps to give the Players some indication of plume travel and the variation of radiation levels between the edges of the plume and plume centerline. The edge of the plume as indicated on the maps correlates to 0.2 mrem /hr. controllers should indicate survey meter readings steadily increasing up to the maximum centerline value as is given on the maps, uaing the roadways on the maps to approximate the plume centerline location. Donimeter readings can be extrapolated by taking the time a survey team remains in an area, times the dose rate from the plume map for the corresponding time block for the area, plus any additional exposure if the team had been in any other aren for approximately 15 minutes or greater. For example, if the team was in an area of 200 mrem /hr for 15 minutes, add 50 mrem to their cumulative dose (i.e., 15 minutes is one quarter of an hour so 200 divided by 4 equals 50). This is cumulative exposure and each controller can keep track of their team's cumulative dose on the plume maps as the Exercise unfolds, controllers should not overload themselves with this calculation. If time does not permit a quick extrapolation to be performed, controllers can simply raise the Player's dosimeter reading by a small amount over their previous reading (e.g., 10 mR) just for drill simulation purposes. O
9-39 1993 Evaluated Ey.ercise A / $ ( ,l RADIOACTIVITY PLUME TRAVEL MAP FOR TIME 1305 - 1315
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9-45 1993 Evaluated Exercise I
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I 9-46 1993 Evaluated Exercise [ RADIOACTIVITY PLUME TRAVEL MAP FOR TIME 1445 - 1500 ( ' w jo# L AKE a
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i 9-47 1993 Evaluated Exorcisa-9.5 PUBLIC INFORMATION CUE CARDS ] 1 This section provides individual messages pertaining to the Toledo Edison
'D public relations response and can be used to initiate and document actions ;
taken by Players at the Joint Public.Information Center. .i l I l n f J O :
)
k ( l l
9 48 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD CUE CARD NO. PR-1X SCENARIO NO. 1993 Evaluated Exercise Public Affairs Duty Officer TIME: 08:55 'l TO: T: 00/55 o***************************************************************************** THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. o***************************************************************************** INFORMATION: Develcp and provide a media advisory to the mock AP/UPI fax. (Use extension 6040 for fax information.) l 9 l l l I
***********************w******************************************************
THIS IS A DRILL
****+************************a************************************************
~. . .
ij 9-49 1993 Evaluated Exercise , DBNPS EMERGENCY PREPARELNESS CUE CARD (Cont'd) CUE CARD NO. PR-1X
}
TO: JPIC Controller TIME:' 08:55 T: 00/55 ANTICIPATED RESPONSE: PADO provides media advisory to mock AP/UPI services. t INSTRUCTIONS: , Do not allow drill information to be sent to AP/UPI offices. Inform controller at the AJPIC to remove fax from the workroom. . Leave one copy at the Equipment Operators' station as expected during an actual emergency. ; O i l
' I
')
l
******************************+*********************************************** .,
THIS IS A DRILL l u l 1
- - - - , ,%- m e -
9-50 1993 Evaluated Exercise DBNPS EMERGENr. "REPAREDNESS EXERCISE CUE CARD SCENARIO No. 1993 Evaluated Exercise CUE CARD NO. PR-2X TO: Public Affairs Duty Officer TIME: 09:10 T: 01/10 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. INFORMATION: Provide media advisory to:
- Alternate JPIC
- U.S. Council for Energy Awareness (Fax Ext. 6040)
- U.S. NRC
- NRC Region III
- Other normal distribution points G
i I I
)
l THIS IS A DRILL
i I
'9-51 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd)
CUE CARD NO. PR-2X . s TO: JPIC Controller TIME: 109:10 T: .01/10 ANTICIPATED RESPONSE: PADO provides media advisory to identified locations. INSTRUCTIONS: Inform the Lead JPIC Controller when action is completed.
+
L O THIS IS A DRILL
*******+++++++++**************************************************************
1 9-52 1993 Evaluated Exercisa -ll DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD CUE CARD NO. PR-3 SCENARIO NO. 1993 Evaluated Exercise T0: Public Affairs Duty Officer TIME: 09:20 l T: 01/20 THIS IS A DRILL . DO NOT initiate actions affecting normal plant operations. INFORMATION: State "This is a drill" at the beginning and end of phone cal?. Contact the PADO via the Edison operator. Requert information on the simulated emergency conditions. Note all responses on this page. Inform the PADO you are a reporter from the Columbus Dispatch. Ask for details of how this emergency impacts on the local public. Following receipt of information, inform the PADO this represents the tenth media call. Provide your extension if operator requests call back number for the PADO. THIS IS A DRILL l l
' + - .- . .
9-53 1993_ Evaluated Exercise j DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) CUE CARD NO. PR ; I TO: JPIC Controller TIME: 09:20 T: 01/20 l ANTICIPATED RESPONSE: I PADO provides information on simulated emergency conditions at DBNPS. l i i l q INSTRUCTIONS: Note accuracy of information provided. Follow up by review of any discussion i between the PAD 0 and JPIC Hanager/ Company Spokesperson. E
?
I
**************************************v***************************************
THIS IS A DRILL
*****<*********+++************************************************************
i 9-54 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD l 1 SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. PR-4X , T0: Public Affairs Duty Officer TIME: 09:30 T: 01/30 THIS IS A DRILL , DO NOT initiate actions affecting normal plant operations. INFORMATION: State "This is a drill" at the beginning and end of phone call. Contact the Company Spokesperson and recommend activation of the Alternate JPIC based on high media interest. O THIS IS A DRILL
I 9-55 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) () TO: JPIC Controller CUE CARD NO. TIME: 09:30 PR-4X-T: 01/30 Affi- IPATED RESPONSE: PADO informs the Company Spokesperson on need to activate the JPIC. Company Spokesperson should commence JPIC Activation Process. INSTRUCTIONS: Do not provide this card if JPIC activation has already commenced. l t THIS IS A DRILL i
******************+++++++++++.-***+********************************************
1
9-56 1993 Evaluated Exercise DBNPS EHERGENCY PREPAREDNESS EXERCISE CUE CARD CUE CARD NO. PR-5X SCENARIO NO. 1993 Evaluated Exercise TO: Company Spokesperson TIME: 09:35 T: 01/35 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
- w********************************************************
INFORMATION: Commence JPIC staff notification for facility activation. O THIS IS A DRILL
9-57 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) / \ CUE CARD NO. PR-5X. V TO: JPIC Controller TIME: 09:35 T: 01/35 ANTICIPATED RESPONSE: Company Spokesperson commences staff notification for JPIC activation. 4 a INSTRUCTIONS: Do not provide this card if JPIC activation has already commenced. j I I l I l j
\* THIS IS A DRILL
9-58 1993 Evalueted Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD CUE CARD NO. PR-6 SCENARIO NO. 1993 Evaluated Exercise TO: Edison Operator TIME: 09:40 T: 01/40 Q***************************************************************************** THIS IS A DRILL , DO NOT initiate actions affecting normal plant operations. Q***************************************************************************** INFORMATION: State "This is a drill" at the beginning and end of phone calls. Call the Edison Operator at Extensic' "000.
- Inform the Operator you are a T- _Jentative of Cable News Network (CNN).
Request information on the emergency and where your trucks and crew should set up for coverage of the Davis-Besse emergency. Ask for the name of an official who can be contacted for up-to-date information en emergency conditions.
' You are leaving from Pittsburgh and do not have a call back number.
THIS IS A DRILL
***4**************************************************************************
~
9-59 1993 Evaluated Exercise' DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) CUE CARD NO.. PR-6 TO: Public-Caller TIME: 09:40 T: 01/40 l ANTICIPATED RESPONSE: Edison Operator should provide informatfor on Edison Club location, Company - Spokesperson or PADO name. , 6 INSTRUCTIONS: If the Edison Operator is unsure of requested information, identify you vill l call back later when you are near Toledo. i
- NOTE OPERATOR RESPONSE.
****************************************************************************** l THIS IS A DRILL
********.************************************************,**+*****************
~
l i
9-60 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD CUE CARD NO. PR-7 SCENARIO NO. 1993 Evaluated Exercise T0: Edison Operator TIME: 09:45 T: 01/45
*************************************************************************ke***
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
**********************************************************w*******************
INFORMATION: State "This is a drill" at the beginning and end of phone calls. Call the Edison Operator at Extension 5000. Ask to speak to an official on the emergency at Davis-Besse. You are a reporter from the Boston Globe. Questions: - How many years has the Davis-Besse reactor been in service?
- How many other emergencies have there been at Davis-Besse since 19857
- Vhat was the power level of the reactor prior to the accident?
I
******************w***********************************************************
THIS IS A DRILL
I 9-61 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) CUE CARD NO. PR-7 TO: Public Caller TIME: 09:45 T: 01/45 l
)
ANTICIPATED RESPONSE: , 1
- Edison Operator should forward the call to Public Concern Operators or the .
' Company Spokesperson. ,
- If contact is made with the Public Concern Operators or Company Spokesperson, the caller could be directed to call USCEA. .
INSTRUC1 IONS: Document response to calls. i Note reference / forwarding phone numbers provided. (
- If directed to USCEA, DO NOT call the forwarding number.
5 Y l O THIS IS A DRILL I
******************+*********************************************************** t
'{
9-62 1993 Evalusted Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD CUE CARD NO. PR-8 SCENARIO NO. 1993 Evaluated Exercise T0: Edison Operator TIME: 09:55 T: 01/55 s
- mm THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
INFORMATION: 5 tate "This is a drill" at the beginning and end of phone calls. Call the Edison Operator at Extension 5000. Ask to speak to an official on the emergency at Davis-Besse. You are a reporter from the Windsor, Canada. Questions: - What level on the nuclear emergency scale is applicable to the Davis-Besse accident?
- Are there any physical injuries to workers?
- Can the emergency affect Lake Erie?
lh l I i l 1 THIS IS A DRILL O l
9-63 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) CUE CARD NO. PR-8 TO: Public Caller TIME: 09:55 T: 01/55 ANTICIPATED RESPONSE:-
- Edison Operator should forward the call to Public Concern Operators or the Company Spokesperson. - If contact is made with the Public Concern Operators or Company Spokesperson',
the caller could be directed to call USCEA. INSTRUCTIONS: Document response to calls. Note reference / forwarding phone numbers provided.
- If directed to USCEA, DO NOT call the forwarding number.
I l THIS IS A DRILL i
9-64 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD CUE CARD NO. PR-9 SCENARIO NO. 1993 Evaluated Exercise Public Concern Operator TIME: 10:20 T0: T: 02/20 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. l _1 INFORMATION: i Use the following questions only during the Alert classification. Call the Toledo Edison Public Concern Operator at Extension 6047. State "This is a drill" for all calls. Log responses to questions. O Name: K. Roush Town: Dayton This is K. Roush from the Dayton Times. Ve got a call from the Governor's Press Secretary canceling an interview becauce of an emergency at Davis-Besse Station. According to her, the Governor must respond to the accident. What does Alert mean? What other types of accidents are there? Vill you FAX any information you have to me? (Provide the full phone number to the Control Cell FAX if agreed.) What other governmental officials are involved? If radiation gets out can it get to Dayton? I'm going to send a crew out. Vhere should they go when they get to the plant? Ve'll need someone to help show then around, vill you be available? This is a drill. THIS IS A DRILL
**************************************+***************************************
'l 9-65. 1993 Evaluated Exercise ;
i DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) , CUE CARD NO. PR-9 TO: Public Caller TIME: 10:20 T: 02/20 ANTICIPATED RESPONSE Public Concern Operators should respond to questions. , If you are referred to another agency:
- 1. Note the number provided
- 2. DO NOT call other agencies during the Alert ECL.
1 INSTRUCTIONS: Provide the full phone number you are using if call back is requested. If Public Concern Operators question how you received their number, inform them ' your call was transferred from the Edison Operator. \
\
l l l l 1 l l l 1 ll
****************************************************************************** l THIS IS A DRILL ******************************************************************k***********
I
9-66 1993 EvaluatQd Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD
~
SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. PR-10 TO: Public Concern Operator TIME: 10:20 T: 02/20 o***************************************************************************** THIS IS A DRILL - DO NOT initiate actions affecting normal plant operations. o***4*.*********************************************************************** INFORMATION: Use the following questions only during the Alert classification. Call the Toledo Edison Public Concern Operator at Extension 6048. State "This is a drill" for all calls. Log responses to questions. O Name: S. Lovery Town: BBC - Suffolk, England Uhat is the cause of your emergency? Uhat is the event scale level of the emergency? Vas the plant operating when the accident happened? Is there any possibility of the event becoming worse? This is a drill.
- +*******************************************************
THIS IS A DRILL
9-67 1993 Evaluated Exercise-DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) CUE CARD NO. PR T0: Public Caller TIME: 10:20 T: 02/20 ANTICIPATED RESPONSE: . Public Concern Operators should respond to questions. If you are referred to another agency:
- 1. Note the number provided
- 2. DO NOT call other agencies during the Alert ECL.
l INSTRUCTIONS: Provide the full phone number you are using if call back is requested. If Public Concern Operators question hov you received their number, inform them your call was transferred from the Edison Operator.
*********************************************************4++t*****************
THIS IS A DRILL
*************k****************************************************************
1 l 9-68 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD CUE CARD NO. PR-11 SCENARIO NO. 1993 Evaluated Exercise TO: Public Concern Operator TIME: 10:30 T: 02/30 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
*************************************f%** 't**********************************
INFORMATION: Use the following questions only during the Alert classification. . Call the Toledo Edison Public Concern Operator at Extension 6047. State "This is a drill" for all calls. Log responses to questions. O Names F. Kanter Town: Oregon I'm a retired mechanic. Where should I go to lend a hand? What exactly is the problem? How much is the pay? This is a drill. THIS IS A DRILL
ll l 9-69 1993 Evalusted Exercise ~ DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) CUE CARD NO. 'PR-11 ! TO: Public Caller TIME: 10:30 T: 02/30 ANTICIPATED RESPONSE: Public Concern Operators should respond to questions. If you are referred to another agency: t
- 1. Note the number provided ,
- 2. DO NOT call other agencies during the Alert ECL.
INSTRUCTIONS: Provide the full phone number you are using if call back is requested. I If Public Concern Operators question how you received their number, inform them your call was transferred from the Edison Operator. 1 I l i
'l
'i THIS IS A DRILL
9-70 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD CUE CARD NO. PR-12 SCENARIO NO. 1993 Evaluated Exercise T0: Public Concern Operator TIME: 10:30 T: 02/30 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. INFORMATION: Use the following questions only during the Alert classification. Call the Toledo Edison Public Concern Operator at Extension 6048. State "This is a drill" for all calls. Log responses to questions. O Name: B. Allton Town: Cleveland I heard on my car radio that Davis-Besse is in trouble again. (You are a reporter from the Cleveland Elain Dealer.) What's the problem? --- How many people are contaminated? Vhat actions have taken place? How much contamination is leaking and where is it going? Are the plant vorkers evacuating? This is a drill. THIS IS A DRILL L
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E ,, ic ' 9-71' 1993 Evaluttsd Exercisa: DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd)
."IL)-<Y CUE CARD NO. PR-12 Af 10:30 TO: Public Caller- ' TIME:
T: 02/30 ANTICIPATED RESPONSE: Public Concern Operators should respond to questions. [. ., h If you are referred to another agency: is 1. Note the number provided
.2. DO NOT call other agencies during the Alert ECL.
INSTRUCTIONS: Provide the full phone number you are using if call back is requested. If Public Concern Operators question how you received their number, inform them [G) your call was. transferred from the Edison Operator. q T l
.i i
I i
. f-
)} . THIS IS A DRILL
++****************************************************************************
7i l
9-72 1993 Evalustad Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. PR-13 TO Public Concern Operator TIME: 10:40 T: 02/40 THIS IS A DAILL ' DO NOT initiate actions affecting normal plant operations. INFORMATION: Use the following questions only during the Alert classification. Call the Toledo Edison Public Concern Operator at Extension 6047. State "This is a drill" for all calls. Log responses to questions. O Name: D. Edvards Town: Oak Harbor Uho determined the meanings of Emergency Classifications? Isn't an emergency an emergency? Why are ve told to do things differently for each classification? This is a drill. THIS IS A DRILL
9-73 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) () T0: Public Caller CUE CARD NO. TIME: 10:40 PR-13 T: 02/40 ANTICIPATED RESPONSE: Public Concern Operators should respond to questions. . If you are referred to another agency:
- 1. Note the number provided
- 2. DO NOT-call other agencies-during the Alert ECL.
l INSTRUCTIONS: Provide the full phone number you are using if call back is requested. , j If Public Concern Operators question how you received their r. umber, inform them your call was transferred from the Edison Operator. l I I l l I l i i i
*******************************************<************************************ l 5
THIS IS A DRILL i
9-74 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD CUE CARD NO. PR-14 SCENARIO NO. 1993 Evaluated Exercise TO: Public Concern Operator TIHE: 10:40 T: 02/40
************************************************************************+*****
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
****************************************************************************** l INFORMATION:
Use the following questions only during the Alert classification. , 1 Call the Toledo Edison Public Concern Operator at Extension 6048. State "This is a drill" for all calls. Log responses to questions. O Name: A. Starr Town: Northwood (Reporter from the Suburban Press.) Provide name only if reisested. What happened? --- Bov many people were injured? Is the public in danger? -- When vill it be fixed? This is a drill. l l l l THIS IS A DRILL
*************+**+*************+*********************************** Jct **********
9-75 1993 Evaluated Exercise . DBNPS EMERGENCY _ PREPAREDNESS CUE CARD (Cont'd) () T0: Public Caller CUE CARD NO. TIME: 10:40 PR-14 i T: 02/40 e ANTICIPATED RESPONSE: , Public Concern Operators should respond to questions. ; If you are referred to another agency:
- 1. Note the number provided
- 2. DO NOT call other agencies during the Alert ECL. ,
INSTRUCTIONS: Provide the full phone number you are using if call back is requested. If Public Concern Operators question how you received their number, inform them your call vas transferred from the Edison Operator. f O- THIS IS A DRILL
9-76 1993 Evaluated Exercisa DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD CUE CARD NO. PR-15 SCENARIO No. 1993 Evaluated Exercise TO: Public Concern Operator TIME: 10:50 T: 02/50 THIS IS A DRILL - DO NOT initiate actions affecting normal plant operations. INFORMATION: Use the following questions only during the Alert classification. Call the Toledo Edison Public Concern Operator at Extension 6047. State "This is a drill" for all calls. Leg responses to questions. O Name: C. Marks Town: Fremont This is radio station VCDB. Crane Creek State Park is being closed. Supposedly this is due to a disaster at the plant. Our next news goes on in five minutes; Vhat is the reason for the evacuation? How long vill it last? What should the people do? Is anyone at the plant injured? Thanks, if anything changes let me know right away. Call me at (provide your full phone number). This is a drill. THIS IS A DRILL
9-77 '1993 Evaluated Exercise , i DBNPS EHERGENCY PREPAREDNESS CUE CARD (Cont'd) () TO: Public Caller CUE CARD NO. TIME: 10:50 PR-15 T: 02/50 , 1 ANTICIPATED RESPONSE: Public Concern Operators should respond to questions. If you are referred to another agency: ,
- 1. Note the number provided '
- 2. DO NOT call other agencies during the Alert ECL.
INSTRUCTIONS: Provide the full phone number you are using if call back is requested. If Public Concern Operators question how you received their number, inform them l your cal) was transferred from the Edison Operator. O ! -O THIS IS A' DRILL
*************************+++++*************+++++******************************
9-78 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. PR-16 T0: Public Concern Operator TIME: 10:50 T: 02/$0 THIS IS A DRILL - DO NOT initiate actions affecting normal plant operations. - INFORMATION: Use the following questions only during the Alert classification. Call the Toledo Edison Public Concern Operator at Extension 6048. State "This is a drill" for all calls. Log responses to questions. Name: Jane / Jim Vills Town: Toledo I'm at VTOL, TVll. Our news desk vas informed on your emergency. Uhat caused the emergency at Davis-Besse? How long has this problem been going on? Is there any radiation problem? Our crev vill be coming out, where should they go for a tour? This is a drill. THIS IS A DRILL
l 1 9-79 1993 Evaluated Exercise 1 i DBNPS EHERGENCY PREPAREDNESS CUE CARD (Cont'd) CUE CARD NO. PR-16 .( TIME:' 10:50 TO: Public Caller ! T: 02/50 ANTICIPATED RESPONSE: , Public Concern Operators should respond to questions. If you are referred to another agency: ]
- 1. Note the number provided
- 2. DO NOT call other agencies during the Alert ECL.
i INSTRUCTIONS: Provide the full phone number you are using if call back is requested. If Public Concern Operators question how you received their number, inform them your call was transferred from the Edison Operator. I t 7 J
****************************************************************************** l THIS IS A DRILL !
****************************************************************************** -l
- l
9-80 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD CUE CARD NO. PR-17X SCENARIO NO. 1993 Evaluated Exercise TO: JPIC Hanager/ Company Spokesperson TIME: 10:50 T: 02/50 f THIS IS A DRILL , DO NOT initiate actions affecting normal plant operations.
****************************************************************************** i I
i INFORMATION: l Develop a bulletin announcing JPIC activation. THIS IS A DRILL
I. 9-81 1993 Evaluated Exercise DBNPS EMFRGENCY PREPAREDNESS CUE CARD (Cont'd) T CUE CARD NO. PR-17X TO: JPIC Controller TIME: 10:50 T: 02/50 ANTICIPATED. RESPONSE: News release / bulletin is prepared announcing JPIC activation. INSTRUCTIONS:
- Do not issue this card if media information or JPIC activation has already been provided.
- Note processing time from start to issue of information. j
'I i
i f I 1 I THIS IS A DRILL i
****************************************************************************** l l
4
i 9-82 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD CUE CARD NO. PR-18 . SCENARIO NO. 1993 Evaluated Exercise Hock Media Leader TIME: 11:10 T0: T: 03/10 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. INFORMATION: Enter the JPIC. Provide your name and assumed media affiliation. status Upon completion of badging requirements start asking questions on plant and employee activities. Have remaining mock media enter the JPIC about 5 minutes following your entrance. ll j
*********************************f******************************************** I THIS IS A DRILL G! l ***************+************w*************************************************
l
-)
9-83 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) I CUE CARD NO. PR-18 TO: JPIC Controller TIME: 11:10 T: 03/10 ANTICIPATED RESPONSE: , I observe media badging activities, l INSTRUCTIONS: I Inform lead controller on media arrival. , (' i
******************************o***********************************************
. - /. Th7S IS A DRILL
*******************************************************************+**********
9-84 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. PR-19 T0: Public Concern Operator TIME: 11:20 T: 03/20 t THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. INFORMATION: Use the following questions only during the Site Area Emergency classification. Call the Toledo Edison Public Concern Operator at Extension 6047. State "This is a drill" for all calls. Log responses to questions. Name: M. Young (Recovering from a knee operation.) Town: Lacarne I'm recovering from surgery and could need help. If the TV says to evacuate, what should I do? This is a drill. THIS IS A DRILL
1 9-85 1993 Evaluated Exercise DBNPS EMERGENCY FREPAREDNESS CUE CARD (Cont'd) CUE CARD NO. PR-19 T0: Public Caller TIME: 11:20 i T: 03/20 ANTICIPATED RESPONSE: Public Concern Operator should resnond to questions. INSTRUCTIONS: Note responses to questions. Provide your complete call back number, if requested. Perform follov-up call if referred to the State of Ohio, Ottava, or Lucas County EMA's. Note response from other agency. \
**********************************************************************w*******
THIS IS A DRILL
**************************************A***************************************
9-86 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD N0. PR-20 T0: Public Concern Operator TIME: 11:20 T: 03/20 THIS IS A DRILL DO NOT initiate actions affecting* normal plant operations. INFORMATION: Use the following questions only during the Site Area Emergency classification. Call the Toledo Edison Public Concern Operator at Extension 6048. State "This is a drill" for all calls. Log responses to questions. Name: N. Tillman Town: Fremont Vhat does this accident mean in terms of employment in Toledo? Vill the emergency affect property near Port Clinton? This is a drill. l THIS IS A DRILL
- .. . . ~ . ... . - . - . . .
i 9-87 1993 Evaluated. Exercise l
-DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd)
CUE CARD NO. PR-20 , TO: Public Caller TIME: 11:20 , T: 03/20 ANTICIPATED RESPONSE: , Public Concern Operator should respond to questions. INSTRUCTIONS: Note responses to questions. Provide your complete call back number, if requested. Perform follow-up call if referred to the State of Ohio, Ottava, or Lucas County EMA's. Note response from other agency. THIS IS A DRILL
*****+********************+***************************************************
9-88 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. PR-21 TO: Public Concern Operator TIME: 11:30 T: 03/30
- h******************************************************
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
- +*********
INFORMATION: Use the following questions only during the Site Area Emergency classification. Call the Toledo Edison Public Concern Operator at Extension 6047. State "This is a drill" for all calls. Log responses to questions. Name: L. Avery Town: Philadelphia I'm a staff reporter from the Philadelphia Enquirer. Have any of the nearby power companies been asked to help? How many people are near the plant? What broke and why? Is the leaking fluid getting into Lake Erie? This is a drill.
****************************w'************************************************
THIS IS A DRILL
l 9 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) CUE CARD NO. PR-21 i T0: Public Caller TIME: 11:30 'j i T: 03/30 ) ANTICIPATED RESPONSE: Public Concern Operator should respond to questions. 1 INSTRUCTIONS: Note responses to questions. Provide your complete call back number, if requested. -
. Perform follow-up call if referred to the State of Ohio, Ottava, or Lucas County _
EMA's. Note response from other agency. .i k I b b P 1 THIS IS A DRILL
*******************************************+**********************************
l 1 _ _ _ _ _ ~.. _ ._.. --
i
~l 9-90 1993 Evaluated Exercise !
i' DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise ' CUE CARD NO. PR-22 l TO: Public Concern Operator TIME: 11:30 l l T: 03/30 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. INFORMATION: Use the following questions only during the Site Area Emergency classification. Call the Toledo Edison Public Concern Operator at Extension 6048. State "This is a drill" for all calls. Log responses to questions. Name: P. Ranier Town: Graytown I own a condo at Green Cove; vhat should I do to protect my property? This is a drill. THIS IS A DRILL
**************************************+***************************************
9-91' 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd). CUE CARD NO. PR-22 TO: Public Caller TIME: 11:30 T: 03/30 ANTICIPATED RESPONSE: Public Concern Operator should respond to questions. INSTRUCTIONS: Note responses to questions. Provide your complete call back number, if requested. Perform follov-up call if referred to the State of Ohio, Ottava, or Lucas County EMA's. Note response from other agency. h
'I e
t t THIS IS A DRILL l l
l 9-92 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. PR-23 T0: Public Concern Operator TIME: 11:40 T: 03/40 l l
******+*******a***************************************************************
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. l ****************************************************************************** l INFORM.ATION: Use the following questions only during the Site Area Emergency classification. Call the Toledo Edison Public Concern Operator at Extension 6047. State "This is a drill" for all calls. Log responses to questions. Name: I. Barton Town: Catauba What should I do to protect myself? I Vhat caused this problem? How many people are going to get sick? l This is a drill. I 1 l
\
THIS IS A DRILL 9
*-****************************+++**********************************************
t 9-93 1993 Evaluated Exercise DBNPS EMERGENCY ~ PREPAREDNESS CUE CARD (Cont'd)
" CUE CARD NO. PR-23 .[
T0: Public Caller TIME: 11:40 T: 03/40 ANTICIPATED RESPONSE: .j i Public Concern Operator should respond to questions. E f INSTRUCTIONS: Note responses to questions. Provide your complete call back number, if requested. Perform follow-up call if referred to the State of Ohio, Ottava, or Lucas County
~
EMA's. Note response from other agency.
\
k THIS IS A DRILL
******+++++++++++++********************+++************************************
- . . . ~ . - . - , - - , .
9-94 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO No. 1993 Evaluated Exercise CUE CARD NO. PR-24 TO: Public Concern Operator TIME: 11:40 T: 03/40 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. INFORMATION: Use the following questions only during the Site Area Emergency classification. Call the Toledo Edison Public Concern Operator at Extension 6048. State "This is a drill" for all calls. Log responses to questions. Name: G. Carter Town: Northwood > Do you have the reactor turned off yet? Is it going to blow up? How would you know if radiation gets out into the air? This is a drill.
**********************************************w*******************************
THIS IS A DRILL
9-95 1993 Evaluated' Exercise DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) g CUE CARD NO. PR-24 T0: Public Caller TIME: 11:40 T: -03/40 ANTICIPATED RESPONSE: Public Concern Operator should respond to questions. INSTRUCTIONS: Note responses to questions. Provide your complete call back number, if requested. Perform follow-up call if referred to the State of Ohio, Ottava, or Lucas County EMA's. Note response from other agency. l THIS IS A DRILL
**********+*******************************************************************
9-96 1993 Evaluated Exercise ) DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO No. 1993 Evaluated Exercise CUE CARD NO. PR-25 TO: Public Concern Operator TIME: 11:50 T: 03/50 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. INFORMATION: Use the following questions only during the Site Area Emergency classification. Call the Toledo Edison Public Concern Operator at Extension 6047. State "This is a drill" for all calls. Log responses to questions. Name: H. Glass Town: Pittsburgh Press Vhen was the plant placed in the emergency condition? Vas anyone injured? Who is in charge? Where can I go for first-hand information? This is a drill.
- ++*****+********************************
THIS IS A DRILL O
- +******++*************************************
9-97 1993 Evaluated Exercise DENPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd)' CUE CARD No. r h ?_5_ TO: Public Caller TIME: 11:50 T: 03/50 ANTICIPATED RESPONSE: Public Concern Operator should respond to questions. P b 4 INSTRUCTIONS: .. j Note responses to questions. ; Provide your complete call back number, if requested. r Perform follow-up call if referred to the State of Ohio, Ottava, or Lucas County EMA's. Note response from other agency. l
~
l I I
*************+***************************************************w************
THIS IS A DRILL j i j
*********+++++++++++++++++***++++++++++++***++*+++++**************************
i
9-98 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. PR-26 T0: Public Concern Operator TIME: 11:50 T: 03/30 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
**************++*********************************+****************************
INFORMATION: Use the following questions only during the bite Area Emergency classification. Call the Toledo Edison Public Concerri Operator at Extension 6048. State "This is a drill" for all calls. ! Log responses to questions. Name: C. Fram Reporter from the San Francisco Examiner Vhat is the extent of damage? Vhat is the effect on the environment? What are the major problems to be repaired first? Who vill fix them? How many people live near the plant? This is a drill. I THIS IS A DRILL
*******************************************w**********************************
9-99 1993 Evaluated Exercise, DBNPS EMERGENCY PREPAF.EDNESS CUE CARD (Cont'd) () T0t Public Caller CUE CARD NO.
. TIME: 11:50 PR-26 T: 03/50 _
ANTICIPATED RESPONSE: Public Concern Operator should respond to questions. INSTRUCTIONS: } Note responses to questions. Provide your complete call back number, if requested. Perform follow-up call if referred to the State of Ohio, Ottava, or Lucas County. EMA's. Note response from other agency.
?
I i
?
THIS IS A DRILL
****************************************************************************** 9
9-100 1993 Evaluated Exercise DENPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SC*cNARIO No. 1993 Evaluated Exercise CUE CARD NO. PR-27 T0: Public Concern Operator TIME: 12:00 T: 04/00
- w**************************
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. INFORMATION: Use the following questions only during the Site Area Emergency classification. Call the Toledo Edison Public Concern Operator at Extension 6047. State "This is a drill" for all calls. Log responses to questions. Name: S. House Town: Oak Harbor My husband /vife works at Davis-Besse. How can I find out if he/she is okay? (Employee name la J. House.) This is a dril.1. l i A$** h*h *h$$ $h *h $
- h*h*hhh****hhh***h***********h***
THIS IS A DRILL
9-101 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) CUE CARD NO. PR-27 ( TO: Public Caller TIME: __ 12:00 j T: 04/00 ANTICIPATED RESPONSE: l
'l Public Concern Operator should respond to questions. )
i i INSTRUCTIONS: Note responses to questions, l l Provide your complete call back number, if requested. l Perform follow-up call if referred to the State of Ohio, Ottava, or Lucas County ! EMA's. Note response from other agency. . i l . < 1 i j f THIS IS A DRILL
***********************************************************+******************
- . . . - . ...,.,,..,....-.n.,,,. ~-, -
9-102 1993 Evaluated Exercise DBNPS EMERGENCi' PREPAREDNESS EXERCISE CUE CARD SCENARIO No. 1993 Evaluated Exercise CUE CARD NO. PR-28 ll TO: Public Concern Operator TIME: 12:00 T: 04/00 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. INFORMATION: Use the following questions only during the Site Area Emergency classification. Call the Toledo Edison Pablic Concern Operator at Extension 6048. State "This is a drill" for all calls. Log responses to questions. Name: E. King O Town: Salem Ve moved into this house last week. My kids don't understand what is going on or what to do. My family is frightened and vant to leave. Vill you explain what this is about? This is a drill. THIS IS A DRILL O
9-103 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) () TO: Public Caller CUE CARD NO. TIME: 12:00 PR-28 T: 04/00 ANTICIPATED RESPONSE: Public Concern Operator should respond to questions. INSTRUCTIONS: Note responses to questions. Provide your complete call back number, if requested. Perform follow-up call if referred to the State of Ohio, Ottava, or Lucas County EMA's. Note response from other agency.
?
P THIS IS A DRILL
I 9-104 1993 Evaluated Exercise DBNPS EMELSENCY PREPAREDNESS EXERCISE CUE CARD i SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. PR-29 1 1 T0: Public Concern Operator TIME: 12:10 T: 04/10 i
****************************************************4*************************
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
**************************************************************w***************
INFORMATION: Use the following questions only during the Site Area Emergency classification. Call the Toledo Edison Public Concern Operator at Extension 6047. State "This is a drill" for all calls. Log responses to questions. Name: A. Stark Town: Graytown I heard on the radio that I'ni supposed to read my emergency brochure. I can't find mine. What should I do? This is a drill. THIS IS A DRILL
9-105 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS CUE CAPD (Cont'd) CUE CARD NO. PR-29 TO: Public Caller TIME: 12:10 T: 04/10 ANTICIPATED RESPONSE: Public Contarn Operator should respond to questions. 4
~ .
- s. ,
. i INSTRUCTIONS:
Note responses to questions. Provide your complete call back number, if requested. 1 Perform follow-up call if referred to the State of Ohio, Ottava, or Lucas County EMA's. Note response from other agency.
\
1 i
'- THIS IS A DRILL
**********************+*******************************************************
9-106 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. PR-30 T0: Public Concern Operator TIME: 12:10 T: 04/10 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. INFORMATION: Use the following questions only during the Site Area Emergency classification. Call the Toledo Edison Public Concern Operator at Extension 6048. State "This is a drill" for all calls. Log responses to questions. Name: D. Klein Town: Port Clinton Does this emergency affect me? If power goes away I won't be able to listen to the news, I don't have a battery povered radio. Vhat should I do? This is a drill.
*****e*******************+*********************+******************************
THIS IS A DRILL
******++++**************++****++**********************************************
N
9-107 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd)
') CUE CARD NO. PR-30 T0: Public Caller TIME: 12:10 T: 04/10 ANTICIPATED RESPONSE:
Public Concern Operator should respond to questions. j r INSTRUCTIONS: Note responses to questions. Provide your complete call back number, if requested. Perform follow-up call if referred to the State of Ohio, Ottawa, or Lucas County , EMA's. Note response from other agency. % e i THIS IS A DRILL
9-108 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. PR-31 TO: Public Concern Operator TIME: 12:20 T: 04/20 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. INFORMATION: Use the following questions only during the Site Area Emergency classification. Call the Toledo Edison Public Concern Operator at Extension 6047. State "This is a drill" for all calls. Log responses to questions. Name: C. Davis Town: Boston (Reporter from the Boston Globe.) When do you think this emergency vill end? Is anyone in danger at the power plant? What actions have the public been told to take? Who is in charge; the state government or the company? This is a drill. THIS IS A DRILL
. _ _. . - . . _ m .
9-109' 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) CUE CARD NO. PR-31 ( T0: Public Caller TIME: 12:20 T: 04/20 ANTICIPATED RESPONSE: Public Concern Operator should respond to questions. INSTRUCTIONS: i Note responses to questions. Provide your complete call back nucher, if requested. . Perform follow-up call if referred to the State of Ohio, Ottava, or Lucas County EMA's. Note response from other agency. I t a
.I f
THIS IS A DRILL
9-110 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. PR-32 T0: Public Concern Operator TIME: 12:20 T: 04/20 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. INFORMATION: Use the following questions only during the Site Area Emergency classification. Call the Toledo Edison Public Concern Operator at Extension 6048. State "This is a drill" for all calls. Log responses to questions. Name: B. Downs Town: Toledo Vhat are my electric rates going to be now? Why should anyone pay for your mistake? Do you know how much this vill cost and the damage to the environment? This is a drill. THIS IS A DRILL
************************++*****+**********************************************
9-111 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) CUE CARD NO. PR-32 ( T0: Public Caller TIME: 12:20 T: 04/20 ANTICIPATED RESPONSE: Public Concern Operator should respond to questions. l l i l * -j INSTRUCTIONS: Note responses to questions. l Provide your complete call back number, if requested. Perform follov-up call if referred to the State of Ohio, Ottava, or Lucas County EMA's. Note response from other agency. ( 1 1
\
l l i i l I THIS IS A DRILL
l 9-112 1993 Evaluated Execcise l DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD No. PR-33 T0: Public Concern Operator TIME: 12:30 T: 04/30 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. INFORMATION: Use the following questions only during the Site Area Emergency classification. Call the Toledo Edison Public Concern Operator at Extension 6047. State "This is a drill" for all calls. Log responses to questions. Name: J. Vise 9 Office of Senator B. Barker Senator Barker vill be arriving at the disaster site this evening by helicopter. Who vill be there to escort him and his staff? There vill be 12 people needing a tour of the nuclear plant with another 40 45 from the press. Could you make arrangements for them to have dinner? This is a drill. l l i THIS IS A DRILL l
i i 9-113 11993 Evaluated Exercise ') i j DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) CUE CARD NO. PR-33 TO: Public Caller TIME: 12:30 T: 04/30 ! ANTICIPATED RESPONSE: l Public Concern Operator should respond to questions. '$ l J INSTRUCTIONS: Note responses to questions. , Provide your complete call back number, if requested. Perform follov-up call if referred to the State of Ohio, Ottava, or Lucas~ County-EMA's. Note response from other agency. ~, i i i I P i
'l i
l i THIS IS A DRIfL i
- r*******************************************************************
i i
9-114 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. PR-34 T0: Public Concern Operator TIME: 12:30 T: 04/30
- 4****************************************************************
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. INFORMATION: Use the following questions only during the Site Area Emergency classification. Call the Toledo Edison Public Concern Operator at Extension 6048. State "This is a drill" for all calls. Log responses to questions. Name: N. Kronberg Town: Oak Harbor My car is in the shop; I don't have any way to get around. What can I do and where should I go? This is a drill.
- t THIS IS A DRILL
l 115 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) () TO: l'ublic Caller CUE CARD NO. TIME: 12:30 PR-34 - l 1 T: 04/30 1 I ANTICIPATED RESPONSE: i Public Concern Operator should respond to questions.
?
INSTRUCTIONS:
'i~
Note responses to questions. Provide your complete call back number, if requested. Perform follow-up call if referred to the State of Ohio, Ottava, or Lucas County EMA's. Note response from other agency. i
+
l r
. THIS IS A DRILL
******++++*****+******++++++**+******+++************************************** .
9-116 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. PR-35 T0: Public Concern Operator TIME: 12:40 T: 04/40 j o***************************************************************************** l THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. c***************************************************************************** INFORMATION: Use the following questions only during the Site Area Emergency classification. Call the Toledo Edison Public Concern Operator at Extension 6047. State "This is a drill" for all calls. l Log responses to questions. Name: J. Mills l Town: Harrisburg Metro Press 1 Is this accident similar to Three Mile Island? How much radiation is in the reactor? Hov do you know its safe to be in Toledo? What is the Governor of Ohio doing for the public? ! This is a drill. THIS IS A DRILL
1 ~ 9-117 1993 Evaluated Exercise-DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) CUE CARD NO. PR-35 ( TO: Public Caller TIME:- 12:40 l T: 04/40 l ANTICIPATED RESPONSE: Public Concern Operator should respond to questions. , i INSTRUCTIONS: Note responses to questions. Provide your complete call back number, if requested. Perform follow-up call if referred to the State of Ohio, Ottava, or 1.ucas County EMA's. Note response from other agency. , t p t
'I THIS IS A DRILL i
I
9-118 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. PR-36 l T0: Public Concern Operator TIME: 12:40 T: 04/40 THIS IS A DRILL D_0 NOT initiate actions affecting normal plant operations.
- +********************************************
INFORMATION: Use the following questions only during the Site Area Emergency classification. Call the Toledo Edison Public Concern Operator at Extension 6048. State "This is a drill" for all calls. Log responses to questions. O Name: K. Pratt Town: Maumee I'm a student at Bowling Green vorking on my doctorate in industrial psychology. How are people reacting at the plant? How about public response - has anyone called and what questions are they asking. How many people live near the plant? Where is your company president, and vill he be going to the plant? This is a drill. 1 l I j THIS IS A DRILL
) ********************************+++++++*****+*********************************
9-119 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) CUE CARD NO. PR-36 v[ \ - T0: Public Caller TIME: 12:40 T: 04/40 ANTICIPATED RESPONSE: Public Concern Operator should respond to questions. INSTRUCTIONS: Note responses to questions. Provide your complete call back number, if requested. Perform follow-up call if referred to the State of Ohio, Ottava, or Lucas County EMA's. Note response from othe. agency. i i 1 1 THIS IS A DRILL
******++*****************************************************************+****
9-120 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. PR-37 TO: Public Concern Operator TIME: 12:50 T: 04/50 o***************************************************************************** THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. o*********************************************+******************************* INFORMATION: Use the following questions only during the Site Area Emergency classification. Call the Toledo Edison Public Concern Operator at Extension 6047. State "This is a drill" for all calls. Log responses to questions. Name: M. Close Staff Writer: Business Veek Hov vell is your company positioned for this set back? What is the name and number of your CE07 This is a drill. Q***************************************************************************** THIS IS A DRILL C*****************************************************************************
I 9-121 1993 Evaluated Exercise-DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) I '\ CUE CARD NO. PR-37 l O 12:50 T0: Public Caller TIME: T: 04/50 F ANTICIPATED RESPONSE: Public Concern Operator should respond to questions. ; P t INSTRUCTIONS: Note responses to questions. Provide your complete call back number, if requested. I Perform follov-up call if referred to the State of Ohio, Ottava, or Lucas County EMA's. Note response from other agency. l t Y F F
'i i
^
O THIS IS A DRILL i t 6
9-122 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. PR-38 TO: Public Concern Operator TIME: 12:50 T: 04/50 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. INFORMATION: Use the following questions only during the Site Area Emergency classification. Call the Toledo Edison Public Concern Operator at Extension 6048. State "This is a drill" for all calls. Log responses to questions. Name: B. Ralston Town: Elmore I've heard about the disaster on my radio. If I need to evacuate how will you tell me? By the way, how are you sure everybody knows what to do? This is a drill.
****************************************************************************** I THIS IS A DRILL ********++**************************++++++**+*********************************
I
9-123 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) CUE CARD NO. PR-38 > T0: Public Caller TIME: 12:50 ; T: 04/50 ANTICIPATED RESPONSE: Public Concern Operator should respond to questions. INSTRUCTIONS: Note responses to questions. Provide your complete call back number, if requested. Perform follow-up call if referred to the State of Ohio, Ottava, or Lucas_ County EMA's. Note response from other agency. 5 t I i THIS IS A DRILL
****************+***********************+++***********************++**********
i
9-124 1993 Evaluated Exercise 1 DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO No. 1993 Evaluated Exercise CUE CARD NO. PR-39 T0: Public Concern Operater TIME: 13:00 T: 05/00 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. INFORMATION: Use the following questions only during the Site Area Emergency classification. Call the Toledo Edison Public Concern Operator at Extension 6047. State "This is a drill" for all calls. Log responses to questions. Name: R. Quill Town: Lima I heard about your emergency, could it affect my health? What level of contamination causes cancer? Vhat are the exposures near Toledo? This is a drill.
- +*********************************+******
THIS IS A DRILL
9-125 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) () Public Caller CUE CARD NO. TIME: -13:00 PR-39
' TO:
T: 05/00 ANTICIPATED RESPONSE: Public Concern Operator should respond to questions. INSTRUCTIONS: Note responses to questions. Provide your complete call back number, if requested. Perform follov-up call if referred to the State of Ohio, Ottava, or Lucas County EMA's. Note response from other agency. THIS IS A DRILL
9-126 1993 Evaluated Exercise , DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. PR-40 g TO: Public Concern Operator TIME: 13:00 T: 05/00 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. INFORMATION: Use the following questions only during the Site Area Emergency classification. Call the Toledo Edison Public Concern Operator at Extension 6048. State "This is a drill" for all calls. Log responses to questions. Name: T. Darke Town: Rocky Ridge I'm here visiting my family. Taey're very old and don't seem to understand why they have to do anything for a problem with a nuclear plant. Vould you please tell me just what the exact danger is to them and what to expect if we go to one of the fallout shelter places? This is a drill. THIS IS A DRILL
9-127 1993 Evaluated Exercise-
- DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd)
CUE CARD NO. PR-40.
- m. -
T0: Public Caller TIME: 13:00 T: 05/00 , ANTICIPATED RESPONSE: Public Concern Operator should respond to questions. i INSTRUCTIONS: Note responses to questions. Provide your complete call back number, if requested. ; Perform follow-up call if referred to tie State of Ohio. Ottava, or Lucas County EMA's. Note response from other agency. I i THIS IS A DRILL
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;- .1
9-128 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. PR 41 TO: Mock Media TIME: Approx. 11:30 T: Approx. 03/20 1 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. INFORMATION: Yield questioning to real media if participating.
- First Media Briefing Focus questions to panel on " people" issues and pre-planned actions.
Challenge State and County PI0s on public health and safety concerns. Develop trends in questioning. lh Challenge the Company Spokesperson and Technical Briefer on plant issues. Question the staffs to report on each identified problem. Do no attempt to tie unrelated events together. m 15 A DR m 9
9-129 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) CUE CARD NO. PR-41 (']J TIME: TO: JPIC Controller Approx. 11:20 T: Approx. 03/20 ANTICIPATED RESPONSE: Mock Media questions focused on people and planning issues. INSTRUCTIONS:
- Note concerns in response provided by the Company Spokesperson and PI0s.
- Observe Technical Briefing, if performed.
s' W P ('-' THIS IS A DRILL i 1 I
9-130 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO No. 1993 Evaluated Exercise CUE CARD NO. PR-42 T0: Mock Media TIME: Approx. 12:20 T: Approx. 04/20 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. INFORMATION: Yield questioning to real media if participating. - Second Briefing Focus questions on the " hazards" of radiation and effects on the EPZ. Challenge PI0s on activities at their parent offices. - Request response to unanswered questions from prior briefing. - Develop trends in questioning.
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THIS IS A DRILL
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i 9-131 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) a CUE CARD NO. PR-42 T0: JPIC Controller TIME: Approx. 12:20 i T: Approx. 04/20 ANTICIPATED RESPONSE: ; Mock media focus questions as necessary. INSTRUCTIONS: Note concerns in response provided by the Company Spokesperson and PIOS. Observe Technical Briefing if performed, , A r i THIS IS A DRILL l
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9-132 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO No. 1993 Evaluated Exercise CUE CARD NO. PR-43 T0: Mock Media TIME: Approx. 13:20 T: Approx. 05/20 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. INFORMATION: Yield questioning to real media if participating. - Third and following briefings Focus questions on management of radiological vaste generated by the accident. Challenge PI0s on management of radiological vaste if found offsite. Ask questions on locations of plants similar to DBNPS. O
- Where are tFey in the U.S. and in other countries? - How many hr had similar accidents?
- Develop trends in questioning. THIS IS A DRILL
9-133 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd)- CUE CARD NO. PR-43 '). s -i TO: JPIC Controller TIME: Approx. 13:20-e T: Approx. 05/20 l ANTICIPATED RESPONSE: Mock media questions focused as necessary. i INSTRUCTIONS:
- Note concerns in response provided by the Company Spokesperson and PI0s. - Observe Technical Briefing if performed.
i F I THIS IS A DRILL 1
9-134 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. PR 44 TO: Public Concern Operator TIME: 13:30 T: 05/30 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. INFORMATION: Use the following questions only during the General Emergency classification. Call the Toledo Edison Public Concern Operator at Extension 6047. State "This is a drill" for all calls. Log responses to questions. O Name: R. Villis Town: Lacarne I need help! My son panicked when he heard the sirens. He was going to pick up an older relative down the road so ve could all get out of the area. The problem is, he backed up into the ditch in from of our home. Nov none of us can get out. What should we do? This is a drill. THIS IS A DRILL
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l 1 9-135 1993 Evaluated Exercise.
- . - . DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) i CUE CARD NO. 'PR 44
( , TIME: 13:30 TO: Public Caller ] T: 05/30 ANTICIPATED RESPONSE: , Public Concern Operators should respond to questions. 1 INSTRUCTIONS: Note response to questions. If referred to another agency, DO NOT perform follow-up call.
- Repeat use of this question if General Emergency continues beyond indicated time. If the original call was made to extension 6047, then call 6048. If the original call was'made to extension 6048, then call 6047.
( i i
'l l
l
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THIS IS A DRILL
.. ~ -. - - -
9-136 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. PR 45 . TO: Public Concern Operator TIME: 13:30 T: 05/30 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. INFORMATION: Use the following questions only during the General Emergency classification. Call the Toledo Edison Public Concern Operator at Extension 6048. State "This is a drill" for all calls. Log responses to questions. O Name: B. Martin Town: Port Clinton My family vent to the zoo and I don't have a ride. Could someone please come and help me? I can't valk because my leg is in a cast from an accident. I vant to leave nov! Vhere vill they take me and how can I let my family know where I'll be? This is a drill.
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THIS IS A DRILL
9-137 -1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS CUE CARD.(Cont'd) CUE CARD NO. PR-45 T0: Public Caller TIME: 13:30-T: 05/30 ANTICIPATED RESPONSE: Public Concern Operators should respond to questions. INSTRUCTIONS: Note response to questions. If referred to another agency, DO NOT perform follow-up call.
- Repeat use of this question if General Emergency continues beyond indicated time. If the original call was made to extension 6047, then call 6048. If the original call was made to extension 6048, then call 6047.
THIS IS A DRILL
9-138 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO No. 1993 Evaluated Exercise. CUE CARD NO. PR 46 T0: Public Concern Operator TIME: 13:40 T: 05/40 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. INFORMATION: Use the following questions only during the General Emergency classification. Call the Toledo Edison Public Concern Operator at Extension 6047. State "This is a drill" for all calls. Log responses to questions. O Name: N. Varren Town: Salem Township (Farm / crop damage concerns) Does the emergency at Davis-Besse affect my crops? Vill your company take samples for checking my crops for radiation? Who pays my bills if I lose my harvest to your mistake? This is a drill.
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THIS IS A DRILL
C 1 9-139 -1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) .; / '\ CUE CARD NO. PR 46 ; O TO: - Public Caller TIME: 13:40 T: 05/40 ANTICIPATED RESPONSE: j Public Concern Operators should respond to questions. l INSTRUCTIONS: Note response to questions. If referred to another agency, DO NOT perform follow-up call.
- Repeat use of this question if General Emergency continues beyond indicated i time. If the original call was made to extension 6047, then call 6048. If ,
the original call was made to extension 6048, then call 6047. . k THIS IS A DRILL
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9-140 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. PR 47 TO: Public Concern Operator TIME: 13:40 T: 05/40 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. INFORMATION: Use the following questions only during the General Emergency classification. Call the Toledo Edison Public Concern Operator at Extension 6048. State "This is a drill" for all calls. Log responses to questions. O Name: M. Browning - Reporter, N.Y. Times Town: New York Hi, this is M. Brovning, what is your name? (Operator should not provide name.) How many people have to evacuate from the fallout created by the explosion? Where vill they be taken to? Are there any fatalities? What time did the disaster occur? What took so long to inform the public? Vould you please spell your name, I didn't get it the first time. This is a drill. THIS IS A DRILL
- ++++**********************+**+********************************
9-141 1993 Evaluated Exercise , DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) CUE CARD NO. PR 47 -(s ,
~l TO: Public' Caller TIME: 13:40 T: 05/40 ANTICIPATED RESPONSE:
Public Concern Operators should respond to questions. INSTRUCTIONS: Note response to questions.
.J If referred to another agency, DO NOT perform follow-up call.
- Repeat use of this question if General Emergency continues beyond indicated time. If the original call was made to extension 6047, then call 6048. If the original call was made to extension 6048, then call 6047. j i
l i O THIS IS A DRILL
=
9-142 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. PR 48 l T0: Public Concern Operator TIME: 13:50 T: 05/50 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. INFORMATION: Use the following questions only during the General Emergency classification. Call the Toledo Edison Public Concern Operator at Extension 6047. State "This is a drill" for all calls. Log responses to questions. O Name: D. Powell Town: Benton Township If my property is damaged, who will pay to fix the problem? Where do I go to fill out paperwork? Who is the person to see for help? This is a drill. THIS IS A DRILL
9-143 1993 Evaluated. Exercise DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) CUE CARD NO. PR-48 '( T0: Public Caller TIME: 13:50 T: 05/50 ANTICIPATED RESPONSE: Public Concern Operators should respond to questions. INSTRUCTIONS: Note response to questions. If referred to another agency, DO NOT perform follow-up call.
- Repeat use of this question if General Emergency continues beyond indicated time. If the original call was made to extension 6047, then call 6048. If-the original call was made to extension 6048, then call 6047.
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O THIS IS A DRILL
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9-144 1993 Evaluated Exercise-DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO No. 1993 Evaluated Exercise CUE CARD NO. PR-49 T0: Public Concern Operator TIME: 13:50 T: 05/50 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. INFORMATION: Use the following questions only during the General Emergency classification. Call the Toledo Edison Public Concern Operator at Extension 6048. State "This is a drill" for all calls. Log responses to questions. O Name: A. Paxton Town: Oak Harbor (stranded motorist) My car von't start and I want to leave. Vill someone come and help me? How much longer can I safely stay here? This is a drill. THIS IS A DRILL
9-145 1993 Evaluated Exercise' f DBNPS EHERGENCY PREPAREDNESS CUE CARD (Cont'd) ! I CUE CARD NO. PR-49 v TO: Public Caller TIME: 13:50 , T: 05/50 ANTICIPATED RESPONSE: Public Concern Operators should respond to questions. i b k INSTRUCTIONS: Note response to questions. ; If referred to another agency, DO NOT perform follow-up call. Repeat use of this question if General Emergency continues beyond indicated time. If the original call was made to extension 6047, then call 6048. If the original call was made to extension 6048, then call 6047. l, E
)
\ THIS IS A DRILL ,
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9-146 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD PR-50 SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. TO: Public Concern Operator TIME: 14:00 T: 06/00
- 4--4***************************************************************************
THIS IS A DRILL D0_ NOT initiate actions affecting normal plant operations. INFORMATION: Use the following questions only during the General Emergency classification. Call the Toledo Edison Public Concern Operator at Extension 6047. State "This is a drill" for all calls. Log responses to questions. O Name: G. Bally Town: Rocky Ridge (Vorking in Toledo) My kids are home and don't have a way to leave. I dropped my car off at the shop on my way to work. It won't be fixed until later today, so I can't get home to help my family. I'm very worried, they called and said there's been sirens and all sorts of other things going on because of the nuclear problem. Please help me get my children to a safe place. ; This is a drill. I l i THIS IS A DRILL l
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9-147 1993 Evaluated Exercise' DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) () TO: Public Caller CUE CARD NO. TIME: 14:00 PR-50 T: 06/00 ANTICIPATED RESPONSE: Public Concern Operators should respond to questions.
-i INSTRUCTIONS:
Note response to questions. If referred to c.nother agency, DO NOT perform follow-up call.
- Repeat-use of this question if General Emergency continues beyond indicated time. If the original call was made to extension 6047, then call 6048. If '
the original call was made to extension 6048, then call 6047. \ 9 R THIS IS A DRILL
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1 l J
9-148 1993 Evaluated Exercise DBNP5 EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. PR-51 g T0: Public Concern Operator TIME: 14:00 T: 06/00 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. INFORMATION: Use the following questions only during the General Emergency classification. Call the Toledo Edison Public Concern Operator at Extension 6048. State "This is a drill" for all calls. Log responses to questions. O Name: B. Remsing (concerned youth) Town: Maumee My mom and dad vent boating with neighbors this morning. They use the docks in Port Clinton, I think. Are they alright? My younger brother is really scared and thinks the radiation can kill us. Can that happen? Is the stuff coming out of the reactor poison? What could it do to the environment? This is a drill. THIS IS A DRILL
9-149 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) / CUE CARD NO. PR-51 t. TO: Public Caller TIME: 14:00 T: 06/00 ANTICIPATED RESPONSE: Public Concern Operators should respond to questions. INSTRUCTIONS: Note response to questions. If referred to another agency, DO NOT perform follow-up call.
- Repeat use of this question if General Emergency continues beyond indicated time. If the original call was made to extension 6047, then calle6048. 'If :
the original call was made to extension 6048, then call 6047. l kg i I 4 i THIS IS A DRILL I J
9-150 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. PR-52 ll T0: Public Concern Operator TIME: 14:10 T: 06/10
- w****************************************************************************
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
- +**********************************************
INFORMATION: Use the following questions only during the General Emergency classification. Call the Toledo Edison Public Concern Operator at Extension 6047. State "This is a drill" for all calls. Log responses to questions. O Name: Dr. P. Shaffer Town: Cincinnati I've been contacted to provide psychological services to your trauma victims. - Where should I go to set up my service office? - Vhat billing number should I use for invoicing? This is a drill. i I THIS IS A DRILL O\ ! l
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9-151 1993. Evaluated Exercise ,. DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) CUE CARD NO. PR-52 T0: Public Caller TIMS: 14:10 T: 06/10 , ANTICIPATED RESPONSE: .; Public Concern Operators should respond to questions. l t INSTRUCTIONS: , Note response to questions. , If referred to another agency, DO NOT perform follow-up call.
- Repeat use of this question if General Emergency continues beyond indicated time. If the original call was made to extension 6047, then call 6048. If .
the original call was made to extension 6048, then call 6047. j THIS IS A DRILL
**************+******************+***********++++**********+******************
i 9-152 1993 Evaluated Exercise l DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. PR-53 TO: Public Concern Operator TIME: 14:10 T: 06/10
- s************.*********************************************************
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
- w*
INFORMATION: Use the following questions only during the General Emergency classification. Call the Toledo Edison Public Concern Operator at Extension 6048. State "This is a drill" for all calls. Log responses to questions. O Name: J. Taylor - Reporter Town: Fallon, Nevada Hi, I'm J. Taylor. What is your name please? (Operator should not provide name.) What is the damage to the Davis-Besse reactor core? Materials getting out into the environment are high-level vaste, aren't they? Vould you estimate the amount of vaste (in cubic feet) created by this problem? Hov vill the vaste be removed when it's collected (by truck, train, etc.)? Please spell your name this time. I don't believe I heard it the first time. This is a drill. THIS IS A DRILL
.~ . . .. - .. . .
i 9-153 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) [) ' CUE CARD NO. PR-53 ' (/ T0: Public Caller TIME: 14: 10 T: 06/10 r ANTICIPATED RESPONSE: Public Concern Operators should respond to questions. P 1 INSTRUCTIONS: Note response to questions. If referred to another agency, DO NOT perform follow-up call.
- Repeat use of this question if General Emergency continues beyond indicated time. If the original call was made to extension 604~, then call 6048. If the original call was made to extension 6048, then et11 6047.
1 1 1 l
****************************************************************************** )
) THIS IS A DRILL
*++***************************************************************************
l
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9-154 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. PR-54 TO: Public Concern Operator TIME: 14:20 T: 06/20 __ THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. INFORMATION: Use the following questions only during the General Emergency classification. Call the Toledo Edison Public Concern Operator at Extension 6047. State "This is a drill" for all calls. Log responses to questions. O Name: L. Bathrow Town: Vashington (Reporter - UPI) Earlier today, I talked with the Ottava and Lucas County offices. They sounded very confident in performing their emergency actions. Vould you say the power company is also performing well? What is the name of your emergency manager? (Note: you are asking who is in charge at the Davis-Besse site.) Vould you be available for further comments over the next three days? This is a drill. THIS IS A DRILL
9-155 1993 Evaluated Exercise-DBP 9 EMERGENCY PREPAREDNESS CUE CARD (Cont'd) CUE CARD NO. PR-54 T0: Public Caller TIME: 14:20 T: 06/20 ANTICIPATED RESPONSE: Public Concern Operators should respond to questions. INSTRUCTIONS: Note response to questions. If referred to another agency, DO NOT perform follow-up call.
- Repeat use of this question.if General Emergency continues beyond indicated time. If the original call was made to extension 6047, then call 6048. If the original call was made to extension 6048, then call 6047.
( I i i I (*********************w******************************************************* , THIS IS A DRILL r 3 . . - - - -- _ . r , , - - >
9-156 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. PR-55 TO: Public Concern Operator TIME: 14:20 T: 06/20 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. INFORMATION: Use the following questions only during the General Emergency classification. Call the Toledo Edison Public Concern Operator'at Extension 6048. State "This is a drill" for all calls. Log responses to questions. O Name: M. Danklefsen Town: Oak Harbor (Sand Beach area) Do the phones still work? I'm trying to find my sister. She's got my car and I can't get out of here. Anyway, nobody ansvers at her number (extension 7883). This is a drill. [ THIS IS A DRILL
9-157 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) PR ) CUE CARD NO. - TO: Public Caller TIME: 14:20 T: 06/20 ' ANTICIPATED RESPONSE: Public Concern Operators should respond to questions. - INSTRUCTIONS: Note response to questions. If referred to another agency, DO NOT perform follov-up call.
- Repeat use of this question if General Emergency continues beyond indicated time. If the original call was made to extension 6047, then call 6048. If the original call was made to extension 6048, then call 6047.
?
l \ THIS IS A DRILL
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9-158 1993 Evaluated Exercise j l DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD i SCENARIO No. 1993 Evaluated Exercise CUE CARD NO. PR-56 g : TO: Hock Media TIME: Approx. 15:00 T: Approx. 07/00 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. INFORMATION: Exit the JPIC. Allow briefing in progress to be complettd. Follov badging instructions. Provide comments and concerns to the JPIC Controller. O , THIS IS A DRILL
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9-159 1993 Evaluated Exercise DENPS EMERGENCY PREPAREDNESS CUE CARD.(Cont'd) () T0: JPIC Controller CUE CARD NO. TIME: PR-56 Approx. 15:00 T: Approx. 07/00 ANTICIPATED RESPONSE: Mock Media exits the JPIC. INSTRUCTIONS: Collect comments and concerns from the mock media. Assemble comments for controller review and facility critique. THIS IS A DRILL
9-160 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. PR-57X g TO: Company Spokesperson TIME: Approx. 15:20 l I T: Approx. 07/20 \ l 1 [ i o*****************************************************************+*********** THIS IS A DRILL l l DO NOT initiate actions affecting normal plant operations. l o***************************************************************************** 1 INFORMATION: Terminate JPIC support. 1 Follow JPIC Termination Procedure. l l l O' i Q***************************************************************************** THIS IS A DRILL
9-161 1993-Evaluated Exercise ; DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd)- l CUE CARD NO. PR-57X ;
}
TO: Lead JPIC Controller TIME: Approx. 15:20 T: Approx. 07/20 , ANTICIPATED RESPONSE: Termination of JPIC support. INSTRUCTION _S_: i, t Collect comments and concerns from the mock media.
~
Assemble comments for l controller review and facility critique. e t b t (~ THIS IS A DRILL
9-162 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1993 Evaluated Exercise CUE CARD NO. PR-58X ll TO: JPIC Manager TIME: Approx. 15:20 T: Approx. 07/20 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. INFORMATION: Inform Edison Operator and Public Affairs of termination of the Emergency Exercise. Inform staff to restore equipment. Conduct staff critique. Collect all logs and notes from the JPIC staff. Provide documents to the Lead Controller during the facility critique. t I I THIS IS A DRILL Ol j l
i 9-163 1993 Evaluated Exercise DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd)
' CUE CARD NO. PR-58X TO: Lead JPIC Controller TIME: Approx. 15:20 T: Approx. 07/20 ANTICIPATED RESPONSE:
JPIC Manager provides notification of termination of Emergency Exercise to Edison Operator and Public Affairs. Logs and notes collected. l l INSTRUCTIONS: Collect comments and concerns from the mor.k media. Assemble comments for , I controller review and facility critique. i i I l 1 l
=1 I
l l l i I
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I
E l i 10-1 1993 Evaluated Exercise (/ 10.0 EQUIPMENT STATUS AND REPAIR CUE CARDS This section contains the equipment status and repair information modeled to coincide with the scenario sequence of events. It includes the following information: 10.1 EQUIPMENT STATUS
SUMMARY
';his section provides equipment operational status'in a tabular format for ease of review and for ease of locating a particular piece of equipment's operating condition in a timely manner.
10.2 EQUIPMENT STATUS SHEETS This section provides individual equipment status sheets to be passed out to Players on a 15 minute basis should the Control Room Simulator become unavailable to conduct the Exercise. 10.3 EQUIPMENT REPAIR DATA This section provides controller guidance to any OSC Controller who may be sent out with a Repair Team during conduct of the Exercise. 10.4 EQUIPMENT REPAIR CUE CARDS This section provides cue cards that may be needed to. O compel Players to complete maintenance evolutions within the allotted time of the sequence of events. only equipment data is provided in Section 10. For in-plant radiation levels that personnel may encounter during repair activities, Controllers must refer to Section 8.3 of this manual. 1 O
l i i 1 10-2 1993 Evaluated Exercise j 10.1 EOUIPMENT STATUS GUMMARY This section provides equipment operational status in a tabular format l for e:ase of review and for ease of locating a particular piece of equipment's operating condition in a timely manner. O O
10-3 1993 Evaluated Exarcica PLANT EQUIPMENT STATUS
SUMMARY
Reactor Coo 1 ant Pumpa Makeup Pumps TtTime Time 1-1 1-2 2-1 2-2 #1 #2 00/00 0F00 ON ON ON ON RUN STBY 00/15 0815 ON ON ON ON RUN STBY 00/30 0830 ON ON ON ON RUN STBY 00/45 0845 ON ON OFF ON RUN OOS 01/00 0900 ON ON OFF ON. RUN OOS 01/15 0915 ON ON OFF ON RUN OOS 01/30 0930 ON ON OFF ON RUN OOS 01/45 0945 ON ON OFF ON RUN OOS 02/00 1000 ON ON OFF ON RUN OOS 02/15 1015 ON ON OFF ON RUN OOS 02/30 1030 ON ON OFF ON RUN OOS 02/45 1045 ON ON OFF ON RUN OOS 03/00 1100 OFF OFF OFF ON OFF OOS 03/15 1115 OFF OFF OFF ON OFF OOS 03/30 1130 OFF OFF OFF ON OFF OOS 03/45 1145 OFF OFF OFF ON OFF OOS 04/00 1200 OFF OFF OFF OFF OFF OOS 04/15 1215 OFF OFF OFF OFF OFF OOS 04/30 1230 OFF OFF OFF OFF OFF OOS 04/45 1245 OFF OFF OFF OFF OFT OOS 05/00 1300 OFF OFF OFF OFF OFF OOS 05/15 1315 OFF OFF OFF OFF OFF OOS i 05/30 1330 OFF OFF OFF OFF OFF OOS 05/45 1345 OFF OFF OFF OFF OFF OOS 06/00 1400 OFF OFF OFF OFF OFF OOS 06/15 1415 OFF OFF OFF OFF OFF OOS OE/30 1430 OFF OFF OFF OFF OFF OOS 06/45 1445 OFF OFF OFF OFF OFF OOS 07/00 1500 OFF OFF OFF OFF OFF OOS. HPI Pumpa Decay Beat Pumps Decay Beat Removal Coolers Time #1 #2 #1 #2 #1 #2 0800 STBY STBY STBY STBY AVAIL AVAIL 0815 STBY STBY STBY STBY AVAIL AVAIL 0830 STBY STBY STBY STBY AVAIL AVAIL ' 0B45 STBY STBY STBY STBY AVAIL AVAIL 0900 STBY STBY STBY STBY AVAIL AVAIL 0915 STBY STBY STBY STBY AVAIL AVAIL 0930 STBY STBY STBY STBY AVAIL AVAIL 0945 STBY STBY STBY STBY AVAIL AVAIL 1000 STBY STBY STBY STBY AVAIL AVAIL 1015 STBY STBY STBY STBY AVAIL AVAIL 1030 STBY STBY STBY STBY AVAIL AVAIL 1045- STBY STBY STBY STBY AVAIL AVAIL 1100 RUN RUN STBY STBY AVAIL AVAIL 1115 RUN RUN STBY STBY AVAIL AVAIL 1130 RUN RUN STBY STBY AVAIL AVAIL 1145 RUN RUN STBY STBY AVAIL AVAIL 1200 RUN RUN STBY STBY AVAIL AVAIL 1215 RUN RUN S13Y STBY AVAIL AVAIL 1230 RUN RUN STBY STBY AVAIL AVAIL 1245 RUN RUN STBY STBY AVAIL AVAIL 1300 RUN RUN STBY STBY AVAIL AVAIL 1315 RUN RUN STBY STBY AVAIL AVAIL 1330 RUN RUN RUN STBY IN SERVICE AVAIL 1345 RUN OFF RUN STBY IN SERVICE AVAIL 1400 OFF OFF RUN STBY IN SERVICE AVAIL 1415 OFF OFF RUN STBY IN SERVICE AVAIL 1430 OFF OFF RUN STBY IN SERVICE AVAIL 1445 OFT OFF RUN STBY IN SERVICE AVAIL 1500 OFF OFF RUN STBY IN SERVICE AVAIL
10-4 1993 Evaluated Exarciss PLANT EOUIPMENT STATUS
SUMMARY
CTMT Spray Pumps CTMT H2 Dilution Blowers CTMT Recirc Fans Time #1 #2 #1 #2 #1 #2 0000 AVAIL AVAIL OFF OFF ON ON 0815 AVAIL AVAIL OFF OFF ON ON 0830 AVAIL AVAIL OFF OFF ON ON 0845 AVAIL AVAIL OFF OFF ON ON 0900 AVAIL AVAIL OFF OFF ON ON 0915 AVAIL AVAIL OFF OFF ON ON 0930 AVAIL AVAIL OFF OFF ON ON 0945 AVAIL AVAIL OFF OFF ON ON 1000 AVAIL AVAIL OFF OFF ON ON 1015 AVAIL AVAIL OFF OFF ON ON 1030 AVAIL AVAIL OFF OFF ON ON 1045 AVAIL AVAIL OFF OFF ON ON 1100 AVAIL AVAIL OFT OFF ON ON 1115 AVAIL AVAIL OFF OFF ON ON 1130 AVAIL AVAIL OFF OFF ON ON 1145 AVAIL AVAIL OFF OFF ON ON 1200 AVAIL AVAIL OFF OFF ON ON 1215 AVAIL AVAIL OFF OFF ON ON 1230 AVAIL AVAIL OFF OFF ON ON 1245 AVAIL AVAIL OFF OFF ON ON 1300 AVAIL AVAIL OFF OFF ON ON 1315 AVAIL AVAIL OFF OFF ON ON 1330 AVAIL AVAIL OFF OFF ON ON 1345 AVAIL AVAIL OFF OFF ON ON 1400 AVAIL AVAIL OFF OFF ON ON 1415 AVAIL AVAIL OFF OFF ON ON 1430 AVAIL AVAIL OFF OFF ON ON 1445 AVAIL AVAIL OFT OFF ON ON 1500 AVAIL AVAIL OFF OFT ON ON .............=.......................=.....................=.......................... CTMT Air Cooler Units Component Cooling Water Pumps -Time #1 #2 #3 41 #2 #3 0 8~0 0 RUN-FAST RUN-FAST SPARE RUN RUN SPARE 0815 RUN-FAST RUN-FAST SPARE RUN RUN SPARE 0830 RUN-FAST RUN-FAST SPARE RUN RUN SPARE 0845 RUN-FAST RUN-FAST SPARE RUN RUN SPARE 0900 RUN-FAST RUN-FAST SPARE RUN RUN SPARE 0915 RUN-FAST RUN-FAST SPARE RUN RUN SPARE 0930 RUN-FAST RUN-FAST SPARE RUN RUN SPARE 0945 RUN-FAST RUN-FAST SPARE RUN RUN SPARE 1000 RUN-FAST RUN-FAST SPARE RUN RUN SPARE 1015 RUN-FAST RUN-FAST SPARE RUN RUN SPARE 1030 RUN-FAST RUN-FAST SPARE RUN RUN SPARE 1045 RUN-FAST RUN-FAST SPARE RUN RUN SPARE 1100 RUN-FAST RUN-FAST SPARE RUN RUN SPARE 1115 RUN-FAST RUN-FAST SPARE RUN RUN SPARE 1130 RUN-FAST RUN-FAST SPARE RUN RUN SPARE 1145 RUN-SLOW RUN-SLOW SPARE RUN RUN SPARE 1200 RUN-SLOW RUN-SLOW SPARE RUN RUN SPARE-1215 RUN-SLOW RUN-SLOW SPARE RUN RUN SPARE 1230 RUN-SLOW RUN-SLOW SPARE RUN RUN SPARE 1245 RUN-SLOW RUN-SLOW SPARE RUN RUN SPARE 1300 RUN-SLOW RUN-SLOW SPARE RUN RUN SPARE 1315 RUN-SLOW RUN-SLOW SPARE RUN RUN SPARE 1330 RUN-SLOW RUN-SLOW SPARE RUN RUN SPARE 1345 RUN-SLOW RUN-SLOW SPARE RUN RUN SPARE 1400 RUN-SLOW RUN-SLOW SPARE RUN RUN SPARE 1415 RUN-SLOW RUN-SLOW SPARE RUN RUN SPARE 1430 RUN-SLOW RUN-SLOW SPARE RUN RUN SPARE 1445 RUN-SLOW RUN-SLOW SPARE RUN RUN SPARE 1500 RUN-SLOW RUN-SLOW SPARE RUN RUN SPARE e
b 10-5 1993 Evaluated Exarcise l l ['
\
PLANT EQUIPMENT STATUS
SUMMARY
Component cooling Heat Exchangers Service Water Pumps (SWP) I Time #1 #2 #3 #1 #2 #3 0800 IN SERVICE IN SERVICE SPARE RUN RUN SPARE 0815 IN SERVICE IN SERVICE SPARE RUN RUN SPARE , 0830 IN SERVICE IN SERVICE SPARE RUN RUN SPARE IN SERVICE IN SERVICE SPARE SPARE 0845 RUN RUN 0900 IN r'RVICE IN SERVICE SPARE RUN RUN SPARE 0915 IN E AVICE IN SERVICE SPARE RUN RUN SPARE 0930 IN SERVICE IN SERVICE SPARE RUN RUN SPARE 0945 IN SERVICE IN SERVICE SPARE RUN RUN SPARE 1000 IN SERVICE IN SERVICE SPARE RUN RUN SPARE 1015 IN SERVICE IN SERVICE SPARE RUN RUN SPARE 1030 IN SERVICE IN SERVICE SPARE RUN RUN SPARE 1045 IN SERVICE IN SERVICE SPARE RUN RUN SPARE 1100 IN SERVICE IN SERVICE SPA RE RUN RUN SPARE. 1115 IN SERVICE IN SERVICE SPARE RUN RUN SPARE 1130 IN SERVICE IN SERVICE SPARE RUN RUN SPARE 1145 IN SERVICE IN SERVICE SPARE RUN RUN SPARE 1200 IN SERVICE IN SERVICE SPARE RUN RUN SPARE 1215 IN SERVICE IN SERVICE SPARE RUN RUN SPARE 1230 IN SERVICE IN SERVICE SPARE RUN RUN SPARE 1245 IN SERVICE IN SERVICE SPARE RUN RUN SPARE 1300 IN SERVICE IN SERVICE SPARE RUN RUN SPARE 1315 IN SERVICE IN SERVICE SPARE RUN RUN SPARE 1330 IN SERVICE IN SERVICE SPARE RUN RUN SPARE 1345 IN SERVICE IN SERVICE SPARE RUN RUN SPARE 1400 IN SERVICE IN SERVICE SPARE RUN RUN SPARE 1415 IN SERVICE IN SERVICE SPARE RUN RUN SPARE 1430 IN SERVICE IN SERVICE SPARE RUN RUN SPARE 1445 IN SERVICE IN SERVICE SPARE RUN RUN SPARE 1500 IN SERVICE IN SERVICE SPARE RUN RUN SPARE { ...................................................................................... y SWP Aux Feedwater Pumps Motor Driven Time Backup #1 #2 Feed Pumo 0800 DILUTION STBY STBY OFF 0815 DILUTION STBY STBY OFF 0830 DILUTION STBY STBY OFF 0845 DILUTION RUN RUN OFF 0900 DILUTION RUN RUN OOS 0915 DILUTION RUN RUN OOS 0930 DILUTION RUN RUN OOS 0945 DILUTION RUN RUN OOS 1000 DILUTION RUN RUN OOS 1015 DILUTION OOS RUN OOS 1030 DILUTION OOS RUN OOS 1045 DILUTION OOS RUN DOS 1100 DILUTION OOS OOS OOS 1115 DILUTION OOS OOS OOS 1130 DILUTION OOS OOS OOS 1145 DILUTION OOS OOS DOS 1200 DILUTION OOS OOS OOS 1215 DILUTION OOS OOS OOS 1230 DILUTION OOS OOS OOS 1245 DILUTION OOS OOS OOS 1300 DILUTION OOS OOS DOS 1315 DILUTION OOS OOS OOS 1330 DILUTION OOS OOS OOS 1345 DILUTION OOS DOS OOS 1400 DILUTION OOS OOS OOS 1415 DILUTION OOS OOS OOS 1430 DILUTION OOS OOS DOS 1445' DILUTION OOS OOS DOS 1500 DILUTION OOS OOS OOS
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10-6 '1993 Evaluated Exercise
- d 10.2 EQUIPMENT STATUS SHEETS This section provides individual equipment status sheets to be passed out to Players on a 15 minute basis.should the control Room Simulator become unavailable to conduct the Exercise.
The data sheets in this section should only be issued if directed by the Load Exercise Controller. If the Simulator remains fully operational, data sheets should not be used.
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10-7 1993 Evaluated Exercise EQUIPMENT STATUS DATA SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 0800 T: 00/00
. **eneeeee**e ....eeeee** eeeeeeeeeeeeee***emeneene=*eneeeeeeeeeeeee****een.
THIS IS A DRILL DO NOT initiate actions affecting normal operations. ene.. *eene.....e*.... **emenee ***eeeeeeeee***eeeeeeeeeeeeeeeee**eeeeeeeee** COMPONENT: STATUS: Reactor Coolant Pumps #1-1...................................... ON 91-2...................................... ON 82-1...................................... ON 82-2...................................... ON Makeup Pumps 11................................................. RUN
#2................................................. STBY HPI Pumps $1.................................................... STBY
#2.................................................... STBY Decay Heat Pumps $1............................................. STBY
#2............................................. STBY Decay Heat Removal Coolers $1................................... AVAIL
#2................................... AVAIL Containment Spray Pumps $1...................................... AVAIL
#2...................................... AVAIL Containment H2 Dilution Blowers $1.............................. OFF
#2.............................. OFF Containment Recirculation Fans $1............................... ON 82............................... ON Containment Air Cooler Units $1................................. RUN-FAST
#2................................. RUN-FAST
#3................................. SPARE Component Cooling Water Pumps 11................................ RUN
#2................................ RUN
#3................................ SPARE l Component C0oling Beat Exchangers $1............................ IN SERVICE l
#2............................ IN SERVICE !
#3............................ SPARE Service Water Pumps #1.......................................... RUN 82.......................................... RUN
#3.......................................... SPARE Backup.......................................... DILUTION Auxiliary Feedwater Pumps #1.................................... STBY
$2.................................... STBY Motor Driven Feedpump........................................... OFF e.....ee........eeeeeeeeeeeeeeeeeeeeeeeeeeeee. eeeen....eeeee................ j THIS IS A DRILL e....... .......... .. ............................................. **eneene l
10-3 1993 Evaluated Exercise EQUIPMENT STATUS DATA SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 0815 T: 00/15 THIS IS A DRILL DO NOT initiate actions affecting normal operations. COMPONENTt STATUS: Reactor Coolant Pumps #1-1...................................... ON
#1-2...................................... ON
#2-1...................................... ON 82-2...................................... ON Makeup Pumps #1................................................. RUN 82................................................. STBY HPI Pumps #1.................................................... STBY
#2.................................................... STBY Decay Heat Pumps #1............................................. STBY
#2............................................. STBY Decay Heat Removal Coolers #1................................... AVAIL
#2................................... AVAIL Containment Spray Pumps #1...................................... AVAIL
#2...................................... AVAIL Containment H2 Dilution Blowers #1.............................. OFF
#2.............................. OFF Containment Rucirculation Fans $1............................... ON 82............................... ON Containment Air Cooler Units #1................................. RUN-FAST
#2................................. RUN-FAST
#3................................. SPARE Component Cooling Water Pumps #1................................ RUN
#2................................ RUN
$3................................ SPARE Component Cooling Heat Exchangers #1............................ IN SERVICE
$2............................ IN SERVICE
#3............................ SPARE Service Water Pumps $1.......................................... RUN 82.......................................... RUN 83.......................................... SPARE Backup.......................................... DILUTION Auxiliary Feedwater Pumps #1.................................... STBY
$2.................................... STBY Motor Driven Feedpump........................................... OFF THIS IS A DRILL i
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10-9 1993 Evaluated Exerciso s EQUIPMENT STATUS DATA SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 0830 T: 00/30 THIS IS A DRILL DO NOT initiate actions affecting normal operations.
............................................e................................
COMPONENT: STATUS: Reactor Coolant Pumps #1-1...................................... ON
#1-2...................................... ON
#2-1...................................... ON ,
12-2...................................... ON Makeup Pumps #1................................................. RUN
#2................................................. STBY HPI Pumps $1.................................................... STDY
#2.................................................... STBY Decay Heat Pumps (1............................................. STBY
#2............................................. STBY Decay Heat Removal Coolers #1................................... AVAIL '
$2................................... AVAIL Containment Spray Pumps $1...................................... AVAIL
$2...................................... AVAIL Containment H2 Dilution Blowers 41.............................. OFF
$2.............................. OFF Containment Recirculation Fans $1............................... ON ON
#2...............................
Containment Air Cooler Unite #1................................. RUN-FAST
#2................................. RUN-FAST i
$3................................. SPARE Component Cooling Water Pumps 41................................ RUN
#2................................ RUN
#3................................ SPARE Component Cooling Heat Exchangers 41............................ IN SERVICE 82............................ IN SERVICE
#3............................ SPARE Service Water Pumps 11.......................................... RUN (2.......................................... RUN
$3.......................................... SPARE Backup.......................................... DILUTION Auxiliary Feedwater Pumps #1.................................... STBY
$2.................................... STBY Motor Driven Feedpump........................................... OFF ;
..........................**......*.......................................... i THIS IS A DRILL t
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10-10 1993 Evaluated Exarc!.ca EQUIPMENT STATUS DATA SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 0845 T: 00/45 THIS IS A DRILL DO NOT initiate actions affecting normal operations. COMPONENT: STATUS: Reactor Coolant Pumps #1-1...................................... ON 91-2...................................... ON
#2-1...................................... OFF
#2-2...................................... ON Makeup Pumps $1................................................. RUN (2................................................. OOS HPI Pumps #1.................................................... STBY
#2.................................................... STBY Decay Heat Pumps $1............................................. STBY
#2............................................. STBY Decay Heat Removal Coolers #1................................... AVAIL
#2................................... AVAIL Containment spray Pumps #1...................................... AVAIL
$2...................................... AVAIL Containment H2 Dilution Blowers #1.............................. OFF S2.............................. OFF Containment Recirculation Fans $1............................... ON ON
#2...............................
Containment Air Cooler Unita 41................................. RUN-FAST
$2................................. RUN-FAST
$3................................. SPARE Component Cooling Water Pumps #1................................ RUN 82................................ RUN f3................................ SPARE Component Cooling Heat Exchangers 61............................ IN SERVICE
$2............................ IN SERVICE
#3............................, SPARE Service Water Pumps 61.......................................... RUN
#2.......................................... RUN
#3.......................................... SPARE Backup.......................................... DILUTION Auxiliary Feedwater Pumps #1.................................... RUN 82.................................... RUN Motor Driven Feedpump........................................... OFF THIS IS A DRILL
10-11 1993 Evaluated Exercise ' s EQUIPMENT STATUS DATA SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 0900 T: 01/00 eeeeeeeee ,*e **emee..... **een eeeeeee******eeneseene ***ene******** ee **e. THIS IS A DRILL DO NOT initiate actions affecting normal operations.
- eeeeeeeeeeee...eeeeeeeeeeeeeeee****emeeeeeeeme***eeeeeeeeeeeeeeeeeeeeee....
COTtPONENT: STATUS: Reactor Coolant Pumps #1-1...................................... ON 91-2...................................... ON
#2-1...................................... OFF
#2-2...................................... ON i Makeup Pumps #1................................................. RUN
#2................................................. OOS HPI Pumps 41.................................................... STBY
#2.................................................... STBY Decay Heat Pumps 41............................................. STBY
#2............................................. STBY Decay Heat Removal Coolers #1................................... AVAIL
#2................................... AVAIL Containment Spray Pumps #1...................................... AVAIL
#2...................................... AVAIL Containment H2 Dilution Blowers #1.............................. OFF
#2.............................. OFF ,
Containment Recirculation Fans #1............................... ON
#2............................... ON i
Containment Air Cooler Units #1................................. RUN-FAST t
#2................................. RUN-FAST
#3................................. SPARE Component Cooling Water Pumps $1................................ RUN
#2................................ RUN
#3................................ SPARE Component Cooling Heat Exchangers #1............................ IN SERVICE
#2............................ IN SERVICE '
#3............................ SPARE Service Water Pumps $1.......................................... RUN
#2.......................................... RUN
#3.......................................... SPARE ,
Backup.......................................... DILUTION
- Auxiliary Feedwater Pumps #1.................................... RUN
#2.................................... RUN l
Motor Driven Feedpump........................................... OOS meneeseeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee**eemen* eeeeeeeeeemseeeeeeeeeee THIS IS A DRILL l eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee..ee.eeeeeeeeeeeeeeeeee...ee...en ! I i i
10-12 1993 Evaluated Exarcise EQUIPMENT STATUS DATA SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 0915 T: 01/15
- een......eeeeeeeeeeeeeeeeeeme*** **=ee. ..........ee...... ** .. ** . ......
THIS IS A DRILL DO NOT initiate actions affecting normal operations. ....ee. ...eeeeee***=*en.......e****eeeeeeeee**ee*=*eeeeee* eeeemene......... COMPONENT: STATUS: Reactor Coolant Pumps #1-1...................................... ON
#1-2...................................... ON
#2-1...................................... OFF
#2-2...................................... ON Makeup Pumps $1................................................. RUN
#2................................................. OOS HPI Pumps #1.................................................... STBY
#2.................................................... STBY Decay Heat Pumps $1............................................. STBY
#2............................................. STBY Decay Heat Removal Coolers #1................................... AVAIL
#2................................... AVAIL Containment Spray Pumps $1...................................... AVAIL
#2...................................... AVAIL Containment H2 Dilution Blowers $1.............................. OFF
#2.............................. OFF Containment Recirculation Fans #1............................... ON
#2............................... ON Containment Air Cooler Units #1................................. RUN-FAST
$2................................. RUN-FAST
#3................................. SPARE Component Cooling Water Pumps $1................................ RUN
#2................................ RUN
#3................................ SPARE Component Cooling Heat Exchangers $1............................ IN SERVICE
#2............................ IN SERVICE
#3............................ SPARE Service Water Pumps $1.......................................... RUN
#2.......................................... RUN
#3.......................................... SPARE Backup.......................................... DILUTION Auxiliary Feedwater Pumps $1.................................... RUN
#2.................................. . RUN Motor Driven Feedpump........................................... OOS
- eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeenne.**eeeeeeeeeee THIS IS A DRILL e...................................ee.......eeeemene***eeeeeeee+ .........e*
9 a 10-13 1993 Evaluated Exercise EQUIPMENT STATUS DATA SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 0930 T: 01/30
... **e************me...........e**=*** ............... * ********e ..... ***
THIS IS A DRILL DO NOT initiate actions affecting normal operations.
.. **** ..................e**ee... *** ..........e** *** ......... ** .......
COMPONENT: STATUS: Reactor Coolant Pumps #1-1...................................... ON )
#1-2.............. ....................... ON
#2-1...................................... OFF 1
#2-2.... ................................. ON Hakeup Pumps $1................................................. RUN
#2................................................. 005 HPI Pumps (1.................................................... STBY
#2.................................................... STBY Decay Heat Pumps #1............................................. STBY
$2............................................. ST3Y Decay Heat Removal Coolers $1................................... AVAIL
$2................................... AVAIL Containment Spray Pumps $1...................................... AVAIL
#2...................................... AVAIL Containment H2 Dilution Blowers 41.............................. OFF 1
#2.............................. OFF Containment Recirculation Fans $1............................... ON
#2............................... ON Containment Air Cooler Units $1................................. RUN-FAST 82................................. RUN-FAST f3-................................ SPARE Component Cooling Water Pumps $1................................ RUN
#2................................ RUN
#3................................ SPARE Component Cooling Heat Exchangers #1............................ IN SERVICE
#2............................ IN SERVICE
#3............................ SPARE Service Water Pumps $1.......................................... RUN
#2.......................................... RUN
$3.......................................... SPARE Backup.......................................... DILUTION Auxiliary Feedwater Pumps $1.................................... RUN
#2.................................... RUN Motor Driven Feedpump........................................... 005
..........e**e........................................................... ***
THIS IS A DRILL e......eee** eemene..e** ...eeeeeeee***e eeeeeeeeeeeeeeeeeeee***ee..... e****
10-14 1993 Evaluated Exarcise EQUIPMENT STATUS DATA SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 0945 T: 01/45 e.............. ....e* ................... ee.... ** ........................ THIS IS A DRILL DO NOT initiate actions affecting normal operations. .........................................................e**e..........e** .. COMPONENT: STATUS: Reactor Coolant Pumps #1-1...................................... ON
#1-2...................................... ON
#2-1...................................... OFF
#2-2...................................... ON Makeup Pumps 41................................................. RUN 82................................................. OOS HPI Pumps #1.................................................... STBY
#2.................................................... STBY Decay Heat Pumps #1............................................. STBY
$2............................................. STBY Decay Heat Removal Coolers $1................................... AVAIL
#2................................... AVAIL Containment Spray Pumps #1...................................... AVAIL
$2...................................... AVAIL Containment H2 Dilution Blowers #1.............................. OFF S2.............................. OFF Containment Recirculation Fans 51............................... ON 82............................... ON Containment Air Cooler Units $1................................. RUN-FAST
$2................................. RUN-FAST
#3................................. SPARE Component Cooling Water Pumpn $1................................ RUN 82................................ RUN
$3................................ SPARE Component Cooling Heat Exchangers $1............................ IN SERVICE
$2............................ IN SERVICE
#3............................ SPARE Service Water Pumps #1.......................................... RUN 82.......................................... RUN
#3.......................................... SPARE Backup.......................................... DILUTION Auxiliary Feedwater Pumps #1.................................... RUN 82.................................... RUN Motor Driven Feedpump........................................... OOS
........................................ **.......e*** ...................... THIS IS A DRILL
10-15 1993 Evaluated Exercise E EQUIPMENT STATUS DATA SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 1000 T: 02/00 THIS IS A DRILL ' DO NOT initiate actions affecting normal operations. COMPONENT: STATUS: Reactor Coolant Pumps #1-1...................................... ON
#1-2...................................... ON
#2-1...................................... OFF
$2-2...................................... ON Makeup Pumps $1................................................. RUN i
82................................................. OOS HPI Pumps 41.................................................... STBY (2.................................................... STBY Decay Heat Pumps $1............................................. STBY
#2............................................. STBY Decay Heat Removal Coolers #1................................... AVAIL
#2................................... AVAIL Containment Spray Pumps $1...................................... AVAIL
#2...................................... AVAIL Containment H2 Dilution Blowers (1.............................. OFF
$2.............................. OFF Containment Recirculation Fans 41............................... ON J
$2............................... ON 1
,1 Containment Air Cooler Units $1................................. RUN-FAST I
#2................................. RUN-FAST l i
93................................. SPARE Component Cooling Water Pumps #1................................ RUN
$2................................ RUN
#3................................ SPARE Component Cooling Heat Exchangers #1............................ IN SERVICE
#2............................ IN SERVICE
#3............................' SPARE Service Water Pumps 41.......................................... RUN
#2.......................................... RUN
#3.......................................... SPARE Backup.......................................... DILUTION Auxiliary Feedwater Pumps 41.................................... RUN
$2.................................... RUN Motor Driven Feedpump........................................... 00S THIS IS A DRILL
10-16 1993 Evaluated Exercise EQUIPMENT STATUS DATA SHEET SCENARIO NO. 1993 Evaluated Exercise TIME: 1015 T: 02/15 ........................... ** ...........e*** ....e**=.... **en............. THIS IS A DRILL DO NOT initiate actions affecting normal operations. .................. *** ...........weemmen....... eeeeeeeeee** e ............ COMPONENT: STATUS: Reactor Coolant Pumps #1-1...................................... ON
#1-2...................................... ON
#2-1...................................... OFF
#2-2...................................... ON Makeup Pumps 41................................................. RUN
#2................................................. OOS HPI Pumps 81.................................................... STBY
#2.................................................... STBY Decay Heat Pumps $1............................................. STBY
#2............................................. STBY Decay Heat Removal Coolers $1................................... AVAIL
#2................................... AVAIL Containment Spray Pumps $1...................................... AVAIL
#2...................................... AVAIL Containment H2 Dilution Blowers #1.............................. OFF
#2.............................. OFF Containment Recirculation Fans (l............................... ON 82............................... ON Containment Air Cooler Units 41................................. RUN-FAST (2................................. RUN-FAST
#3................................. SPARE Component Cooling Water Pumps 41................................ RUN 82................................ RUN
#3................................ SPARE Component Cooling Heat Exchangers $1............................ IN SERVICE
#2............................ IN SERVICE
#3............................ SPARE Service Water Pumps #1.......................................... RUN
$2.......................................... RUN
#3.......................................... SPARE Backup.......................................... DILUTION Auxiliary Feedwater Pumps $1.................................... OOS
#2.................................... RUN Motor Driven Feedpump........................................... OOS e.................................................eeeeeeeeeeeeee........ **ee THIS IS A DRILL
.................................. ce.................................... *e.
10-17 1993 Evaluated Exercise EQUIPMENT STATUS DATA SHEET. SCENARIO NO. 1993 Evaluated Exercise TIME: 1030 T: 02/30
**ee.*ee**e.**e........................**e.......e***e.........*e******
THIS IS A DRILL DO NOT initiate actions affecting normal operations.
................e**** ememe...eeee**eme **=eseeeeeeeeeeeeee***=**** ........
COMPONENT: STATUS: Reactor Coolant Pumps #1-1...................................... ON 91-2...................................... ON (2-1...................................... OFF
#2-2...................................... ON i Makeup Pumps #1................................................. RUN
#2................................................. OOS :
t HPI Pumps #1.................................................... STBY
#2.................................................... STBY j Decay Heat Pumps #1............................................. STBY}}