ML20235T271
| ML20235T271 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 08/20/1987 |
| From: | NEBRASKA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20235T268 | List: |
| References | |
| PROC-870820, NUDOCS 8710130004 | |
| Download: ML20235T271 (455) | |
Text
{{#Wiki_filter:p LNEBRASKA PUBLIC POWER DISTRICT O COOPER NUCLEAR' STATION.' 1987 ANNUAL EMERGENCY PREPAREDNESS EXERCISE - INTRODUCTION The Cooper Nuclear Station Emergency Plan describes'the emergency response capabilities for a nuclear emergency at the Cooper Nuclear Station, including support from: Federal, State, and local government agencies and private <- organizations. The CNS Emergency. Plan provides for continuous' emergency preparedness, including the conduct:of an annual full-scale e'xercise. l The purpose of the exerciseiis to activate and evaluate major portions of the emergency response organization and facilities and other aspects of the Emergency Plan and associated Emergency Plan Implementing. Procedures, in l _. accordance with Nuclear Regulatory Commission-(NRC) Regulation 10CFR50.47(b) ' ' and_ Appendix E. The exercise is conducted jointly with appropriate State and local agencies in order to assess State and local government emergency response plans, as required by Federal Emergency. Management Agency (FEMA) Regulation 44CFR350.9(b). The conduct and evaluation of the exercise provides additional training for emergency response organization personnel and a means to further enhance Nebraska Public Power District's emergency response capability. O This Exercise Manual has beenldeveloped to provide the basis for the conduct of , a simulated radiological accident at the Cooper Nuclear Station located near Brownville in Nemaha County,. Nebraska through which the capabilities and effectiveness of the Emergency Response Plans for the Nebraska Public Power District, the states of Nebraska, Missouri., and.their respective counties, can be evaluated. This manual is to be utilized by- the controller / evaluators and evaluators'from the utility, controller / evaluators from state and local agencies and observer / evaluators from the NRC.and FEMA to initiate, control, .j and evaluate the activities of the participants;in the exercise. Exercise
" players" will not have prior knowledge of the nature of the simulated incident or any parts thereof, This Exercise Manual is the control mechanism for-the conduct of the exercise and is subject to limited, controlled distribution.
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COOPER NUCLEAR STATION ( 1987 EMERGENCY PREPAREDNESS EXERCISE TABLE OF CONTENTS INTRODUCTION TABLE OF CONTENTS LIST OF FIGURES i GENERAL INFORMATION 1.0 SCOPE AND OBJECTIVES 1.1 Scope 1.2 Objectives 1.2.1 Nebraska Public Power District Objectives 1.2.2 State of Missouri Objectives 1.2.3 Missouri County Objectives 1.2.4 State of Nebraska Objectives 1.3 FEMA Objectives Cross-Reference 2.0 EXERCISE INFORMATION .
,s 2 .,1 Exercise Participants
[ } 2.2 Exercise Organization (j 2.3 Emergency Response Facilities 2.4 Exercise Conduct 2.5 Evaluation and Critique 3.0 TRAVEL INFORMATION 3.1 Directions to Cooper Nuclear Station 3.2 Accommodations
4.0 REFERENCES
/ ABBREVIATIONS-ACRONYMS / DEFINITIONS l 4.1 References 4.2 Abbreviations-Acronyms l 4.3 Definitions 5.0 CONTROLLER / EVALUATOR GENERAL INFORMATION 51 Precautions and Limitations 5.2 Controller / Evaluator Instructions 5.3 Evaluation Instructions . -
6.0 SCHEDULE OF EVENTS 1 l (o.J
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1 COOPER NUCLEAR STATION g%. i, ,/ 1987 EMERCENCY PREPAREDNESS EXERCISE v-TABLE OF CONTENTS (Continued) 7.0 EXERCISE SCENARIO 7.1 Narrative Summary of the Exercise Scenario 7.2 Onsite Sequence of Events 8.0 MESSACE FORMS AND PLANT DATA SHEETS 9.0 ONSITE RADIOLOGICAL AND CHEMISTRY DATA 9.1 / 9'. 2 i 9.3 ( 10.0 0FFSITE RADIOLOGICAL DATA 11.0 PUBLIC INFORMATION MESSACES l f'"\
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COOPER NUCLEAR STATION 1987 EMERGENCY PREPAREDNESS EXERCISE LIST OF FIGURES Section 2.0 FIGURE 2.1 Control Room and. Technical Support Center FIGURE 2.2- Emergency Operations Facility FIGURE 2.3 General Office Emergency Center. j FIGURE 2.4 Media Release Center Secti~on 3.0 1
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FIGURE 5.1 Controller / Evaluator Assignments l Section 6.0 FIGURE 6.1 Schedu.e of Events i l 1
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1.0 SCOPE AND OBJECTIVES 0 3.x '1.1 SCOPE The.1987 Cooper Nuclear Station Annual Emergency' Preparedness
- Exercise, to be conducted on October.7, 1987, will test and provide the. opportunity to evaluate the Nebraska Public Power' District, the states of Nebraska and Missouri, and their respective. counties' emergency plans and procedures. It will also. test each emergency response organization's ability..to assess and respond to. emergency conditions, and coordinate efforts with other. agencies for the protection of the health and safety of the public.
l The exercise will have ' full-scale participation from the State' of l Missouri 'and partial-. participation by; the State of Nebraska. The. L warning system sirens and EBS notificati0ns for the' emergency planning zone will be-activated during the exercise. Whenever practical, the exercise will incorporate provisions'for." Free Play" on the part of the participants. The scenario will dipict.a simulated sequence of events, resulting in a radiological release of sufficient' magnitude'to warrant rnobilization of State and local.. agencies to respond to the emergency. , 1-. 2 OBJECTIVES The Cooper Nuclear Station (CNS) 1987. Emergency. Preparedness Exercise Program objectives are based on the Nuclear. Regulatory Commission [ (FRC) requirements delineated in-10CFR50.47, Appendix E. Additional guidance provided in NUREG-0654, FEMA-REP-1, Revision'1,' NUREG-0696 and NUREG-0737 Supplement 1 was also utilized in developing these objectives. The major objective of. the exercise is to' evaluate the integrated capability of a major portion of the basic elements. existing within the onsite and offsite emergency plans and emergency response organizations. The specific objectives' of the exercise to be demonstrated are listed below. 1.2.1 Nebraska Public Power District Objectives
- 1. Demonstrate the' activation, and operation of emergency response facilities, including the Control Room, Technical Support Center, Operations Support Center,.
Emergency Operations Facility, Media Release Center and the General Office Emergency Center.
- 2. Demonstrate the reliability and effective' use of,- ,
emergency communications equipment and use of .j appropriate procedures.
- 3. Demonstrate proficiency in recognizing and classifying il emergency con aans. , lj u
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'4 Demonstrate the. initial notification of Federal, State O and local, corporate, and plant emergency' response. ,
personnel.
. 5. Demonstrate the ability to provide follow-up. .
notifications to Federal,. State and local, corporate,' and plant emergency response personnel.
- 6. Demonstrate the ability to coordinate the available ,
emergency.. response resources of NPPD, State and local organizations.
- 7. Demonstrate'the ability to properly. access.-
radiolo5 ical and meteorological data and formulate an.- initial accurate,' timely offsite radiological. dose proj ection.
- 8. Demonstrate.the: ability to continuously assess the-impact of the release of radioactive materials to'the environment.
- 9. Demonstrate'the continuity of.' authority and transition of responsibilities between emergency. facilities as a result of escalating accident classification.
- 10. Demonstrate the ability' to formulate 'and make protective action recommendations to protect plant-p personnel and the general public based on plant conditions'and/or field monitoring information,
- 11. Demonstrate the mobilization of onsite and offsite radiological monitoring teams and the appropriate use of equipment, procedures, and communications.
- 12. Demonstrate the capability of offsite radiological monitoring teams to collect and' transport sample media.
l 13. Demonstrate the ability to receive'and analyze sample l media from the radiological monitoring teams. 14 Demonstrate the ability to monitor and control emergency worker exposure within the plant.
- 15. Demonstrate adequate.. equipment and procedures to monitor-for contamination of emergency workers.and-equipment, and to perform decontamination as required.
- 16. Demonstrate the capability to obtain, co. ordinate and
,. assemble emer5ency information for timely-dissemination to the public via the media, using t-effective' visual aids.
- 17. Demonstrate the capability of the NPPD MRC to reply to inquiries of both a technical and political nature.
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- 18. Demonstrate the' capability of NPPD IAC personnel- to C respond directly.to (simulated) input from the public.
- l, concerning real.versus rumoredJevents occurring at-l Cooper Nuclear Station or within the'10' mile EPZ.
- 19. Demonstrate decision-making and' coordination with 1 L offs' M agencies; in .de-escalating and terminating the - !
emergency and in planning ~ reentry to evacuated areas.
- 20. Demonstrate the ability to plan recovery operations.
and identify.the need for additional resources. This objective will be accomplished via tabletop discussions. 1.2.2 State of Missouri objectives l Emergency Operations Center
- 1. Demonstrate. ability.to mobilize staff and activate -j facilities promptly. ~i d
- 2. Demonstrate ability to make decisions' and to - -{
coordinate emergency activities.
- 3. Demonstrate. ability to.communicat'e with'all.. -
. appropriate locations, organizations,'and fieldJ personnel' -
D 4. Demonstrate adequacy of facilities /and displays to l
\ support emergency operations.
- 5. Demonstrate ability ~to communicate with all j appropriate locations, organizations, and field I personnel.
l Forward Command Post
- 1.
- Demonstrate ability to mobilize staff and activate facilities protnptly.
- 2. Demonstrate ability to make. decisions and to-coordinate emergency activities.
- 3. Demonstrate adequacy of-facilities and displays to.
support emergency operations, j l 4 Demonstrate ability to communicate .with all' ~ l appropriate locations, organizations, and. field l personnel. .j i
- 5. Demonstrate ability to formulate and distribute .
l appropriate. instructions to the public in a timely ! manner. .; u 1-4 !
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- 6. . Demonstrate the ability.co continuously monitor.and.
f control emergency worker exposure.
'7. Demonstrate' ability to provide. ads nee coordination of f information released. *;
. . I Information Authentication Center
'1. Demonstrate l ability to mobill e staff and activate facilities'promptly.
- 2. . Demonstrate ability to make decisions and to coordinate emergency. activities.
- 3. Demonstrate adequacy of facilities and' displays-to-support emergency operations.
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- 4. Demonstrate ability-to communicate.with all-appropriate' locations, organizations, and field personnel.
- 5. Demonstrate the ability to continuously monitor;and ,
control emergency worker exposure.
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- 6. Demonstrate ability to provide' advance' coordination of-information released.
Dose Assessment 6 .i j
- 1. Demonstrate ability to mobilize staff and activate facilities promptly.
- 2. Demonstrate ability to make decisions-and to .q coordinate emergency activities. .
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- 3. Demonstrate ability to communicate with all' appropriate locations, organizations, and field .:
personnel. j
- 4. Demonstrate ability'to mobilize and deploy field-monitoring teams . in a timely fashion. -j 1
- 5. Demonstrate appropriate equipment and procedures'for determining ambiant radiation levels, d
- 6. Demonstrate appropriate equipment and procedures for measurement of airborne low as 10' pCi/cc radioiodine in the presence of concentrations noble gases. -as" I
- 7. Demonstrate ability to project dosage to the public. . . j via plume exposure, based on plant and field data, and'
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to determine appropriate protective measure', based on i PAG's, available shelter, evacuation' time estimates, I and other appropriate factors.
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- 8. Demonstrate the ability to continuously monitor and I O control emergency worker exposure. 1
\J N 9. Demonstrate th'e ability to make the decision, based on 1
predetermined criteria, whether to issue KI to emergency workers'and/or the general public.
- 10. Demonstrate the ability to supply and administer KI, once the decisions has been made to do so.
Field Monitoring 1
- 1. Demonstrate ability to mobilize staff and activate facilities promptly.
- 2. Demonstrate ability to make decisions and to coordinate emergency activities. .
- 3. Demonstrate adequacy of facilities and displays to j support emergency operations.
4 Demonstrate ability to communicate with all appropriate locations, organizations, and field personnel.
- 5. Demonstrate ability to mobilize and deploy. field monitoring teams in a' timely fashion.
- 6. Demonstrate appropriate equipment and procedures for V measurement of airborne radiciodine concentrations as low as 10~ pCi/cc in the presence of noble gases.
- 7. Demonstrate the ability to continuously monitor and control emergency worker exposure. .
Media Release Center 1
- 1. Demonstrate ability to mobilize staff and activate I facilities promptly.-
- 2. Demonstrate ability to make decisions and to coordinate emergency activities.
- 3. Demonstrate adequacy of facilities and displays to support emergency operations.
- 4. Demonstrate ability to communicate with all appropriate locations, organizations, and field i personnel. l 1
- 5. Demonstrate ability to brief the media in a clear, )
accurate and timely manner. 6 Demonstrate ability to provide advance coordination of l t information released. , ( i i 1-6 I
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. Medical
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.k 1. . Demonstrate the ability to continuously monitor and
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control emergency worker exposures,
- 2. DemonstrateLadequacy of ambulance; facilities-and procedures'for handling contaminated individuals.
- 3. Demonstrate adequacy of'hospita1Lfacilities and
procedures for handling' contaminated individuals. 1.2.3 Missouri County Obiectives Atchison
- 1. Demonstrate ability to mobilize, staff.and activate- ;;
facilities'promptly. __
- 2. Demonstrate ability to fully. staff' facilities.and maintain staffing around,the clock.
- 3. Demonstrate ability to make de'isions c and to -
fj coordinate emergency activities. 1
- 4. Demonstrate adequacy of facilities and displays to 1 support emergency operations.-
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1 e"'s 5. Demonstrate ability to communicate lwith all f q appropriate locations,. organizations, and field (-- personnel.
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- 6. Demonstrate ability to alert the public within the .
10-mile EPZ, disseminate an initial instructional ~ message within 15 minutes.
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- 7. Demonstrate ability to formulate and' distribute appropriate instructions to'the public in a timely )
fashion, .j
- 8. Demonstrate the ability toccontinuously monitor'and-control emergency worker exposure.
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- 9. Demonstrate the ability to make the decision,l based on ]
predacermined criteria, whether to issue KI to I emergency workers and/or the general population. '
- 10. Demonstrate the abilityLeo provide advance- '
coordination of information releases. i i Nodaway ) I
- 1. Demonstrate the ability to continuously monitor and control emergency work exposure, 1
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1.'2.4 State of Nebraska Objectives : A ff State Emergency Operations Center
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'1. Mobilize stafffand activate-facilities. -
- 2. : Implement operational status and' functions to include:
Notification and. follow-up' contacts with State, Federal,:. local governments and private organizations;-
; decision-making and coordination; and, use of visual aids.
. 3. Demonstrate primary and back-up communications with appropriate locations, organizations, and field elements.
'4. Formulate appropriate public.information releas,es; coordinate with IAC, whenl activated,. prior to release;.
c participate in' appropriate rumorontrol functions.
- 5. . Support recovery and' reentry planning', including.
decisions to relax. protective actions. FCP/ EOF (Governor's Authorized Repres'entative)
- 1. Mobilize staff and activate? facilities.
- 2. Implement operational statusLand functions to. include:
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, . decision-making'and coordination; communications;-and, use of visual aids. -
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- 3. Provide. timely notifications to the State'EOC, fiel'd
' elements and local governments, as appropriate, regarding changes in-plant status and emergency. action levels; and, . formulate emergency instructions for the public in coordination with the IAC.
- 4. Based on plant and Rad Health' recommendations determine appropriate protective measures..
.5. Formulate recovery and reentry plans, including decisions.to relax protective actions.
FCP/ EOF / Rad Health (Dose Assessment and Field Team Coordination): 1
- 1. Mobilize staff and activate facilities.
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- 2. Implement operational statusLand functions =to include:
decision-making'and coordination; communications;'and, use of visual aids.
- 3. Mobilize and deploy field monitoring teams in a timely-manner.
I 4. Project dosage to public, based.on plant and field [ data and recommend appropriate protective measures. 1 - 8:
- 5. Monitor and control emergency worker exposure.
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( j 6. Formulate recovery and reentry _ plans, including decisions to relax protective actions,
- 7. Oversee and support Rad Monitoring of evacuees.
Rad Field Teams
- a. Maintain communications with Field Team Coordinator.
- b. Determine ambient radiation levels and measure airporneradioiodineconcentrationsaslowas 10 pCi/cc in the presence of noble gases.
Information Authentication Center __
- l. Mobilize staff and activate facilities.
- 2. Implement operational status and functions to include:
coordination with Utility, Federal, States, and local government agencies and organizations; formulate public information and instructions; and use of visual aids.
- 3. Insure advance coordination of media releases with FCP l f- and MRC and coordinate appropriate rumor control i
(N, functions. The IAC is responsible for issuing news releases'to the EBS station (KFAB) directly regarding immediate protective actions. This function will be simulated at this location. Media Release Center I
- 1. Mobilize staff and activate facilitier.
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- 2. Implement operational status and functions to include: ,
communications, decision-making, advance coordination of news releases; briefing media clearly and , accurately; issuing instructions to public in a timely l manner; and, use of visual aids.
- 3. Establish public hotline and participate in rumor control functions. Public botline will be l demonstrated using existing public service telephones.
Installation of a toll free public hotline will be simulated. Nemaha County Emergency Operations Center
- 1. Mobilize staff and activate facilities.
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- 2. Implement operational status and functions to include:
r'~'N Notifications and follow-up contacts with city and (' ' ' ' )- county government agencies and organizations; decision-making and coordination; and, use of' visual aids. -
- 3. Demonstrate primary and backup communications with appropriate locations, organizations, and field elements.
- 4. Alert the public within the 10-mile EPZ, and issue an instructional message within 15 minutes.
- 5. Formulate and distribute news releases and maintain coordination with the IAC when activated.
- 6. Coordinate local resources and manage an orderly
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evacuation.
- 7. Monitor and control emergency worket exposure.
- 8. Support recovery / reentry planning activities.
Nemaha County Decontamination for Emergency Workers
- 1. Mobilize staff and activate facilities.
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,- ss 2. Implement operational status and functions to include:
( ) monitor and control emergency worker exposure; and,
\s / demonstrate procedures for decontamination of emergency workers, equipment., and vehicles.
Nemaha County Medical
- 1. Mobilize staff and activate facilities.
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- 2. Monitor and control emergency worker exposure.
3, Demonstrate appropriate procedures for handling contaminated individuals. i Otoe County , I l' Emergency Operations Center
- 1. Mobilize staff and activate facilities.
- 2. Implement operational status and functions to include:
notification and follow-up contacts with city and county government agencies and organizations; decision making and coordination; and use of visual aids.
- 3. Demonstrate primary and backup communications with
/ appropriate locations, organizations, and field ! elements.
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' 4. Demonstrate advance coordination of' news releases with f"N IAC.
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'Public (Evacuees). Decontamination Station
-1. Mobilize staff:and activate facilities.
- 2. Implement operational status and functions to include:
. monitor and control emergency workers exposure;
' demonstrate procedures for registering, monitoring, and decontamination of, evacuees, equipment'and vehicles.
Registration & Mass Care.
- 1. Mobilize. staff and activate facilities.
- 2. Demonstrate' communications between EOC and'
-Registration Center. .
- 3. Demonstrate adequacy'of facilities for mass care of evacuees.
1.3 35 FEMA EXERCISE OBJECTIVES
- 1. Demonstrate ability to' mobilize staff-and activate facilities promptly.
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2 '. Demonstrate ability to fully staff facilities and maintain staffing around the clock.
- 3. Demonstrate ability to make decisions and.co coordinate emergency.
activities.
- 4. ' Demonstrate adequacy of facilities and displays and to support emergency operations.
- 5. Demonstrate ability.to communicate.with all appropriate locations,-organizations, and field personnel.
6 '. Demonstrate ability to mobilize and deploy field monitoring-teams in a timely fashion. , 1
- 7. Demonstrate appropriate equipment and procedures for determining
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j ambient radiation. levels. j t
- 8. Demonstrate appropriate equipment and procedures for measurement' 7
of airborne radioiodine concentrations.as low as 10 pCi/cc in the presence of noble gases, y
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- 9. Demonstrate appropriate equipment and procedures for ,
. collections, transport and. analysis of soil, vegetation, . snow, - >
water, and milk. yl
- 10. Demonstrate ability to project dosage toEthe public via plume.
exposure, based on plant and field data, and to' determine. 1 1 ' l J
i l l l appropriate protective measures, based on PAC's, available 1
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shelter, evacuation time estimates,-and all'other appropriate (v / factors.
- 11. Demonstrate ability to project dosage to the public via '.)
ingestion pathway exposure, based on field data, and to ' determine appropriate protective measure, based on PAG's and . other relevant factors. ] l
- 12. Demonstrate ability to implement protective actions for I
ingestion pathway hazards.
- 13. Demonstrate ability to alert the public within the 10 mile EPZ, and disseminate an initial instructional message, within 15 )
minutes. ) l l 14 Demonstrate ability to formulate and distribute appropriate j instructions to the public, in a timely fashion, j 1
- 15. Demonstrate the organization ability and resources necessary to l manage an orderly evacuation of all or part of the plume EPZ. j i
- 16. Demonstrate the organizational ability and resources necessary to deal with impediments to evacuation,' such as inclement j weather or traffic obstructions. i
- 17. Demonstrate the organizational ability and resources necessary
,s to control access to an evacuated area. j 1
's_ / 18. Demonstrate the organizational ability and resources necessary to effect an orderly evacuation of mobility-impaired individuals l
within the plume EPZ, l 19. Demonstrate the organizational ability and resources necessary I to effect an orderly evacuation of schools within the plume'EPZ.
- 20. Demonstrate ability to continuously monitor and control emergency worker exposure.
- 21. Demonstrate ability to make the decision, based on pre-determined criteria, whether to issue KI emergency workers and/or the general population.
- 22. Demonstrate the ability to supply and administer KI once the decision has been made to do so.
- 23. Demonstrate ability to effect an orderly evacuation of onsite personnel.
24 Demonstrate ability to brief the media in a clear, accurate, timely manner.
- 25. Demonstrate ability to provide advance coordination of information released.
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- 26. Demonstrate ability to establish and operate rumor control in a f^N, . coordinated fashion.
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- 27. Demonstrate adequacy of procedures for registration and radiological monitoring of evacuees. -
- 28. Demonstrate adequacy of facilities for mass care of evacuees.
- 29. Demonstrate adequacy of equipment and procedures for decontamination of emergency workers, equipment, and vehicles.
- 30. Demonstrate adequacy of ambulance facilities and procedures for handling contaminated individuals.
- 31. Demonstrate adequacy of hospital facilities and procedures for hanc' .ing contaminated individuals.
32.' Demonstrate ability to identify need for, request, and obtain Federal assistance.
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- 33. Demonstrate ability to' relocate to and operate the' alternate EOF /EOC.
- 34. Demonstrate ability to estimate total population exposure.
- 35. Demonstrate ability to determine and implement appropriate measures for controlled recovery and reentry.
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i A SECT. ION 2.0 EXERCISE INFORMATION 1 l l l i i l 1 i 2 - 16
l 12.0 - EXERCISE INFORMATION 'l s"
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2'.1 ~ EXERCISE PARTICIPANTS
, The' participants in the exercise will include the following:
2.1.1 Nebraska-Public Power District
- 1. Facilities Management and Support Personnel
- a. Control Room (CR)
'b, Technical Support Center (TSC)
- c. Operations Support' Center (OSC)-
- d. Emergency Operations Facility (EOF)
- e. General Office Emergency Center.(GOEC)
- f. Media Release Center-(MRC).
2.1.2 Onsite/Offsite Agencies / Organizations
- 1. Federal
- a. Nuclear Regulatory Commission (NRC)
- b. Federal Emergency Management Agency-(FEMA).
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- 2. State of Nebraska
- a. Health Department
- b. All State agencies simulated at State EOC
- 3. State of Missouri
- a. Health Department
- b. All State agencies will participate at-State EOC 2.2 EXERCISE ORGANIZATION l 1he organization for this exercise will consist of the Exercise Coordinator, the Lead Exercise Controller, .the _ Controller / ~j Evaluators, the Evaluators, L the Observers, the Observer / Evaluators-and the Players as follows:
I 2.2:.1 The Exercise Coordinator ( ) is. responsible for. thel conduct of a' successful post-exercise Controller / Evaluator - De-Briefing and the CNS/NRC critique. He-is: responsible for the conduct of, a successful exercise, L and will' coordinate- , exercise preparations, including : the . development . of' the'
,. scenario and messages. Subsequent to the conduct of- the .
\ exercise, the Exercise ' Coordinator ' will . coordinate the 2 - 17
, .. - - _ - - _- -- - --- - o
preparation of a consolidated evaluation package, and prepare and follow up on an itemized list of corrective actions (O) V recommended as a result of the evaluation and critique. 2.2.2 The Lead Exercise Controller (Bill Keller) is responsible for - the conduct of a successful exercise and will coordinate - exercise preparations including the development of the scenario and messages. The Lead Exercise Controller will ensure the safe conduct of the exercise and is responsible for resolution of any scenario-related inter-facility questions, as well as the assurance that the conduct of the exercise does not adversely impact the operation of the station. The Lead Exercise Controller will coordinate the preparation of a consolidated evaluation package and prepare and follow-up on an itemized list of corrective actions recommended as a result of the evaluation and critique. 2.2.3 The Controller / Evaluators (see Figure 5.1) . are qualified personnel selected to perform functions as follows: A. A Lead Controller / Evaluator is assigned to each emergency. response facility. The Lead Controller / Evaluator is responsible for all Controller / Evaluator, Evaluator, Observer and Observer / Evaluator activities for that facility and, as appropriate, its associated teams. Controller / Evaluators for teams or sub-areas of a facility report to the Lead Controller / Evaluator of that facility, p.
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B. The Controller / Evaluators will deliver " Exercise Messages" to designated players at specified times and places during the exercise , inj ect or deliver contingency messages as required to prompt the appropriate player responce and keep the exercise actions moving according to the scenario, observe the exercise at other assigned locations, and prepare an evaluat. ion. Controller / Evaluators will submit written recommendations to the Lead Controller / Evaluator, who will summarize all comments for submittal to the Exercise Coordinator. The Controller / Evaluators are provided with instructions and evaluation forms in Section 5.0 of this manual. ' 2.2.4 The Evaluators are primarily QA personnel who are assigned to judge the effectiveness 'of participating organizations, personnel, and activities in response to the scenario. They will evaluate performance on the basis of standards or i requirements contained in the appropriate Emergency Plan, Implementing Procedures, Exercise messages, and as described herein (See Section 5.0). 2.2.5 The Observers from Nebraska Public Power District and other organizations may be authorized, on a limited basis, to participate in the exercise for the purpose of observing exercise activity for personal educations. 2.2.6 The Observer / Evaluators are members of the NRC or FEMA l ('j evaluation teams and will have prior knowledge of.the exercise l 2 - 18 L _ - - _ __ _ ._
scenario. At their assigned locations they will observe.the exercise and prepare _an evaluation to be presented at CNS/NRC Of critique as indicated in the Schedule of Events '(see, Figure-6.1). 2.2.7 The Players include CNS and . other Nebraska . Public ' Power District personnel assigned to' perform emergency functions as. described in.the Emergency Plan and Implementing Procedur_es.' Players from offsite organizations and agencies (county,
' State,.and private industry)-are participants in'the exercise, as described' in their respective' emergency plans and standard -
operating' procedures. 2.3 EMERGENCY RESPONSE FACILITIES During the exercise,-the following emergency response' facilities will i be activated to manage, assess and' support the response to the I simulated emergency as required by the scenario.
- 2. 3.1 Control Room (CR)
Emergency assessment and control' is . initially directed from the CR by the Shift Supervisor prior to activation of the TSC. The CR is located in the. Control Building and is equipped.with an emergency bypass ventilation system allowing the CR to.be habitable during Design Basis Accidents (as defined in the CNS' USAR). The CR containe plant instrumentation, ' required b technical drawings, CNS records, and communications equipment. V 4 i In order to' effectively respond to emergency situations, the following communication equipment is available'in the CR: o Telephone . communications consisting of normal PBX, . emergency bypass line, and microwave. o Intercom communications consisting of the Gaitronics , intercom and the ITT intercom (with executive override i capabilities). o Telephone hotlines to the following: NRC (ENS) and the l Nebraska EOC/ Nebraska State Patrol Headquarters. i t o National Warning System (NAVAS). o High and low band radio communications. - 2.3.2 Technical Support Center (TSC) The TSC (Figure-2'.1) is the focal point for onsite emergency ! coordination and for directing and assisting'the Control Room I (CR) during station emergency conditions. The follo' wing l functions are performed in the TSC: s 2 - 19
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- )
o Provide management and technical support to station- ) N operations personnel during an' emergency.. ! o Relieve the reactor operators of ' duties not directly related to reactor system manipulations (e . g . , ' - communications), o Perform Emergency Operations Facility (EOF) f anctions for an ALERT SITE AREA EMERGENCY, or GENERAL EMERGENCY until the EOF becomes. functional and is adequately manned. The TSC is located adjacent to the Control Room. Figure 2.1 provides a layout of the TSC. The TSC is . provided with radiological protection and monitoring equipment to protect personnel under. most conditions, 'the .. exception being core - degradation and leakage to the area above the refueling floor. In . the unlikely event that this type of accident were to occur at-
. CNS, TSC personnel would relocate to the Control Room, the OSC's, and/or the EOF as defined in EPIPs 5.7.7 and 5.7.8.
To ensure adequate radiological protection of TSC-personnel, a radiation monitoring system is provided in the TSC. . This- system consists ' of monitoring equipment dedicated to the TSC, capable of continuous indication of dose rates and airborne radioactivity concentrations, g Local alarms provide early warning to TSC personnel. The TSC ventilation system is comparable to the Control Room ventilation system. Although not seismically'
- qualified, redundant, or automatically. activated, it-does include high efficiency particulate air filters and charcoal filters. System capacity is based on design-basis accident airborne radioactivity lovels, independent of thyroid blocking provisions (potassite iodide) .
An emergency locker, containing the equipment listed in Appendix E of the Emergency Plan, is provided to protect personnel who must.. exit the TSC. .In addition, the locker contains equipment necessery - to provide continued TSC operation during the presence of low level airborne radioactivity or radioactive surface contamination. If the TSC becomes uninhabitable, the TSC Emergency Response functions will be transferred to the Control Room. The personnel manning the TSC aid in determining the cause of the emergency and formulating action plans to mitigate the emergency. To ' facilitate this function, a. set of as-built drawings of the station, schematics and diagrams, technical specifications, station operating procedures, emergency operating procedures, station operating records, p . records needed ' to perform the functions of the EOF when it i is not operational, and a . copy of the Updated Safety 2 - 20
Analysis Report are available to personnel in the TSC f'-] itself or in the adjacent Control Room. V / In addition to the above, the TSC is equipped with the following communications facilities: o NPPD Microwave Link, station intercom system, Lincoln Telephone and Telegraph PBX telephone extensions, sound power phone station intercom system, NRC (ENS)- Hotline, and NRC Health Physics Network (HPN) telephone. o Hotline to Nebraska Emergency Operations Center and NSF Headquarters. o As backup communications, an alternate emergency intercom system which connects the Operations Support Centers, Control Room, and Emergency Operations Facility (EOF). Remote control consoles for both onsite and offsite communications and portable radios are also available. 2.3.3 operations Support Center (OSC) ; j i The OSCs are the assembly and staging areas for.CNS personnel pooled for emergency response assignments. The OSCs provide
,- locations where plant logistic support can be coordinated
( during an emergency. Designated emergency response. personnel (, will report to their assigned OSCs. Three areas within the station are designated as Operations ' f/ipport Centers: A. Hot Chemistry Lab Area - This Operacions Support Center will be manned by members of the station Chemistry and Health Physics staff. v B. Electrical Shop - This Operations Support Center will be 1 manned by members of the station Electrical and Instrument j 6 Control staffs. j l C. Mechanical Maintenance Shop - This Operations Support I Center will 'be manned by Mechanical Maintenance personnel.In an ALERT or a higher classification of emergency, personnel will report to their respective OSCs. .1 If assistance fren one or more of the OSCs is required by I TSC personnel, actions will be coordinated through the l Chemistry and Health Physics Coordinator and the ' Maintenance & OSC Coordinator. located in the TSC. Since the OSCs are the normal work areas for the personnel who will man them, they are adequately sized. Furthermore, ; equipment needed to respond to an emergency is readily ~ available. Communications available to each Operatiana Support [ \ Centers consists of: 2 - 21
?
C_____. 'i
N o Lincbin Telephone and Telegraph PBX: extensions, y station intercom system, and an alternate emergency
'( intercom system to.the:other OSCs, TSC, CR, and EOF.
Portable radios are also available.if requi. red. In the event any_or all of'the OSCs become-uninhabitable, personnel will be relocated to the Security Building Auditorium.
- l. 2.3.4' Emergency Operations Facility (EOF)
The EOF (Figure 2.2) is located adjacent to the Securityz Building, outside the' station security area. .The. EOF is the l
' emergency response facility where the following functions are carried out:
o Management of the offsite. emergency response functions, o Coordination of radiological and environmental assessment. o . Determination of recommended protec tive actions for the public, o Coordination of emergency response activities with federal, state, and local agencies. The EOF has sufficient space to-accommodate CNS emergency - response personnel and representatives from local, state, and ( federal response agencies. I During SITE AREA or GENERAL EMERGENCY conditions,fthe. EOF will be manned. Offsite monitoring teams composed of personnel who are familiar with and trained in the use of survey instruments and equipment will'be dispatched from the EOF. The emergency I locker in the EOF contains material and' equipment needed for offsite monitoring and reentry activities. This equipment includes' procedures, protective clothing, radiation detection instrumentation, dosimetry,- air sampling equipment, ) respiratory ' protection equipment, personnel decontamination supplies, and counting instruments. A list of this equipment is included in EPIP 5.7.1, as well as in Appendix E. Results 21 of offsite surveys and sample analyses will be reported to the: j EOF for evaluation and assessment, . and to aid in the I development of recommendations to offsite authorities. Personnel in the EOF, in addition to those in the TSC, have L the . capability to access meteorological and ' release rate , l information using SPDS to determine the projected downwind i doses. All of this data is prominently displayed in the EOF; { and is readily available to local / state / federal authorities- j for use in-makin6 an independent determination of protective j actions, etc.~ , j
.l I
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I 2 - 22 i E________.____a___._ ____z_ _ _ _ _ _ _ . _ _ _ . _ . _ _ . _ _ _m_.____ _ j
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N Communications available in thh EOF are ss follows:
/' N '
( ) , o Dedicated NRC hotline (ENS) located in the NRC area; the' NRC Health Physics Network (HPN) located in the NRC area; a sufficient number ' of . additional' " plug in" commercial
'j celephones to provide ~ access to onsite and offsite locations'(including state and local emergency operation centers).
o Remote control consoles for radio communications with A inplant and CNS field monitoring teams.
, jl o CNS station intercom system and alternate graergency '
intercom to the CR,' TSC, and OSCs.. , I o Dedicated intere,om" system between the-EOF and the Nebraska State Field Command' Post. j o Hotline to (Nebraska Emerg$ncy Operations Center and NSP Headquarters. ; , o Hotline to COEC and MRC. Document communice. tion. by facsimile transmission equipment I between the EOF, the TSC, the NRC operations center, MRC,- ; COEC, and the State of Hebrasks EOC, is also provided, j (
,~ Information available in the EOF includes'.' Station Technical j ; Specifications, Operating Procedures, Emergency Operating d Procedures, Updated Safety Analysis Report, environs 1 radiological monitoring recoros, and selected as-built j drawings. In additional, copies of state'and local emergency ,q response plans and information pertinent to evacuation is also maintained. .
The Nebraska Field Command Post and the Nebrar,ka State Patrol Mobile Communications Unit will be stationed adjacent to the EOF. Electrical power hookups are available to these vans. Communications between the EOF and the communication vans consists'of direct intercom and telephone via external plug-in at the EOF. Radio communication is also available. 2.3.5 General Office Emergency Center (GOEC[
- l The GOEC (Figure 2.3) is located on the fourth floor of the NPPD General Office Building in Columbus, Nebraska. The GOEC .,
is the emergency response facility which will provide' the Emergency Director, and his staff, the following support:
?
o Engineerin6 and technical support. ; o Licensing, logistics, and legal support. ci Communications and facility equipment support. f'~'g ' g \s,s/ o Public relations support. a 2 - 23 1
' ( v s' i
__.m_____..
1 , ; During a SITE AREA or GENERAL EMERGENCY condition, the GOEC
- l. '/ '% will be manned by senior NPPD personnel and will provide (j support to the Emergency Director as required.
l To assure timely and accurate information is available to the general public, the District has established an Information Authentication Center (IAC). The center, located in the GOEC, l is the primary means for controlling rumors regarding the situation at CNS. Personnel manning the IAC have up-to-date-information on plant status since a direct, continuous line of communication is maintained between the GOEC and the EOF. Furthermore, NPPD Public Affairs personnel, as well as senior technical management personnel are available to respond to any
-questions IAC staff members may have regarding plant status, radiological releases, protective actions, etc.
All calls to the Columbus General Office and the District l offices will be referred to the IAC. Additionally, all calls. I to the telephone number listed in the CNS Emergency Planning Information Booklet are forwarded to the-IAC. Finally, any calls made to CNS will be referred to the General Office. If a consistent number of similar inaccurate statements or questions concerning plant status are received by the IAC staff, they will ensure that a news release, which will clarify or correct any misconception, is developed and issued to the media. T Communications, other than normal telephone facilities l (vj available in the GOEC, consists of: o Dedicated line from the EOF and Media Release Center, j 1 2.3.6 Media Release Center (MRC) The MRC (Figure 2.4), located in Omaha, Nebraska, serves as i the focal point for contact with the media. The MRC will be I staffed by NPPD senior management personnel who will act as j
~
spokesmen for the District. Accurate and timely information - ! will be transmitted to the MRC-from the GOEC and/or the EOF. The MRC is the emergency response facility where the following l functions are carried out: o Media briefings and news releases, o Coordination with Public Information Officers of other agencies. Communications, other than normal telephone facilities available at the MRC, are as follows:
- o. Dedicated .ine from EOF and GOEC.
I U-2 - 24
j 2.4 EXERCISE CONDUCT
/~'g.
(v) 2.4'.1 overview The exercise will simulate an abnormal radiological incident at Cooper Nuclear Station which- will start with the-Notification of Unusual Event class and escalate to a General Emergency. During the course of the exercise, in order to evaluate coordination with appropriate State and local agencies, incidents will arise which require response by offsite emergency response organizations / agencies. The exercise will- also simulate an offsite radiological release which , will require deployment of CNS and state radiological ! monitoring teams. 4 The conduct of the exercise will demonstrate the effectiveness. of participating organizations and personnel, and activities - in support of the appropriate emergency plans and implementation procedures. The simulated emergency will be de-escalated, the recovery phase will be initiated,-and the exercise will then be terminated. 2.4.2 Actions Emergency response actions during the simulated emergency will
-m include: Recognition and classification of emergency
( V) conditions; assessment of onsite/offsite radiological consequences, alert / notification and mobilization of emergency response organizations, implementation of in-plant correct actions, activation / operation of emergency response facilities and equipment, preparation of reports, messages, and record ; keeping; and recommendation and simulated implementation of ' protective actions. " 2.4.3 Communications The exercise vill also demonstrate the effective use of communications systems. The telephone is the primary means of communication and will be attempted first, with radio as a i backup, unless radio is the only means available. Separate , telephone numbers will be used for Controller / Evaluator { communications to prevent the Players from learning the- ' sequence of events in advance. Close coordination between controller / Evaluators is essential. 2.4.4 Players The success of the exercise is largely dependent upon player reaction, knowledge of appropriate emergency plans and implementing procedures, and an understanding of the obj ectives of the exercise. Initial conditions which will ; affect player action or reaction will be provided to the p) players at the time the exercise begins. However, most of the \ V l 2 - 25 i
--m-_ - -. - . _ _ ___ _, _ -_ _ _ - _ _ _ _ _ _ _ - - - _ _ - - , _ - _
1 elements of the exercise play will be introduced through the
'p use of message' forms; _ Players,_therefore,!are responsible for,
('j initiating . actions during. the exerciseL in accordance : with L instructions, responsibilities, and tasks . for their particular- .
- function. Each Player will advise- his/her - !
Controller / Evaluator and Observer / Evaluator prior to ;j
- performing emergency response actions to ensure that the '
Player is credited'for those actions. A'. The Control . Room will be. the central point for . distribution of exercise messages, and is the key to
'i ensuring that the exercise progresse_s on schedule.
-Simulated plant parameters will be provided to the Control
~
Room operators using plant data and status sheets. - Since it is required that the emergency escalate to the General Emergency ' level in' ' order to exercise offsite activities, it_will be necessary to postulate noncredible situr.tions , . The operators will accept the exercise - messages as written. If corrective actions are postulated. that would terminate the emergency, they should be identified to the Lead Exercise Controller, so that the scenario will progress as designed. The exercise Players are expected to " free play" the-scenario to the extent 1 practical. Notifications of, 'and contact with supervisors, plant management, and offisite agencies will- { be made in accordance with the Emergency Plan Implementing j Procedures.
- B. The TSC will be the coordination poir2 for onsite emergency response activities. TSC and 80F personnel will be aware that if the exercise is to proceed as planned, and if-the offsite organizations are to be exercised, it u will be necessary to postulate noncredible situations, i This is done to ensure that all aspects of the onsite and offsite emergency response organizations are tested. TSC and EOF personnel will accept ' exercise messages as written. The intended response is not to explain why a situation could not occur, but to react as though it did.
If corrective actions are postulated that would terminate the emergency, they should be noted to the Lead Exercise Controller. The exercise Players in the TSC ' and EOF are expected to
" free play" the scenario to the extent practical.
Notifications of, and contact with supervisors, plant management, and offsite agencies should be made in . accordance with the Emergency Plan' Implementing Instructions. The scenario is designed to exercise onsite q and offsite emergency response capabilities. Players are reminded not to be excessively concerned'with'- ] the mechanics or cause of the exercise scenario. This j exercise is designed ; to evaluate the Emergency Plan, :) (N Emergency Plan Implementing Procedures, and' emergency. ' f preparedness training program; not the probability,. J Ll
.2 - 26 l
- _ _ - _ - - - _ - _ _ - _ -- - = .
reasonability, or detailed mechanics of the simulated
/]
accident. Additionally, the exercise . is a training
']
\ process for Nebraska Public Power District personnel to practice coordination with outside organizations in a simulated emergency environment. Players should note any areas needing improvement that come to their attention during the exercise and submit them to the appropriate Controller / Evaluator at the conclusion of the exercise.
2.5 EVALUATION AND CRITIQUE The exercise will be evaluated by individuals who have expertise in the activity in their assigned location. The Contro11ar/ Evaluators, Evaluators and Observer / Evaluators will evaluate exercise performance on the basis of requirements contained in the Emergency Plan, Emergency Plan Implementing Procedures and exercise scenario. Controller / Evaluators and Evaluators will prepare evaluation forms and provide recommendations to the Exercise Coordinator. After the Exercise is completed, the Exercise . Coordinator will conduct a Post-Exercise Critique. In addition, the NRC and FEMA Observer / Evaluators will conduct a critique of'onsite emergency preparedness, based on their evaluation of exercise performance. Deficiencies in the Emergency Plan, Emergency Plan Implementing Procedures, the emergency preparedness training program, facilities, equipment and/or other areas will be identified through the critique process. The deficiencies will be documented by the Exercise p Coordinator and corrected by the individuals who havo responsibility in the area of the identified deficiency. The schedule for the et..tiques is included in Section 6.0. O G 2 - 27
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_~~ [ l l l e j SECTION 3.0 TRAVEL INFORMATION l 1 1 4 l 3 - 28
I 1 l.3.0. TRAVEL INFORMATION'~ This section of the Exercise Manual provides information to those individuals fror2 Nebraska Public- Power District, other utilities,~ local, state, federal government, and/or other organizations who will attend the - exercise. l Permission'to observe.the exercise'must be obtained from:
}
Roger Roemmich . Emergency Planning Supervisor-Nebraska Public Power District General Office:
- 1414 15th' Street Columbus, NE 68601 3.1 TRAVEL .
o Air Eppley; Field (80 miles from Cooper Nuclear Station) Omaha, Nebraska o Automobile Directions lfrom Eppley Field Airport: .Take' Abbott Drive south. to U.S.' Highway 6/ Interstate 480.- Proceed east on U.S.
\'
Highway 136. Proceed west on U.S.: Highway'136 to Brownville.
. In Brownville, follow signs.to Cooper Nuclear Station entrance- \s,_,) ' (approximate travel time - 1.5 hours)..
1 Directions from Kansas City, Missouri: Take.. Interstate 291 north to U.S. Highway 136. ' Proceed west-on U.S. Highway 136 to Brownville. In Brownville, follow signs to Cooper Nuclear Station entrance (approximate' travel! time - 2.5 hours).
.3 4
i 3 - 29 :; ' s I 1 .
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l-L_-- _ ___ __: _ _ _ - _ _ - - - - . - _
l 3.2 ' ACCOMMODATIONS 3 l ('~')g ( o Auburn, Nebraska
- Auburn Inn -
U.S. 73-75 North Auburn (402) 274-3143
- Friendship Inn Palmer House Motel U.S. 73-75 l South Auburn (402) 274-3193 )
1
- Grand Central Hotel 1114 J i Auburn .
(402) 274-3148 o Rock Port, Missouri
- Rock Port Inn (Best Western)
I-29 & U.S. 136 Rock Port (816) 744-6282
- Super 8 Motel ,s I-29 & U.S. 136 Rock Port (816) 744-5357 9
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'I 3 - 30 l
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1 PLANT: COOPER LOCATION: Brownville, NE ! ! OCENSEE: Nebraska Public Power District i y J- DIRE !ONS FROM EPPLEY a o EPPLEY V V'. ' FIELD AIRPORT:
""" Take Abbott Onve South to U.S. Highway 6/ interstate s* FIELD ?- 480. Take uS. Highway 6/ Interstate 480 East to interstate i
, 29. Take 129 South to U.S. Highway 136. Take U.S.136 g -
West to Brownville. In Brownville, foitow signs south to !
/
Cooper Nuclear Station entrance. Total approx. oistance I (73 OMAHA /' " 80 "'d*5- I I""E CO
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4.0 REFERENCES
/ ABBREVIATIONS - ACRONYMS / DEFINITIONS 1
1 l l 4 I 1 1 4 - 32 l l i _ _ - _ - _ _ _ _ _ _ _ _ _ _ . _ \
- m. -
1
4.1 REFERENCES
(% 4.1.1 10CFR 50.47, 50.54, Appendix E 4.1.2 44CFR 350.9 4.1.3 NUREG-0654/ FEMA-REP-1, Rev. 1, Criteria for Preparation and - Evaluation of Radiological Emergency Response Plans and ! Preparedness in Support of Nuclear Power Plants-4 .1' . 4 CNS Updated Safety Analysis Report 4.1.5 CNS Emergency Plan, Rev. 2 (3/84) 4.1.6 CNS Emergency Plan Implementing Procedures 4.1.7 General Office Guidelines to the Cooper Nuclear Station Emergency Plan, Rev. 3 (2/85) 4.1.8 CN3 License and Technical Specifications 4.1.9 CNS Piping and. Instrumentation Drawings 4.1.10 Nebraska Radiological Emergency Response Plan for Nuclear ,l Power Plant Incidents (4/83) 4.1.11 Missouri Nuclear Accident Plan (9/84) 4.1.12 Iowa Emergency Plan Change 1 (3/82) 4.1.13 State of Kansas Nuclear Facilities Incident Emergency Response Plan (1981) 4.1.14 Radiological Emergency Response Plan for Nuclear Power Plant Incidents - Nemaha County Change 1.'(3/82) 4,1,15 Radiological Emergency Response Plan for Nuclear Power Plant Incidents - Richardson County Change 1 (3/82) 4.1.16 Radiological Emergency Response Plan for Nuclear Power Plant Incidents - Otoe County Change 1 (3/82) 4.1.17 Atchison County Radiological Emergency Respense Plan (9/84)
-[
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4.2. ABBREVIATIONS - ACRONYMS I 4.2.1 A/E ' Architect Engineer. 4.2.2 AEOF Alternate Emergency Operations' Facility 4.2.3 AGM-N Assistant General Manager - Nuclear - 4.2.4 ALARA. As Low As Reasonably Achievable 4.2.5 A0G Augmented Off Gas-4 . 2 -. 6 ARMS Area Radiation Monitor (s). ] 4.2.7 ATWS Anticipated Transient Without Scram r) 4.2.8 BLUEBIRD NSP Mobile Communication Center 4.2.9 BOP- Balance of Plant ] 4 4.2.10 BRH Bureau of Radiological Health 4.2.11 BWR . Boiling Water Reactor 4.2.12 CAM (s) Constant Air Monitor (s) i 4.2.13 CD Civil Defense 4.2.14- CFR Code of Federal' Regulations 4.2.15 CMT Containment 4.2.16 CNS Cooper Nuclear Station 4.2.17 CR Control Room ' _ 4.2.18 CRUSH State Civil Defense Mobil Communication Vehicle (NB) 4.2.19 DAAS Designated Assembly Area Supervisor 4.2.20; DAS Data Acquisition System 4.2.21 DOE Department of Energy 4.2.22 DOE-IRAP DOE Interagency Radiological Assistance Plan 4.2.23 EAL(s) Emergency Action Level (s)= 4.2.24 EBS Emergency Broadcast System a 4.2.25 ECCS ~ Emergency' Core Cooling System j l [ 4.2.26 4.2.27 ED EOC
- Emergency Dir'ehtor Emergency Operating Center q
4.2.28 EOF Emergency Operations Facility 4.2.29 EPA- Environmental Protection Agency 4.2.30 'EPC Emergency Planning Coordinator 4.2.31 EPI Emergency Plan Information 4.2.32 EPIP(s) Emergency Plan Implementing Procedures (s) 4.2.33 EPZ Emergency. Planning Zone l 4.2.34 ERF(s) Emergency Response Facility (s)- l- 4.2.35 ERP Elevated Release Point l 4.2.36 FEMA Federal Emergency Management. Agency j 4.2.37 FRERP Federal Radiological Emergency Response Plan j 4.2.38 GE General Electric ! l 4.2.39 G0 General Office 4.2.40 GOEC General Office Emergency Center j 4.2.41 GOG(s) General Office Guidelines (s) ' 4.2.42 HP Health Physicist ' 4.2.43 HPCI High Pressure Core Injection' l l 4.2.44 HPN Health Physics Network 4.2.45 HVAC Heating Ventilation Air Conditioning '3 4.2.46 IAC Information Authentification Center . 4.2.47 INPO Institute.of Nuclear Power Operations 4.'2.48 KI Potassium Iodide 4.2.49 LCO Limiting Condition of Operation l 4.2.50 LOCA Loss of Coolant Accident 4.2.51 .LPCI Low Pressure Core Injection j f' sy 4.2.52 LT&T Lincoln Telephone and Te'2 graph
'( 4.2.53 LWR Light Water Reactor q 4 - 34 ]
i i w________-_---___-_-_------_-_--_--- _ - - - - _ - - - - - - - - - - - - - - - -
y .
'4.2.54; MPC : ' Maximum Permissable Concentration
)""N 4.2.55 MRC Media Release Center 4 4.2.56 NAVAS National Warning System
.4.2.57 NPPD: Nebraska Public Power District 4.2.58 NRC Nuclear Regulatory Commission 4 4.2.59 .NSP- Nebraska State Police 4.2.60 OSC. Operations Support. Center.
< 4-.2.61 PAC (s) Protective Action Guide (s) l
'4.2.62 . PAP . Principal Assembly Point 4.2.63 PASS Post Accident Sampling System .
4.2.64 PIO Public Information Officer 4.2.65 PRMS Process Radiation Monitor System 4.2.66 RACA Radiation Access Control Area-4.2.67 RCP . Reactor Coolant Pump 4.2.681 RCS Reactor Coolant System 4.2.69 RHR. Residual' Heat Removal 4.2.70 RM Radiation Manager 4.2.71 RMT Radiation Monitoring Team-4.2.72, SC .Climatronics' Sigma Computer _, 4 . 2.' 7 3 = SEMA State' Emergency Management Agency-(Mo): 4.2.74 SJAE Steam Jet Air Ejector 4.2.75 'SRV Safety Relief. Valve 4.2.76' SWP Special Work Permit 4.2.77 TIC Technical Information Center 4.2.78 TLD Thermoluminescent Dosimeter 4.2.79 TSC Technical Support. Center = 4.2.80 USAR Updated Safety Analysis Report 4.2.81 VFD Volunteer Fire Department
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\ 4.2.82 WSFO- W'enther Service Forecast Office-1 u
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'4.3 DEFINITIONS l
g 4.3.1 ALERT: The' level of emergency classification which' indicates
. % that events are in progress.or have occurred which involve an actual or potentialLdegradation of the level of safety of the -
plant.
- 4. 3. 2 ANTICIPATED TRANSIENT WITHOUT SCRAM (ATWS): Failure'of the reactor control rods to insert into the core upon demand,--
'4.3.3- ASSESSMENT ACTIONS: Actions taken during or after an l'
emergency to obtain and' process information necessary to determine the character.and magnitude of the emergency and to implement specific corrective emergency measures.
4.3.4 CONTAMINATION
-Ing'estion, inhalation, or direct contact with water, air, soil, or tangible objects which are emitting ' ionizing radiation. A. contaminated object has a level of < radioactive material.' adhering to its surface higher than an established limit. 4.3.5 CONTROL ROOM (CR): - The CR, operating under . the direction of - the Control Room Supervisor, is the primary point at which station conditions are monitored and controlled. It is-the point where corrective actions are taken to mitigate an-emergency situation and where the initial assessment and. . classification of an emergency are made.
4.3.6 CONTR0'LLER
A member of the. exercise control group. Each-
, Controller may be 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. j i 4.3.7 CORRECTIVE ACTIONS: Measures taken to reduce the severity of, or terminate.an emergency situation at, or near,-the source of the problem; to prevent an uncontrolled release of- , q radi6 active material; or~to reduce the magnitude of the ! radioactive release.
4.3.8 DECONTAMINATION
The process by which the body or an object t is relieved of radioactive substances. R 4.3.9 DOSE ASSESSMENT: The process of estimating the amount of radiation a person will potentially receive as a result of a radiological release. 4.3.10 DRILL: A supervised event aimed at evaluating, developing, and maintaining skills in a particular operation. - 4.3.11 -EMERCENCY ACTION LEVELS (EALs): Parameters;used to designate' a particular class-of emergency. These parameters-are. s
)
indicators of the emergency's severity orl potential severity 4 and are guides to aid in determining appropriate emergency. ~ _; response measures. 4 .. l 1
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g . 4.3.12- EMERGENCY OPERATIONS CENTER (EOC): An emergency response (~N facility from which government officials exercise direction and control. V) 4.3.13 EMERGENCY' OPERATIONS FACILITY (EOF): The EOF'is the focal point for.overall NPPD management of an emergency at CNS, and is used for the coordination of onsite and offsite radiological emergency operations. When activated, the EOF is under the direction of the Emergency Operations Facility Director, who is responsible.for maintaining continued coordination with governmental authorities regarding radiological consequences of an incident. 4.3.14 EMERGENCY PLANNING ZONE (EPZ): Defined area established around CNS for which emergency planning is set forth in detail. These are the areas in which the_ potential need for protective action (s) is recognized and addressed. EPZs are defined for both the plume and ingestion exposure pathways. 4.3.15 EMERGENCY RESPONSE FACILITY: Any of several onsite and offsite centers which are activated to coordinate eme'rgency actions. Included in this category are the Control Room, Technical Support Center, Operations Support Center, ; Emergency Operations Facility, Alternate Emergency Operations Facility, Media Release Center and State and local Emergency Operations Centers. . 4.3.16 EVALUATOR: A member of the exercise evaluation group. An
. evalualol may serve in a cual capacity as both a Controller d and Evaluator. Each Evaluator may be assigned to one or more activities or functions for the purpose of evaluating, recording, critiquing, and making recommendations for improvements.
4.3.17 EXCLUSION AREA: The area surrounding CNS in which the } Nebraska Public Power District has the authority to determine j all activities, including exclusion or removal of persons and j property from the area during accident' conditions. , j 4.3.18 EXERCISE: An event which tests the overall functions and I capabilities of organizations involved in responding to an j emer[,ency situation. An exercise shall simulate an emergency ' that results in offsite authorities participating?- 4.3.19 GENERAL EMERGENCY: The most severe level of emergency 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. Releare of radioactive material can be reasonably expected to exceed PAG exposure levels offsite. 4.3.20 GENERAL OFFICE EMERGENCY CENTER (GOEC)_: Located at NPPD Headquarters, Columbus, Nebraska. The GOEC will be manned by senior management personnel with authority to commit
'(O \
corporate resources (i.e., manpower, facilities, equipment, information, funds, etc.) to assist the CNS Emergency Response and Recovery organizations. 4 - 37
1 J { 1 I i 4.3.21 INFORMATION AUTHENTICATION CENTER (IAC): That portion of the J (N GOEC, EOF, and MRC where information concerning the emergency ( ) is gathered and coordinated. 4.3.22 INCESTION EXPOSURE PATHWAY: The pathway through which principal exposure would be from the ingestion of contaminated water or foods, such'as milk or fresh j vegetables. The time of potential exposure could range in length from hours to months. The ingestion exposure pathway d Emergency Planning Zone includes the area within a 50-mile radius of CNS. 4.3.23 LOCAL EMERCENCY RESPONSE PLANS: Plans for local governmental ; response to radiological emergencies at CNS (i.e., Nemaha, ' Otoe, and Richardson counties in Nebraska and Atchison county in Missouri). The plans set forth specific responsibilities and procedures for emergency agencies responsible for offsite emergency operations and the protection of the affected population. 4.3.24 MEDIA RELEASE CENTER (MRC): Located in the Omaha-Douglas County building, 1819 Farnam Street, Omaha, Nebraska is the central area for coordinating media releases. The MRC is a fully equipped media staging area, and has sufficient resources to handle TV, radio, etc., personnel. This facility also serves as the Omaha Douglas County Emergency Operations Center, m ( \ , 4.3.25 NOTIFICATION OF UNUSUAL EVENTS: The lowest level of
\s ,) 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.
4.3.26 _0BSERVER: Any individual who is authorized to observe the Exercise, but is not authorized to interact with the players. 4.3.27 OBSERVER / EVALUATOR: A member of either the NRC or FEMA I evaluation team. {
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I 4.3.28 ,0FFSITE: All land and water areas outside the Owner-Controlled Area fence ~ surrounding the CNS. 1 4.3.29 ONSITE: All land and water areas within the Owner-Controlled Area fence surrounding the CNS. 1 4.3,30 OPERATIONS SUPPORT CENTER (OSC): There are three OSC's at i CNS. In the event of an emergency, these centers will serve as staging areas and support bases for emergency personnel. The OSC's are the manpower marshalling points for station personnel awaiting assignment to emergency repair teams, monitoring teams, damage control teams, inplant assignments, or other emergency response activities. 4.3.31 PARTICIPANT: An individual who has some part in the g'~'3 exercise, whether as a Controller / Evaluator, Evaluator, ( 1 Observer, Observer / Evaluator or Player, wJ 4 - 38 u---_i__ _---_. _ _ _ - - - - _ - - - - - - - - - - - - - - - - - - - - - _
r
'4.3.32 PLAYERS: All individuals (CNS, Nebraska Public Power A District personnel, and individuals from offsite . (v )
organizations and agencies) who are assigned to perform functions of the emergency response organization, as described in the appropriate Emergency Plan and Emergency ' Plan Implementing Procedures. 4.3.33 , PLUME EXPOSURE PATHWAY: The pathway through which principal exposure is by whole body exposure to gamma radiation (from the plume and deposited materials) and inhalation exposure (from the passing radioactive plume). The time of potentini exposure could range in length from minutes to days. The Plume Exposure Pathway Emergency Planning Zone includes-the area within a 10-mile radius of CNS. 4.3.34 POPULATION AT RISK: Those persons for whom protective actions would be taken. 4.3.35 PROCESS RADIATION MONITORING SYSTEM: Instrumentation designed to detect abnormal radiation levels in process and effluent pathways and to activate appropriate alarms and controls. 4.3.36 PROTECTED AREA: The area within the Site Boundary encompassed by physical barriers and to which access is controlled for security purposes: 4.3.37 PROTECTIVE ACTIONS: Emergency measures taken to prevent or
,( minimize radiological exposure. These commonly include j
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(/ in-house shelter, evacuation, respiratory protection, and- i thyroid blocking. ! 4.3.38 PROTECTIVE ACTION GUIDES (PACS): The projected radiological
- dose (or dose commitment values) to. individuals in the general public that would warrant protective action against a release of radioactive material. Protective actions are ,
warranted if the dose _ reduction achieved is not offset by i risks associated with taking the protective actions. PAGs are guides used as a decision aid in an actualfemergency i response situation. The PAG does not include the dose that has unavoidably occurred prior to'the assessment. (
Reference:
Manual of Protective' Action Guides and Protective Actions for Nuclear Incidents; as revised June , 1980; EPA-520/2-75-001.) ' 4.3.39 RADIATION ACCESS CONTROL AREA (RACA)t 'Any area in which the general area radiation level is equal to or exceeds 5.0 mrem /hrorradioactiveloosesurfaceentaminatinisequa} 2 to or exceeds 100'dpm/100 cm beta-gamma, or 20 dpm/100 cm alpha activity. ; 4.3.40 RADIOLOGICAL MONITORING TEAMS (RMT's): Two-person teams responsible for monitoring radiation-levels in the environment and co11 acting soil, air, and water samples for (~N laboratory analysis. 4 - 39 w____ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ._ _ _ - a
4.3.41 RECOVERY ACTIONS: Post-emergency actions to restore the ! [] i t station as nearly as possible to its pre-emergency condition.
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V- 4.3.42 SITE AREA EMERGENCY: The level of emergency classification j which indicates that events are in progress or have occurred j which involve actual or likely major failures of plant _
' functions needed for protection of the public. Any relesses ]
of radioactive material are not expected to exceed Protection
]
Action Guide (PAC) exposure levels, except within the Site 1 Boundary. ) 4.3.43 STATE EMERCENCY RESPONSE PLANS: Plans for governmental response to radiological emergencies at CNS (i.e., Nebraska, . Missouri, Iowa, and Kansas). The plan (s) sets forth specific responsibilities and procedures for emergency agencies ; responsible for offsite emergency operations and the protection of the affected population. ( 4.3.44 TECHNICAL SUPPORT CENTER (TSC): The TSC, located adjacent to ! the Control Room, provides space and equipment for emergency response personnel to monitor station conditions, analyze problems, and provide short and long-term technical guidance to the CR and EOF. The TSC contains pertinent technical ! documents and drawings: The habitability of the TSC is-similar to that of the CR.
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SECTION 5.0 CONTROLLER / EVALUATOR INFORMATION l i l l
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~ - - - - - - - - - - - - - - _ _ _ _ _ _ _ _ _ _ _ , _ _ _ _
5.0 CONTROLLER / EVALUATOR CENERAL INFORMATION fx
- (V)- Each controller / Evaluator and Observer / Evaluator should be familiar with the following:
a .~ The basic objectives of the exercise.
- b. The assumptions and precautions being taken.
- c. The exerciso scenario, including the initiating events and . the expected course of-action to be taken,
- d. The various locations that will be involved and the specific items to ,
be observed at those locations. '
- e. The evaluation check lists provided herein, as appropriate.
5.1 PRECAUTIONS AND LIMITATIONS This section provides guidance for all exercise Controller / Evaluators, Evaluators and Observer / Evaluators for the conduct of this exercise. Prior to initiation of the exercise, a briefing will be held to review the entire exercise process with all the exercise Controller / Evaluators, Evaluators and Observer / Evaluators identified in this manual. 5.1.1 Should, at any time during the course of the conduct of this exercise, an actual emergeacy situation arise, all activities
; and communications related to the exercise will be suspended.
( It will be the responsibility of any exercise Controller / Evaluator that becomea aware of an actual emergency to suspend exercise response 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 may notify all other controller / Evaluators to suspend all exercise activities. The Lead Exercise Controller will make a determination at that point whether to continue, suspend, or-terminate the exercise. 5.1.2 Should, at any time during the course of the conduct of this exercise, .an exercise , Controller / Evaluator witness an exercise participant undertake any action which would, in the opinion of the Controller / Evaluator, place either an individual or component in an unsafe condition, the Controller / Evaluator is responsible for intervening in the individual's actions and terminating the unsafe activity immediately. Upon termination of the activity, the Controller / Evaluator is responsible for contacting the Lead Exercise Controller and informing him of the situation. The Lead Exercise Controller will make a determination at that point whether to continue, place a temporary hold on, or terminate the exercise. A 5.1.3 Manipulation of any plant operating systems, valves, breakers, or controls in response to this exercise scenario 5 - 42
4 are only to be. simulated. There is to be no alteration of any plant operating equipment, systems, ' or circuits during 4 tis' response to this exercise scenario. 5.1.4 All repair activities associated'with the exercise scenario- ' will be simulated, with extreme caution exercised around operating. equipment. 5.1.5' All telephone communications, radio transmissions, and public 4
; address announcements.'related to the exercise must begin.and..
. end with the scatement, "This is a ' drill." Should a Controller / Evaluator witness an exercise participant not observing this. practice, it is _ the Controller / Evaluator's responsibility to remind the individual of the need to follow this procedure.
5.1.6 Any motor vehicle. responding in this exercise. whether for medical, rescue, fire fighting, law enforcement,. field monitoring, etc, activities, should observe all . normal operating laws includin8 posted ' speed limits, stop lights / signs, one way. streets, etc. 5.1.7 Should any onsite security actions be required in responsa to this exercise,. exercise participants are to cooperate. as directed by the Security Force, and security representatives are to be prudent and tolerant in their actions. 5.1.8- Exercise participants are to inject as much realism into the , exercise as is consistent with its safe performance; however, i k caution must be used to prevent over reaction. 5.1.9 Care must be taken to prevent any non-participating individuals cho may observe exercise activities from believing that an actual emergency exists, Any axercise Controller / Evaluator who-is aware of~an individual or group of individuals in the immediate vicinity who iny have become alarmed or confused about the situation, should approach that individual or group and explain the nature of:the exercise
'and its intent.
5.1.10 If an Evaluator or Observer / Evaluator is aware of any of the above situations, he or she should immediately identify this to a Controller / Evaluators. 5.2 CONTROLLER / EVALUATOR INSTRUCTIONS 5.2.1 Controller / Evaluators will' position themselves at theirL assigned locations.30 minutes prior to.the activation of the-facility for which they have responsibility. (See Table 5.1) 5.2.2 Communications will be tested prior to; exercise commencement, All ' wa tches and clocks will be synchronized with the Lead
- l. Exercise Controller as part of the communications testing.
5.2.3 All Controller / Evaluators wil?' comply with instructions from the Lead Exercise Controller. 5 , [
7_ , 1 a I 1 5.2.4 Each Controller / Evaluator.will have copies of the messages l
.["' controlling the progress- of the exercise scenario. No l
(' message shall be delivered out of sequence or other than as written unless specifically authorized' by the Lead Exercise
)
j Controller. 5.2.5 Messages controlling the progress of the scenario are noted with a number. Contingency messages are noted with a number followed by the letter "X" (e.g., 10X). Contingency messages are only delivered if certain conditions indicated on the g message are met. j 5.2.6 Each onsite Controller / Evaluator will have copies of plant I data sheets. Data sheets will be distributed only in the Control Room. 5.2.7 Controller / Evaluators will nol provide information to the Players regarding scenario progression or resolution of problems encountered in the course of the simulated emergency. The exercise participants are expected. to obtain information through their own organizations and exercise their own judgement in determinin6 response actions and resolving problems. 5.2.8 Some Players may insist that certain parts of the scenario are unrealistic. The Lead Controller / Evaluators have the sole authority to clarify any questions regarding scenario
,ss content.
5.3 EVALUATION INSTRUCTIONS Each Controller / Evaluator will take detailed notes regarding the progress of the exercise and response of the exercise participants at their assi 5ned locations. Each Controller / Evaluator should carefully, note the arrival and departure times of participants, the times when major activities or milestones occur, and problem areas encountered. 5.3.1 Objectives for Emergency Response Facilities The following general objectives are based on Attachment F of the . Surveillance Procedure 6.3.11.1 of the CNS Operations Manual.
- 1. General Office Emergency Center (GOEC),
- a. Provide support and assistance to CNS emergency team as requested by the Emergency Director and/ or EOF Director,
- b. Provide clearance of NPPD policy statements relating to emergency recovery actions / operations.
- c. Provide engineering and licensing support, Im\
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- 2. Control Room (CR). i
) a. Determination of EAL.
- b. Up-grade or de-escalate EAL.
- c. Notification procedure (State, Federal, Local, CNS essential personnel).
- d. . Follow up information and documentation.
- e. Development and evaluation of alternative 'to terminate / mitigate problem (s),
- f. ' Methods used to stabilize plant and maintain control,
- g. Use of TSC, EOF, and outside technical assistance.
l h. Provisions for providing information ~ to NRC and l' Emergency Response Organizations.
- i. Implementation of CNS EPIPs.
- j. Performing initial, and provisions for on-going. I l habitability surveys.
- 3. Technical Support Center (TSC) m
[ a. Directing and coordinating the CNS Emergency ( Organization.
- h. Communication with and notification of: 3 1
l i 1) Corporate NPPD. j j l 2) Control Room.
- 3) EOF.
l 1
- 4) OSCs. 7 i
- 5) ' Chemistry and Health Physics (onsite and offsite.
teams). I
- 6) NRC, State, and emergency organizations,
- c. Perform initial, 'and provisions for on-going, habitability surveys.
- d. Notification, follow-up information, and documentation.
- e. Providing the' Control Room with technical assistance / transfer of responsibility. ,,
!,JI f. Determining plant condition and EAL classification.
5 - 45
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,~ ,, g. Health Physics - Chemistry and Health Physics Coordinator: / \
- 1) Dispatch of onsite and offsite teams.
- 2) Site evacuation' coordination / decontamination.
- 3) Exposure guidelines, control, and limits.
l 4) Dose projections and PAC determination using EPZ maps, computer dose projection information, available radiation data, trending of-information, and status flow. -
- 5) Coordination with offsite emergency organization.
- 6) Communication with the Emergency Director.
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- 7) Sampling frequency and data use.
- 8) Direction, control, coordination, and practices of repair teams.
- h. TSC Engineering assessment activities:
- 1) Reference material av'ailability.
~N g s 2) Contacts with Engineering and industry support groups.
( )
- 3) Communication with the Control Room
- 1. Mechanical and Electrical Support Maintenance and OSC Coordinator:
.1) Coordinate repair team-entry with Health Physics OSC support.
- 2) Advise personnel of hazarda and necessary precautions.
- j. Fivid transfer of responsibilities from the TSC to EOF and subsequent coordination.
- 4. Operational Support Centers (OSCs),
- a. Communication with appropriate TSC/ EOF Emergency Coordinators.
- b. Accountability of personnel / communications to TSC/ EOF.
- c. Ensure that all equipment and personnel are in a
,s state of readiness.
k, d, Observe and notify TSC/ EOF of any discrepancies. 5 - 46
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,_ e. Performance of habitability surveys. ,i ~/ 6
( / f. Evacuation of all non-essential personnel to designated area. g
]
- g. Dispatch teams providing nececsary ' safety equip' ment guidance cautions / precautions.
- h. Ensure teams have functional communication devices. ',
Emergency Operations Facility (EOF) 5. a .' Fluid transfer of responsibilities to the EOF from . TSC.
- b. Communicate and update notifications with:
sl
- 1) Control Room. /
.?
- 2) TSC.
/
l
- 3) Corporate NPPD.
l 4 , 4) OSCs (Health Physics, Maintenance, and I&C l Electrical). NRC, State, and other emergency organizations.
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5) ( 6) Media.
- c. Evacuation of all non-essential personnel.
- d. Performance of habitability survey.
e, Assumption from TSC of responsibilities for f 7 notifications, dose assessment, and emergency ~ f classification.
- f. Ensuring after plaht is restored to a safe condition that post-emergency plan is activated and offsite personnel and agencies are notif'ad,
- g. Providing verbal and written summary to NPPD y Assistant General Manager - Nuclear and offsite authorities when emergency conditions are resolved within eight hours. .
g y
- 6. Security.
l l a. Ensure stati'on security CAS, SASo and Access Control. 2 # l b. Communications with: , 1 /N i \ s
%~s Y i.
l
- i n
5 - 47 , si n
,j . j
)
.l
- 1) TSC Security / Administrative / Logistics
-['Y <
Coordinator.
? . (O 2) EOF Security / Administrative / Logistics Coordinator. -
- 3) Outside support agencies.
- c. Receipt of necessary emergency update status from the TSC or EOF.
- d. ' Accountability - POS Group. master list is available.
- e. ProvidingCNSpersonnelwithnecessarykogistic support.
l
- 7. Media Release Center (MRC).
- a. Media briefings and news releases.
- b. Coordination with Public Information Officers of-other agencies,
- c. Communication with:
- 1) EOF.
~g 2) COEC.
7
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\ 5.3.2 Emergency Response Facility Checklists Emergency Response Facility checklists are based on Attachment E of the Surveillance Procedure 6.3.11.1 of the CNS operations Manual. These checklists are to be completed
, by the respective controller / Evaluator and provided to the Exercise Coordinator at the conclusion of the exercise. The following is a listing of the checklists, by title; actual checklists are included as Appendix 1 to this section. i 1. Control Room (CR).
- 2. Operational Support Center (OSC).
- 3. Technical Support Center (TSC).
- 4. Onsite Monitoring Team.
- 5. Inplant Rescue and Repair.
- 6. Offsite Monitoring Team.
- 7. Emergency Operations Facility (EOF).
- 8. Ceneral Office Emergency Center (GOEC).
O I 9. Media Release Center (MRC). 5 48
5.3.3 Controller / Evaluator Critique Worksheets [n Controller / Evaluator Critique Worksheets are to be completed i
)' . at each of the respective locations listed below. Upon termination of the exercise, each Controller / Evaluator is to +
provide the completed Worksheet to the Exercise Coordinator. The actual Worksheets are included as Appendix 2 to this section.
- 1. Control Room (CR).
- 2. Technical Support Center (TSC).
- 3. Health Physics OSC.
4.-HP Onsite Radiological Monitoring.
- 5. HP Offsite Radiological Monitoring.
- 6. Electrical /I6C OSC.
7.. Mechanical Maintenance OSC.
- 8. Maintenance and Repair Teams.
. 9. Emergency Operations Facility.
l 10 General Office Emergency Center. I 11 Media Release Center. l l l e O 5 - 49
COOPER NUCLEAR STATION DRESS REHEARSAL EXERCISE t FIGURE 5.1 CONTROLLER / EVALUATOR ASSIGNMENTS FACILITY / ASSIGNMENT CONTROLLER / EVALUATOR Control Room TBA Technical Support Center TBA Emergency Operations Facility TBA Chemistry and Health Physics TBA Electrical / Instrumentation and Control TBA Operations Support Center - Maintenance TBA Radiation Monitoring Teams TBA Repair Teams - Maintenance TBA
- PASS TBA General Office Emergency Center TBA Media Release Center TBA
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<- s i %.s 5 - 50 1
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e 4 i
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f L I 1 I j u i APPENDIX 1 EMERGENCY RESPONSE FACILITIES CHECKLISTS I l i l
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$ - 51 I
i CONTROL ROOM CONTROLLER / EVALUATOR l i (Y Name: Date: j l 1 OBJECTIVES TIME COMMENTS
. 1. Shift Supervisor / Unit Operator response to a simulated alarm (s).
- 2. Shift Superv1sor/ Unit Operators 3 determination of the emergency and its magnitude (Emergency Action Level). i I
- 3. Shift Supervisor to direct the Unit Operator to complete EPIP 5.7.6, _
Attachment "A", and give it to the Operations Communicator.
- 4. Alerting of on-site personnel for l actuation of appropriate Emergency Response Facilities by the Shift )
Supervisor.
- 5. Notification of the Division Manager q of Nuclear Operations. ,1 e 1
[* 6. Timely notification.of and communications with onsite and offsite facilities, agencies, and personnel per EPIP'5.7.6, Attachments "B", "C",
"D", "E", "F", and "C".
- 7. Shift Supervisor performs accountability of Control Room personnel and informs the Security /
Administrative / Logistics Coordinator ! in the TSC (at Alert of higher emergency classification).
- 8. Shift Supervisor directs the Unit Operator to perfom on-going habit-ability survey.
- 9. Unit Operator continues' observation of plant instrumentation applicable to accident scenario.
i
- 10. Continued communications with the Emergency Director concerning new developments pertinent to operation j and control of the plant in the TSC or l
1 EOF /AEOF. ( 11. Initial dose projection, if necessary. l 5 - 52 l
.t.
OPERATIONAL SUPPORT CENTER (OSC) CONTROLLER / EVALUATOR
/~'N (NAME) f }
Name: Date: 'j I J OBJECTIVES TIME COMMENTS
- 1. Performance of the OSC Supervisor in coordinating Emergency Assignment )
duties.
- 2. Use of OSC Supervisor Checklist.
- 3. Performance of arriving emergency response personnel in completing ;
assignments. _ {
- 4. OSCs Supervisor's performance in i procuring accountability of OSC ]
l personnel and reporting to the TSC. ) l l 5. Dispatch of all visitors, contractors, I and non-essential personnel to the l Security Building Auditorium.
- 6. Habitability surveys. l m k
. .[\ l l
\
- 7. Performance of the OSC Coordinators in dispatching Health Physics, Mechanical l
and Electrical maintenance personnel from their respective OSCs.
- 8. Implementation of first aid and rescue ,
work. -
- 9. Notification of and communications with onsite TSC, EOF, and Control Room personnel.
- 10. Maintaining the necessary documentation (Supervisor's log, survey forms, exposure records, etc.).
1 h V ~ 5 - 53 l
i TECHNICAL SUPPORT CENTER (TSC) CONTROLLER / EVALUATOR
/3 Name: Date:
OBJECTIVES TIME COMMENTS
- 1. Ensure all communication devices are operational, i
i
- 2. Completion of initial dose assessment by the Chemistry and Health Physics I
Coordinator.
- 3. Verification of habitability.
- 4. Accountability. _
- 5. Completion of notifications and )
l establishment of communication with 1 onsite and offiste emergency facilities and with onsite and offsite radiological monitoring teams.
- 6. Operation of the computer facility.
- 7. Use of the Radiological Status Board .
p) r and Status Board for Identifying Station Problems. ./ i
'O '
l 8. Maintenance of necessary documentation (logs, checklists, etc.).
- 9. Interaction and support provided to the Control Room.
- , 10. Fluid transition of personnel from the TSC to the EOF.
- 11. Maintain communications with the EOF.
- 12. Performance of the Chemistry and Health Physics Coordinator /
Radiological Manager is dispatching onsite and offiste radiological monitoring teams, l ' N d 5 - 54
ONSITE MONITORING TEAM CONTROLLER / EVALUATOR
,m Name: Date:
OBJECTIVES - TIME COHMENTS
- l. Dispatch of the Onsite Monitoring Team by the Chemistry.and Health Physics Coordinator (TSC).
- 2. Actions by the Onsite Monitoring Team to make initial surveys outside the plant buildings and perimeter fence (check avoidance of entry directly into downwind activity release sector, proceeding with caution, etc.). __
- 3. Proper wearing of protective clothing, respiratory equipment, and personnel monitoring devices.
- 4. Air sampling and survey instrument techniques.
- 5. Communications with the Chemistry and Health Physics Coordinator (TSC).
rs ) 6. Use of survey / decontamination
\.s_,/ techniques at designated control po:nt prior to re-entry into the Chemistry j and Health Physics OSC.
)
i
- 7. Frequent check of, dosimeters to i ascertain exposure.
i l .'
- 1 1
l
,, ~ ~
5 v 5 - 55
l j 4
<~
INPLANT RESCUE CONTROLLER / EVALUATOR p - Q 'Name: Date: j , OBJECTIVES TIME COMMENTS j
- 1. Dispatch of Inplant Survey Team by the-
~ Chemistry and Health Physics Coordinator;(TSC).
- 2. Inplant Survey Team's arrival time at the release. source area to investigate !
further details or radiological i conditions. NOTE _ Observe method (s) of area _ entry, use of portable survey instruments, etc.
- 3. Corrective action taken by personnel dispatched to the area to isolate or reduce hazards.
- 4. Methods used'for assuring all'non-essential personnel have evacuated the area.
] \ 5. .Following control or emergency conditions, an evaluation of methods-used by monitoring personnel in barricading and posting the affected area and preparations for re-entry by personnel.
NOTE Special attention should.be given to-use of protective clothing, -I respiratory equipment, personnel monitoring devices, portable-survey-instruments, and air samplers.- 6, Communication with the Chemistry and . Health Physics Coordinator (TSC).
- 7. -Use of survey / decontamination techniques at designated control point prior to re-entry into the Chemistry and Health Physics OSC.
i
- 8. Frequent checks of dosimeters to ascertain exposure.
5 - 56 i
1 l i 0FFSITE MONITORING TEAM CONTROLLER / EVALUATOR Name: Date: OBJECTIVES TIME COMMENTS
- 1. Timely _ dispatch of the Offsite Monitoring Team by the Chemistry and _.
Health Physics Coordinator / j Radiological Manager (TSC/ EOF). j
- 2. Checking actions of the Offsite y Monitoring Team in proceeding to the j offsite affected area (check avoidance . j I
of activity release sector enroute).
- 3. Ability to find sampling locations (receptor sites).
4 Monitoring team's performance of initial offsite surveys. l l
- 5. Maintenance of appropriate j documentation.
- 6. Use of respiratory equipment as rg appropriate and personnel monitoring 3
[ J devices, l V
- 7. Frequent check of dosimeter to ascertain exposure. )
- 8. Air sampling and portable instrument survey techniques.
- 9. Communications with the Radiological o mager, nr. if the Emergency W erations Tacility is not operation, the Chemistry and Health Physics Coordinator at the TSC, in reporting radiological drita and other pertinent I information. !
- 10. Retrieval of offsite TLDs and air samples from samplers at the Environs Monitoring Stations.
I l
- 11. Delivery of samples to the EOF. I m
5 - 57 L 1------___-_
]
i i i i EMERGENCY OPERATIONS FACILITY (EOF) CONTROLLER / EVALUATOR
.f,\
s sm
/ Name: Date:
)
.)
OBJECTIVES TIME COMMENTS ] l
- 1. Notification and activation of support personnel.
- 2. Establish communications with the TSC, .!
offsite radiological monitoring teams, j and offsite support agencies. ! I
- 3. Use of the Radiological Manager's and- )
EOF Director's checklists. l 1
- 4. Setup' of the EOF and equipment.
- 5. Functional sys. tem checkout of the' -
emergency equipment.
- 6. Performance of EOF personnel I accountability.
- 7. Habitability monitoring (use of area j radiation monitor and constant air j f- monitor). ]>
s_ / 8. Maintenance of necessary documentation (logs, checklists, etc.).
- 9. Escalation of de-escalation of EAL
, classification.
- 10. Use of status boards.
- 11. Provisions for Engineering support.
- 12. Provisions for Administrative support.
- 13. Coordination with vendor and service firms.
- 14. Release of information to the GOEC, MRC, and NRC as well as offsite agencies (accuracy and timeliness).
/*
v 5 - 58
GENERAL OFFICE EMERGENCY CENTER CONTROLLER / EVALUATOR ( ) Name: Date: OBJECTIVES TIME COMMENTS
- 1. Notification and activation of .
personnel and facility.
- 2. Use of General Office Guideline 5.2 and Checklist:
- a. GOEC Director
- b. Public Information Director
- c. Resources Manager
- 3. Establish communications with EOF.
- 4. Maintenance of necessary documentation (logs, reports etc.).
- 5. Use of status boards.
- 6. Provisions for additional support:
- a. Engineering e- s b. Legal.
\~s/)
[ c. Cost / Estimating
- d. Administrative
- 7. Development and release of initial press release. {
- 8. Establish communications with MRC.
- 9. Information Coordinator with EOFAdRC.
- 10. Intra-District Notification.
- 11. Effectiveness of IAC. .)
i
- 12. Use of INFO Nuclear Network, j
- 13. Use of other documents (COCs, E Plan, )
etc.). 4
]
\s_/ ,
5 - 59 ) i
I MEDIA RELEASE CENTER CONTROLLER / EVALUATOR o (
\s_/
I Name: Date: .I OBJECTIVES TIME COMMENTS -l
- 1. Notification and activation of personnel and facility.
- 2. ' Use of General Office Guideline 5.3 and Checklist- l l
1
- a. MRC Public Affairs Advisor i
- b. MRC Public Information Officer !
y c. MRC Security Liaison
- 3. Use of General Office Guideline 5.4. l 1
l 4. Establish communications with: ] 1 i
- a. COEC
- b. EOF i 5. Development and presentation of l l initial media briefing. J 1
[/~~.I 6. Development and release of initial
\s_s/ press release. i
- 7. Development and release of follow-up briefings and releases.
- 8. Maintenance of necessary documents (logs, attachments to GOG 5.4, etc.).
- 9. Effectiveness of IAC/MRC Interface.
l
- 10. Effectiveness of dealing with news media.
1 [\ 5 - 60 \ - _ _ _ _ -
I i i I
-1
( ' e a AFFENDIX 2 CONTROLLER / EVALUATOR CRITIQUE WORK SHEETS 4 5 - 61 1 - ' '-- ' ' i - - _ . .i.i....7shI .. m. ..i.i .. -.i - - -
7 NPPD 1987 ANNUAL EMERGENCY PREPAREDNESS EXERCISE [h CONTROLLER EVALUATOR CRITIQUE WORK SHEETS
\}-
ELECTRICAL /I&C OSC . Time: 0830-1345 Event: Classification of the Emergency condition as:
- a. Alert ;
- b. Site Area Emergency
- c. General Emergency '
l EMERGENCY RESPONSE ACTIVITIES:
- 1. Activate Electrical /I&C OSC
- 2. Coordination with the TSC and the Control Room l
J j
)
ITEMS TO NOTE: l Use of OSC Supervisor's checklist (Attachment C; EPIP 5.7.8) ! Performance of the Electrical /I&C OSC Supervisor in coordinating I l emergency assignment duties, per EPIP 5.7.8
' Perform habitability survey and report results to the Chemistry / Health Physics Coordinator in the.TSC, per EPIP 5.7.8 (g Performance of accountability check i ) Use of Attachment A; EPIP 5.7.10 (d Declaration of OSC operability Briefing of personnel regarding station status and radiological *I conditions' .
Initiation of an OSC log j (continued on next page) l I OVERALL COMMENTS: l
'I J
l l Controller / Evaluator 5 - 62
p .s NPPD 1987 ANNUAL EMERCENCY PREPAREDNESS EXERCISE' t CONTROLLER EVALUATOR CRITIQUE WORK SHEETS s
'J.
i) ELECTRICAL /I&C OSC Time: 0830-1345 (continued) Event: EMERCENCY RESPONSE ACTIVITIES: 8 ITEMS TO NOTE: Provide support, as requested by the Maintenance OSC Coordinator Provide periodic briefings regarding station status and radiological conditions Select personnel for repair activities Briefing of repair personnel by the Electrical /I6C OSC Supervisor-concerning:
- a. Technical instruction - specific activities to be performed-
- b. Specific tools and equipment which may be needed
- c. References to documents, such as procedures, drawings and technical manuals.
Dispatch Electrical /I6C repair personnel to the TSC
'"'N, Maintenance of the OSC log 's_s/
OVERALL COMMENTS: 1
,c s Controller / Evaluator -
s_- 5 - 63 j
l l NPPD 1987 ANNUAL EMERGENCY PREPAREDNESS EXERCISE
'T CONTROLLER EVALUATOR CRITIQUE WORK SHEETS
'[V i
ELECTRICAL /I&C OSC l l Time: 1345-End of Exercise Event: Recovery and reentry EMERCENCY RESPONSE ACTIVITIES:
- l. Deescalation of emergency classification j
- 2. Restoration of emergency equipment !
ITEMS TO NOTE: Provide continuing Electrical /I&C support to the Maintenance OSC Coordinator 3 Provide briefing regarding station status and radiological . conditions i Inventory all emergency equipment and restore equipment to the Emergency Locker , Complete the OSC log i 4 l
) i b) '
(V i l i i OVERALL COMMENTS: 1 1 1 1 I (~x 1 Controller / Evaluator 5 - 64 4 _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ . . _ _ _ _ _ _ _ _ _ _ __ _._._J
NPPD 1987 ANNUAL EMERGENCY PREPAREDNESS EXERCISE I
/' 7 CONTROLLER EVALUATOR CRITIQUE WORK SHEETS 'l \") MECHANICAL MAINTENANCE OSC l
Time: 0830-1345 Event: Classification of the Emergency 'I ; condition as:
- a. Alert
- b. Site Area Emergency j
- c. General Emergency j EMERCENCY RESPONSE ACTIVITIES: _
- l. Activate Mechanical Maintenance OSC l
- 2. Coordination with the TSC and the Control Room f ITEMS TO NOTE:
Use of OSC Supervisor's checklist (Attachment C; EPIP 5.7.8) l Performance of the Mechanical Maintenance OSC Supervisor in i coordinating emergency assignment duties, per EPIP 5.7.8 Perform habitability survey and report results to the Chemistry / Health Physics Coordinator in the TSC, per EPIP 5.7.8 l , ~s Use of Attachment A; EPIP 5.7.10 l l Declaration of OSC operability j ( Briefing of personnel regarding station status and radiological conditions Provide support as requested during the medical emergency Initiate an OSC log Provide support as requested by the Maintenance OSC Coordinator l OVERALL COMMENTS: 1 1
)
,,- g
' i t
v/ Controller / Evaluator 5 - 65 _=_=
l NPPD 1987 ANNUAL EMERGENCY PREPAREDNESS EXERCISE (' CONTROLLER EVALUATOR CRITIQUE WORK SHEETS V MECHANICAL MAINTENANCE OSC Time: 0830-1345 Event: I 1 EMERGENCY RESPONSE ACTIVITIES: j 1 l l 1 l i ITEMS TO NOTE: ] Provide periodic briefings regarding station status and radiological conditions Briefing of repair personnel by the Mechanical Maintenance OSC j Supervisor concerning: i
- a. Technical Instructions - specific activities to be performed
- b. Specific tools and equipment which may be needed _.
- c. References to documents, such as procedures, drawings and technical manuals Dispatch Maintenance Repair personnel to the TSC Maintenance of the OSC log 7s (y
OVERALL COMMENTS: l i { t I (.- Q Controller / Evaluator i 4 5 - 66 l l
i 1 NPPD 1987 ANNUAL EMERGENCY PREPAREDNESS EXERCISE )
' /~_
, CONTROLLER EVALUATOR CRITIQUE WORK SHEETS i
s_. ' MECHANICAL MAINTENANCE OSC 1 Time: 1345-End of' exercise Event: Recovery and reentry EMERGENCY RESPONSE ACTIVITIES: 1
- 1. Deescalation of emergency classification
- 2. Restoration of emergency equipment l ITEMS TO NOTE:
Provide continuing Electrical /I&C support to the Maintenance OSC Coordinator Provide briefing regarding station status and radiological conditions Inventory all emergency equipment and restore equipment to the Emergency Locker Complete the OSC log ( ~s
- i
%)
i i OVERALL COMMENTS: l l I \ I l I l; i 4 fs t v
\s_,/ Controller / Evaluator 5 - 67
.)
l i NPPD 1987 ANNUAL EMERCENCY PREPAREDNESS EXERCISE i
'"'T CONTROLLER EVALUATOR CRITIQUE WORK SHEETS
[V HP ONSITE RADIOLOGICAL MONITORING Time: 1215-1345 Event: Radiological Release EMERCENCY RESPONSE ACTIVITIES:
- 1. Dispatch of onsite and perimeter monitoring teams
- 2. Onsite Radiological Monitoring ,
l l ITEMS TO NOTE: Team members are briefed by HP OSC Supervisor prior to dispatch concerning: jl i a. Survey Instrument i l
- b. Protective clothing / Respiratory protection
- c. Dosimetry
- d. Precautions - Radiation levels / Stay times J l
- e. Air sampling techniques I f. Communications with Chemistry / Health Physics Coordinator in the ;
TSC 1
]
- g. Documentation - necessary forms, maps , etc. [
f'~s g TSC - Chemistry / Health Physics Coordinator dispatches 'onsite ; E i monitoring teams (EPIP 5.7.18 and 5.7.19) i
\s - Team members obtain appropriate:
- a. Protective clothing
- b. Respiratory protection j
- c. Dosimetry ;
- d. Survey instrument - at the EOF l
Team members acquire radios from security personnel at access J control point i Team member (s) perform (s) radio check (s) with CAS/TSC ! l OVERALL COMMENTS: I O 1 (s_,/ Controller / Evaluator 5 - 68
NPPD 1987 ANNUAL EMERGENCY PREPAREDNESS EXERCISE
/'~') CONTROLLER EVALUATOR CRITIQUE WORK SHEETS i'-'/ HP OFFSITE RADIOLOGICAL MONITORING Time: 1215-1345 Event: Radiological Release EMERGENCY RESPONSE ACTIVITIES:
- 1. Offsite/ perimeter boundary radiological. monitoring ITEMS TO NOTE:
Timely dispatch of offsite team members by Chemistry / Health Physics Coordinator in the TSC or Radiological Manager in the EOF to ' Security Building Offsite team members briefed by Ch.emistry/ Health Physics Coordinator concerning: (EPIP 5.7,18) . l a. Appropriate MET data j l b. Protective clothing / Respiratory protection
- c. Dosimetry
- d. Appropriate air sample and survey instrumentation techniques Team members to procure keys to offsite vehicles from security js Team members select two nonessentials to absist with offsite (N monitoring functions Procure emergency kits from. emergency lockers storage area in Security Building l Perform instrument checks, zero dosimeters !
Depart Security Building - turn in badges to Security Guard but { retain dosimeter and TLD l Perform radio checks ! Gas vehicles Inform TSC/ECT that are prepared for dispatch . l b OVERALL COMMENTS: I i js k, _ Controller / Evaluator 5 - 69
L . l' .- l .. L , .1 i
. . NPPD 1987 ANNUAL EMERGENCY PREPAREDNESS EXERCISE 1 CONTROLLER EVALUATOR CRITIQUE WORK SHEETS 'I MAINTENANCE AND REPAIR TEAMS -
l Time: 0730-End of exercise Event: The CR/TSC requests dispatch of team , ,y l i J EMERCENCY RESPONSE ACTIVITIES:
'i
- 1. Direction and control of Maintenance and Repair Teams j
- 2. Response actions by Maintenance and Repair Teams Li ITEMS TO NOTE:
-Familiarity and implementation of EPIP 5.7.15 i Problem _identifD ation, evaluation of options,and discussion between Team c. embers and:
- a. Appropriate OSC Coordinator '
- b. Maintenance and OSC Coordinator '
- c. Chemistry / Health Physics Coordinator
- d. Engineering-Familiarity with Maintenance and Repair Team lockers Verification of equipment operability, if appropriate '
Research of prints, Tech Manuals, procedures and related resource , documents, as' required ' Team briefing prior to entry including:
- a. Actions to be taken
- b. Options to consider
- c. Precautions, both radiological and job related
- d. Desired reports i
- e. Communications methods
- f. Designation of Team Leader -I (continued on next page)
OVERALL COMMENTS:
\
.. j L _i d
^
1 1' l. I !
\ Controller / Evaluator l
.i 5 - 70 n
u__. . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . _ j
l NPPD 1987-ANNUAL EMERCENCY PREPAREDNESS EXERCISE [']) CONTROLLER EVALUATOR CRITIQUE WORK SHEETS MAINTENANCE AND REPAIR TEAMS Time: 0730-End of exercise Event: The CR/TSC requests dispatch
.(continued) of team EMERCENCY RESPONSE ACT1VITIES:
ITEMS TO NOTE: Precautions taken upon entry, as requited j Understanding of messages provided to Maintenance and Repair Team i Leader Use of survey meter and checking of dosimetry based upon station conditions l Actions taken by the Team at the specific job site including: ! I a. Initial troubleshooting steps, if required
- b. Availability and use of resource materials
- c. Identification of spare / replacement parts needed rw d. Precautions to'be taken: e.g., tag out, precautions against electrical shock, etc.
(dI
- e. Use of special tools / adapters /etc.
- f. Manufacturers support requirements
- g. Job estimates associated with time and manpower Transmittal of reports and status information to the TSC Actions taken on progress, as required OVERALL COMMENTS:
O-
\ / Controller / Evaluator 5 - 71 1
1 l
'l i
NPPD 1987 ANNUAL EMERGENCY PREPAREDNESS EXERCISE
/ CONTROLLER EVALUATOR CRITIQUE WORK SHEETS
\ t V HEALTH PHYSICS OSC 1
'l Time: 0830-1345 Event: Classification of Emergency 'i Conditions as:
-l
- a. Alert i
- b. Site Area Emergency j
- c. General Emergency j i
EMERGENCY RESPONSE ACTIVITIES:
- 1. Activate Health Physics OSC j
- 2. Perform onsite survey activites as directed
]
ITEMS TO NOTE: Use of HP OSC Supervisor's checklist (Attachment C; EPIP 5.7.8) Performance of the Health Physics OSC Supervisor in coordinating emergency. assignment duties, per EPIP 5.7.8 Performance of Habitability Survey and reporting of results to the Chemistry / Health Physics Coordinator in the TSC, per EPIP 5.7.8' Performance of accountability check n Use of Attachment A; EPIP 5.7.10 f I Declaration of OSC operability Performance of onsite radiological monitoring activities and follow-up habitability checks, per EPIP 5.7.19, as directed by the Chemistry /HP Coordinator Briefing of Repair Team personnel concerning:
- a. Appropriate ARM readings
- b. Protective clothing / respiratory protection requirements
- c. Access routes available
- d. Precautions - radiation levels /atay times / dosimetry
, e. Survey instruments
~
(continued on next page) ! l OVERALL COMMENTS; - i 4 1 r% , { \ i Q' Controller / Evaluator 1 5 - 72
- -____ j
NPPD 1987 ANNUAL EMERGENCY PREPAREDNESS EXERCISE
/ CONTROLLEREVALUATORCRITIQUEWORKSHEf{S_
'~' HEALTH PHYSICS OSC -i Time: 0830-1345 (continued) Event: Classification _ of Emergency Conditions at!
?
Ta. Alert
- b. ' Site Area Emergency
- c. General Emergency EMERCENCY RESPONSE ACTIVITIES:
- 1. Activate Health Physics OSC l ,
- 2. Perform onsite survey activities as directed ITEMS TO NOTE: -
- f. Communications with Chemistry /plealth Physics Coordinator in the TSC
- g. Documentation /necessary equipment / dosimetry Timely dispatch of teams by Chemistry / Health Physics OSC Supervisor !
as authorized by the Chemistry / Health Physics Coordinator Chemistry Health Physics Coordinator advised of team dispatch l Briefing and dispatch of personnel to the EOF for performance of offsite monitoring activities, per EPIP 5.7.18, if accomplished i (jN-g} during this time frame m Briefing of OSC personnel regarding station and radiological conditions Initiation and maintenance of an OSC log a l I i OVERALL COMMENTS: t i gg _, ) Controller / Evaluator, 5 - 73'
NPPD 1987 ANNUAL EMERGENCY PREPAREDNESS EXERCISE
/,_ j . CONTROLLER EVALUATOR CRITIQUE WORK SHEETS
\
)
HEALTH PHYSICS OSC Time: 0830-End EMERCENCY RESPONSE ACTIVITIES:
- 1. Implement emergency. radiation exposure control, as required
- 2. Perform personnel monitoring and documentation
'3. Perform onsite turvey activities, as directed 4 Provide support to Repair Team activities ITEMS TO NOTE:
Performance of onsite radiological monitoring activities, per EPIP 5.7.19, as directed by the Chemistry /HP Coordinator
- a. Radiological monitorin6 at selected building locations
- b. Personnel monitoring and decontamination activities, per EPIP 5.7.13 Evaluation of radiological hazards in preparation for entry to reactor building Check of exposure records for team members and transmittal to Chemistry / Health Physics Coordinator in the TSC fwg Preparations by Health Physics personnel for entry 1(EPIP 5.7.19)
!v)
~
(continued on next page) OVERALL COMMENTS: i Controller / Evaluator i i l / ., 1 k 5 - 74 1
i
'v.
h- 1 t i NPPD 1987 ANNUAL EMERGENCY PREPAREDNESS EXERCISE i
,/'~'} ,
CONT"0LLER EVALUATOR CRITIQUE WORK SHEETS .
'~'
HEALTH PHYSICS OSC
}
Time: 0830-End (cor.tinued)
~' } / -)
EMERGENCY RESPONSE ACTIVITIES: . s :'
? J'
%)
;./ .i ITEMS TO NOTE: >#
~d,
- a. Zeroing'dosimetors/high and{ low. range .
- b. Source checking; survey. instruments .
- c. Donning protettive clothing
- d. Obtaining appropriate respiratory protection 7-
//
- e. Obtaining necessary forms and essentials (for collecting inplant PASS / environs samples .f 4
Set up of access conttol point for . reentry
. Verification that team members are prepared for entry Informing of the Chemistry / Health Physics Coordinator in the TSC that the team members are prepared to be dispatched 7s Survey and decontaminate, if necessary; team member (s) upon their g ) return to the HP OSC
%~s/ Reports pro /ided to the Chemistry / Health Physics Coord*nator in the TSC regarding team member (s) return, exposure updates for team, members, and Periodic status briefings provided in the OSC Maintenance of the OSC log l
l ' OVERALL COMMENTS: ' I
}
i
)
9. s_, .j Controller / Evaluator 5 - 75
1
)
NPPD 1987 ANNUAL EMERCENCY PREPAREDNESS EXERCISE
/} - CONTROLLER EVALUATOR CRITIQUE WORK SHEETS
')
\
HEALT11 PHYSICS OSC
-]
Time: 1245-End of exercise Event: Deescalation Reentry and Recovery EMERGENCY RESPONSE ACTIVITIES:
- 1. Deescalation of the emergency classification
- 2. Restoration of emergency equipment .)
l ITEMS TO NOTE: Provide continuing HP support to the Chemistry /HP Coordinator Provide briefing regarding station status and radiological i conditions Evaluation of station radiological conditions and transmittal of status to the Chemistry /HP Coordinator Inventory of all emergency equipment and restoration of equipment to the Emergency Locker Complete OSC log l l 1 i 1
)
l OVERALL COMMENTS: l I l , I l l l
,,-~s I
(,
,, ) . Controller / Evaluator j 4
5 - 76 I
NPPD 1987 ANNUAL EMERGENCY PREPAREDNESS EXERCISE f CONTROLLER EVALUATOR CRITIQUE WORK SHEETS
~k MEDIA RELEASE CENTER Time: 1000-End of exercise Event: Classification of the Emergency Condition as a:
- a. Site Area Emergency
- b. General Emergency EMERGENCY RESPONSE ACTIVITIES:
- 1. Activation of MRC
- 2. Coordination with GOEC/ EOF
- 3. Media Interface -
ITEMS TO NOTE: I Activation of MRC, Special emphasis on
- a. Security Activities
- b. Transfer of functios from GOEC to MRC
- c. Use of checklists , i Information flow from GOEC/ EOF. Were all available resources I utilized?
Coordination with state PIO's; was it efficient? continuous? i Press release development. Was it timely? Based upon scenario j [' timeline information? Was it accurate? ; x NPPD/ Media interface. Was it successful? Were all resources that l were available utilized? Documentation. Were briefing packages available? Were sufficient releases available? Were MRC personnel keeping adequate logs? , Effectiveness of " media". Were questions "hard-hitting", l appropriate, and probing? - l l l OVERALL COMMENTS: l l l l 1 l l /"' i i l (w Controller / Evaluator 5 - 77
i
)
'NPPD 1987 ANNUAL EMERGENCY PREPAREDNESS EXERCISE
['"' CONTROLLER EVALUATOR CRITIQUE WORK SHEETS
)
GENERAL OFFICE EMERGENCY CENTER ) 4 Time: 1000 (approx.) Event: Emergency Classification as Site AREA EMERGENCY EMERGENCY RESPONSE ACTIVITIES:
- 1. Notification of CO Personnel i
- 2. Activation of GEOC
- 3. Serve as MRC until Omaha facility is activated- ,
l l ITEMS TO NOTE: l OVERALL COMMENTS: l l l i Controller / Evaluator. l l 4 5 - 78
~
NPPD 1987 ANNUAL EMERGENCY PREPAREDNESS EXERCISE u\ ['~' CONTROLLER EVALUATOR CRITIQUE WORK SHEETS l GENERAL OFFICE EMERGENCY CENTER Time: 1000 (approx.) Event: Emergency Classification as Site AREA EMERGENCY EMERGENCY RESPONSE ACTIVITIES:
- 1. Notification of GO Personnel
- 2. Activation of GEOC
- 3. Serve as MRC until Omaha facility is activated I
ITEMS TO NOTE: . I
'l Initial Notification per GOG 5.1 is executed " Fan Out" process efficient and timely. Are messages understood. ]
j Actuation of GEOC (per GOG 5.3) is executed. Resource specialist is familiar with duties and equipment set-up, Is adequate assistance available? Utilized? j What type of communications checks are made? j Are they considered to be adequate? { pr-~g Transition to emergency support roles. Are all members of GOEC
, aware of their duties? Are check lists beings utilized? Is an \s-} initial briefing conducted? -
Are checklists being utilized? Is an initial briefing Have personnel, who are designated to report to CNS. been dispatched (simulated). , Check with GOEC Resources Manager and ask him to describe what actions would be taken. Verify utilization of , COG's and emergency telephone direct'ory ) Establishment of the IAC. Is it efficient? Are personnel aware of j CNS status? Are initial notifications to NPPD regional managers ; being made? (continued on next page) OVERALL COMMENTS: i
~
n f ( Controller / Evaluator 5 - 79 , i _ _ _ - _ _ - _ _ _ _ - - _ _ _ _ - _ _ - _ - _ _ _ _ _ _ _ _ - _. ____--_-_a
NPPD 1987 ANNUAL EMERCENCY PREPAREDNESS EXERCISE
/ \ CONTROLLER EVALUATOR CRITIQUE WORK SHEETS O GENERAL OFFICE EMERGENCY CENTER Time: 1000 (approx.) (continued) Event:
-EMERGENCY RESPONSE ACTIVITIES:
/
ITEMS TO NOTE: Are TV radio monitoring facilities available Additional support; offsite notifications. American Nuclear.
]
Insurers been contacted? Has any consideration been given to j additional COEC staffing or NED support? . Contact with EOF. Is it established and maintained efficiently? Initial press release (prior to MRC activation). Is it complete? j accurate, and developed in a timely manner? Have appropriate ! checks or clearances been given prior to it being issued? Transfer of Public Affairs / Media interface from GOEC to MRC. Is it efficient, are status reports given? Is communication / coordination G with GOEC/MRC/ EOF acceptable? bJ I GOEC Staff support. Are all GOEC personnel aware of their duties? Do they interact with each other effectively? 1 l l l i l OVERALL COMMENTS: kj Controller / Evaluator 5 - 80 1 L_____-__--___-__--_.-_-_--_---____--. .- . _ - . - - - _ - - . - - - -
NPPD 1987 ANNUAL EMERGENCY PREPAREDNESS EXERCISE g
/'~'\ CONTROLLER EVALUATOR CRITIQUE WORK SHEETS
\) GENERAL OFFICE EMERGENCY CENTER-Time: 1000 (approx.) (continued) Event:
4 EMERGENCY RESPONSE ACTIVITIES: i ITEMS TO NOTE: I Establishment of the IAC. Is it efficient? Are personnel aware of CNS status? Are initial notifications to NPPD regional managers being made? Are TV radio monitoring facilities available? ; 2 Additional support; offsite notifications. ,American Nuclear Insurers been contacted? Has any consideration been'given to , additional GOEC staffing or NED support? i contact with EOF. Is it established and maintained efficiently? 4 l
'r ')
i
%~ ,r OVERALL COMMENTS:
i l l l l i l l l j
'~ s k Controller / Evaluator i
5 - 81 1 I
'l u-- 3
NPPD 1987 ANNUAL EMERGENCY PREPAREDNESS EXERCISE
. [] CONTROLLER EVALUATOR CRITIQUE WORK SHEETS GENERAL OFFICE EMERGENCY CENTER Time: 1215 (approx.) Event: Emergency Classification as a General Emergency EMERGENCY RESPONSE ACTIVITIES:
- 1. Effectiveness of IAC
- 2. Effectiveness of GOEC to support CNS response organization i
ITEMS TO NOTE:
~
Capability of IAC to identify rumors and to cause the issuance of a i press release in an attempt to squelch the rumor . Ability of Public Affairs personnel to respond to a' number of different types of questions from the' general public, COEC Technical Support. Is'it adequate to provide detailed information to NPPD General Manager and Board Members? Is sufficient expertise available to support CNS EOF'and TSC staff? Coordination with MRC/ EOF. Is it being maintained? ( l
%.s 1 i
OVERALL COMMENTS: D ( y\ Controller / Evaluator 5 - 82 _____.______m ..-m.__-
NPPD 1987 ANNUAL EMERGENCY PREPAREDNESS EXERCISE
/'"'N CONTROLLER EVALUATOR CRITIQUE WORK SHEETS
,Y GENERAL OFFICE EMERGENCY CENTER Time: 1345-End of exercise Event: Recovery Planning
'EMERCENCY RESPONSE ACTIVITIES:
- 1. Recovery Organization Effectiveness
- 2. Press Release from GOEC ITEMS TO NOTE:
Transformation of the GOEC Emergency organization into a recovery organization. . Effectiveness of the GOEC Recovery Organization. Does it interface I with the CNS organization? Has adequate consideration been given , to In-House expertise? Does it effectively respond to the questions raised by the NPPD CM (i.e. question from the Nebraska' , Governor)? L Press Release, Is the " deescalation" of the MRC handled
.f efficiently? Is there a release issued from the GOEC?
I I i I OVERALL COMMENTS: ! l l 1 l 1 1 l g_,/ Controller / Evaluator 5 - 83 1
NPPD 1987 ANNUAL EMERGENCY PREPAREDNESS EXERCISE
- I\~ CONTROLLER EVALUATOR CRITIQUE WORK SHEETS
}
'"I TECHNICAL SUPPORT CENTER Time: 0830-0930 Event: Fuel Handling Accident EMERCENCY RESPONSE ACTIVITIES:
- 1. Activate and place TSC in operation.
- 2. Verify that required notifications are made
- 3. Assume responsibility for offsite communications ITEMS TO NOTE:
Reference and. adherence to EPIP 5.7.7 Use of Attachment B; EPIP 5.7.7 (CNS Emergency Planning Coordinator Checklist) Use of Attachment C; EPIP 5.7.7 (TSC Director Checklist) Use of Attachment D; EPIP 5.7.7 (Security / Administrative / Logistics Coordinator Checklist) Use of Attachment E; EPIP'5.7.7 (Maintenance and OSC Coordinator Checklist) Use of Attachment F; EPIP 5.7.7 (Chemistry and Health Physics s Coordinator Checklist) (\d-s ) Use of Attachment C; EPIP 5.7.7.(Engineering Coordinator Checklist) Reference and adherence to EPIP 5.7.10 Use of Attachment A; EPIP 5.7.10 (Individual Accountability Sheet) Use of Attachment B; EPIP 5.7.10 (Personnel Accountability and Assignments Summary) Declaration of TSC operability and assumption of respone!.oilities (Should be accomplished within one hour of ALERT class) Confirmation of the event classification using: Attachment A; EPIP 5.7.1 (Accident Classification Guide Flow Chart) l (continued on next page) 1 I OVERALL COMMENTS: l l i i l l 1
- f%)
( / Controller / Evaluator l 5 - 84 1 L________ _ _ _ _ _ _ _ _ _ _ _ _ . _ . . _ . _ . . _ _
NPPD 1987 ANNUAL EMERCENCY PREPAREDNESS EXERCISE [h CONTROLLER EVALUATOR CRITIQUE WORK SHEETS t ) TECHNICAL SUPPORT CENTER Time: 0830-0930 (continued) Event: Fuel Handling Accident EMERGENCY RESPONSE ACTIVITIES: ITEMS TO NOTE: l Attachment C; EPIP 5.7.1 (Classification Cuide) Br.iefing'of the TSC staff regarding station status
- Reference and adherence to EPIP.5.7.6 -
*Use of Attachment A; EPIP 5.7.6 (Nuclear Power Plant Incident Initial Report)
*Use of Attachment C; EPIP 5.7.6 (Emergency Notification Call checklist)
** Dispatch of' Search and Rescue Team when personnel are missing during Accountability.
** Dispatch of First Aid Team and Health Physics Support to aid the ]'
contaminated, injured victim.
- May have been performed by Control Room
** May continue to be performed from the Control Room
*Use of Attachment E; EPIP 5.7.6 (Emergency Notification Record)
*Use of Attachment F; EP1P 5.7.6 (Nuclear Power Plant Incident Follow-up Information Form)
OVERALL COMMENTS-1 1 I
.: i , Controller / Evaluator I
(g 5 - 85 j
. ~ .
NPPD 1987 ANNUAL EMERGENCY PREPAREDNESS EXERCISE
/' '\ CONTROLLER EVALUATOR CRITIQUE WORK SHEETS \'h TECHNICAL SUPPORT CENTER Time: Oc30 0930 (continued) Event: Fuel Handling Accident P
EMERGENCY RESPONSE ACTIVITIES: ITEMS TO NOTE: Requests for and understanding of status information from the
- Control Room Use of status boards for., display of. station and radiological problems Coordination of assessment and response actions with the Control Room
** Establishment of communication with the NRC on ENS " Hotline" OVERALL COMMENTS: i 1
I I l l l
. ,,/ Controller / Evaluator i
5 - 86 i _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ____1_
? NPPD 1987 ANNUAL EMERCENCY PREPAREDNESS EXERCISE
- /N CONTROLLER EVALUATOR CRITIQUE WORK SHEETS N
\
TECHNICAL SUPPORT CENTER Time: 1000-1215 Event: Recire. Pump Impeller Disintegration with Resultant High Radiation Levels Inplant EMERGENCY RESPONSE ACTIVITIES:
- 1. Assess Core Condition
- 2. Declare SITE AREA EMERCENCY 3, Conduct required notification 4 Initiate activation of EOF
- 5. PASS sample should be taken
- 6. Establish communication with EOF, once activated
. 7. Transfer of offsite communication and radiological monitoring activities to the EOF, once activated -.
ITEMS TO NOTE: Confirmation of the event classification using: Attachment A; EPIP 5.7.1 Attachment B; EPIP 5.7.1 gg ' t.ttachment C; EPIP 5.7.1 { ' Reference and adherence to EPIP 5.7.6 -
\ Use of Attachment C; EPIP 5.7.6 Use of Attachment E; EPIP 5.7.6 Use of Attachment F; EPIP 5.7.6 Reference and implementation of EPIP 5.7.11 Transfer of information and responsibility to TSC "r.elief" personnel by TSC personnel relocating to the EOF Continuing evaluation of response options available (continued on next page)
OVERALL COMMENTS: ,
/ , \ Controller / Evaluator 5 - 87
NPPD 1987 ANN AL EMERGENCY PREPAREDNESS EXERCISE tN CONTROLLER EVALUATOR CRITIQUE WORK SHEETS t' - ' ) TECHNICAL SUPPORT CENTER Time: 1000-1215 (continued) Event: Recirc. Pump Impeller Disintegration with Resultant-High Radiation Levels Inplant EMERGENCY RESPONSE ACTIVITIES: ITEMS TO NOTE: l Direction and control of inplant and onsite radiological activities per EPIP 5.7.19 -.
. Communications with Control Room regarding radiological information Coordination of dose projection activities with the Control Room and EOF per EPIP(s) 5.7.16 and 5.7.17 Reference and adherence to Chemistry Procedure 8.4.1.1 Direction and control of offsite monitoring activities per EPIP 5.7.18 Assessment of offsite radiological hazards per EPIP 5.7.20 f- s
- Communications with NRC on ENS " Hotline" ..
l [ ) Display of radiological conditions on the status board -
\m/ Requests for and understanding of status information from the ,
Control Room j Use of status board for display of station problems 1 Briefing of the TSC Staff regarding station status Transmittal of status information to the EOF and to the OSCs l Coordination of assessment and response actions with the Control Room
*May be performed from the Centrol Room and/or EOF l
)
I 1 OVERALL COMMENTS: ;
?
l' k_ Controller / Evaluator 5 - 88
,____m_____ - _ _ _ _ __ t
'NPPD 1987 ANNUAL EMERGENCY PREPAREDNESS EXERCISE
/N CONTROLLER EVALUATOR CRITIQUE WORK SHEETS k
# TECHNICAL SUPPORT GENTER Time: 1215-1345 Event: _ Loss of Fission Product Barriers and Release of Radioactive Material to the Environment EMERGENCY RESPONSE ACTIVITIES: l
- 1. Declare CENERAL EMERGENCY
- 2. Assess station conditions ITEMS TO NOTE:
Confirmation of the event classification using:
- a. Attachment A, EPIP 5.7.1
- b. Attachment C; EPIP 5.7.1 Reference and adherence to EPIP 5.7.13 ,
l Evaluation of equipment malfunctions and options available to i restore to an operable status i Formation of repair teams and direction and control of repair f-ss activities, per EPIP 5.7.15 , ( ) Reference and adherence to EPIP 5.7.12,.as appropriate, as well as
\s_ / EPIP 5.7.14 Trending of key parameters Assessment as to the extent of core damage by:
- a. Evaluation of Containment High Range Monitor levels
.b. Post Accident Sampling System
- c. Communications with General Electric Company Coordination of dose projection activities with the Control Room and EOF per EPIP(s) 5.7.16 and 5.7.17 Direction and control of inplant and onsite radiological monitoring l activities per EPIP 5.7.19 !
(continued on next page) OVERALL COMMENTS: _ i i
/^%
Controller / Evaluator 5 - 89 i
NPPD 1987 ANNUAL EMERGENCY' PREPAREDNESS EXERCISE
/s CONTROLLER EVALUATOR CRITIQUE WORK SHEETS-l 1
\- TECHNICAL SUPPORT CENTER Time: 1215-1345 (continued) Event: Loss of Fission Product Barriers and Release of Radioactive Material to the Environment 1
EMERGENCY RESPONSE ACTIVITIES: ITEMS TO NOTE: Display of radiological conditions on the status board
- Communications with NRC on the ENS " Hotline" Requests for and understanding of status information from the Control Room Use of status board for display of station problem Briefi.sg of the TSC Staff regarding station status .
Transmittal of status information to the E0f and to the OSCs Coordination of assessment and response actions with the Control Room e-~x .
/ ) *May be performed from the Contro1 Room and/or E0'F N!
~
1 1 OVERALL COMMENTS: I
/'~s
( Controller / Evaluator N.~ 5 - 90 b
NPPD 1987 A'INUAL EMERCENCY PREPAREDNESS EXERCISE- ./~T
! t CONTROLLER EVALUATOR CRITIQUE WORK SHEETS TECHNICAL SUPPORT CENTER Time: 1345-End of exercise Event: Deescalation Recovery and Reentry EMERGENCY RESPONSE ACTIVITIES:
- 1. Recommend deescalation of the emergency classification ITEMS TO NOTE:
Evaluation of station conditions Recommendations associated with deescalation of the emergency classification based upon using:
- a. Attachment A; EPIP 5.7.1
- b. Attachment C; EPIP 5.7.1 Continuing assessment of the extent of core degradation-Direction and control of inplant and onsite radiological monitoring activities, per EPIP 5.7.19 Display of radiological conditions on the status board
- Communication with NRC on the ENS " Hotline" Understanding of and requests for status information from the
( Control Room N_- Use of status board for display of station problems Briefing of the TSC Staff regarding station status Transmittal of status information to the EOF and to the OSCs Coordination of assessment and response with the* Control Room
*May be performed from the Control Room and/or EOF i
i I OVERALL COMMENTS: l l l l f e x
\
(' _,/ Controller / Evaluator-5 - 91 ,
+
. 1 I
J l I NPPD 1987 ANNUAL EMERCENCY PREPAREDNESS EXERCISE CONTROLLER EVALUATOR CRITIQUE WORK SHEETS f -
's CONTROL ROOM .
-]
Time: 0745-0830 Event: Tech. Spec. Shutdown
.l EMERGENCY RESPONSE ACTIVITIES:
- 1. Declare' NOTIFICATION OF UNUSUAL EVENT
- 2. Conduct required notifications ITEMS TO NOTE:
Understanding of message Reference and adherence to EPIP 5.7.1 Use of Attachment A; EPIP 5.7.1 (Accident Classification Guide Flow l Chart) _ _ l' Use of Attachment B; EPIP 5.7.1 (Classification cuide) Use of Attachment C; EPIP 5.7.1 (Classification Guide) Reference and adherence to EPIP 5.7.2 Use of. Attachment A; EPIP 5.7.2 (NOUE Implementing Procedure Checklist) Reference and adherence to EPIP 5.7.6 (N Use of Attachment A; EPIP 5.7.6 (Nuclear Power Plant Incident ( I Initial Report)' bl Use of Attachment C; EPIP 5.7.6 (Emergency Notification Call Checklist) Communications with NRC on ENS " Hotline" OVERALL COMMENTS: l l 1
~
1 l l I i [ Controller / Evaluator l i
~
5 - 92 q
.(,
NPPD 1987 ANNUAL EMERGENCY PREPAREDNESS EXERCISE [ CONTROLLER EVALUATOR CRITIQUE WORK SHEETS k. CONTROL ROOM Time: 0745-0830 Event: Tech. Spec. Shutdown EMERCENCY RESPONSE ACTIVITIES: ITEMS TO NOTE: Use of Attachment A; EPIP 5.7.6 (Nuclear Power Plant Incident Initial' Report) Use of Attachment C; EPIP 5.7.6-(Emergency Notification Call Checklist) Communications with NRC on ENS " Hotline" O ( i I OVERALL COMMENTS:
)
. I
)
.j I
i
/~
r ,
\
v Controller / Evaluator l I 5 - 93 l
l l i NPPD 1987 ANNUAL EMERGENCY PREPAREDNESS EXERCISE l [~N CONTROLLER EVALUATOR CRITIQUE WORK SHEETS - k. U CONTROL ROOM Time: b830-0930 Event: Fuel Handling Accident EMERCENCY RESPONSE ACTIV*ITIES:
- 1. Declare ALERT
- 2. Evacuate the refueling floor
- 3. Conduct required notifications
- 4. Initiate on-shift augmentation
- 5. Establish communication with TSC, once activated
- 6. Transfer of offsite communication function to TSC, once activated 3
ITEMS TO NOTE: Understanding of message Reference and adherence to EPIP 5.7.1 Use of Attachment A; EPIP 5.7.1 Use of Attachment B; EPIP 5.7.1 Use of Attachment C; EPIP 5.7.1 Reference and use of operating / alarm / emergency procedures p Reference and adherence to EPIP 5.7.3 l Use of Attachment A; EPIP 5.7.3 (ALERT Implementing Procedure G . Checklist) Actuation of the Emergency Alarm Paging System Announcement
- Relief of Shift Supervisor as Emergency Director
** Reference and adherence to EPIP 5.7.6 (continued on next page)
OVERALL COMMENTS: l l i i Controller / Evaluator - O 1 5 - 94 I 1 ________.________=-U
, -- 3 u
NPPD'1987 ANNUAL EMERGENCY PREPAREDNESS EXERCISE
'~
CONTROLLER EVALUATOR CRITIQUE WORK SHEETS' CONTROL ROOM Time: 0830-0930 .(continued) Event: Fuel Handling Accident-EMERGENCY RESPONSE ACTIVITIES:
' ITEMS TO NOTE:
l '*Mey have been previously accomplished L
**May be performed by .TSC ;
Use of. Attachment C; EPIP 5.7.6 Use of Attachment D; EPIP 5.7.6 (Station Internal Call List). Use of Attachment E; EPIP 5.7.6 (Emergency Notification Record): Use of Attachment F; EPIP 5.7.6.(Nuclear Power. Plant Incident). Follow-up Information Form) Communications with NRC on ENS " Hotline" , Inter facility communications j f-~s Reference and adherence to EPIP 5.7.10 ]
.p_ Use of Attachment A; EPIP 5.7.10.(Individual Accountability Sheet) {
*** Awareness of personnel accountability. status '
*** Dispatch & Coordination of Search and Rescue Team if personnel missing during Accountability y
*** Shift Supervisor's responsibility unless relieved as Emergency Director OVERALL COMMENTS:
i i i i 1 j Controller / Evaluator I b i
\
5 - 95 ; i
)
NPPD 1987 ANNUAL EMERGENCY PREPAREDNESS EXERCISE i
/N r <
CONTROLLER EVALUATOR CRITIQUE WORK SHEETS ! 1 sN '/ CONTROL ROOM , Time: 1000-1215 Event: Recire. Pump Impeller Disintegration with Resultant I, High Radiation Levels Inplant EMERGENCY RESPONSE ACTIVITIES: 4
- 1. Declare SITE AREA EMERGENCY l
- 2. Conduct required notifications l
ITEMS TO NOTE: Understanding of message Reference and adherence to EPIP 5.7.1 Use of Attachment A; EPIP 5.7.1 ;
*Use of Attachment B; EPIP 5.7.1 1 Use of Attachment C; EPIP 5.7.1 d Conduct evaluar. ion and judgment exercised in recommending a SITE AREA EMERGENCY 3 Reference and adherence to EPIP 5.7.4 I
,- s Use of Attachment A; EPIP 5.7.4 (SITE AREA EMERGENCY Implementing j
[ ) Procedure Checklist) !
\w_ ,/ Actuation of the Emergency Alarm Paging System Announcement Reference to and use of operating / alarm / emergency procedures !
*May be documented by TSC (continued on next page)
OVERALL COMMENTS: ) l l i
,_ Controller / Evaluator
)
s s_ - 2 5 - 96
1 I l l
'NPPD 1987' ANNUAL EMERGENCY PREPAREDNESS EXERCISE J
.f'N CONTROLLER EVALUATOR CRITIQUE WORK SHEETS l
\' ') CONTROL ROOM Time: 1000-1215 (continued) Event: Recire. Pump Impeller Disintegration with Resultant High Radiation Levels Inplant EMERCENCY RESPONSE ACTIVITIES:
ITEMS TO NOTE: __ Transmittal of station status information to TSC l Coordination of assessment and response actions with the TSC
** Communications with NRC on ENS-" Hotline" y Coordination with TSC to insure that required notifications are made J
**May be performed by TSC I
(<~/ s _- s l I i i l OVERALL COMMENTS: l l l lO Controller / Evaluator 5 - 97
t NPPD 1987-ANNUAL EMERGENCY PREPAREDNESS EXERCISE
/ CONTROLLER EVALUATOR CRITIQUE WORK SHEETS-
~ {-
= CONTROL ROOM:
Time: 1215-1345 Event: Loss'of Fission' Product 1 Barriers and Release of Radioactive Material to the-Environment EMERGENCY RESPONSE ACTIVITIES:
- 1. Declare GENERAL EMERGENCY L- .2. Conduct required notifications
'3. Assess statino conditions ITEMS TO NOTE: .
Understanding of message Reference and adherence to EPIP 5.7.1' Use of Attachment lA; EPIP.S.7.1
*Use of Attachment.B;.EPIP 5.7.1 Use of Attachment C; EPIP 5.7.1 -;
Reference and adherence to EPIP 5.7.5. Use of Attachment A; EPIP 5.7.5 (GENERAL EMERGENCY. Implementing Procedure Checklist)-
.Use of Attachment B; EPIP 5.7.5 (Flow Chart for GENERAL EMERGENCi ~
Offsite Protective Decisions) . Condition evaluation and judgment exercised in' recommending a , GENERAL EMERCENCY 1
, Actuation of Emergency Alarm Reference to use of operating / alarm / emergency procedures Transmittal of station status information to TSC and EOF' ,
Coordination of assessment and response actions with the TSC and l EOF j
** Communications with:NRC on ENS " Hotline"- l
*May be documented by TSC OVERALL COMMENTS:
( Controller / Evaluator 5 - 98
1 l l NPPD 1987 ANNUAL EMERGENCY PREPAREDNESS EXERCISE (Ni i CONTROLLER EVALUATOR CRITIQUE WORK SHEETS CONTROL ROOM Time: 1215-1345 Event: Loss of Fission Product Barriers and Release of Radioactive Material to the Environment EMERGENCY RESPONSE ACTIVITIES: j i ITEMS TO NOTE: i l Understanding of message Transfer of station status information to the,TSC cnd EOF Coordination of assessment and resonse with the TSC and EOF 1 j r*% . V l 1 I OVERALL COMMENTS: l l 1 i
~ \s_sl Controller / Evaluator 5 - 99
i o NPPD 1987 ANNUAL EMERGENCY PREPAREDNESS EXERCISE C0!; TROLLER EVALUATOR CRITIQUE WORK SHEETS O)
\
CONTROL ROOM Time: 1345-End of exercise Event: Deescalation Recovery and Reentry l EMERGENCY RESPONSE ACTIVITIES:
- 1. Recommendations re: Deescalation of the Emergency Classification ITEMS TO NOTE:
Transmittal of station status information to the TSC and EOF Coordination of assessment and response actions with the TSC and j EOF - l Evaluation of conditions and recommendations regarding event ; deescalation
^
(%.)T 1 OVERALL COMMENTS: J l l l l i y5 I
'( Controller / Evaluator 5 - 100 l
o l
! .i NPPD 1987 ANNUAL EMERGENCY P:tEPAREDNESS D1RCI'.iE .
[] CONTROLLER EVALUATOR CRITIQUE WORK SHEET _S U EMERGENCY OPERATIONS FACILITY > Time: 1900-1215 Event: Recire. Pump Impeller Disintegration vfth Resultant High Radiation Levels Inplant EMERGENCY RESPONSE ACTIVITIES:
- l. Activate EOF
- 2. Assumption of Offsite Communication and. Radiological Monitoring responsibilities from the TSC ITEMS TO NOTE:
l Reference and adherence to EPIP 5.7.9 ', Use of Attachment C; EPIP 5.7.9 (EOF Director Checklist) Use of Attachment D; EPIP 5,7.9 (GNS Emergency Planning Coordinator Checklist) Use of Attachment E; EPIP 5.7.9 (SAL Manager Checklist) Use of Attachment F; EPIP 5.7".9 (Communications Manager Checklist) Use of Attachment G; EPIP S.7.9 (Radiological Manager Checklist) l Use of Attachment H; EPIP 5.7.9 (Technical Information Coordinator [] Checklist) (j
*Ref.erence and adherence to EPIP 5.7.6
*Use of Attachment A; EPIP 5.7.6 (Nuclear Power Plant Incident Initial Report)
*1fse of Attachment C; EPIP 5.7.6 (Emergency Notification Call List)
*Use of Attachment E, EPIP 5.7.6 (Emergency Notification Record)
*Use of Attachment F; EPIP 5.7.6 (Nuclear Power Plant Incident Follow-up Information Form)
** Establishment of communications with the NRC on dNS " Hotline" Initial briefing of the EOF staff regarding
- station status (continued on next page)
OVERALL COMMENTS: i 1 1 .I h I
\s . Controller / Evaluator 5 - 101
._-____ - _ - _____ _-___A
t :L l l NPPD 1987 ANNUAL EMERCENCY PREPAREDNESS EXERCISE D CONTROLLER EVALUATOR CRITIQUE WORK SHEETS k EMERCENCY OPERATIONS FACILITY Time: 1000-12!.5 (continued) Event: Recire. Pump Impeller Disintegration with Resultant ! High Radiation Levels Inplant i EhERGENCY RESPONSE ACTIVITIES: ITEMS TO NOTE: Declaration of. EOF operability and assumption of responsibilities. (Should be accomplished within one (1) hour of SITE AREA EMERGENCY declaration) Assessment of the need to evacuate non-essential personnel from the. site.and c. coordination thereof,-if not previously-done, per EPIP; 5.7.11. ! Coordination of dose projection activities with the -TSC - Direction and control of offsite radiological monitoring activities-per EPIP 5.7.18 Periodic briefings to offaite teams regarding station status and radiological conditions Assessment of offsite radiological hazards per EPIP 5.7.20 Communications and interface with state representatives in the EOF j regarding: d a. Offsite radiological monitoring' activities
- b. Projected exposures and PAGs -
- c. Media information Display of station and offsite radiological conditions on the designated status boards Requests for and understanding of status'information from the TSC and the Control Room Identification of actual or potential manpower, technical, and/or equipment' support needs,.if any, and coordination with the GOEC
*May have been performed by TSC
**May continue to be performed from Control Room or TSC-OVERALL COMMENTS:
I
- d W
3 Controller / Evaluator 5 - 102
lS ,
,? ) <
J d NPPD 1987 ANNUAL EMERGENCY PREPAREDNESS EXERCISE [' CONTROLLER EVALJMTCR CRITIOUE WORK SHEETS EMERtlh.NCYOPERATIONSFACILITY s Time: '1215 1345 Event: Loss of Fission Product' Barriers and Release of Radioactive Material to the Environment EMERGENCY RESPONSE ACTIVITIES:
- 1. Declare GENERAL EMERGENCY
- 2. Conduct required notification
- 3. Coordination of dose projection and radiological monitoring activities
_ with offsite agencies
- 4. Development of information regarding station status, radiological conditions, and overall. emergency status for transmitul to the media -
- 5. Continuing communications update with offset agencies-ITEMS TO NOTE:
Developing protective action recommendations based upon station status radiologic.21 release, and offsite" radiological monitoring X activities (\
- Communications with NRC on the ENS " Hotline" Communications and interface with state representatives in the EOF regarding:
- a. Offsite radiological monitoring activities 3
- b. Projected exposures and PACS
- c. Media information '
Transmittal of station status and offsite radiological status information to the GOEC and MRC~ J e
*May continue to be perform = 4 from the Control Roon and/or TSC (continued on next page)
OVERALL COMMENTS: m Controller / Evaluator ; 5 - 103 _ _ _ _ _ _ _ _ _ - - _ - _ _ _ - - . _ _ _ _ _ _ _ _ - _ _ . _ _ _ _ _ _ . - _ _ _ __ ._ - . - _ . -- J
NPPD 1987 ANNUAL EMERGENCY PREPAREDNESS EXERCISE
/ \ CONTROLLER EVALUATOR CRITIQUE WORK SHEETS
/-
EMERGENCY OPERATIONS FACILITY-Time: 1215-1345 (continued) Event: Loss of Fission Product Barriers and Release of-Radioactive Material to the Environment-EMERGENCY RESPONSE ACTIVITIES:
- l 1
ITEMS TO NOTE: Periodic staeus briefings to personnel assembled in the EOF Display of station and offsite radiological conditions on the 3 designated status boards l Identification of actual or potential manpower, technological, and/or equipment support needs, if any, and coordination with the GOEC [m')
\._/
3 l OVERALL COMMENTS: Controller / Evaluator 5 - 104
i NPPD 1987 ANNUAL EMERGENCY PREPAREDNESS EXERCISE f CONTROLLER EVALUATOR CRITIQUE WORK SHEETS 1 EMERGENCY OPERATIONS FACILITY Time: 1215-1345 Event: Loss of Fission Prodttet .{
~
Barriers and Release of Radioactive Material to the Environment i EMERGENCY RESPONSE ACTIVITIES: 1
- 1. Coordination of dose projection and radiological monitoring activities with offsite agencies
- 2. Development of information regarding station status, radiological conditions, and overall emergency status for transmittal to the media
- 3. Continuing communications update with offsite agencies
~
ITEMS TO NOTE: , 1 Coordination of dose projection activities with the TSC per EPIPs 5.7.16 and 5.7.17 i Direction and control of offsite radiological monitoring j activities, per EPIP 5.7.18 Periodic briefings to offsite teams regarding station status and O' radiological conditions f ,/ Interpretation and evaluation of offsite radiological sampling ( results and assessment of offsite radiological hazards per EPIP > 5.7.20 Coordination of the dose projection and offsite radiological ; monitoring activities with the forward command centers operated by ! the States of Nebraska, and Missouri Developing protective action recommendations based upon station status, radiological release, and offsite radiolo6 cal1 monitoring : activities !
- Communications with NRC on the ENS " Hotline" (continued on next page)
OVERALL COMMENTS: 9 i
\ i
/ Controller / Evaluator 5 - 105
L
)
NPPD 1987 ANNUAL EMERGENCY PREPAREDNESS EXERCISE O CONTROLLER EVALUATOR CRITIQUE WORK SHEETS EMERGENCY OPERATIONS FACILITY Time: 1215-1345 (continued) Event: Loss of Fission Product ! Barriers and Release of Radioactive Material to the Environment i 1 l EMERGENCY RESPONSE ACTIVITIES: 1 ITEMS TO NOTE: Communications and interface with the state representatives of the j EOF regarding: {
- a. Offsite radiological monitoring activities j
- b. Proj ected exposures and PAGs I
- c. Media information l
*May continue to be performed from the Control Room and/or TSC i O
O l 1 OVERALL COMMENTS: i i l 1 i Controller / Evaluator 5 - 106 l
NPPD 1987 ANNUAL EMERGENCY PREPAREDNESS EXERCISE
,A CONTROLLER EVALUATOR CRITIQUE WORK SHEETS
( l-EMERGENCY OPERATIONS FACILITY Time: 1000-End (continued) EMERGENCY RESPONSE ACTIVITIES: ITEMS TO NOTE: Transmittal of station status and offsite radiological' status information to the GOEC and MRC Periodic status briefings to personnel assembled in the EOF Display of station and offsite radiological conditions on.the designated status boards Requests for an understanding of status information from the TSC and Control Room Identification of actual or potential manpower, technological, and/or equipment support needs, if any, and coordination with the GOEC m
*May continue to be performed from the Control Room and/or TSC OVERALL COMMENTS: i i
I i I I j f% I ' NJ) Controller / Evaluator 5 - 107 i l l
NPPD 1987 ANNUAL EMERGENCY PREPAREDNESS EXERCISE CONTROLLER EVALUATOR CRITIQUE WORK SHEETS EMERGENCY OPERATIONS FACILITY Time: 1345-End of exercise Event: Deescalation Recovery and Reentry EMERGENCY RESPONSE ACTIVITIES:
- 1. Recommend deescalation of the emergency classification
- 2. Coordination of dose projection and radiological monitoring activities l with offsite agencies-
- 3. Development of information regarding station status, radiological conditions, and overall emergency status for transmittal to the media 4 Continuing communication update with offsite agencies ITEMS TO NOTE:
Evaluation of offsite radiological conditions Recommendations associated with deescalation of the emergency classification based upon:
- a. Termination of the radiological release
- b. Offsite radiological conditions p c. Accident Classification Guide Flow Chart l References and adherence to EPIP 5.7.6
[
% Use of Attachment A; EPIP 5.7.6 Use of Attachment C; EPIP 5.7.6 Use of Attachment E; EPIP 5.7.6 i
(continued on next page)- OVERALL COMMENTS: l A i ( Controller / Evaluator 5 - 108
i NPPD 1987 ANNUAL EMERGENCY PREPAREDNESS EXERCISE I [ CONTROLLER EVALUATOR CRITIQUE WORK SHEETS EMERGENCY OPERATIONS FACILITY Time: 1345-End of exercise Event: (continued) - I EMERGENCY' RESPONSE ACTIVITIES: JITEMS TO NOTE
- J Communications and interface with the state representatives of tha l EOF regarding: .
a. Offsite radiological monitoring activities l
- b. Projected exposures and PAGs j Environmental sampling c.
']
- d. Media information .-
l Transmittal of station status and offsite radiological status j l information to the GOEC and MRC Status briefings to personnel in the EOF Display of station and offsite radiological conditions from the TSC rs h and status boards
/ Requests for an understanding of status information from the TSC i
%. /
and Control Room i l l OVERALL COMMENTS: 1
]
l 1
/
t 5 Controller / Evaluator i 5 - 109 l L_-__-__-_-____-__----_---_-_-__---_-___-_ - - --____-______n
i SECTION 6.0 SCHEDULE OF EVENTS-i l l 6 - 110 E-_ ___ _ ^
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V E 7 7 7 7 7 7 E L 8 8 8 8 8 8 U / / / / / / N D E 6 6 6 7 7 8 O E T 0 0 .0 0 0 0 I l l A / / / / / / . T C D 0 0 0 0 0 0 A S 1 1 1 1 1 1 T S 1 l lI llll llllllll lll1lll llllllll1 R 6 A E E L R C U U G N I F R E e P s O i O g c C n r i y e f c x e n E i e r g s B r s e e r m n o E d t g e f a n l r e u i a a i T l f u p r N a e n e B E v i n r - V E r A P e E / B D r re y e r os c r l o fi n o l t c e t o a gr g a r u ne r u e t l i x e l u n a fE m a q o v e E v i C E i s E t
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t SECTION 7.0 i EXERCISE SCENARIO O 9 i I I i i j i O 'C___________________._______. _ _ _ _ _ _ _ .J
i 7.2
.n. COOPER NUCLEAR STATION
-V 1987 EVALUATED EXERCISE SEQUENCE OF EVENTS
-00/15 Initial Conditions established:
The reactor is currently at 100% power, with the core near the end of life, i i Reactor Coolant System Dose Equival'ent- Iodine (DEI) is - 2.0 uCi/gm, and has been slowly increasing over the past . 1 several weeks. CNS/NPPD management has decided to continue operation until the activity reaches a value of 2.5.uC1/gm. The "A" RHR pump is out of service due to replacement of,the coupling. A thirty-day LCO has been in effect since .1200, 10/2/87. The 1A SLC pump is out of service due to replacement of a seized bearing. A seven day LCO has been in effect since 1430, 10/6/87.
. Fuel handling evolutions are in progress. Ceneral Electric personnel are performing inspections of fuel bundles in preparation for shipment.
r' (web
Leak rates: (. Identified: 1.2 gpm Unidentified: 0.4 gpm Weather forecast information is as follows: Winds will be from the south-southwest at 5 to 10 mph, shifting to a more westerly direction by late morning. Chance of precipitation is less than 10%. 00/00 Commence the 1987 Cooper Nuclear Station evaluated emergency preparedness exercise. 00/15 The Control Room receives the completed data sheet from the daily surveillance check required on the 1B SLC pump as a result of the lA pump being out of service. Surveillance test results indicate that the 1B SLC pump is inoperable, and Tech. Specs require that the plant be in hot shutdown within 6 hours. Operators should inform Station management, contact the Load Dispatcher, and begin preparations for shutting down the reactor. The Load Dispatcher will indicate that the grid margin is extremely low, and requests that CNS limit their rate ' of shutdown to 50 MW per hour.until 10:30 a.m., by which time he will have sufficient grid margin to lose CNS. --______.ma.m____m-_-_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ . _ _
00/20 The Shift Supervisor should declare an UNUSUAL EVENT,. in q A) accordance with EPIP 01 (Procedure 5.7.1). Initiating Condition 6.1: "Any Tech. Spec. LCOs_resulting in an immediate shutdown." 01/00 During inspections of spent fuel bundles, a bundle is dropped as it is being raised for inspection. (The bundle bail handle broke and releaseo the bundle). The fuel bundle dropped approximately 12 feet, and landed upright, without impacting I I any of the other stored bundles. The radiation monitor on the 1 1 refueling bridge is alarming, and the operator noticed bubbles rising to the surface of the pool as he evacuated the area, and notified the Control Room. l 1 O The Shift Supervisor should declare an ALERT, based on the fuel 4 i handling accident, and activate the TSC and OSC. l l 01/45 The TSC and OSC should be activated by this time, and assisting l d in the resolution of the fuel handling problem. The "A" RPS MG set trips, causing a half scram and the inboard group 2, 3, 6 isolations. Efforts are initiated to troubleshoot and repair the problem with the MG Eset. After ' power is restored to the "A" RPS bus from the alternate power supply, all of the group isolations are successfully reset, i except the Nor'th Scram Instrument ' Volume (SDIV) drain valve- - (' (CV-34). V} C___________._.___ __ - - - - - - - -
02/00 Annunciators in the Control Room indicate a "not drained" alarm J in the CRD scram discharge instrument volume (SDIV). An operator is dispatched to investigate the problem. The Control Room receives a report that a puddle of water has been found on the floor near the SDIV drain valve. Health i Physics and Maintenance should be contacted to assess and repair the problem. 1 1 02/30 The "A" Recirc pump undergoes a catastrophic failure,'when the .) 1 impeller separates from the shaft. Debris from the impeller and casing enter the core, resulting in damage when it impacts l and abrades the cladding. OV MSIVs isolate on 3X Normal main steam line radiation levels; the reactor scrams; HPCI and RCIC initiate and successfully restore reactor water level; SRVs cycle as required to maintain RPV pressure within the appropriate band. Operators should elect to initiate a cool down to cold shutdown conditions. i The noise 'in the area of the - SDIV startled the individual who was attempting to repair the. leakage on the'SDIV drain valve; he slipped and fell in the puddle o'f water. He will be~found to be contaminated and injured. O d
Fuel cladding damage continues to worsen, due to debris in the (~} (_j core, i Control Room personnel are unable to insert all in-core detectors (IRMs, SRMs) due to obstruction by the Recire, pump i debris. A SITE AREA EMERGENCY should be declared, per EPIP 01 (Procedure 5.7.1), Initiating Condition 2.5: "Dec,raded core with possible loss of coolable geometry". l 03/00 Operators have initiated a cooldown, and established a cooldown rate of approximately'100 degrees an hour. 04/45 Shortly after shutdown cooling is initiated, a water hammer in the RHR Shutdown Cooling (SDC) suction lien causes a 20" tee 1 connection outside the drywell, on the suction side of the General pumps, to rupture. Reactor water level drops very rapidly Emergency below the low low level set points causing groups 2, 3, and 6 isolations. The inboard (M0-18) and outboard (MO-17) SDC isolation valves fail to fully close, resulting in a ~500 gpm leak to the Reactor Building. Reactor Building ARMS alarm and a release to the environment begins via SGTS and the Elevated i Release Point as the 1.ot water (~300*F) flashes to steam. -The ! AC inboard isolation valve (M0-18) has stroked partially shut and is mechanical bound. The DC outboard isolation valve (M0-17) has a blown fuse in the DC power supply to the valve motor. i
. _ . _ _ _ . _ _____a
04/50 Reactor vessel level drops below triple low level (-145.5")
/'~T V causing the RHR pumps and Core Spray pumps to auto start and all RHR valves to align for LPCI injection. RHR suction valve M0-13B, D open normally, providing suction from the' torus for pumps B and D. MO-13C does not open normally due to a breaker i
problem, indicated by the position lights going out, causing
.]
RHR C pump to trip on low suction pressure. Diesel Generator Auto Starts are successful. Reactor level drops to -155" before increasing very rapidly due to injection of two LPCI and two core spray pumps. I 04/55 LPCI/CS have recovered RPV water level. With Isolation valve RHR MO-17 partially shut, the leak rate out of the ruptured SDC
, suction piping has steadied at approximately 500 gpm.
Operators will make preparations for initiating alternate shutdown cooling per procedures, raise RPV level to the main steam lines, and dump coolant to the torus by way of an open l SRV. Decay heat is then dissipated by operating RHR in Suppression Pool Cooling mode. Makeup to the RPV is provided by either a Core Spray or LPCI pump. i 1 05/30 Repair teams are successful in shutting MO-17, the RHR shutdown cooling outboard isolation valve. Operators shut the valve and isolate the ruptured RHR shutdown cooling suction line. 1he release to the environment continues until all the activity has been exhausted from the Reactor Building by the Standby Cas fq Treatment System. Ci ~ _ _ _ - _ - - - - - - - _ _ _ - - - _ - _
i Operators begin raising RPV water level in preparation for O Q initiation c,f alternate shutdown' cooling. 05/45 Pressure controller for the "B" RHR heat exchanger reflects" , I fluctuations in two pressure differential between RHR and RHR l l SW. J 06/00 A catastrophic tube rupture in the "B" RHR Heat Exchanger while the d/p controller was fluctuating causes a major contamination i l problem in the Service Water System and the discharge fiume. Operator actions to reduce the amount of effluent are hindered due to an inability to isolate the Heat Exchanger;.however, ) l with the pumps tripped.the release is minimized. 1 1 O 06/15 Reactor / Suppression Pool System heats up at approximately 4 l 1 6*F/15 minutes with no decay heat removal. In-plant radiation levels have decreased significantly and the ERP release rate is near background since the hot water in the basement has 1 subcooled such that vapor is no longer escaping the break area. l 06/45 Samples confirm contamination of the RHR SW due to the ruptured tube. The release to the Missouri River, however, has been
.. l diluted to below Tech. Spec. limits. j i
Radiation levels within the EPZ have returned to pre-accident background levels as the plume is dispersed. Recovery I
- q. activities are initiated.
l l ___- i
i 07/00 The "C" RHR pump suction valve is opened. Alternate Shutdown Cooling is re-established using the "C" RHR pump through the "A" Heat Exchanger. 08/00 The exercise is terminated. O 4 l
)
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I O j i l l
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i i 4 e SECTION 8.0 MESSAGES AND PLANT DATA SHEETS i O O
g'~'} 1987 Evaluated Exercise Time - C.O.B./1600 N~ ! - . Message Number: I.C. (Day Before) t - 10/06/87 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSACE Message for: CNS/NPPD Management Simulated Plant Conditions: Message:
***THIS IS A DRILL ***
~ ,
As part of tomorrow's exercise, the following conditions are postulated to I exist, as of 1600 today: l o CNS is operating at 100% rated power and has 11 months of equivalent full power operation, i o "A" RHR pump is inoperable due to coupling replacement. A gs thirty-day LCO has been in effect since 0930 9/30/87. The parts
/ should arrive tomorrow (10/8/87), and repairs should be completed-
\s within 8 hours.
o Reactor Coolant Dose Equivalent Iodine activity is 2.0 pCi/gm, and has been slowly increasing over the past several weeks. CNS/NPPD management has decided to continue operation until the activity reaches 2.5 yC1/gm. o RCS leakage is as follows: Identified: 1.2 gpm Unidentified: 0.4 gpm
)
o Inspection of spent fuel bundles in preparation for shipment is j scheduled to begin at 0700 10/7/87. 4 ( ,/ i e
/N 1987 Evaluated Exercise Time - C.O.B./1600 Message Number: 1.C. (Day Before) 10/6/87 t.-
COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE
]
For Controller Use Only: CONTROLLER INFORMATION: o Distribute this information to ' CNS management and'other cognizant personnel to inform them of significant pre _-existing conditions for the scetterio. EXPECTED ACTIONS: o Review and distribute throughout each manager's organization. rh ' (v>) . t N
fe~^s 1987 Evaluated Exercise Time - 0715 t )
'- Message Number: I.C. t - -00/15 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSACE.
Message for: Control Room Simulated Plant Conditions: See attached plant data. Message:
***THIS IS A DRILL ***
The following initial conditions have been postulated for the exercise: o CNS is operating at 100% rated power and has 11 months of equivalent full power operation, o "A" RHR pump is inoperable due to coupling replacement. A thirty-day LCO has been in effect since 0930 9/30/87. The parts should arrive tomorrow (10/8/87), and repairs should be completed f-_s g wichin 8 hours. C ' o Reactor Coolant Dose Equivalent Iodine activity is 2.0 pCL/gm, and has been slowly increasing over the past several weeks. CNS/NPPD management. has decided to continue operation until the activity reaches 2.0 pCi/gm. o RCS leakage is as follows: Identified: 1.2 gpm ; Unidentified: 0.4 gpm ( o The lA SLC pump is out of service due to replacement of a seized bearing a seven-day LCO has been in effect since 1630 10/6/87, o Relocation of three spent fuel bundles is scheduled to occur at 0700 10/7/87. o Current weather is as follows: o Winds from the south-southwest 14 mph, temperature at 59'F. Chance of rain is less than 10%. j A ks _,) : I a l j
f
- 1 i
I A 1987 Evaluated Exercise. Time - 0715 (Cont'd) { V Message Number: 1.C. t - -00/15 (Cont'd) COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Message for: Control Room Simulated Plant Conditions: Message:
***THIS IS A DRILL ***
The following abbreviations are used on the subsequent data sheets to define system / equipment status. o STBY - Equipment / component is aligned for normal auto start signals and if an auto start signal is received, ' the equipment will auto start / realign as designed. g o OPER . Equipment / component is operating at normal pressures and eflow unless other conditions (annunciators,' system flow, V) r pressure, etc.) provided indicate otherwise. o UNAVAIL - Equipment / component is out of service and requires corrective action external to the Control Room before it may be operated. o ISOLATED - Equipment / component is either manually or automatically isolated. The system may be unisolated if the isolation signal is cleared / reset, or appropriate jumpers are installed. o TRIPPED - Equipment / component is in a tripped condition. Trips may be reset if the trip initiation signal is cleared, provided that there is no other cause for the trip. o AVAIL - Equipment / component is in a ' standby configuration, but since it has no auto start capability, it must be manually started / aligned if desired to place it in service. V
I i
-I 1987 Evaluated Exercise Time - 0715
( sessage Number I.C. COOPER NUCLEAR STATION t - -00/15 EMERGENCY PREPAREDNESS EXERCISE PLANT DATA . PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 100% APRM l RHR A UNAVAIL 0 0 REACTOR LEVEL 35"
- NR RHR C STBY 50 REACTOR PRESSURE 1000 psig RHR B STBY 50 0 CORE D/P (psig) 17.25 d 1
0 RER D STBY 50 CORE FLOW (10 lbm/hr) 71.0 6 CS A STBY 50 0 FLOW (10 lbs/hr) l CS B STBY 50 0 FEEDWATER A .4.8 HPCI STBY- 50 0 FEEDWATER B 4.8 l Drywell Pressure .3 (psig) MAIN STEAM A 2.4 Torus Level 0 (inches) MAIN STEAM B 2.4 r OPEN CLOSED MAIN STEAM C 2.4 f ' MSIV 8 0 MAIN STEAM D 2.4 FLOW PANEL 9-4 CRD A 50 (gpm) STATUS PRESS (psig) FLOW (gpm) CRD B AVAIL (gpm) RCIC STBY 50 0 LEVEL PRESS SQUIB PUMPS B RWCU A OPER 1000 100 SLC 75 % 0 (psig) ON Avail RWCU B AVAIL 0 0 RRPA 90 % SPD J M SCELLANEOUS PANELS RRPB 90 % SPD DIESEL GEN A STBY DIESEL GEN B STBY SBGT A STBY SBGT B STBY g-- s DRYWELL COOLING NORMAL {
's TORUS WATER TEMP 80 *F l
1
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1987 Evaluated Exercise Time - 0715 d Message Number: 1.C. t - -00/15 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE For Controller Use Only: CONTROLLER INFORMATION: o Ensure that all drill participants in the Control Room understand the conditions postulated at the beginning of the exercise. o Discuss / define the extent of " free play" and simulation. appropriate for the exercise. EXPECTED ACTIONS: i i
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I (N 1987 Evaluated Exercise Time - 0730 j
\* i Message Number: t - 00/00 1
COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Message for: Control Room Simulated Plant Conditions: See attached Plant Data Message:
***TMIS IS A DRILL ***
Make the following PA announcem'nt: e
)
- We are now commencing the 1987 Cooper Nuclear
" Attention all personnel.
Station Emergency Preparedness Evaluated Exercise. All announcements prefaced by "This is a drill" are intended for designated exercise participants only. If an actual incident occurs, an announcement will be made directing response to the emergency situation." (Repeat) [^)% 4 i
-(
i ('3987 Evaluated Exercise Time - 0730
,,kessageNumber 1 COOPER NUCLEAR STATION t ' - 00/00 i EMERGENCY PREPAREDNESS EXERCISE PLANT DATA +
PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm)' REACTOR POW'RE 100% APRM-RER A UNAVAIL 0 0 REACTOR LEVEL 35" -+ _ NR
)
RHR C STBY 50 REACTOR PRESSURE 1000 psig j i RHR B STBY 50 0 CORE D/P'(psig) 17.25 l 6 RHR D STBY 50 CORE FLOW (10 lba/hr) 71.0 6 CS A STBY 50 0 FLOW (10 lbs/hr) CS B STBY 50 0 FEEDWATER A 4.8 HPCI STBY 50 0 FEEDWATER B 4.8 Drywell Pressure .3 (psig) MAIN STEAM A 2.4 Torus Level 0 (inches) MAIN STEAM B 2.4 /^g OPEN CLOSED MAIN STEAM C 2.4 kU )MSIV 8 0 MAIN STEAM D 2.4 FLOW PANEL 9-4 CRD A 50 (gpm) STATUS PRESS (psig)' FLOW (gpm) CRD B AVAIL (gpm) RCIC STBY 50 0 LEVEL PRESS SQUIB PUMPS B RUCU A OPER 1000 100 SLC 75 % 0 (psig) ON Avail
~
RUCU B AVAIL 0 0 RRPA 90 % SPD MISCELLANEOUS PANELS RRPB 90 % SPD DIESEL GEN A STBY DIESEL GEN B STBY SBGT A STBY SBGT B STBY g DRYWE u C00u No NOR m j k TORUS WATER TEMP 80 *F 1 i i
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RADIATION MONITOR DATA Time - 0730 O t - 00/00 AREA RADIATION MONITORS READING STATION DESCRIPTION (mr/hr) 1 Rx Bldg Fuel Pool Area (SE Sth Floor) 90 2 Rx Bldg Fuel Fool Area (SE Sch Floor) 2 3 Rx Bldg New Fuel Area (SE 5th Floor) 0.03 4 Rx Bldg Rx Water C"eanup Demineralized Area 15 (SW 3rd Floor) 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 1 6 Rx Bldg Neutron Monitor System Index Area 90 (TIP Room 1st Floor) 7 Rx Bldg Neutron Monitor System Drive Mech Ares 2 (SE lst Floor) 8 Rx Bldg Control Rod Hydraulic Equipment Area 0.8 (S 1st Fisor) 9 Rx Bldg Control Rod Hydraulic Equipment Area 9 (N 1st Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) 0.4 11 Rx Bldg RHR Pump Room (SW Quad) 9 12 Rx Bldg RHR Pump Room (NW Quad) 15 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 7 9 14 15 16 Rx Bldg CS Pump Room (SE Quad) Turbine Bldg Turbine Front Standard Turbine Bldg Turbine Bldg Mezz Control Corridor 7 100 0.2 17 Turbine Bldg Turbine Bldg Basement control Corridor 0.04 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 8 19 Turbine Bldg Turbine Bldg Coraensate Pump Area 0.1 20 Control Room Main Control Reom 0.015 21 Grade Level Control Corridor 0.25 , 22 Radwaste Control Room 0.02 ! 23 Radwaste Pump Room 7 24 'Radwaste Basement Equipment Area 3 25 Radwaste Demin Valve Room 2 l 26 Radwaste Conveyor Aisle Operating Area 0.03 27 SPARE 28 Radwaste Lab Area 0.2 29 Centrifuge East 10 30 Centrifuge West 9 Panel 9-02 Personnel Airlock Area 903' .105 R/hr Panel 9-02 Ladder 903' to 2nd Level .070 R/hr
- Alarm OS Offscale O
* . g i
i
~} RADIATION MONITOR DATA Time - 07/30 t - 00/00 1 PROCESS AND VENT MONITORS y PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 1.0 E-3 uCi/sec ERP Stack Normal Eff (RMP-RM sA) 5.5 E-1 uCi/sec ERP Stack High Range (RMP-RM-3B) 0 uCi/sec Turbine Bldg Vent Eff (RMV-RM-20A). 1.5 E 3 uCi/sec Turbine Bldg High Range (IsMV-RM-20B) 0 uCi/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 1.0 E-3 uCi/sec RW/ARW Bldg High Range (RMV RM-30B) 0 uCi/sec.
PANEL 9-10 Mn. Stm. Rar' Monitor Ch. Al, B1 300 mR/hr 350 mR/hr Ch. A2, B2 300 mR/hr 260 mR/hr SJAE Off Gas Log Rad Monitor Ch. A,.B 35 mR/hr 25 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hr. 0.6 mR/hr Service Water 10 cps ( Reactor Equipment Cooling 20 cps ( i 1
~
l I xj
1987 Evaluated Exercise Time - 0730 Message Number: 1 t - 00/00 .I l l COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE For Controller Use Onlyt CONTROLLER INFORMATION: o Ensure that the PA announcement is made. _ EXPECTED ACTIONS: 1 i l 1 i j I l l 1 I
)
i O , l l I _ --__________--a
q 1987 Evaluated Exercise . Time - 0745 Message Number: 2 t - 00/15 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE 1 Message for:- Centrol Room Simulated Plant Conditions: See attached. Plant Data Message: -
***THIS IS A DRILL ***
See the attached Surveillance Sheet. O . i l l 1 4 1 l c____________________.__E.________________________________
, O 1,987 Evaluated Exercise Time - 0745 .g 1 y dessage Number 2 COOPER NUCLEAR STATION t - 00/15 EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 100% APRM 1
RHR A UNAVAIL 0 0 REACTOR LEVEL 35"
- NR RHR C, STBY 50 REACTOR PRESSURE 1000 psig RHR B J TBY 50 0 CORE D/P (psig) 17.2'5 6
RHR D STBY 50 CORE FLOW (10 lbm/hr) 71.0 0 CS A STBY 50 0 FLOW .(10 lbs/hr) CS B STBY 50 0 FEEDWATER A 4.8 HPCI. STBY 50 0 FEEDWATER B 4.8 Drywell Pressure .3 (psig) MAIN STEAM A 2.4 Torus Level 0 (inches) MAIN STEAM B 2.4
/ i OPEN CLOSED MAIN STEAM C 2.4 MSIV 8 0 MAIN STEhM D 2.4 FLOW PANEL 9-4 CRD A 50 (gpm)
STATUS PRESS (psig) FLOW (gpm) CRD B AVAIL (gpm) RCIC STBY 50 0 LEVEL PRESS SQUIB PUMPS RWCU A OPER 1000 100 SLC 75 % 0 (psig) ON UNAVAIL j 1 RWCU B AVAIL 0 0 i RRPA 90 % SPD MISCELLANEOUS PANELS RRPB 90 % SPD DIESEL GF'; A STBY l DIESEL CEN B STBY SBGT A STBY l SBGT B STBY DRYWELL COOLING NORMAL O> TORUS WATER TEMP 80 *F
)
l i
0 8 O 8 I I
= = 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 8 6 8 6 2 0 2 0 e t
)
4 1 12 0 1 . 4 ) F 1 1 m ig 0 O i s ( T p e
. ( r e t u
r u a r s s e e p r m P 5 e 1 r o - T t s c u a r e o R T l 0 3 E - S I C R M N E 0 O X 0 5 0 0 0 5 0 0 0 5 0 0 5 0 0 T E I 4 2 0 2 1 1 + - 1 1 2
+ + - - - 2 1 1
+ + -
A SS ) T E n 0 ) n S i ( N A i ( R A D E T A l e v l e v e E L AR D L L e hG
~
( C U E P S DP t r o c s u r N R S a 5 o R P e T 1 E Y R P C O N O E C G R E 0 M 3 E ' 1 3
)
0 0 0 0 M 0 8 6 0 0 0 0 0 d 0 R 1 7 6 5 4 3 2 1 P 0 - . A
)
% i g
G s p V ( ( A e r e r u s i s e 5 s c w 1
- e r o r e P P x r l E o l e
t d c w t e : a y a e r N1 l u a e R 0 3 D v g E a 7 s 8 s 9 e 1 M
[N i ) RADIATION MONITOR DATA Time - 0745 t - 0/15
%/
AREA RADIATION MONITORS READING STATION DESCRIPTION (mr/hr) 1 Rx Bldg Fuel Pool Area (SE.Sth Floor) 90 2 Rx Bldg Fuel Pool Area (SE 5th Floor) 2 3 Rx Bldg New Fuel Area (SE Sth Floor) 0.03 4 Rx Bldg Rx Water Cleanup Demineralized Area 15 (SW 3rd Floor) 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 1 6 Rx Bldg Neutron Monitor System Index Area. 90 (TIP Room ist Floor) 7 Rx Bldg Neutron Monitor System Drive Mech Ares 2 (SE lst Floor) , ! 8 Rx Bldg Control Rod Hydraulic Equipment Area 0.8 (S ist Floor) 9 Rx Bldg Control Rod Hydraulic Equipment Area 9 (N lst Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) 0.4 11 Rx Bldg RER Pump Room (SW Quad)- 9 12 Rx Bldg RHR Pump Room (NW Quad) 15 13 Rx Bldg RCIC/CS Pump Room (NE Quad) p -~s
. 7 , 14 Rx Bldg CS Pump Room (SE Quad) 7 15 Turbine Bldg Turbine Front Standard 100 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.2 17 Turbine Bldg Turbine Bldg Basement Control Corridor 0.04 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 8 19 Turbine Bldg Turbine Bldg Condensate Pump Area 0.1 20 Control Room Main Control Room 0.015 21 Grade Level Control Corridor 0.25 22 Radwaste Control Room 0.02 23 Radwaste Pump Room 7 24 Radwaste Basement Equipment Area 3 25 Radwaste Demin Valve Room 2 26 Radwaste Conveyor Aisle Operating Area 0.03 27 SPARE 28 Radwaste Lab Area 0.2 29 Centrifuge East 10 30 Centrifuge West 9 Panel 9-02 Personnel Airlock Area 903' ,105 R/hr Panel 9-02 Ladder 903' to 2nd Level .070 R/hr l
l
- Alarm l OS Offseale l
Nu/ >
RADIATION MONITOR DATA Time - 0745 f}N (
\__
t - 00/15 PROCESS AND VENT MONITORS PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 1.0 E-3 uCi/sec ERP Stack Normal Eff (RMP-RM-3A) 5.5 E-1 uCi/sec ERP Stack High Range (RMP-RM 3B) 0 uCi/sec Turbine Bldg Vent Eff (RKV-RM-20A) 1.5 E-3 uCi/sec Turbine Bldg High Range (RMV-RM-20B) 0 uCi/see RW/ARW Bldg Combined Eff (RMV-RM-30A) 1.0 E-3 uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) 0 uCi/sec PANEL 9-10 Mn. Stm. Rad Monitor Ch. A1, B1 300 mR/hr 350 mR/hr Ch. A2, B2 300 mR/hr 260 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 35 mR/hr 25 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 14 mR/hr 15 mR/hr f- s Service Water 10 cps /\ Reactor Equipment Cooling 20 cps s pJ
l h l 1 1987 Evaluated Exercise Time - 0745 7' s Message Number: 2 t - 00/15 l l COOPER NUCLEAR STATION-EMERGENCY PREPAREDNESS EXERCISE MESSAGE
\
For Controller Use Only: CONTROLLER INFORMATION: o The' data sheet (from SLC operability surveillance test) indicates that both SLC pumps are now inoperable, placing the plant in a 6 hour LCO-(hot shutdown within 6 hours). EXPECTED ACTIONS:
- 1. Infore station manageuent
- 2. Begin preparations for a shutdown
- 3. Declare an Unusual Event
/%
{U 1 I v
1
)
[N 1987 Evaluated Exercise Time - 07/50 t ! Message Nwrber: 3X t - 00/20
+
j
. COOPER NUCLEAR STATION I EMERGENCY PREPAREDNESS EXERCISE MESSAGE Message for: Shift Supervisor 1 Simulated Plant Conditions:
Message:
***Tt!IS IS A DRILL ***
Due to a dan'gerously slim grid margin, the Load Dispatcher requests that you l limit your shutdown rate to 50 mW/hr, until.1030, at which time you may shutdown at the maximum rate allowed by-your procedures. 1 V 1 l l
/
l t m)s _________.______________m_.___________.__.___-__.____________________m__._
1 ( 1987 Evaluated Exercise Time - 07/50 Message Number: 3X t - 00/20 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE' MESSAGE For Controller Use Only; i l CONTROLLER INFORMATION: , o The reactor must remain at a relatively high'(> 75%) until the scram transient occurs at 10:00 (02/30), m I EXPECTED ACTIONS: l OV l i I j j O ! 4
]I
-[ 1987 Evaluated Exercise Time - 0800
's Message Number: 4 t - 00/30 .
COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXEP.CISE MESSAGE Message for: Control Room Simulated Plant Conditions: See attached Plant Data Message:
***THIS IS A DRILL ***
s l t J k l
]
.-_-- -___ - __ -__O
O }987 Evaluated Exercise Time - 0800 kessageNumber 4 COOPER NUCLEAR STATION t - 00/30 EMERGENCY PREPAREDNESS EXERCISE PLANT DATA ' PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 100% APRM l RHR A UNAVAIL 0 0 REACTOR LEVEL 35"
- NR RHR C STBY 50 REACTOR PRESSURE 1000 psig RRR B STBY 50 0 CORE D/P (psig) 17.25 0
RHR D STBY 50 CORE FLOW ~(10 lbm/hr) 71.0 0 CS A STBY LO O FLOW (10 lbs/hr)
~
CS B STBY 50 0 FEEDWATER A 4.8 HPCI STBY 50 0 FEEDWATER B 4.8 Drywell Pressure .3 (psig) MAIN STEAM A 2.4 Torus Level 0 (inches) MAIN STEAM B 2.4 i [
\
OPEN CLOSED MAIN STEAM C 2.4
\
MSIV 8 0 MAIN STEAM D 2.4 l < FLOW PANEL 9-4 CRD A 50 (gpm) STATUS PRESS (psig) FLOW (gpm) CRD B AVAIL (gpm) RCIC STBY 50 0 LEVEL PRESS SQUIB PUMPS RWCU A OPER 1000 100 SLC 75 % 0 (psig) ON UNAVAIL s RWCU B AVAIL 0 0 RRPA 90 % SPD MISCELLANEOUS PANELS i RRPB 90 % SPD DIESEL GEN A STBY DIESEL GEN B STBY l SBGT A STBY SBGT B STBY m DRYWELL COOLING NORMAL TORUS WATER TEMP 80 'F l - - - - _. -_____ -- - O
08 8 g o I
= =
0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 8 6 4 0 8 6 4 2 O ) 2 0 e t
) 1 12 1 '
F 1 1 . i m ig 0 O ( s T p e ( r e t u r u a r s s ep e r m P 5 1 e r o
- T t s c u a r e o R T
_ 0 3 E * - SI C R N E o 0 0 0 0 O X 0 0 5 0 0 5 5 0 5 0 T E I - 4 2 0 2 1 1 + 1 1 2 1
+ + - - - 2 1
+ +
A SS ) 0 T E n ) n S i ( N A l i ( R D T e v l e A E A e v E L AR D L L e C P S r o s U E DP t c u r N R S a 5 o R P e T 1 E Y R P C O N O E - C G R E 0 M 3 E 3
)
0 0 0 0 0 M 0 8 6 2 0 0 0 0 0 0 0 10 R 1 7 6 5 4 3 2 P 0 - A
)
% ig G s p
V ( A e ( r e r u i s e 5 s t c w 1
- e r o r e P P x r l E o l e
t d c w te /* a y a e r l u R 0 3 D a e - v E ga 7 s s 8 9 e 1 M
/N RADIATION MONITOR DATA Time - 0800 (v) c - 00/30 AREA RADIATION MONITORS READING STATION DESCRIPTION (mr/hr) 1 Rx Bldg Fuel Pool Area (SE 5th Floor) 90 1 2 Rx Bldg Fuel Fool Area (SE 5th Floor) 2 3 Rx Bldg New Fuel Area (SE 5th Floor) 0.03 4 Rx Bldg Rx Water Cleanup Demineralized Area 15 (SV 1rd Floor) 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 1 6 Rx Bldg Neutron Monitor System Index Area 90 (TIP Room 1st Floor) 7 Rx Bldg Neutron Monitor System Drive Mech Ares 2 (SE lst Floor) 8 Rx Bldg Control Rod Hydraulic Equipment Area 0.8 (S 1st Floor) 9 Rx Bldg Control Rod Hydraulic Equipment Area 9 (N lst Floor) 10 Rx Bldg HPCI Pump Room (SU Quad) 0.4 11 Rx Bldg RHR Pump Room (SW Quad) 9 12 Rx Bldg RHR Pump Room (NW Quad) 15 j f -s 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 7 ; 14 Rx Bldg CS Pump Room (SE Quad) 7 \s 15 Turbine Bldg Turbine Front Standard 100 16 Turbine Bldg " rbine Bldg Mezz , Control Corridor 0.2 17 Turbine Bldg 't abine Bldg Basement Control Corridor 0.04 ;
18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 8 { 19 Turbine Bldg Turbine Bldg Condensate Pump Area 0.1 ] 20 Control Room Main Control Room 0.015 j 21 Grade Level control Corridor 0.25 j 22 Radwaste Control Room 0.02 23 Radwast Pump Room 7 24 Radwaste Basement Equipment Area ~ 3 25 Radwaste Demin Valve Room 2 26 Radwaste Conveyor Aisle Operating Area 0.03 27 SPARE 28 Radwaste Lab Area 0.2 29 Centrifuge East 10 30 Centrifuge West 9 ! l Panel 9-02 Personnel Airlock Area 903' .105 R/hr Panel 9-02 Ladder 903' to 2nd Level .070 R/hr i i
- Alarm ;
OS Offscale
,a \
( i \s_-) I
I, I l l (s RADIATION MONITOR DATA Time - 0800 t - 00/30 V PROCESS AND VENT MONITORS PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 1.0 E-3 uCi/sec ERP Stack Normal Eff (RMP-RM-3A) 5.5 E-1 uCi/sec ERP Stack Hip,h Range (RMP-RM-33) 0 uCi/see Turbine Bldg Vent Eff (RMV-RM-20A) 1.5 E-3 uCi/sec Turbine Bldg High Range (RMV-RM-20B) 0 uCi/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 1.0 E-3 uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) 0 uCi/sec PANEL 9-10 Mn. Stm. Rad Monitor Ch. A1, B1 300 mR/hr 350 mR/hr Ch. A2, B2 300 mR/hr 260 mR/hr i SJAE Off Cas Log Rad Monitor Ch. A, B 35 tuR/hr 25 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 14 mR/hr 15 mR/hr l
,-~ Service Water 10 cps
( i Reactor Equipment Cooling 20 cps n l l I w l l
4
)
l
^s 1987 Evaluated Exercise .. Time - 0800-t:
Message Number: 4 .t - 00/3W . J COOPER NUCLEAR STATION l l EMERGENCY PREPAREDNESS EXERCISE MESSAGE d For Controller Use Only: CONTROLLER INFORMATION: I l EXPECTED ACTIONS _: u 4 1 1 1 l l
]
1 1 1 4 I I O l 1 _. __m________.
l
'(x ' 1987 Evaluated Exercise Time - 0805 D) i Message Number: SX t - 00/35 COOPER NUCLEAR STATION l
EMERGENCY PREPAREDNESS EXERCISE MESSAGE l l l l Message for: Control Room Shift Supervisor Simulated Plant Conditions: Message:
***THIS IS A DRILL ***
Declare an LL 3UAL EVENT, per EPIP 5.7.1 Initiating Condition 6.1; "Any Technical Specification LCOs resulting in immediate shutdown." p -
\
w
)
l i i I
1987 Evaluated Exercise Time - 0805 \x~-) Message Number: 5X t - 00/35 . COOPER NUCLEAR STATION-EMERGENCY PREPAREDNESS EXERCISE MESSAGE For Controller Use only: CONTROLLER INFORMATION: o Deliver this message only if an UNUSUAL EVENT has not already.been declared, and if there are no discussions-in progress which would result in that declaration. EXPECTED ACTIONS: O
I 1987 Evaluated Exercise Time - 0815 j
\ !
Message Number: t - 00/45 6 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Message for: Control Room l 1 1 Simulated Plant Conditions: See attached Plant Data Message: 1
***THIS IS A DRILL *** - ~ \
L _ _ - - - . - - - - _ _ _ _ _ - - _ - - - _ _ _
b D 1987 Evaluated Exercise Time - 0815
/ I
_ ( Jessage Number 6 COOPER NUCLEAR STATION , t - 00/45 EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 100% APRM RHR A U_NAVAIL 0 'O REACTOR LEVEL 35" -* NR RHR C STBY 50 REACTOR PRESSURE 1000 psig RHR B STBY 50 0 CORE D/P (psig) 17.25
- 6 RHR D STBY 50 CORE FLOW (10 lbm/hr) 71.0 6
CS A STBY 50 0 FLOW (10 lbs/hr) CS B STBY 50 0 FEEDUATER A 4.8 HPCI STBY 50 0 FEEDWATER B 4.8 Drywell Pressure .3 (psig) MAIN STEAM A 2.4 Torus Level 0 (inches) MAIN STEAM B 2.4
/" T OPEN CLOSED MAI'N STEAM C 2.4 MSIV 8 0 MAIN STEAM D 2.4 FLOW PANEL 9-4 CRD A 50 (gpm) .
STATUS PRESS (psig) FLOW (gpm) CRD B AVAIL (gpm) RCIC STBY 50 0 LEVEL PRESS SQUIB PUMPS RWCU A OPER 1000 100 SLC 75 % 0 (psig) ON UNAVAIL RUCU B AVAIL 0 0 RRPA 90 % SPD MISCELLANEOUS PANELS RRPB 90 % SPD DIESEL GEN A STBY DIESEL CEN B STBY SBGT A STBY SBCT B STBY DRYWELL COOLING NORMAL TORUS WATER TEMP 80 *F S
-____________.____.___.d
e-c 0 M 1
= = 0 0 0 0 0 0 0 0 0 0 0 0 .
0 0 0 0 8 6 2 c 2 0 8 6 e t
)
4 1 2 1 1 0 ) F 1 1 m ig 0 O i s ( T p e ( r e t u r u a s r s e p e r m P 5 e 1 r - T t o s c u a r e o T R - 0 _ 3 E - S I C R U N E 0 O XE I 0 0 5 1 0 1 0 5
+
0 0 5 0 0 1 0 5 1 0 0 2 4 2 0 2 T 1 _ + + - - 2 1
+ +
A SS
)
n 0 T S E i (
)
n N A l i ( R D T e v l e A E A e v E L AR D L L e C P S r o s
- U E DP t c
u r N R S a 5 o R P e T 1 E Y R P C O N O E C G R E 0 M 3 E . 3
) '
0 0 0 9 0 0 M 0 8 6 4 2 0 0 0 0 0 0 0 R 1 7 6 5 4 3 2 1 P 0 , A
)
% ig G s p
V ( A ( e r e r u i s e 5 s s c w 1 e r o - r e P P x r l E l e t d c w t e i a y a e r u R 0 D (
~
l 3 a e - v E ga s 7 s 8 9 e 1 M
! l
/'~'g RADIATION MONITOR DATA Time - 0815 t
t - 00/45 l AREA RADIATION MONITORS READING STATION DESCRIPTION (mr/hr) 1 Rx Bldg Fuel Pool Area (SE 5th Floor)- 90 2 Rx Bldg Fuel Fool Area (SE 5th' Floor) 2 i 3 Rx Bldg New Fuel Area (SE Sch Floor) 0.03 4 Rx Bldg Rx Water Cleanup Demineralized Area 15 , (SW 3rd Floor) ' 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor)
~
1 6 Rx Bldg Neutron Monitor System'Index Area 90 (TIP Room ist Floor) 7 Rx Bldg Neutron Monitor System Drive Mech Ares 2 (SE 1st Floor) 8 Rx, Bldg Control Rod Hydraulic Equipment Area 0.8 (S lst Floor) 9 Rx Bldg Control Rod Hydraulic Equipment Area 9 (N lse Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) 0.4 11 Rx Bldg RHR Pump Room (SW Quad) 9 12 Rx Bldg RHR Pump Room (NW Quad) 15 fss 13 Rx Bldg RCIC/CS Pump Room (NE Quad)' 7 . 14 Rx Bldg CS Pump Room (SE Quad) 7-
\,_, 15 Turbine Bldg Turbine Front Standard 100 16 Turbine Bldg Turbine Bldg Mez Control Corridor 0.2 17 Turbine Bldg Turbine Bldg Basement Control Corridor 0.04 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 8 19 Turbine Bldg Turbine Bldg Condensate Pump Area 0.1 20 Control Room Main Control Room 0.015 21 Grade Level Control Corridor 0.25 22 Radwaste Control Room 0.02 23 Radwaste Pump Room 7 24 Radwaste Basement Equipment Area 3 25 Radwaste Demin Valve Room 2 26 Radwaste Conveyor Aisle Operating Area 0.03 27 SPARE 28 Radwaste Lab Area 0.2 29 Centrifuge East 10 30 Centrifuge West 9-Panel 9-02 Personnel Airlock Area 903' .105 R/hr Panel 9 02 Ladder 903' to 2nd Level .070 R/hr
- Alarm OS Offscale
\
( i pg : RADIATION MONITOR DATA Time 0815 l t .00/45 PROCESS AND VENT MONITORS PANEL VBDG-Rx Bldg Vent'Eff (RMV-RM-40) . 1.0 E-3 uCi/sec ERP Stack Normal Eff (RMP RM-3A) -5.5 E-1 uCi/sec-ERP Stack High Range (RMP-RM-3B) 0 uCi/sec Turbine. Bldg Vent Eff (RMV-RM-20A) 1.5 E-3 uCi/sec Turbine Bldg High Range (RMV-RM-20B)' . O. uCi/sec RW/ARW Bldg Combined Eff-(RMV-RM-30A) 1.0 E-3 uCi/sec RW/ARW Bldg High Range.(RMV RM 30B) 0 uCi/sec'
- PANEL 9-10 1
Mn. Stm. Rad Monitor Ch. A1, B1 . 300 mR/hr 350 mR/hr. Ch. A2, B2 300 mR/hr 260 mR/hr SJAE Off Cas Log Rad Monitor Ch. A, B .. 35 mR/hr 25 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch.'A, B 14 mR/hr .15 mR/hr Service Water 10 cps
,, Reactor Equipment Cooling .20 cps
! ( m -
9 1987 Evaluated Exercise Message Number: 6 Time - 0815 t - 00/45 C00 PEPS NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE For Controller Use Only: CONTROLLER INFORMATION: EXPECTED ACTIONS:
~
9 4 9 .
l1 i
)
1987 Evaluated Exercise Time - 0830 t
\ Message Number: 7 t - 01/00 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE 1
)
Message for: Fuel Handling Team ) I Simulated Plant Conditions: I Message: ,
***THIS IS A DRILL ***
While being raised for inspection, a fuel bundle dropped approximately 12 feet when the bundle bail broke. There are bubbles rising to the surface of the ' pool, and the ARM is alarming. rt < i l 1 J l l 1
-i 4 - _ _ - _ _ - - _ _ - - _ - _ _ - _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ ._ a
I i 1987 Evaluated Exercise Time - 0830 i - Message Number: 7 t - 00/50 .
.\
COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE I For Controller Use Only: CONTROLLER INFORMATION: l. I EXPECTED ACTIONS: i 1 l i i 1
l t l 1987 Evaluated Exercise ' Time - 0830 O. Message Nmnber: 8 t - 01/00 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE-Message for: Control Room Simulated Plant Conditions: See attached Plant Data . Message: , f
***THIS IS A DRILL ***
The following annunciators have been received in the Control Room: REFUEL AREA HIGH RADIATION REACTOR BUILDING VENT HIGH RADIATION j i Indications in the Control Room include: RMP-RR-455 Red Pen 8 mR/hr Black Pen 9 mR/hr l ' RMP-RM-452A 7 mR/hr RMP-RM-4523 8 mR/hr j 1
~
k 1
l I l 87 Evaluated Exercise Time - 0830 "
\stessage Number 8 COOPER NUCLEAR STATION t - 01/00 EMERGENCY PREPAREDNESS EXERCISE PLANT DATA l PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR' POWER 100% APRM RHR A UNAVAIL 0 0 REACTOR LEVEL 35" -+ NR RHR C STBY 50 REACTOR PRESSURE 1000 psig j l
RHR B STBY 50 0 CORE D/P (psig) 17.25 6 RHR D STBY 50 CORE FLOW (10 lbm/hr) 71.0 6 CS A STBY 50 0 FLOW (10 lbs/hr) l CS B STBY 50 0 FEEDWATER A 4 '. 8 HPCI STBY 50 0 FEEDWATER B 4.8 Drywell Pressure .3 (psig) MAIN STEAM A 2.4 Torus Level 0 (inche's) MAIN STEAM B 2.4 OPEN CLOSED MAIN STEAM C 2.4 tO MSIV 8 0 MAIN STEAM D 2.4 FLOW I s PANEL 9-4 CRD A 50 (gpm) STATUS PRESS (psig) FLOW (gpm) CRD B AVAIL (gpm) j RCIC STBY SO 0 LEVEL PRESS SQUIB PUMPS RWCU A OPER , 1000 100 SLC 75 % 0 (psig) ON UNAVAIL j RWCU B AVAIL 0 0 RRPA 90 % SPD MISCELLANEOUS PANELS l RRPB 90 % SPD DIESEL GEN A STBY DIESEL GEN B STBY SBGT A STBY SBGT B STBY ( r DRYWELL COOLING NORMAL TORUS WATER TEMP 80 *F l L______________._____________________________._____.___.___ _ _ _ _ _ _ _ _ . . . _
- c
@ o g
l
= = 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 6 6 4 2 0 2 0 8 6 2 0 )
e t
)
4 1 1 1 F 1 1 m ig 0 O ( s iT p e ( r e t u r a u r s e s e p r m P 5 1 e r o
- T t s c u r
a e o R T 0 3 E - E C 5 R 3 N E o 0 0 0 0 0 O X 0 5 0 0 0 5 5 0 5 0 T E I 1 1 + - 1 1 2 4 2 0 2 2 1 1
+ + - - -
+ + -
A SS ) T E i n 0 ) n S ( i N A l ( R D T e v l e A E A e v e E L AR D L L C P S r s o U E DP t c u r N R S a 5 o R P e T 1 E Y R P C O N O E C G R E 0 3 M - E
- ,!il! i .!,'
3
)
0 0 0 0 M 0 8 6 0 0 0 0 0 0 0 R 1 7 6 5 4 3 2 1 P 0 . . A
)
% g G isp V (
A e ( r e r u s is e 5 s c w 1
- e r o r e P P -
x r l E o l e t d c w t e v a y r a e
. u R 0 3
D
- - l a e
/ v E ga s
7 s 8 e 9 1 M
,! l; 11lcl
/'~'N RADIATION MONITOR DATA Time - 0830
( ) t - 01/00
' AREA RADIATION MONITOR _S READING, STATION DESCRIPTION (mr/hr) 1 Rx Bldg Fuel Pool Area (SE 5th Floor) 100 2 Rx Bldg Fuel Pool Area (SE Sth Floor) 60 *-
3 R:: Bldg New Fuel Area (SE 5th Floor) 0.1 4 Rx Bldg Rx Water Cleanup Domineralizer Area 15 (SW 3rd Floor) 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 1 6 Rx Bldg Neutron Monitor System Index Area 90 (TIP Room ist Floor) 7 Rx Bldg Neutron Monitor System Drive Mech Ares 2 (SE lst Floor) ) 8 Rx Bldg Control Rod Hydraulic Equipment Area 0.8 (S ist Floor) 9 Rx Bldg Centrol Rod Hydraulic Equipment Area 9 (N lst Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) 0.4 11 Rx Bldg RHR Pump Room (SW Quad) 9 12 Rx Bldg RHR Pump Room (NW Quad) 15 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 7
) 14 Rx Bldg CS Pump Room (SE Quad) 7 d 15 Turbine Bldg Turbine Front Standard 100 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.2 17 Turbine Bldg Turbine Bldg Basement Control Corridor 0.04 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 8 19 Turbine Bldg Turbine Bldg Condensate Pump Area 0.1 20 Control Room Main Control Room 0.015 ;
21 ~ Grade Level Control Corridor. - 0.25 l 22 Radwaste Control Room 0.02 ) 23 Radwaste Pump Room 7 24 Radwaste Basement Equipment Area 3 q 25 Radwaste Demin Valve Room .2 j 26 Radwaste Conveyor Aisle Operating Area 0.03 ' 27 SPARE 28 Radwaste Lab Area 0.2 j 29 Centrifuge East 10 l 30 Centrifuge West 9 Panel 9-02 Personnel Airlock Area 903' .105 R/hr Panel 9-02 Ladder 903' to 2nd Level .070 R/hr i
- Alarm .
OS Offscale v-r j
RADIATION MONITOR DATA Time - 0830
%, t - 01/00 PROCESS AND VENT MONITORS l
PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 5.6 E-3 uCi/sec l ERP Stack Normal Eff (RMP-RM-3A) 2.0 EO uCi/sec ERP Stack High Range (RMP-RM-3B) 0 uCi/see Turbine Bldg Vent Eff (RMV-RM-20A) 1.5 E-3'uCi/sec , Turbine Bldg High Range (RMV RM-20B) 0 uCi/sec l RW/ARW Bldg Combined Eff (RMV-RM-30A) 1,0 E-3 uCi/sec RW/ARW Bldg High Range-(RMV-RM-30B) 0 uCi/sec
^
PANEL 9-10 Mn. Stm. Rad Monitor Ch. A1, B1 300 mR/hr 350 mR/hr Ch. A2, B2 300 mR/hr 260 mR/hr SJAE Off Cas Log Rad Monitor Ch. A, B 35 mR/hr . 25 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 14 mR/hr 15 mR/hr r Service Water 10 cps f g Reactor Equipment Cooling 20 cps , I 1 l
, i
l l i 1987 Evaluated Exercise Time - 0830 l
\' !
Message Number: 8 t - 01/00 i COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE ii For Controller Use Only: CONTROLLER INFORMATION: g The Spent Fuel bundle was damaged when it was dropped, releasing fission gases to the refueling area, causing the Refuel Area ARM to Alarm. 1 EXPECTED ACTIONS: o Complete actions of Annunciator 9-3-3 Alarm Response. ! Procedure 2.3.2.23 l o Implement Emergency Procedure 5.3.5, Refueling Floor High Radiation l
- o Notify plant personnel to clear area o Request HP surveys / investigations I
o Declare an ALERT per EPIP 5.7.1, Initiating Condition 8.1: Fuel i Handling Accident on RefuelinS Floor. I o Implement EPIP 5.7.3; ALERT ! l l 1 I l i e s : x
i f 1987 Evaluated Exercise Time - 0845 Message Number: 9 t - 01/15 COOPER NUCLEAR STATION l EMERGENCY PREPAREDNESS EXERCISE MESSAGE Message for: Control Room l Simulated Plant Coaditions: See attached Plant Data
" l
. Message: 1 i
***THIS IS A DRILL ***
l t l I i e 1 l 1
/ 7 .987 Evaluated Exercise Time - 0845 dessageNumber 9 COOPER NUCLEAR STATION t- 01/15 EMERGENCY PREPAREDNESS EXERCISE PLANT DATA J PANEL 9-3 PANEL 9-5 S_TATUS PRESS (psig) FLOU(gpm) REACTOR POWER 100%' APRM RHR A UNAVAIL 0 0 REACTOR LEVEL 35" .* NR RHR C STBY 50 REACTOR PRESSURE 1000 psig l RER B STBY 50 0 CORE D/P (psig) 17.25 6
RHR D STBY 50 CORE FLOW (10 lbm/hr) 71.0 6 CS A STBY 50 0 FLOW -(10 lbs/hr) CS B STBY 50 0 FEEDWATER A 4.8 HPCI STBY 50 0 FEEDWATER B 4.8 i Drywell Pressure .3 (psig) MAIN STEAM A 2.4 Torus Level 0 (inches) MAIN STEAM B 2.4
,CN OPEN CLOSED MAIN STEAM C 2.4 (J MSIV 8 0 MAIN STEAM D 2.4
_F_LOS PANEL 9-4 CRD A 50 (gpm) STATUS PRESS (psig) FLOW (gpm) CRD B AVAIL (gpm) RCIC STBY 50 0 LEVEL PRESS SQUIB PUMPS RWCU A OPER 1000 100 SLC 75 % 0 (psig) ON UNAVAIL RWCU B AVAIL 0 0 RRPA 90 % SPD MISCELLANEOUS PANELS RRFB 90 % SPD DIESEL GEN A STBY DIESEL CEN B STBY SBGT A STBY SBGT B STBY l g DRYWELL COOLING NORMAL k w TORUS WATER TEMP 80 *F l
O+c M g o
= = 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 8 6 4 2 0 2 0 8 6 e t
)
4 1 2 1 1
)
F 1 1 m ig 0 ( i s T p e ( r e t u r u a s r s e e p r P 5 m 1 e r o - T t s c u r a e o R T 0 3 E - S I C R N E D ~ O X 0 5 0 0 0 5 0 5 0 0 0 5 0 0 I T E 1
+ +
1 + - 1 1 2 4 2 2 1 0 12
+ + -
A SS ) 0 T E n ) - S i ( i n N A l ( R D T e v l e
] A E A e v E AR D e GC L U
N R E P S DP L t r o c L s u r o S a 5 R P e T 1 E Y R P C O N O E C G R E 0 M 3 E 3
)
M 0 0 0 8 0 6 0 2 0 0 0 0 0 0 0 0 10 R 1 7 6 5 4 3 2 P 0 . . A
)
% ig G s p
V ( A e ( r c r u s i s ' e 5 s c w 1 e r o r . e P P x r l E . o l e t d c w t e 1
- a y a e r Gl R D u 0 3 - a e v
E ga 7 s 8 s 9 e 1 M
q t i i
.. RADIATION MONITOR DATA Time - 0845 '
I
\s,-
t - 01/15 i :; AREA RADIATION MONITORS-READING STATION DESCRIPTION (mr/hr) j 1 1 Rx Bld5 Fuel Pool Area (SE 5th Floor) 90 q 2 Rx Bldg Fuel Pool Area (SE 5th Floor) 60
- q 3 Rx Bldg New Fuel Area (SE 5th Floor) 0.1 ]
4 Rx Bldg Rx Water Cleanup Demineralized Area 15 (SW 3rd Floor) 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 1 6 Rx Bldg Neutron Monitor System Index Area 90 (TIP Room ist Floor) 7 Rx Bldg Neutron Monitor System Drive Mech Ares 2 (SE lst Floor) 8 Rx Bldg Control Rod Hydraulic Equipment Area 0.8 (S 1st Floor) ' 9 Rx Bldg Control Rod Hydraulic Equipment Area 9 (N lst Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) 0.4 q 11 Rx Bldg RHR Pump Room (SW Quad) 9 12 Rx Bldg RHR Pump Room (NU Quad). 15 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 7
, 14 Rx Bldg CS P, ump Room (SE Quad) 7 15 Turbine Bldg Turbine Front Standard 100 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.2 17 Turbine Bldg Turbine Bldg Basement Control Corridor 0.04 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 8 j 19 Turbine Bldg Turbine Bldg Condensate Pump Area 0.1 20 Control Room Main Control Room 0.015 )
21 Grade Level Control Corridor 0.25 1 22 Radwaste Control Room 0.02 'l 23 Radwaste Pump Room 7 j 24 Radwaste Basement Equipment Area 3 25 Radwaste Demin Valve Room 2 26 Radwaste Conveyor Aisle Operating Area .0.03 27 SPARE 28 Radwaste Lab Area 0.2 29 Centrifuge East 10 30 Centrifuge West 9 Panel 9-02 Personnel Airlock Area 903' .105 R/hr Panel 9-02 Ladder 903' to 2nd Level .070 R/hr
- Alarm ,
OS Offscale j l s 0
._ ___ _ - _-_______ m
i [~N RADIATION MCNITOR DATA Time - 0845 1 t - 01/15' PROCESS AND VENT MONITORS PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 0 uCi/sec ERP Stack Normal Eff (RMP-RM-3A) 7.5 E-1 uCi/sec ERP Stack High Range (RMP-RM-3B) 0 uCi/see Turbine Bldg Vent Eff (RMV-RM-20A) 1.5 E-3 uCi/sec-Turbine Bldg High Range (RMV-RM-20B) 0 uci/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 1.0 E-3 uCi/see RW/ARU Bldg High Range (RMV-RM-30B) 0 uCi/sec PANEL 9-10 Mn. Stm. Rad Monitor Ch. A1, B1 300 mR/hr 350 mR/hr Ch. A2, B2 300 mR/hr 260 mR/hr SJAE Off Cas Log Rad Monitor Ch. A, B '35 mR/hr 25 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 14 mR/hr 15 mR/hr Service Water 10 cps Reactor Equipm.ent Cooling 20 cps ( I
1 J p 1987 Evaluated Exercise Time - 0845 Message Number: 9 t - 01/15 - COOPER NUCLEAR' STATION' EMERGENCY PREPAREDNESS' EXERCISE MESSAGE 4 For Controller Use Only: CONTROLLER INFORMATION:
- o Data reflects continued operation ~at 100% power, 1
l j EXPECTED ACTIONS: o Health Physics should have' responded to the scene of the fuel handling accident and initiated radiological surveys of the area, and personnel involved.
\
1 U l
C I J (N 1987 Evaluated Exercise Time - 0850
. ]
Message Number: 10X- t - 01/20
'1 l COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Message for: Shift Supervisor (Emergency Director)
Simulated Plant Conditions: Message:
***THIS IS A DRILL *** j l
Declare an ALERT, per EPIP 5.7.1, Initiating Condition 8.1: " Fuel Handling Accident on Refueling Floor".
\
l i 1
\
4 l 4 l b ( -l ! l i l 1 l j i
'l A <
b ; l l
f 1967 Evaluated' Exercise Time - 0850
\
Message Number: 10X t - 01/20 " 1 1 COOPER NUCLEAR STATION l l EMERCENCY PREPAREDNESS EXERCISE MESSAGE
]
For Controller Use Only: CONTROLLER INFORMATION: i o Deliver this message only.if an ALERT has not already been declared, and if there are no discussions in progress that would result . in J that declaration, i 1 EXPECTED ACTIONS: ) i I I
^h (V
l l
]
i ( w , L___________ _____________.______:._________.__:______.__
i l
-] 1987 Evaluated Exereise ,
Tirne - 0900 Message Number: 11 t - 01/30 . COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE - 1 1 Message for: Control Room I l Simulated Plant Conditions: See attached Plant Data ) Message: .j l
***THIS IS A DRILL ***
i . o .
'1 i
H i l l i (
'I I
I
987 Evaluated Exercise Time - 0900
' v iessage Number 11 COOPER NUCLEAR STATION t- 01/30-EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER _100% APRM RER A UNAVAIL 0 0_ REACTOR LEVEL 35" b NR RHR C STBY 50 REACTOR PRESSURE 1000 psig .
RHR B 'STBY 50 0 CORE D/P (psig) '17.25 6 RilR D STBY 50 CORE FLOW (10 lbm/hr) 71.0 0 CS A STBY 50 0 FLOW (10 lbs/hr)- CS B ~ STBY 50 0 FEEDWATER A 4.8 HPCI STBY 50 0 FEEDWATER B 4.8 Drywell Pressure .3 (psig) MAIN STEAM A 2.4 Torus Level 0 (inches) MAIN STEAM B 2.4 OPEN CLOSED ' MAIN STEAM C 2.4 4 MSIV 8 0 MAIN STEAM D 2.4 FLOW PANEL 9-4 CRD A 50 (gpm) STATUS PRESS (psig) FLOW (gpm) CRD B AVAIL (gpm) RCIC STBY 50 0 LEVEL PRESS SQUIB PUMPS RUCU A OPER 1000 100 SLC 75 % 0 (psig) ON UNAVAIL RUCU B AVAIL 0 0 , l RRPA 90 % SPD MISCELLANEOUS PANELS RRPB 90 % SPD DIESEL GEN A STBY I DIESEL GEN B STBY
)
SBGT A STBY !
^
SBGT B STBY I I DRYWELL COOLING NORMAL l 'v TORUS WATER TEMP 80 *F i
0 0 0 g o 1
= = -
0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 8 6 4 2 0 2 0 8 6 e t
)
4 1 12 1 0 ) F 1 1 m g 0 i T is p ( ( e r e t u r u a s r s e e p r P 5 m 1 e r o - T s t c u a r e o R T 0 3 L E - SI C
. R M N E 0 O X 0 5
0 0 0 5 0 0 5 0 0 0 5 0 0 I E 1 1 + - 1 1 2 4 2 O 2 T + + - - - 2
+
1
+
1 A SS ) 0 T n S E
) -
i ( in N A l ( R D T e v l e A E A e v E L AR D l , e L C P S r U E DP o s t u N R c r S a 5 o R P e 1
- T E Y R P C O N O E C G R
E 0 M 3 E 3
)
0 0 0 0 0 0 M 0 8 6 4 0 0 0 0 O 0 0 0 R 1 7 6 5 4 J 2 1 P 0 _ _ A
)
% ig G s p
V ( A ( e r e r u s i s e 5 s c w 1
- e r o r e P P x r E o l
l e t d c w te u a y r a e l u R 0 3 D a e v E ga 7 s s 9 8 e 1 M lli !lI
1
./ RADIATION MONITOR DATA Time - 0900 '( ,
t - 01/30.- AREA' RADIATION MONITORS READING STATION DESCRIPTION (mr/hr) , 1 Rx. Bldg Fuel Pool Area (SE 5th Floor) 90 1 2 Rx Bldg Fuel Fool Area (SE 5th Floor) 60 * ! 3 Rx Bldg New Fuel Area (SE Sth Floor) . 0.05 4 Rx Bldg Rx Water Cleanup Demineralized Area 15 (SW 3rd Floor) 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 1 6 Rx Bldg Neutron Monitor System Index Area 90 l (TIP Room 1st Floor) l 7 Rx Bldg Neutron Monitor System Drive Mech Ares' 2 (SE 1st Floor) ' 8 Rx Bldg Control Rod Hydraulic Equipment Area 0.8 (S 1ct Floor) 9 Rx Bldg Control Rod Hydraulic Equipment Area 9- i (N lst Floor) l 10 Rx Bldg HPCI Pump Room (SW Quad) 0.4 ! 11 Rx Bldg RHR Pump Room (SW Quad) 9 - 12 Rx Bldg RHR Pump Room (NW Quad) 15 13 Rx. Bldg RCIC/CS Pump Room (NE Quad) 7 14- Rx Bldg CS Pump Room (SE Quad) 7
\ 15 Turbine Bldg Turbine Front Standard .100 i 16 Turbine Bldg Turbine Bldg Me z Control Corridor 0.2 17 Turbine Eldg Turbine Bldg Basement Control Corridor 0.04 l
18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 8 19 Turbine Bldg Turbine Bldg Condensate Pump Area 0.1 20 control Room Main Control Room 0.015 12 1 Grade Level Control Corridor 0.25 22 Radwaste Control Room 0.02 23 Radwaste Pump Room 7 24 Radwaste Basement Equipment Area 3 25 Radwaste Demin Valve Room 2 26 Radwaste Conveyor Aisle Operating Area 0.03 27 SPARE 28 Radwaste Lab Area 0.2 29 Centrifuge East 10 30 Centrifuge West 9 Panel 9 02 Personnel Airlock Area 903' .105 R/hr Panel 9-02 Ladder 903' to 2nd Level .070 R/hr
- Alarm OS Offscale a
I
/}, RADIATION MONITOR DATA Time - 0900 ( ,/ t - 01/30 PROCESS AND VENT MONITORS PANEL VBDG Rx Bldg Vent Eff (RMV RM-40) 0 uCi/sec ERP Stack Normal Eff (RMP RM-3A) 6.0 E-1 uCi/sec ERP Stack High Range (RMP-RM-3B) O. uCi/sec Turbine Bldg Vent Eff (RMV-RM-20A) 1.5 E-3 uCi/see Turbine Bldg High Range (RMV-RM-20B) 0 uCi/see RW/ARW Bldg Combined Eff (RMV-RM 30A) 1.0 E-3 uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) 0 uCi/sec PANEL 9-10 Mn. Stm. Rad Monitor Ch. Al, B1 300 mR/hr 350 mR/hr Ch. A2, B2 300 mR/hr 260 mR/hr SJAE Off Cas Log Rad Monitor Ch. A, B 35 mR/hr 25 mR/hr-Rx Bldg Vent Ind/ Trip Unit Ch. A, B 14 mR/hr 15 mR/hr s Service Water 10 cps g Reactor Equipment Cooling 20 cps L (
4 1987 Evaluated Exercise Time - 0900
. Message Number: 11 t - 01/30 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE For Controller Use Only:
CONTROLLER INFORMATION: o Plant continues to operate at 100% power. EXPECTED ACTIONS: 9 9 k- 1 L_________.___________________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . . _ . . _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ .________m ___.______a
1987 Evaluated Exercise Time - 0915 f'% Message Number: 12 t - 01/45 . COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Message for: Control Room Simulated Plant Conditions: See attached Plant Data Message:
***THIS IS A DRILL ***
The following annunciators have been receivdd in the Control Room: AUTO SCRAM TRIP SYSTEM A MANUAL SCRAM TRIP SYSTEM A REACTOR NEUTRON MONITOR SYSTEM TRIP MAIN STEAM ISOLATION VALVE (S) NOT FULL OPEN TRIP DISCHARGE VOLUME HIGH WATER LEVEL TRIP TURBINE CONTROL VALVE FAST CLOSURE REACTOR VESSEL HIGH PRESSURE TRIP ( Rx VESSEL LOW LEVEL TRIP TURBINE STOP VALVE CLOSURE TRIP MAIN STEAM LINE HIGH RADIATION TRIP GROUP 1 ISOLATION CHANNEL A PRIMARY CONTAINMENT HIGH PRESSURE Indications in the Control Room include: RPSPP "A" Power Available Light not Energized
- All Control Rod " full out" red lights are on No Blue Scram lights on OD-7 (Attached)
Groups 2, 3, 6 inboard isolation valves closed i i\
q 987 Evaluated Exercise Time - 0915 Q essage Number 12 COOPER NUCLEAR STATION t - 01/45 EMERGENCY PREPAREDNESS EXERCISE PIANT DATA - PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 100%_ _APRM RHR A UNAVAIL 0 0 REACTOR LEVEL 35"
- NR RHR B STBY 50 REACTOR PRESSURE 1000 psig !
I RHR C STBY 50 0 CORE D/P (psig) 17.25 6 RHR D STBY 50 CORE FLOW (10 lbm/hr) 71.0 6 CS A STBY 50 0 FLOW (10 lbs/hr)- CS B STBY 50 0 FEEDWATER A 4.8 HPCI STBY 50 0 FEEDWATER B 4.8 Drywell Pressure .3 (psig) MAIN STEAM A 2.4 j 1 Torus Level 0 (inche's) MAIN STEAM B 2.4 I i OPEN CLOSED MAINNTEAMC 2.4 O\ MSIV 8 0 MAIN STEAM D 2.4 FLOW PANEL 9-4 CRD A 50 (gpm) STATUS PRESS (psig) FLOW (gpm) CRD B AVAIL (gpm) RCIC STBY 50 0 LEVEL PRESS SQUIB PUMPS RWCU A _0PER 1000 100 SLC 75 % 0 (psig) ON UNAVAIL RWCU B AVAIL 0 0 RRPA 90 % SPD MISCELLANEOUS PANELS RRPB 90 % SPD DIESEL GEN A STBY
. DIESEL GEN B STBY SBGT A STBY SBGT B STBY DRYWELL COOLING NORMAL
'd TORUS WATER TEMP 80 *F
o N g
= = 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 0 8 6 4 2 0 8 6 4 2 0 )
e t
) 1 1 1 F
1 1 m g 0 O i is ( T p e ( r e t u r a u s r s e e p r P m e 5 1 r o
- T t s c r u
a e o R T 0 3 E - S I C R 0 N E 0 0 0 O X 0 0 5 0 0 5 0 5 0 5 0 I E 1 1 + - 1 1 2 4 2 0 2 T + + - - - 2
+
1
+
1 A SS ) n 0 ) T S E i ( i n N A l ( R D T e v l e A E A e v EL R A D L L e S r C P o s U E DP t c u r N R S a 5 o R P T _ e 1 E Y R . P C O N O E C G R E 0 3 M - E ' 3
)
0 0 0 0 0 M 0 8 6 2 0 0 0 0 0 0 0 0 R 1 7 6 5 4 3 2 1 P 0 - _ . A
)
% g G is p
V ( A e ( r e r u i s e 5 s c w 1
- e r o r c P P x r l E o l e
t d 2 c w t e # a y a e r l u R 0 3 D
- a e , v g E a 7 s s
8 9 e 1 M l
a
/N RADIATION MONITOR DATA Time - 0915 ;
( ) t .01/45: AREA RADIATION MONITORS READINC STATION DESCRIPTION (mr/hr) I 1 Rx Bldg Fuel Pool Area (SE Sch Floor) 90 1 2 Rx Bldg Fuel Pool Area (SE Sth Floor) 40
- 3 Rx Bldg New Fuel Area (SE Sch Floor) . 0.03 4 Rx Bidg Rx Water Cleanup Demineralized Area 15 (SW 3r6 Floor) 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 1 6 Rx Bld8 Neutron nonitor System Index Area 90 (TIP Room ist Floor) 7 Rx Bldg Neutron Monitor System Drive Mech Ares 2. j (SE 1st Floor) -
8 Rx Bldg Control Rod Hydraulic Equipment Area 0.8 (S 1st Floor) 9 Rx Bldg Control Rod Hydraulic Equipment Area 9 (N ist Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) 0.4 11 - Rx Bldg RHR Pump Room (SW Quad) 9 12 Rx Bldg RHR Pump Room (NW Quad)- 15 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 7 ( 14 Rx Bldg CS Pump Room (SE Quad) 7 15 Turbine Bldg Turbine Front Standard 100 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.2 17 Turbine Bldg Turbine Bldg Basement Centrol Corridor 0.04 18 Turbine Bids Turbine Bldg'Rx Feed Pump Area 8 19 Turbine Bldg Turbine Bldg Condensate Pump Area 0.1 20 Control Room Main Control Room 0.015 21 crade Level Control Corridor 0.25 u 22 Radwaste Control Room 0.02 23 Radwaste Pump Room 7 24 Radwaste Bas'ement Equipment Area 3 25 Radwaste Demin Valve Room 2 26 Radwaste Conveyor Aisle Operatin5 Area 0.03 27 SPARE 28 Radwaste Lab Area 0.2 29 Centrifuge East 10 30 Centrifuge West 9 Panel 9-02 Personnel Airlock Area 903' .105 R/hr Panel 9-02 Ladder 903' to 2nd Level .070 R/hr
- Alarm OS Offscale L_________.__.______,__________..__________._____ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ - _
1 i ["] RADIATION MONITOR DATA Time - 0915
) t - 01/45 l
1 PROCESS AND VENT MONITORS PANEL VBDG Rx Bldg Vent Eff (RMV-PR-40) 0 uC1/sec ERP Stack Normal Eff (RMP-RM-3A) 6.0 E-1 uCi/sec ERP Stack High Range (RMP-RM-3B) 0 uCi/sec Turbine Bldg Vent Eff (RMV-RM-20A) 1.5 E-3 uCi/see Turbine Bldg High Range (RMV-PR-20B) 0 uCi/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 1.0 E-3 uCi/sec RW/ARW Bldg High Range (RMV-PR-30B) 0 uCi/sec PANEL 9-10 ! Mn. Stm Rad Monitor Ch. A1, B1 300 mR/hr 350 mR/hr Ch. A2, B2 300 mR/hr 260 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 35 mR/hr 25 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 13 mR/hr 14 mR/hr Service Water 10 cps Reactor Equipment Cooling 20 cps m . 1 1 l l 1 ( i t i e I ( 1 l
j l
/~T 1987 Evaluated Exercise Time - 0915 I k
\ Message Number: 12 t - 01/45 l
*l COOPER NUCLEAR STATION I
EMERGENCY PREPAREDNESS EXERCISE MESSAGE For Controller Use Only: . l CONTROLLER INFORMATION: ) 1 o The "A" Reactor Protection. System (RPS) motor-generator set (MG set) l tripped due to a faulty voltage regulator, causing all scram annunciators and 1/2 scram indications to alarm in the Control Room l and causing 1/2 isolations for Groups 2, 3 and 6. o Allow electricians to repair in real time. Completion of repair is not critical to the scenario time line. 1 ( o The switch to Alternate power for "A" RPS should be acknowledged as '
. successful by the Control Room controller. Groups 2 and 3 1/2 isolation resets are also successful except that Scram Instrument Volume (STV) Inboard Drain Valve does not reopen. See message
)
V i EXPECTED ACTIONS: o Control Room will dispatch an operator or an electrician to ' determine cause of "A" RPS MG set trip. (See message ). 1 I o Control Room operators switch to alternate feed for "A" RPS per procedure 2.4.6.12 and re energize. o Control Room operators then reset isolations per 2.1.22. o When the MG Set is restarted after repairs, Control Room will switch power back to the MG Set. I l l l f k
l
~
\ ! .) 1 1
<-s- 1987 Evaluated Exercise Time - 0920 (approx.) \.
s Message Number: 13 t - 01/50 (approx.) COOPER NUCLEAR STATION
'i EMERGENCY PREPAREDNESS EXERCISE MESSAGE l
Message for: Control Room Simulated Plant Conditions: Message:
***THIS IS A DRILL ***
Indications in the Control Room include: 1 o RPS 'A' is re-energizedsand all isolations are reset. o All Group 2, 3, and 6 isolation valves have red light indications, except o CRDH CV-32A, B - Red lights illuminated ( o CRDH-CV Red lights off
- Green light illuminated l
l l l-l l \
f] 1987 Evaluated Exercise Time - 0920 (approx.) Message Number: 13 t - 01/50 (approx.) COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE For Controller Use Only: CONTROLLER INFORMATION: o Deliver this message only after Control Room operators take appropriate actions to restore alternate power to RPS "A" and~to reset the Group 2, 3 and 6 half isolations. o Scram Discharge Instrument Volume drain valve CV34 has failed to re-open when the isolation is reset. (Refer to Attached drawing). EXPECTED ACTIONS: o Dispatch an operator to investigate an attempt reopening malfunctioning drain valve. \ N 1 l 1 r f\ ___.__.__._._1...___________
D N E 3 3 I S 2 2 r
+ + e V V D D t
it m e 3 s j S S s n lu d ( f f E . o o a r " o K V < T U M DC* L k k A n n l m OO6 V a a e r RL 4 BB v e' 'la B N I h h'L 'A > A t t - R r u - ~ - D -. ) S o oh SM V E NS L 'A S O V L ) T L E E S 4 N A 3 1 3 E V 2 V N 2 I ( ,< V A T l DR S E D L R D
) I I E T .. d <
HN U . T A O .. O: S U L A ) O C . 4 A T ( H ) n 3 1 M w .
. 2 32 o e.
- O .
2 ( R d '
. M 9 '
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)
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l f[<d , U . L _. '- O 7I gL V A S A E .. 1' G P 3 _ T R R A . L E C H 4 )C OR E C _ 3 1 3 T S P 2 H I 2 NP ID M ( E S E R A l l g T _ P O M M 7. I J. UL OM A LE . T R . f O OV e. *2 _ g# > _ A E VE . M9 1 T D V S L p 3 g O E _ L E S A L N N . A V G RE R6YiL.. P R A R CN V AI D R 8 A T S G S D . H A _ I
-
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N, 1987 Evaluated Exercise Time - 0925 (approx.) '\ '
Message Number: 14 t - 01/55 (approx..) COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Message for: Repair Teara Investigating Trip of the "A" RPS MG Set Simulated Plant Conditions: Message: ~. l ***THIS IS A DRILL *** o Initial tests indicate extremely low voltage at the RPS power supply ) from the MG Set (<<30 volts). o When cover of the Voltage Regulator is removed to investigate the undervoltage problem; a broken lead on the rotating field slip ring is discovered. l
/O, N ,)
s
+
e.
! \ l
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)
.)
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N 1987 Evaluated Exercise Time - 0925 (approx.) ~' Message Number: 14 t - 01/55 (approx.)
COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSACE For Controller Use Only: CONTROLLER INFORMATION: o Provide this information only after appropriate troubleshooting has
~~
been conducted. o Repair / replacement may be simulated on a "real-time" basis. This . event does not impact the scenario time line. EXPECTED ACTIONS: o Inform the Control Room, and make arrangements to repair the broken
- f. lead.
I
\
i i l f
- I l l x-l
1987 Evaluated Exercise Time - 0930 ( Message Number: 15 t - 02/00 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Message for: Control Room Simulated Plant Conditions: See attached Plant Data Message: l _ 1 l ***THIS IS A DRILL *** Annunciators in the Control Room Include: NORTH SDIV NOT DRAINED Indications in the Control Room Include: CRDH-CV-34 Green lights illuminated s_-) l l l
,-,s
(\
I i i I I l 1 Time - 0930
}987EvaluatedExercise b jessage Number 15 COOPER NUCLEAR STATION t -
02/00 EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psigj FLOW (gpm) REACTOR POWER 100% APRM RHR A UNAVAIL 0 0 REACTOR LEVEL 35"
- NR RHR C STBY 50 REACTOR PRESSURE 1000 psig l RHR B STBY 50 0 CORE D/P (psig) 17.25 6
RHR D STBY 50 CORE FLOW (10 lbm/hr) 71.0 6 CS A STBY 50 0 FLOW (10 lbs/hr) l CS B STBY 50 0 FEEDWATER A 4.8 HPCI STBY 50 0 FEEDWATER B 4.8 Drywell Pressure .3 (psig) MAIN STEAM A 2.4 i I i Torus Level 0 (inches) MAIN STEAM B 2.4 fG r 4 OPEN CLOSED' MAIN STEAM C 2.4 MSIV 8 0 MAIN STEAM D 2.4 FLOW PANEL 9-4 CRD A 50 (gpm) l STATUS PRESS (psig) FLOU(gpm) CRD B AVAIL (gpm) l RCIC STBY 50 0 LEVEL PRESS SQUIB PUMPS RWCU A OPER 1000 100 SLC 75 % 0 (psig) ON UNAVAIL RWCU B AVAIL 0 0 l l RRPA 90 % SPD MISCELLANEOUS PANELS l ) RRPB 90 % SPD DIESEL GEN A STBY I 1 DIESEL GEN B STBY SBGT A STBY SBGT B STBY q DRYWELL COOLING NORMAL TORUS WATER TEMP 80 *F _ _ _ _ _ _ _ - - _____________-__n
(( a 0 0 0 1 g o
== 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 8 6 4 2 0 2 0 8 6 e t
)
4 1 12 1 0 -
)
F 1 1 m g 0 O q i T isp ( ( e r e u t r u a s r s e p e r P m r 5 1 e o - T t s c u r a e o R T I 0 3 E - S I C R N E 0 O X 0 5 0 0 0 5 0 5 0 0 0 5 0 0 T E I 4 2 0 2 1 1 + - 1 1 2
+ + - - - 2 1 1
+ +
A SS ) 0 T n S E
) -
( i n N A i ( R A E D T A l e v l e e v E L A R D L L e
.C r P S o s U E DP t c
u r N R S a 5 o R P e 1 T E Y R P C O N O E C G R E 0 M 3 E ' 1 3
)
0 0 0 0 0 M 0 8 6 2 0 0 0 0 0 0 0 0 R 1 7 6 5 4 3 2 1 P 0 . A
)
_ g isp _ G _ V ( _ A e _ ( r e r u i s e 5 s s c w 1
- e r o r e P P x r l E o l e
t d w te ;e c a y _ a e r l u R 0 3 D a - r e _ v g E a _ 7 ss 8 9 e 1 M
['~% RADIATION MONITOR DATA Time - 0930 ( t - 02/00 AREA RADIATION MONITORS READING STATION DESCRIPTION (mr/hr) 1 Rx Bldg. Fuel Pool Area (SE 5th Floor) 90 2 Rx Bldg Fuel Pool Area (SE 5th Floor) 30
- 3 Rx Bldg New Fuel Area (SE 5th Floor) 0.03 4 Rx Bldg Rx Water Cleanup Demineralized Area 15 (SW 3rd Floor) 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 1 6 Rx Bldg Neutron Monitor System Index Area. 90 (TIP Room ist Floor) 7 Rx Bldg Neutron Monitor System Drive Mech Ares 2 (SE 1st Floor) -
l 8 Rx Bldg Control Rod Hydraulic Equipment Area 0.8 (S 1st Floor) 9 Rx Bldg Control Rod Hydraulic Equipment Area 9 (N 1st Floor) l 10 Rx Bldg HPCI Pump Room (SW Quad) 0.4 l 11 Rx Bldg RHR Pump Room (SU Quad) 9 12 Rx Bldg RHR Pump Room (NW Quad) 15 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 7' 4 14 Rx Bldg CS Pump Room (SE Quad) 7 l \%_ ,/ 15 Turbine Bldg Turbir.e Front Standard 100 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.2 17 Turbine Bldg Turbine Bldg Basement Control Corridor 0.04 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 8 19 Turbine Bldg Turbine Bldg Condensate Pump Area 0.1 20 Control Room Main Control Room 0.015 21 Grade Level Control Corridor 0.25 22 Radwaste Control Room 0.02 23 Radwaste Pump Room 7 24 Radwaste Basement Equipment Area 3 25 Radwaste Demin Valve Room 2 26 Radwaste Conveyor Aisle Operating Area 0.03 27 SPARE 28 Radwaste Lab Area 0.2 29 Centrifuge East 10 30 Centrifuge West 9 Panel 9-02 Personnel Airlock Area 903' .105 R/hr Panel 9-02 Ladder 903' to 2nd Level .070 R/hr
- Alarm OS Offscale s
I _______________j
{ RADIATION MONI. TOR DATA Time - 0 PROCESS AND VENT MONITORS l PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 0 uCi/sec ERP Stack Normal Eff (RMP-RM-3A) 6.0 E-1 uCi/sec ] ERP Stack High Range (RMP-RM-3B) 0 uCi/sec l Turbine Bldg Vent Eff (RMV-RM-20A) 1.5 E-3 uCi/see Turbine Bldg High Range (RMV-RM-20B) 0 - uC1/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 1.0 E-3 uCi/see RW/ARW Bldg High Range (RMV-RM-30B) 0 uCi/sec l I
'l PANEL 9-10 Mn. Stm. Rad Monitor Ch. A1, B1 300.mR/hr 350 mR/hr Ch. A2, B2 300 mR/hr 260 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 35 mR/hr 25 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 12 mR/hr 13 mR/hr !
Service Water 10 cps
/nJ Reactor Equipment Cooling 20 cps G ,
/~'N 1987 Evaluated Exercise Time - 0930 Message Number: 15 t - 02/00
)
COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE For Controller Use Only: 1 CONTROLLER INFORMATION: a i o Because SDIV drain valve CV34 remained closed when the isolations were reset, the Scram Discharge Volume has started fill (alarm level is lib"), due to leakage by the scram valves. At this rate, the 92" SDV High Water Level Trip would occur in approximately 2 hours. ] l o Per Procedure 2.3.2.27, an operator will.be dispatched to open the ] valve. Upon inspection of the valve, he will find it closed but { 1eaking at the packing. (See message ) ! EXPECTED ACTIONS: C o Verify scram discharge volume vent and drain valves open. o Check full core display for any scram valves open indication. I o Dispat:h operator to check status of volume vent and drain valves. If valve is closed, open manually and stand by while operating o , manually. o Maintain communications with Control Room. The "B" solenoid for CV-34 was already denergized. i 1 1 i i
l C 1987 Evaluated Exercise Time - 0935 (approx.) b} Message Number: 16X t 02/05 (approx.) COOPER NUCLEAR STATION EMEF.GENCY PREPAREDNESS EXERCISE MESSAGE Message for: Operator investigating SDIV Drain Valve CV-34 Simulated Plant Conditions: Message:
***THIS IS A DRILL ***
l l There is a puddle of water on the floor near the Scram Discharge Instrument Volume drain line. Valve CV-34 ic closed, and leaking water from the packing. l l l 1 l l I l i 1 _ _ - - _ - - _ _ _ _ _ _ _ _ _ - _ _ _ - _ _ _ _ - _ _ _ _ _ _ - _ - _ _ _ _ _ __-____-____a
l l f'~'s 1987 Evaluated Exercise Time - 0935 (approx.) Message Number: 16X t - 02/05 (approx.). COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE For Controller Use Only: CONTROLLER INFORMATION: n Deliver this information to the operator dispatched to investigs ce the closed drain valve (CV-34). 1 I EXPECTED ACTIONS: o Attempt to open valve (successful) o Call mechanic to fix packing leak l fx j 1
(N 1987 Evaluated Exercise Time - 0940 ( Message Number: 17X t - 02/10 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Message for: TSC Maintenance Coordinator Simulated Plant Conditions: Message:
***THIS IS A DRILL ***
l Dispatch a mechanic to repair the packing leak in CRDH-CV-34 at this time. 1 i d 1 [. u
i 1987 Evaluated Exercise Time - 0940 i
/$ l i 1 l
Message Number: 17X t - 02/10 1 i COOPER NUCLEAR STATION 1 EMERGENCY PREPAREDNESS EXERCISE MESSACE i i For Controller Use Only: 1 j CONTROLLER INFORMATION: i o Deliver this message if a mechanic is not being dispar;hed to repair .] CRDH-CV-34. This mechanic will be the contaminated, .njured man and ; is required to be in location near the North SDIV prior to 1000 a.m. EXPECTED ACTIONS: ) i
\
J . l 1
]
i I
1 I l (~' 1987 Evaluated Exercise Time - 0945 I k Message Numbert. 18 t - 02/15 COOPER NUCLEAR STATION ] EMERCENCY PREPAREDNESS EXERCISE MESSAGE i Message for: Control Room I l I Simulated Plant Conditions: See attached Plant Data j Message: ,
***THIS IS A DRILL ***
Annunciators in the Control Room include: RECIRC. PUMP A MOTOR VIBRATION HIGH .. 1 - a i 4
^
l l l l
~ /
1 i
- _ .-_-._--_-----__A
I 987 Evaluated Exe,rcise Time - 0945 y lessage Number 18 COOPER NUCLEAR STATION t - 02/15 EMERCENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 100% APRM RHR A UNAVAIL 0 0 REACTOR LEVEL 35"
- NR RHR C STBY 50 REACTOR PRESSURE 1000 psig i
RHR B STBY 50 0 CORE D/P (psig) 17.25 l 1 6 RHR D STBY 50 CORE FLOW (10 lbm/hr) 71.0 I 6 CS A STBY 50 0 FLOW (10 lbs/hr) CS B STBY 50 0 FEEDWATER A 4.8 HPCI STBY 50 0 FEEDWATER B , 4.8 l Drywell Pressure .3 (psig) MAIN STEAM A 2.4 I Torus Level 0 (inches) MAIN STEAM B 2.4
. 1 OPEN CLOSED MAIN STEAM C '] ,
2.4 j ,d \ MSIV 8 0 MAIN STEAM D 2.4
]
1 _ FLOW PANEL 9-4 CRD A 50 (gpm) ) l STATJU PRESS (psig) FLOW (gpm) CRD B AVAIL (gpm) RCIC STBY 50 0 LEVEL PRESS S SQUIB P_ UMP _S, RWCU A OPER 1000 100 SLC 75 % 0 (psi d ON UNAVAIL RWCU B AVAIL 0 0 j RRPA 90 % SPD MISCELLANEOUS PANELS i RRPB 90 % SPD DIESEL GEN A STBY DIESEL GEN B STBY SBGT A STBY SBGT B STBY DRYWELL COOLING NORMAL (j TORUS WATER TEMP 80 'F 1
a c 0 8 S ' 8 1 I
= = 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 8 6 2 0 2 0 8 6 e t
)
4 1 12 0 1 4 ) F 1 1 - m g 0 O . i is ( T p e
- ( r e t u
r u a s r s e e p r P m r 5 1 e o - T t s c u a r e o R T 0 3 E - S I C R N E 0 _ O X 0 5 0 0 0 5 0 5 0 0 0 5 0 0 T E I 2 O 2 _ 1 1 + - 1 1 2 4
+ + ' - - - - 2
+
1
+
1 A S
)
T SE n 0 ) n S i ( N A l i ( R D T e _ l A E A v e
- e v E R D L e L A r L C P S o s U E DP t c
u r N R a o P 'S 5 R e 1
- T E Y R
_ P C O N O E C G . R E 0 M 3 E 3
)
0 0 0 0 0 M _ 0 8 6 2 0 0 0 0 0 0 0 0 R 1 7 6 5 4 3 2 1 _ P 0 A
)
% g G isp V (
A e ( r e r u i s e 5 s s c w 1 e r o - r e P P x r _ E o l l t e d e e c w t a y _ a e r _ l u R 0 3 D _ a e v E ga 7 s s 8 e 9 1 M
/T RADIATION MONITOR DATA Time - 0945
.t - 02/15
! )
U AREA RADIATION MONITORS
, READING STATION DESCRIPTION (mr/hr) 1 Rx Bldg Fuel Pool Area (SE Sch Floor) 90 2 Rx Bldg Fuel Pool Area (SE 5th Floor) 20
- 3 Rx Bldg New Fuel Area (SE 5th Floor) 0.03 4 Rx Bldg Rx Water CleanupfDemineralizer Area 15 (SW 3rd Floor) . .
5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 1 6 Rx. Bldg Neutron' Monitor System Index Area 90 (TIP Room 1st Floor). 7 Rx Bldg Neutron Monitor System Drive Mech Ares - 2 (SE lst Floor) 8 Rx Bldg Control Rod Hydraulic Equipment Area 0.#
-(S lst Floor) 9 Rx Bldg Control Rod Hydraulic Equipment Area 9 (N lst Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) 0.4 11 Rx Bldg RHR Pump Room (SW Quad) 9 12 Rx Bldg RHR Pump Room (NW Quad) 15 p- s 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 7 14 .Ebc Bldg CS Pump Room (SE Quad) 7 15 Turbine Bldg Turbine Front Standard 100 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.2 17 Turbine Bldg Turbine Bldg Basement ~ Control Corridor 0.04 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 8 19 Turbine Bldg Turbine Bldg Condensate Pump Area 0.1 20 Control Room Main Control Room 0.015 21 Grade Level Control Corridor 0.25 22 Radwaste Control Room 0.02 23 Radwaste Pump Room 7 24 Radwaste Basement Equipment Area 3 25 Radwaste Demin Valve Room 2 26 Radwaste Conveyor Aisle Operating Area 0.03 27 SPARE 28 Radwaste Lab Area 0.2 29 Centrifuge East 10 30 Centrifuge West 9 l Panel 9-02 Personnel Airlock Area 903' .105 R/hr Panol 9-02 Ladder 903' to 2nd Level .070 R/hr
- Alarm OS Offscale >
/
- s. s
i A RADIATION MONITOR DATA Time - 0945 t - 02/15 PROCESS AND VENT MONITORS
, PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) ~0 . uCi/sec , ERP Stack Normal Eff (RMP-RM-3A) 6.0 E-1 uCi/sec .i ERP Stack High Range (RMP-RM-3B) 0 uCi/sec 1 Turbine Bldg Vent Eff (RMV-RM-20A) 1.5 E-3 uCi/see Turbine Bldg High Range (RMV-PJ1-20B) 0 uCi/sec l RW/ARW Bldg Combined Eff (RMV-RM-30A) 1.0 E-3 uCi/sec~ )
RW/ARW Bldg High Range (RMV-RM-30B) 0 uCi/sec .l 1 l PANEL 9-10 - Mn. Stm. Rad Monitor Ch. A1, B1 300 mR/hr 350 mR/hr . Ch. A2, B2 300 mR/hr 260 mR/hr I SJAE Off Gas Log Rad Monitor Ch. A, B 35 mR/hr 25 mR/hr. , Rx Bldg Vent Ind/ Trip Unit Ch. A, B 11 mR/hr 12 mR/hr Service Water - 10 cps i J Reactor Equipment Cooling 20 cps I i l l r O
% 1987 Evaluated Exercise Time - 0945 U Message Nu-her: 18 t - 02/15
.j 1
COOMR NUCLEAR STATION i EMERGENCY PREPAREDNESS EXERCISE MESSAGE I, For Controller Use Only: CONTROLLER INFORMATION: o "A" Recirculation Pump has begun to deteriorate slowly as indicated ) by the initially small increase in vibration. Control Room l operators will not be allowed shutdown. If the pump is run-back, the vibration will reduce to nelow ala';m levels. If operators ' attempt to increase che pump qssed after clearing the alarm, the vibration remains less than the alarm set The alarm will also i clear when they push the " RESET" button. l l l EXPECTED ACTIONS: i
\ o Implement Annunciator 9.4.3 Alarm Response Procedure 2.3.2.26 U o Monitor pump vibration amplitude usir.g process computer point on a q trend pen.
.]
I l f l l I l l 1 e l i u
1987 Evaluated Exercise Time - 1000 (] Message Number: 19 t - 02/30
.I COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Message for: Control Room I I
Simul'ated Plant Conditions: See attached Plant Dar.a I Message: )
***THIS IS A DRILL ***
Annunciators in the Control Room include: l RECIRC PUMP A MOTOR HIGH VIBRATION l MG SET A DRIVE MOTOR LOCKOUT f RECIRCULATION GENERATOR A LOCKOUT MAIN STEAM LINE HIGH RADIATION TRIP MAIN STEAM LINE ISOLATION VALVES NOT FULL OPEN TRIP 1 GROUP 1 ISOLATION CHANNEL A(B) i AUTO SCRAM TRIP SYSTEM A(B)
\ RECIRC A(B) TRIP HICH PRESSURE / LOW LEVEL REACTOR VESSEL CHANNEL A(B) LCW LOW WATER LEVEL LOW-LOW SET LOGIC A OR B ARMED REACTOR BUILDING HICH RADIATION Indications in the Control Room include:
All SCRAM blue lights are on Full core display: all full in green lights are on , HPCI normal autostart d RCIC normal autostart -l SRV 71D, F amber lights are on Valve position indication lights for Groups 1, 2, 3, 6, 7 indicate successful isolation All electrical transfers are normal l e m U
1 I l I 1 l r1987 Evaluated Exercise Time - 1000 essage Number 19 COOPER NUCLEAR STATION t - 02/30 EMERCENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 0 APRM l RHR A UNAVAIL 0 0 REACTOR LEVEL -40t WR l I RHR C _ STBY 50 REACTOR PRESSURE 1050 psig l RHR B STBY 50 0 CORE D/P (psig) 2.8 I 0 RHR D STBY 50 CORE FLOW (10 lbm/hr) 7.1 6 CS A STBY 50 0 FLOW (10 lbs/hr) CS B STBY 50 0 FEEDWATER A 0 HPCI OPER 1200 4,250 FEEDWATER B 0 l Drywell Pressure .3 (psig) MAIN STEAM A 0 Torus Level 0 (inches) MAIN STEAM B 0 l OPEN CLOSED MAIN STEAM C 0
\A)
U MSIV O 8 HAIN STEAM D 0 FLOW PANEL 9-4 CRD A 160 (gpm) STATU3 PRESS (psig) FLOW (gpm) CRD B AVAIL (gpm) RCIC OPER 1150 400 LEVEL PRESS SQUIB PUMPS RWCU A ISOIATED 0 0 SLC 75 % 0 (psig) ON UNAVAIL RWCU B ISOLATED 0 0 RRPA 0 % SPD MISCELLANEOUS PANELS RRPB 0 % SPD DIESEL GEN A OPER DIESEL CEN B OPER l l SBGT A OPER 1 SBGT B OPER p DRYWELL COOLING NORMAL TORUS WATER TEMP 80 *F
g M" p
. = = 0 0 0 0 0 0 0 0 0 0 0 0 -
0 0 0 0 8 6 2 0 2 0 8 6 e t
)
4 1 2 1 0 1
)
F 1 1 m ig 0 O _ i s ; ( T p e ( r e t u r u a r s s e e p r P m r 5 1 e o - T t s - c u a r e o R T 0 3 E - S I C N E R 4 o O X 0 5 0 0 0 5 0 0 5 0 0 0 5 0 0 I T E 1 1 + - 1 1 2 4 2 0 2
+ + - - - 2 1 1
+ -
A SS ) I 0
+
T n S E
) -
i ( n N A ( i R A E A D T l e v l e e v E L A R D L L e ( C P S U E DP N R t r o c _ s u r P S a 5 o R e 1
- T E Y R P C _.
O N O E C G R E 0 M 3 E 0 3
)
0 0 0 0 0 0 M 0 8 6 4 2 0 0 0 0 0 0 0 R 1 7 6 5 4 3 2 1 P ' 6l q 0 - . A
)
% i g
G s p V ( A ( e r e r u i s e 5 s s c w 1
- e r o r e P P x r
_ E o H t c d c w t e 9
# a y
_ a e r u R 0 D
- l a
v e 3 _ E ga 7 s _ s 8 9 e 1 M
i i j'N RADIATION MOTITOR DATA Time - 1000-3.v ) t - 02/30 AREA RADIATION MONITORS ~- . READING l STATION DESCRIPTION (mr/hr) 1 Rx Bldg Fuel Pool Area (SE Sch Floor) 90
~2 Rx Bldg Fuel Fool Area (SE 5th Floor) 10
- j 3 Rx Bldg New Fuel Area (SE 5th Floor) 0.03 i 4 Rx Bldg Rx Water Cleanup Demineralized Area 80 (SW 3rd Floor) '
5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 20 6 Rx Bldg Neutron Monitor System Index Area 90 . ; (TIP Room 1st Floor) ! 7 Rx Bldg Neutron Monitor System Drive Mech Ares 2 ) (SE 1st Floor) ; (. 8 Rx Bldg Control Rod Hydraulic Equipment Area 0.8 j (S lst Floor) ( Rx Bldg Control Rod Hydraulic Equipment Area
~
9 9 (N lst Floor) ! 10 Rx Bldg HPCI Pump Room (SW Quad) OS
- l 11 Rx Bldg RHR Pump Room (SW Quad) OS
- 12 Rx Bldg RHR Pump Room (NW Quad) OS * !
p 13 Rx Bldg RCIC/CS Pump Room (NE Quad) OS *
/)
(/ 14 15 Rx Bldg CS Pump Room (SE Quad) Turbine Bldg Turbine Front Standard OS *- 50 j 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.2 ] 17 Turbine Bldg Turbine Bldg Basement Control Corridor 0.04 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 8 i 19 Turbine Bldg Turbine Bldg Condensate Pump Area 0.1 1 20 Control Room Main Control Room 0.015 21 Grade Level Control Corridor 0.25 - 22 Radwaste Control Room 0.02 23 Radwaste Pump Room 7 24 Radwaste Basement Equipment Area 3 25 Radwaste Demin Valve Room 2 26 Radwaste Conveyor Aisle Operating Area 0.03 27 SPARE 28 Radwaste Lab Area 0.2 29 Cen'trifuge East 10 30 Centrifuge West 9 Panel.9-02 Personnel Airlock Area 903' l.2 R/hr Panel 9-02 Ladder 903' to 2nd Level 0.9 R/hr
- Alarm '
OS Offseale V i
i l l [' RADIATION MONITOR DATA Time - 100') i t - 02/:s0 s PROCESS AND VENT MONITORS 1 PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 0 uCi/sec -] ERP Stack Normal Eff (RMP-RE-3A) 6 0 E-1 uCi/sec 1 ERP Stack High Range.(RMP-RM-3B) 0 uCi/see Turbine Bldg Vent Eff (RMV-RM-20A) 1.5 E-3 uCi/see Turbine Bldg High Range (RMV-RM-20B). O uCi/sec
.- RW/ARW Bldg Combined Eff (RMV-RM-30A) >1.0 E-3 uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) 0 -uCi/sec .q i
PANEL 9-10 I Mn. Stm.' Rad Monitor Ch. A1, B1 1200 mR/hr 1350 mR/hr l Ch. A2, B2 1200 mR/hr 1150 mR/hr. l SJAE Off Gas Log Rad Monitor Ch, A, B 150 mR/hr 140 mR/hr l . Rx Bldg Vent Ind/ Trip Unit Ch. A, B 10 mR/hr 11 mR/hr 1 i Service Water 10 cps iteactor Equipment Cooling 20 cps i j l j 1
1 l l Time - 1000' (] t - 02/30
)
CONTROL ROD MAP 51 00 00. 00 00 00 ' j 47 00 00 00' 00 00 00 00 00 00 1 43 00 00 00 00- 00 00 00 00 00 00
.j 39 00 00 00 00 00 00 00 00 00 00 00 '
35 00 00 00 00 00 00 00 00 00 00 00 00 00 {
. . . .i 31 00 00 00 00 00 00 00 00- 00 00 00 00 00 )
p 27 00 00 00 00 00 00 00 00' 00 00 00. 00 00 23 00 00 00 00 00 00 00 00 00 00 00 00 00 19 00 00 00 00 00 00 00 00 00 00 00 00 00 .i 13 00 00 00 00 00 00 00 00 00 00 00 11 00 00 00 00 00 00 00 00 00 00 00 i
's ,
07 00 00 00 00 00 00 00 00 00 00 03 00 00 00 00 00
\
02 06 10 14 18 22 26 30 34 38 42 46 50 J
!A ' '
.,g,
,4 ,
l - ( { ;;
,] 1987 Evaluated Exercise Time - 1000 Message Number: 19 t - 02/30 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSACE For Controller Use Only: CONTROLLER INFORMATION: o "A" Recire Pump impeller catastrophically separates from.its shaft. Debris from the impeller and casing enter the core and damage occurs-due to blocked flow channels and mechanical impingement on cladding, o The MSIVs isolate on 3X Normal Main Steam Line High Radiation. The reactor scrams and HPCI'and RCIC initiate and successfully restore reactor water level. SRVs cycle to control reactor pressure. A _ i cooldown to cold shutdown may be initiated, j
, )
o All group isolations are normal. . EXPECTED ACTIONS: ' \x 1 o Carry out immediate scram actions and verify automatic actions. o Operators begin torus coolin6 line up for RHR. 'I o Announce Scram and Hi Main Steam Radiation Alarm hazard on plant P.A. l l l O
[N 1987. Evaluated Exercise Time - 1000 t - 02/30 Message Number: 20 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Message for: Iodividual repairing CV-34 Simulated Plant Conditions: Message: , l
***THIS IS'A DRILL ***
The sudden noise caused by the reactor scram and water flow to the SDIV startled you, causing you to slip and fall in the puddle. You are unconscious. A i ( 9 e
f'~5s 1987' Evaluated Exercise Time - 1000
$\- ') Message Number: 20 t - 02/30 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE For Controller Use Only:
CONTROLLER INFORMATION: o See attached sheets for details regardi.ng results of contamination surveys and personnel injuries. l EXPECT 8D ACTIONS: I o HP on location will radio for help. f ' e a
l 1 O l The reactor scram /CRD activity startled the mechanic who jumped back, slipped and fell in the area where water had been leaking. Ile is unconscious ' and contaminated with a possible concussion. t.h., $ bsh , 6LEEb Mwy F l sacs ,
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V Q i o rier _s. A sact s. 3o i I riez Contamination levels of areas LOCATION CONTAMINATION LEVEL j
- I s ./ 1, 2 2000 cpm I 3 2500 cpm /
4 2200 epm 5 2800 cpm 6, 7 2100 cpm 8 1900 cpm General area radiation is 9 mR/hr. I Floor contamination is 4000 epm. Nasal smear (if taken) < 100 cpm Sean for ingestion of nuclides (if taken) indicates negative. First decontamination reduces all contamination levels by a factor of 2. Second decontamination reduces all contamination levels by another factor of 5. i ***THE IS A DRILL *** 1 V
'p CONTAMINATED VICTIM'S VITAL SIGNS Ambulance Arrives > - Ambulance Arrives Right Af ter Injury Within 30 minutes
- After 30 minutes *
, (Unconscious) (Unconscious) (Conscious)
. Pupils Unequal but reactive Unequal but reactive - Sluggish but reactive
~
Blood Pressure 140/60 140/60 130/70 Pulse 100 100' 80 Skin Pale, cool, sweaty Pale, cool, sweaty . Improving Respiration . 16 16 16 Note: These vital signs (depending on ambu' lance arrival time) will also be used initially ; at hospital
. 1 I
l 1 1 i I
***THIS E A DRILL *** I i
l 1 l _ _ _ _ _ . _ _ _ _ . _ _ _ _ . _ _ . _ . . _ _ _ _ _ _ . _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ . _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ ___ . _ _ _ _ _ __ ___________ __.______.________ _______ _ _ J
1987 Evaluated Exercise Time - 1005 (approx.)
\,, .
Message Number: 21X t - 02/35 (approx.) COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Message for: Control Room Simulated Plant Conditions: See attached Plant Data Messare: m
***THIS IS A DRILL ***
o TIP will not fully insert i o IRM Nos. ,
, and will also not insert I O '
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1987 Evaluated Exercise Time - 1005 (approx.) Message Number: 21X t - 02/35 (approx.) COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE For Controller Use Only: CONTROLLER INFORMATION: o Deliver this information as -Control Room Operator: take expected actions to drive the TIP and IRMs. o IRMs and SRMs should have been inserted per Procedure 2.1.4, Step VII.A.17. o Failure to complete insertion of incore instrumentation indic'ates
. flow channel blockage in the affected areas.
EXPECTED ACTIONS: l
. o Map area of suspected flow b, lockage. ;O .
o Declare a SITE AREA EMERGENCY per EPIP 5.7.1, Initiating Condition 2.5; Degraded Core with possible loss of coolable geometry; EAL 2.5.2, inability to insert in-core detectors, I l 1 l J
I 1 1
- /'"' 1987 Evaluated Exercise Time'- 1005 i Message Number: _22 t - 02/35 c 1
COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Message for: Control Room Simulated Plant Conditions: See attachment Plant Data , Message:
***THIS IS A DRILL ***
Annunciators in the Control Room include: , LOW-LOW SET LOGIC A OR B ARMED RELIEF VALVE OPEN REACTOR BUILDING HIGH RADIATION Indications in the Control Room include: O RV-71D, F Blue lights off l 1 i l l
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l I k 1 i _.___.._____..______._____.______.__J
i l I I i Time I005 ft987EvaluatedExercise - C J!essage Number 22 COOPER NUCLEAR STATION t - 02/35 EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (paig) FLOW (gpm) REACTOR POWER 900 SRM RHR A UNAVAIL
- 0 0 REACTOR LEVEL 40* VR l
RHR C STBY 50 REACTOR PRESSURE 1000 l RHR B STBY- 50 0 CORE D/P (psig) 0.3 l RHR D STBY 50 CORE FLOW (10 lbm/hr) 0.1 6 CS A STBY 50 0 FLOW (10 lbs/hr) ; CS B STBY 50 0 FEEDWATER A 0 , I HPCI OPER 1200 4250 FEEDWATER B 0 Drywell Pressure .3 (psig) MAIN STEAM A 0 Torus Level 0 (inches) MAIN STEAM B 0 l 1 O OPEN CLOSED MAIN STEAM C 0 I l MSIV 0 8 MAIN STEAM D 'O 1 FLOW ; i PANEL 9-4 CRD A 50 (gpm) l STATUS PRESS (psig) Fi.0W(gpm) CRD B AVAIL (gpm) RCIC OPER 1150 400 LEVEL PRESS SOUIB PUMPS RWCU A ISOLATED 0 0 SLC 75 % 0 (psig) ON UNAVAIL RWCU B ISOLATED 0 0 RRPA 0 % SPD MISCELLANEOUS PANELS RRPB 0 % SPD DIESEL GEN A OPER DIESEL GEN B _,OPER SBGT A OPER SBGT B OPER_ DRYWELL COOLING NORMAL TORUS WATER TEMP 82 'F
/ g
' g
= = 0 0 0 0 0 9 0 0 0 0 0 0 g 0 .
0 0 0 0 8 6 e 4 2 0 8 2 o ) 2 0 t 1 1 1
) 1 1 F
m g j 0 O i is ( T ( p e
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u s - r t u a _ s r s e - e p r P m r 5 1 e _. o - T s t c _ u _ a _ r e o - R T ~ 0 3 E - S I C J R Y O N E , ' O X 0 5 0 0 0 5 0 0 0 0 5 0 0 I T E 1
+ +
1 + 1 1 2 4 2 2 1 0 2 1 A SS )
- + + -
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in i ( N A ( R A D TA l e v l e E E R e v e L A, D L L C P SD r U E o s P t u r N R c S a 5 o R P e T 1 E Y R P C O N O E C G R . E M _ 0 3 E
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0 0 0 0 0 M 0 8 6 4 0 0 0 0 0 0 0 R 1 7 6 5 4 2 1 P -
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I I e O 1987 Evaluated Exercise , Time - 1005 Message Number: 22 t - 02/35 -) 1 1 COOPER NUCLEAR STATION I f EMERGENCY PREPAREDNESS EXERCISE MESSAGE ) For Controller Use Only: 1 CONTROLLER INFORMATION: o Reactor Water level restored and maintained by HPCI and RCIC. j o Low low set SRVs cycle normally to control pressure, o Reactor Building High Radiation alarm'is due to HPCI and RCIC steam f I lines. , EXPECTED ACTIONS: o Operators may secure one of the SBGT fans. ! J o Monitor post scram automatic functions. l 1 j l l 1 n v
^
1987 Evaluated Exercise Time - 1015 [
\ Message Number: 23 t - 02/45 .
COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE. Message for: Control Room Simulated Plant Conditions: .See attached Plant Data Message:
***THIS IS A DRILL ***
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[ ' 1987 Evaluated Exercise Time - 1015 i 6 - ( ,dessage Number 23_ COOPER NUCLEAR STATION t - 02/45 EMERGENCY PREPAREDNESS ~ EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 900 SRM RHR A UNAVAIL 0 0 REACTOR LEVEL 35"* WR CiR C STBY 50 REACTOR PRESSURE 950 , RHR B TRS. CLG 100 14,000 CORE D/P (psig) 0.3 J l 6 RHR D TRS. CLG 100 CORE FLOW (10 lbm/hr) 0.1
]
0 CS A STBY 50 0 FLOW (10 lbs/hr) CS B STBY 50 0 FEEDWATER A 0 HPCI i OPER 1200 As Req'd FEEDWATER B 0 Drywell Pressure .3 (psig) MAIN STEAM A 0 Torus Level .25 (inches) MAIN STEAM B 0 f
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OPEN CLOSED MAIN STEAM C 0 MSIV 0 8 MAIN STEAM D 0 FLOW PANEL 9-4 CRD A 50 (gpm) l STATUS PRESS (psig) FLOW (gpm) CRD B AVAIL (gpm) RCIC OPER 1100 400 LEVEL PRESS SQUIB PUMPS RWCU A ISOL 0 0 SLC 75 % 0 (psig)' ON UNAVAIL RWCU B ISOL 0 0 RRPA 0 % SPD MISCELLANEOUS PANELS RRPB 0 % SPD DIESEL CEN A OPER DIESEL GEN B OPER I SBGT A OPER SBGT B STBY DRYWELL COOLING NORMAL ( (/ TORUS WATER TEMP 88 'F
'o g.
= = -
0 0 0 0 0 0 0 0 0 0 0 0 0 o 0 '0 2 o o 8 6 e t
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4 1 2 1 0 1 ~ 8 6 -
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)
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+ + - - - 2 1 1 A SS )
- + + -
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,i l /N RADIATION MONITOR DATA' Time - 1015 :
(N._,e) t - 02/45 I AREA RADIATION MONITORS j READING j STATION DESCRIPTION (mr/hr) ) I 1 Rx Bldg Fuel Pool Area (SE 5th Floor) 90 2 Rx Bldg Fuel Pool Area (SE Sch Floor) 2 , 3 Rx Bldg New Fuel Area (SE Sth Floor) 0.03 j 4 Rx Bldg Rx Water Cleanup Demineralized Area' 90 *- j (SW 3rd Floor) 5 Rx Bldg Sludge.and Decant Pump Area (S 2nd Floor) 25 6 Rx Bldg Neutron Monitor System Index Area 90 (TIP Room ist Floor) " 7 'Rx Bldg Neutron Monitor System Drive Mech Ares 2 (SE 1st Floor) 8 Rx Bldg Control Rod Hydraulic Equipment Area 0.8 (S ist Floor) , I 9 Rx Bldg Control Rod Hydraulic Equipment Area 9 ! (N ist Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) OS * ; 11 Rx Bldg RHR Pump Room (SW Quad) OS * ; 12 Rx Bldg RHR Pump Room (NW Quad) , OS
- l f- s g) 13 Rx Bldg RCIC/CS Pump Room (NE Quad) '
OS
- l 14 Rx Bldg CS Pump Room (SE Quad) OS * *
\,2 15 Turbine Bldg Turbine Front Standard 10 j 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0,2 l 17 Turbine Bldg Turbine Bldg Basement Control Corridor 0.04 !
18 Turbine Bldg Turbine Bldg Rx Feed Pump Area -8 19 Turbine Bldg Turbine Bldg Condensate Pump Area 0.1 20 Control Room Main Control Room 0.015 21 Grade Level Control Corridor 0.25 1 22 Radwaste Control Room 0.02 23 Radwaste Pump Room 7 l 24 Radwaste Basement Equipment Area 3 l 25 Radwaste Demin Valve Room . 2 l l 26 Radwaste Conveyor Aisle Operating Area 0.03 27 SPARE ! 28 Racw aste Lab Area 0.2 l 29 Centrifuge East 10 30 Centrifuge West 9 l Panel 9-02 Personnel Airlock Area 903' 1.2 R/hr Panel 9-02 Ladder 903' to 2nd Level 0.9 R/hr
- Alarm OS Offscale
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O RADIATION MONITOR DATA Time - 1015 ( t - 02/45
~,
PROCESS AND VENT MONITORS PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 0 uCi/sec ERP Stack Normal Eff (RMP-RM-3A) 6.0 E-1 uCi/sec q ERP Stack High Range (RMP-RM-3B) 0 uCi/sec l Turbine Bldg Vent Eff (RMV RM-20A) 1.5 E-3 uCi/sec Turbine Bldg High Range (RMV-RM-20B) 0 uCi/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 1.0 E-3 uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) 0 uCi/see PANEL 9-10 l Mn. Stm. Rad Monitor Ch. A1, B1 45 mR/hr 40 mR/hr Ch. A2, B2 40 mR/hr 45 mR/hr SJAE Off Gas Log Rad Monit'or Ch. A, B 1 mR/hr 1 mR/hr .i Rx Bldg Vent Ind/ Trip Unit Ch. A, B 2 mR/hr 3 mR/hr . Service Water 10 cps
, Reactor Equipment Cooling 20 cps *
) \ I l d 1 c_____________________________________________ _ _ - _ _ . _ _ _ _
j 1987 Evaluated Exercise ' Time - 1015
~tA)
Message Number: 23 t - 02/45 i i COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE For Controller Use only: CONTROLLER INFORMATION: o ' Data reflects reactor pressure. control by SRV 71D, F low low set logic (between 850 and 1015 psig) and level con ~ trol by HPCI and RCIC. j o B&D RHR lined up for Torus Cooling. EXPECTED ACTIONS: o Operators to limit controlled cooldown rata to cold shutdown to approximately 100*F/hr. l l l \ i i l l____________________ _ _ _ _ - . _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ j
4
/s 1987 Evaluated Exercise Time - 1025 (approx.)
Message Number: 24X t- 02/55 (approx.) 4
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COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE i Message for: Emergency Director Simulated Plant Conditions: Message: __
***THIS IS A DRILL *** I 1
Declare a Site Area Emergency per EPIP 5.7.1, Initiating Condition 2.5:
" Degraded core with possible loss of coclable geometry".
1 I 1 I ps .
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(s_/ I i w_---_-___________________________________-___________-____________. _ _ _ _ _ _ __ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
1 l l 1 l 1987 Evaluated Exercise Time - 1020 (approx.) i/'] j
\ ') Message Number: 24X t- 03/50 (approx.)
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COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE For Controller Use Only: CONTROLLER INFORMATION: o Deliver.this message only_if a Site Area Emergency has not already been declared, and if there are no discussions in progress that would result in that declaration.
]q EXPECTED ACTIONS: )
i l i v .i i 1 1 1 l l I
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I i l l 1987 Evaluated Exercise . Time - 1030
'% Message Number: 25 t - 03/00 .
COOPER NUCLEAR STATION
)
EMERGENCY PREPAREDNESS EXERCISE MESSAGE 1 l Message for: Control Room I Simulated Plant Conditions: See attached Plant Data l l Message:
***THIS IS A DRILL *** j I
1 I i 1 l r
f m 1987 Evaluated Exercise Time - 1030
!essage Number 25 COOPER NUCLEAR STATION t -
03/00 EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 900 SRM RHR A UNAVAIL 0 0 REACTOR LEVEL 35"* WR RHR C STBY 50 REACTOR PRESSURE 550 RHR B TRS. CLG 100 14,000 CORE D/P (psig) 0.3 6 RER D TRS CLG 100 CORE FLOW (10 lbm/hr) 0.1 6 CS A STBY 50 0 FLOW (10 lbs/hr) CS B STBY 50 0 FEEDWATER A 0 HPCI OPER 750 As Reg'd FEEDUATER B 0 Drywell Pressure .3 (psig) MAIN STEAM A 0 Torus Level 0.3 (inches) MAIN STEAM B 0 OPEN CLOSED MAIN STEAM C 0 MSIV 0 8 MAIN STEAM D 0 i FLOW j i PANEL 9-4 CRD A 50 (gpm) i I STATUS PRESS (psig) FLOU(gpm) CRD B AVAIL (gpm) i RCIC OPER 700 400 LEVEL PRESS SQUIB PUMPS l RWCU A ISOL 0 0 SLC 75 % 0 (psig) ON UNAVAIL I RUCU B ISOL 0 0 -- { RRPA 0 % SPD MISCELLANEOUS PANELS RRPB 0 % SPD DIESEL GEN A OPER i DIESEL GEN B OPER ) 1 SBGT A OPER j SBGT B STBY l DRYWELL COOLING NORMAL i ( TORUS WATER TEMP 87 'F i
D' l 7
= = ' 0 0 n 0 0 0 0 0 0 n 0 0 0 0 0 0 0 0 e t 4 1
2 a g 8 6 2 0 ) 2 1 0 1 8 6
) 1 m- F g 0 i
is O ( T p e ( r e u r t u a s r ~ s e e p r P m r 5 1 e o :
- T "
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) 0 3
S I C _ R y N E , O X 0 0 5 0 0 5 0 0 0 0 0 T E I 2 1 1 + ~ 1 2 4 2 0
+ + - ~ - 2 1 1
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+ + -
_ T S E ( in ) n
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_ N A l ( i _ R D T e v l e _ A E A e v E L R A D L L e C P S r U E DP o s _ t u N R c r o _ S a 5 R P e T _ 1 _ E Y R P C O N O E _ C G R E 0 _ M 3 E , J _ ) M 0 0 0 0 0 _ 8 6 0 0 0 . 0 4 2 0 0 0 0 0 R 7 6 5 4 3 2 1 P - 0 - A _ )
% ig G s p
V ( _ A e _ ( r _ e r u s _ i s e - 5 s _ c w 1 e r o - r e P _ P _ x r E o l l e t _ de n c w t 2 a y a e r u R 0 D b3 l a - v e E ga 7 s 9 8 e . 1 M
l fG RADIATION MONITOR DATA Time 1030 )
-( t - 03/00 :)
)
AREA RADIATION MONITORS READING j STATION DESCRIPTION (mr/hr) l 1 Rx Eldg Fuel Pool Area (SE Sch Floor) 90 2 Rx Bldg Fuel Fool Area (SE 5th Floor) 2 3 Rx Bldg New Fuel Area (SE 5th Floor) 0.03 4 Rx Bldg Rx Water Cleanup Demineralized Area 110 * ! (SW 3rd Floor) j 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 30 ; 6 Rx Bldg Neutron Monitor System Index Area 90 . (TIP Room ist Floor) 1 7 Rx Bl.dg Neutron Monitor System Drive Mech Ares 2 I (SE 1st Floor) - l 8 Rx Bldg Control Rod Hydraulic Equipment Area' 2 j (S ist Floor) ; 9 Rx Bld3 Control Rod Hydraulic Equipment Area 9 l (N lst Floor) i 10 Rx Bldg HPCI Pump Room (SW Quad) OS
- 11 Rx Bldg RHR Pump Room (SW Quad) OS
- 12 Rx Bldg RHR Pump Room (NW Quad) OS * !
13 Rx Bldg RCIC/CS Pump Room (NE Quad) OS
- l
/c 14 Rx Bldg CS Pump Room (SE Quad) OS *
( 15 Turbine Bld5 Turbine Front Standard 2
]
l 16 Turbine Bldg Turbine Bldg Mezz Control Corridor. 0.2 ! 17 Turbine Bldg Turbine Bldg Basement Control Corridor 0.04 j 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 8 19 Turbine Bldg Turbine Bldg' Condensate. Pump Area 0.1 20 Control Room Main Control Room 0.015 21 Grade Level Control Corridor 0.25 22 Radwaste Control Room 0.02 23 Radwaste Pump Room 7 ! 24 Radwaste Basement Equipment Area 3 1 25 Radwaste Demin Valve Room 2 l 26 Radwaste Conveyor Aisle Operating Area 0.03 ; 27 SPARE j 28 Radwaste Lab Area 0.2 i 29 . Centrifuge East 10 ] 30 Centrifuge West 9 ) i Panel 9-02 Personnel Airlock Area 903' l.5 R/hr i Panel 9-02 Ladder 903' to 2nd Level 1.1 R/hr
- Alarm OS Offscale O j i
w _ __ _ - _ -- -_- . - a
'C RADIATION MONITOR DATA- Timo - 1030
( t - 03/00 s. PROCESS AND VENT MONITORS PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 0 uCi/sec ) ERP Stack Normal Eff (RMP-RM 3A) 6.0 E-1 uCi/sec I ERP Stack High Range (RMP-RM-3B) 0~ uCi/sec Turbine Bldg Vent Eff (RMV-RM-20A) 1.5 E-3 uCi/see Turbine Bldg High Range (RMV-RM-20B) 0 uCi/sec RW/ARW Bldg Combined Eff (RMV RM-30A) 1.0 E-3 uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) 0 uC1/see PANEL 9-10 Mn. Sem. Rad Monitor Ch. Al, B1 45 mR/hr 40 mR/hr ] Ch. A2, B2 40 mR/hr 45 mR/hr SJAE Off Cas Log Rad Monitor Ch. A, B 1 mR/hr 1 mR/hr Rx Blds Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hr 0.7 mR/hr i Service Water 10 cps I r Reactor Equipment Cooling 20 cps V 3 l I i l O i) b l
i i j
~'s 1987 Evaluated Exercise Time.- 1030
^~' Message Number: 25 t - 03/00 COOPER NUCLEAR STATION ij
. EMERGENCY PREPAREDNESS EXERCISE MESSAGE For Controller Use Only:
CONTROLLER INFORMATION: o Cooldown at 100*F/hr continues , EXPECTED ACTIONS: l o Assess cause of accident j o Request PASS sample w Complete actions required by EPIP 5.7.4, Site Area Emergency
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i (] 1987 Evaluated Exercise Time - 1045 Message Number: 26 t - 03/15
.,s C3',PER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE I
Message for: Control Room Simulated Plant Conditions: See attached Plant Data Message:
***THIS IS A DRILL ***
i I i l I l 4 i j j t
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i I, k., -. 987 Evaluated Exircise Time - 1045 if'l bassage Number. 2 p_ . COOPER NUCLEAR STATION t - 03/15 EMERGENCY PREPAREDNESS EXERCISE PLANT DATA ! j
, PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) RFACTOR POWER. 900 SRM -
RHR A UNAVAIL 0 0 REACTOR LEVEL 35"4 WR l 1 RHR C STBY 50 REACTOR PRESSURE 410 l 1 RHR B TRS. CLC 100 14,000 CORE D/P (psig) 0.3 ) 0 RHR D TRS. CLG 100 CORE FLOW (10 lbm/hr) 0.1 6 CS A STBY 50 0 FLOW (10 lbs/hr) CS B STBY , 50 0 .FEEDWATER A 0 HPCI OPER ,, 600 As Reo'd FEEDWATER B 0 Drywell Pretsure .3 (psig) MAIN STEAM A 0 j l i Torus Level 0.3 (inches) MAIN STEAM B 0 ' l ,/ OPEN CLOSED MAIN STEAM C 0 I
' MSIV 0 8 MAIN STEAM D 0 FLOW PAflFL!M CRD A 50 (gpm)
STATUS PRjg(psig) FLOW (epm) CRD B AVAIL (gpm) ) l l RCIC OPER _ 560 400 LEVEL PRESS SQUIB PUMPS 1 1 RWCU A ISOL 0 0 SLC 75 % 0 (psig) ON UNAVAIL l RWCU B ISOL _, 0 0 RRPA 0 % SPD MISCELLANEOUS PANELS RRPB 0 % SPD DIESEL GEN A OPER j DIESEL GEN B OPER ! i SBCT A OPER i SBGT B STBY DRYWELL C00LINC NORMAL v TORUS WATER TEMP _ 87 'F 1
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RADIATION MONITOR DATA Time - 1045 (N)
%f t - 03/15 AREA RADIATION MONITORS READING STATION DESCRIPTION (mr/hr)~
11 Rx Bldg Fuel Pool _ Area.(SE 5th Floor) 90 2 Rx Bldg Fuel Pool Area (SE Sch Floor) 2 3 Rx Bldg New Fuel Area (SE 5th Floor) 0.03 4 Rx Bldg Rx Water Cleanup Demineralized Area 125 * (SW 3rd Floor) 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 35 6 Rx Bldg Neutron Monitor System Index Area 90 (TIP Room 1st Floor) 7 Rx Bldg Neutron Monitor System Drive Mech Ares 5 (SE ist Floor) 8 Rx Bldg Control Rod Hydraulic Equipment Area- 5 (S ist Floor) 9 Rx Bldg Control Rod Hydraulic Equipment Area 9 (N 1st Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) OS * , 11 Rx Bldg RHR Pump Room (SW Quad) OS
- 1 12 Rx Bldg RHR Pump Room (NW Quad) OS *
'p
- r. 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 05
- l ; 14 Rx Bldg CS Pump Room (SE Quad) OS *
\ 15 Turbine Bldg Turbine Front Standard 2 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.2 l 17 Turbine Bldg Turbine Bidg Basement Control Corridor 0.04 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 8 19 Turbine Bldg Turbine Bldg Condensate Pump Area 0.1 l 20 Control Room Main Control Room 0.015 l 21 Crade Level control Corridor 0.25 22 Radwaste Control Room 0.02 23 Radwaste Pump Room 7 l
24 Radwaste Basement Equipment Area 3 25 Radwaste DAmin Valve Room 2 26 Radwaste Conveyor Aisle Operating Area 0.03 27 SPARE 28 Radwaste Lab Area 0.2 29 Centrifuge East 10 30 Centrifuge West 9 Panel 9-02 Personnel Airlock Area 903' 1.5 R/hr Panel 9-02 Ladder 903' to 2nd Level 1.1 R/hr
- Alarm OS Offscale
[ t
\
l _ _ _ _ _ . - _ _ _ _ _ - _ _ - . _ - - - _ _ - _ _ _ _ - - _ - _ . - - _ - - _ . - - _ _ _ _ . . . - - _ _ - - _ _ . . _ - - - - _ _ _ _ - _ _ . . _ - _ _ . _ . _ _ _ _ - - _ _ _ _ - . - - . -..___--.__-s - - _ _ _ _ - . . _ - ~.----__._a
' g RADIATION MONITOR' DATA Time - 1045
( ) t - 03/15
%/
PROCESS AND VENT MONITORS
-PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) .O uCi/sec ERP Stack Normal Eff (RMP RM-3A) 6.0 E-1 uCi/sec ERP Stack High Range (RMP-RM-3B) 0 uCi/sec Turbine Bldg Vent Eff (RMV RM-20A) 1.5 E-3 uCi/see Turbine Bldg High Range (RMV-RM-20B) 0 uCi/see RW/ARW Bldg Combined Eff (RMV-RM-30A) 1.0 E-3'uCi/sec RW/ARW Bldg High Range (RMV-RM 308) 0 uCi/see PANEL 9-10 Mn. Stm. Rad Monitor Ch. A1, B1 45 mR/hr 40 mR/hr Ch. A2, B2 40 mR/hr 45 mR/hr SJAE Off Cas Log Rad Monitor Ch. A, B 1 mR/hr 1 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hr 0.7 mR/hr s Service Water 10 cps -
[ ; Reactor Equipment Cooling 20 cps
%d ,
/
1 k t___________ . _ . - - - - - - - - - - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _-- -
1 I i p 1987 Evaluated Exercise Time - 1045-Message Number: 26 t - 03/15 - COOPER NUCLEAR STATION EMERCENCY PREPAREDNESS EXERCISE MESSAGE l i For Controller Use Only: CONTROLLER INFORMATION: o Cooldown continues at approximately 100'F/hr.
" 4 EXPECTED ACTIONS: 1
)
f' is i I i i i i I
' _ - - . . _ _ ____-__-_____a
1987 Evaluated Exercise Time - 1100 Message Number: 27 t - 03/30 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE J l Message for: Control Room 1 Simulated Plant Conditions: See attached Plant-Data Message: -
***THIS IS A DRILL *** -
O d 1 1
r m1987 Evaluated Exercise Time - 1100 i i Q iessage Number 27 COOPER NUCLEAR STATION t - 03/30 EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 900 SRM RHR A UNAVAIL 0 0 REACTOR LEVEL 35"*- WR RHR C STBY 50 REACTOR PRESSURE 310 RHR B TRS. CLG 100 14,000 CORE D/P (psig) 0.3 6 RHR D TRS. CLG 100 CORE FLOW (10 lbm/hr) 0.1 6 CS A STBY 50 0 , FLOW (10 lbs/hr) CS B STBY 50 0 FEEDWATER A 0 HPCI OPER 490 As Reg'd FEEDWATER B 0 Drywell Pressure .3 (psig) MAIN STEAM A 0 Torus Level 0.3 (inches) MAIN STEAM B 0 OPEN CLOSED ' MAIN STEAM C 0 q MSIV 0 8 MAIN STEAM D 0 FLOW PANEL 9-4 CRD A 50 (gpm) l STATUS , PRESS (psig) FLOW (gpm) CRD B AVAIL (gpm) RCIC OPER 450 400 LEVEL PRESS SQUIB PUMPS RWCU A ISOL 0 0 SLC 75 % 0 (psig) ON UNAVAIL RWCU B ISOL 0 0 RRPA 0 % SPD MISCELLANEOUS PANELS RRPB 0 % SPD DIESEL GEN A OPER DIESEL GEN B OPER SBGT A OPER SBGT B STBY DRYWELL COOLING NORMAL k,/ TORUS WATER TEMP 87 *F l i l l
r O I-p
= = 0 0 0 1
0 0 0 0 - 0 0 0 0 0 0 0 - 0 0 0 0 2 0 8 6
'e 8 6 4 2 o t 4 2 0 ) 1 1
) 1 1 1 g
F m . O O i T isp ( ( e r e u r t a u s r s e e p r m P 5 e 1 r - T o t s c u r a e o R T 0 3 _ E - S I _ C N E R 3 3, _ O X 0 5 0 0 0 5 0 0 5 0 5 0 0 I T E 1
+ +
1 + -
~
1 2 4 2 2 1 0 2 1
+ +
A SS ) 0 T E S in (
)
n N A i ( R D T l e l v e _ A E A e v E L A R D L L e C P S r U E DP o s _ t u r N R c _ S a 5 o R P T . e 1 E Y R P C O N O E _ C G R E 0 3 _ M - E A b. _ ) _ 0 0 0 0 0 _ M 0 8 6 4 0 0 0 0 0 0 0 _ R 1 7 6 5 4 3 2 1 _ P 0 - . _ A _ )
% g G isp
_ V ( A e ( r _ e r - u _ i s e - 5 s s c w 1
- e
_ r o r e _ P P _ x r l E o l e - t d t c _ w e t e a y _ a e r _ / l u R 0 3 D _ a - _ v e E ga 7 s _ s 8 9 e 1 M
.l -. l 1 '
['"'s RADIATION MONITOR DATA Time - 1100 (x_ t - 03/30 AREA RAD 7JtTION MONITORS ~ READING STATION ' DESCRIPTION (mr/hr) 1 Rx Bldg Fuel Pool Area (SE Sth Floor) 90 2 Rx Bldg Fuel Fool Area (SE Sch Floor) 2 3 Rx Bldg New Fuel Area (SE Sth Floor) 0.03 4 Rx Bldg Rx Water Cleanup Demineralized Area 140 * (SW 3rd Floor) 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 40 6 Rx Bldg Neutron Monitor System Index Area 100 (TIP Room ist Floor) 7 Rx Bldg Neutron Monitor System Drive Mech Ares 10 (SE lst Floor) I 8 Rx Bldg Control Rod Hydraulic Equipment Area 10 1 (S 1st Floor) 9 Rx Bldg' Control Rod Hydraulic Equipment Area 1C j (N 1st Floor) ] 10 Rx Bldg HPCI Pump Room (SU Quad) OS
- J 11 Rx Bldg RHR Pump Room (SW Quad) OS
- 12 Rx Bldg RHR Pump Room (NW Quad) OS
- 4 13 Rx Bldg RCIC/CS Pump Room (NE Quad) OS
- l
[sj 14 Rx Bldg CS Pump Room (SE Quad) OS
- l
\s_s/ 15 Turbine Bldg Turbine Front Standard 2 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.2 17 Turbine Bldg Turbine Bldg Basement Control Corridor 0.04 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 8 ]
19 Turbine Bldg Turbine Bldg Condensate Pump Area 0.1 ] 20 Control Room Main Control Room 0.015 21 Grade Level control Corridor 0.25 22 Radwaste Control Room 0.02 23 Radwaste Pump Room 7 l 24 Radwaste Basement Equipment Area 3 ; 25 Radwaste Demin Valve Room 2 l 26 Radwaste Conveyor Aisle Operating Area 0.03 27 SPARE 28 Radwaste Lab Area 0.2 29 Centrifuge East 10 30 Centrifuge West 9 Panel 9-02 Personnel Airlock Area 903' 1.8 R/hr Panel 9 02 Ladder 903' to 2nd Level 1.3 R/hr
- Alarm '
OS Offscale (
I f'~' RADIATION MONITOR DATA Time - 1100 1
\
t - 03/30 PROCESS AND VENT MONITORS , 1 PANEL VBDG ! Rx Bldg Vent Eff (RMV-RM-40) 0 uCi/sec ERP Stack Normal Eff (RMP-RM-3A) 6.0 E-1 uCi/see ERP Stack High Range (RMP-RM-3B) 0 uCi/sec Turbine Bldg Vent Eff (RMV-RM-20A) 1.5 E-3 uCi/sec Turbine Bldg High Range (RMV-RM-20B) 0 uCi/sec -i" RW/ARW Bldg Combined Eff (RMV-RM-30A) 1.0 E-3 uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) 0 uCi/see J PANEL 9-10 Mn, Stm. Rad Monitor Ch. A1, B1 45 mR/hr 40 mR/hr 4 Ch. A2, B2 40 mR/hr 45 mR/hr l SJAE Off Gas Log Rad Monitor Ch. A, B 1 mR/hr -1 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hr 0.7 mR/hr , I l l Service Water 10 cps , Reactor Equipment Cooling l ['x ); 20 cps ! 1 I l 1 1 l 1 l' . t i l
f' 1987 Evalusted Exercise Time - 1100
\
Message Number: 27 -t - 03/30 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE For Controller Use Only: CONTR01.LER INFORMATION: FlPECTED ACTIONS: r r
p 1987 Evaluated Exercise Time - 1115
\ - Message Number: 28 e - 03/45 COOPER NUCLEAR STATION ^
EMERGENCY PREPAREDNESS EXERCISE MESSAGE Message for: Control Room Simulated Plant Conditions: See attached Flant Data Message: ,
***THIS IS A DRILL ***
l l
'J 1
1 1 m -_____u_ m_-__ _ _ _ m___- ---. _m.m_______- - _ . - _ _ . _ . _ _ _ _ - - - _ _ _ _ a .____ _ __ ___,, m_ _ _ - . __ __
i ( 1987 Evaluated Exercise Time - 1115
)
(u jessage Number 28 COOPER NUCLEAR STATION t - _ 03/45 EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 900 SRM RHR A UNAVAIL 0 0 REACTOR LEVEL 35"* WR RHR C STBY 50 REACTOR PRESSURE 230 RHR B TRS. CLG 50 14,000 CORE D/P (psig) 0.3 6 RHR D TRS. CLG 50 CORE FLOW (10 lbm/hr) 0.1 ) 6
.CS A STBY 50 0 FLOW (10 lbs/hr)
CS B STBY 50 0 FEEDWATER A 0 l HPCI OPER 410 As Reo'd FEEDWATER B- 0 j Drywell Pressure .3 (psig) MAIN STEAM A 0 Torus Level 0.3 (inches) MAIN STEAM B 0 [ OPEN CLOSED MAIN STEAM C 0 t MSIV 0 8 MAIN STCAM D 0 FLOW PANEL 9-4 CRD A 50 (gpm) , STATUS PRESS (psig) FLOW (gpm) CRD B AVAIL (gpm) RCIC OPER 375 400 LEVEL PRESS , SQUIB PUMPS RWCU A ISOL 0 0 SLC 75 % 0 (psig) ON LHAVAIL RWCU B ISOL 0 0 RRPA 0 % 'SPD MISCELLANEOUS PANELS RRPB 0 % SPD DIESEL GEN A OPER DIESEL GEN B OPER ' SBGT A OPER SBGT B STBY DRYWELL COOLING NORMAL i TORUS WATER TEMP 87 *F
CV - U
?-
G g
= =
0 0 0 0 0 0 0 0 0 0 0 0 - 0 0 0 0 0 8 e t. ) 4 1 2 1 0 1 8 4 2 0 ) F 2 1 1 6 m g 0 i O is ( T ( p e r e u r t u a r s s e p e r P m r 5 1 e T o - t s c u _ a r e o R T 0 3 _ E - S _ I C R n 3 N E . _ O X 0 5 0 0 0 5 0 0 5 0 0 E _ I 1 + 1 4 2 0 2 T 2 _ 1
+ + - - 2 1 '
1 A SS ) 0
+ + -
ST E ( in -
)
n N A l i ( R D T e v l e A E A E L R A D L e _ L v e OV C U N R P E S DP t r o c s u r P S a 5 o R e T 1 _ E Y R _ _ P C _ O N _. - O E - C G - R - _ E 0 _ M 3 - E 3
)
_ M 0 0 0 8 0 6 0 4 0
'0 0 0 0 0 0 0 R 1 7 6 5 4 3 2 1
_ P 0 . _ A -
)
% ig G - s p
_ V - ( A ( e _ r _ e r u _ i s e , 5 s s _ c w 1 e _ r o - r _ e P P x r _ E o l l de t e g c w y _ t z a _ a e r u R 0 D vE l 3 a -
^ v 'e g
- '( 7 a s s 8 9 e 1 M
/N RADIATION MONITOR DATA' Time - 1115 j' t - 03/45 AREA RADIATION MONITORS READING STAYION, DESCRIPTION (mr/hr) 1 Rx Bldg Fuel Pool Area (SE 5th Floor) 90 2 Rx Bldg Fuel Pool Area (SE 5th Floor) 2 3 Rx Bldg New Fuel Area (SE 5th Floor) 0.03 4 Rx Bldg Rx Water Clear.up Demineralized Area 155 *
(SW 3rd Floor) 5 Rx Bldg Sludge and Decant Fump Area (S 2nd Floor) 45 6 Rx Bldg Neutron Monitor System Index Area ,120 (TIP Room ist Floor) 7 Rx Bldg Neutron Monitor System Drive Mech Ares 12 (SE lst Floor) 8 Rx Bldg Control Rod Hydraulic Equipment Area 12 (S 1st Floor) 9 Rx Bldg Control Rod Hydraulic Equipment Area 12 (N ist Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) OS
- 11 Rx Bldg RHR Pump Room (SW Quad) OS
- 12 Rx Bldg RHR Pump Room (NW Quad) OS
- f r- 13 Rx Bldg RCIC/CS Pump Room (NE Quad) OS
- 14 Rx Bldg CS Pump Room (SE Quad) OS *
( 15 Turbine Bldg Turbirce Front Standard 2 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.2 17 Turbine Bldg Turbine Bldg Basement Control Corridor 0.04 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 8 19 Turbine Bldg Turbine Bldg Condensate Pump Area 0.1 20 Control Room Main Control Room 0.015 21 Grade Level Control Corridor 0.25-22 Radwaste Control Room 0.02 23 Radwaste-Pump Room 7 24 Radwaste Basement Equipment Area 3 25 Radwaste Demin Valve Room 2 26 Radwaste Conveyor Aisle Operating Area 0.03 27 SPARE 28 Radwaste Lab Area 0.2 i 29 Centrifuge East 10 30 Centrifuge West 9 Panel 9-02 Personnel Airlock Area 903' l.8 R/hr Panel 9-02 Ladder 903' to 2nd Level 1.3 R/hr
- Alarm _
OS Offscale l ye 's k v
/N RADIATION MONITOR DATA Time'- 1115
( ) t - 03/45
%/
PROCESS AND VENT MONITORS PANEL VBDG Rx. Bldg Vent Eff (RMV-RM-40) 0 uCi/see i ERP Stack Normal Eff (RMP-RM 3A) 6.0 E-1 uCi/see ERP Stack High Range (RMP RM-3B) 0 uCi/see Turbine Bldg Vent Eff (RMV-RM-20A) 1.5 E-3 uCi/see Turbine Bldg High Range (RMV-RM-20B) 0 uCi/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 1.0 E-3 uCi/sec RW/ARW' Bldg High Range (RMV-RM 30B) 0 uCi/sec PANEL 9-10 Mn. Stm. Rad Monitor Ch. Al, B1 45 mR/hr 40 mR/hr Ch. A2, B2 40 mR/hr 45 mR/hr SJAE Off. Gas Log Rad Monitor Ch. A, B 1 mR/hr 1 mR/hr- - Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hr 0.7 mF./hr Service Water 10 cps Reactor Equipment Cooling 20 cps ( l l l e e
-(N 1987 Evaluated Exercise Time - 1115 U Message Number: 28 t - 03/45 i COOPER NUOLEAR STATION EMERCENCY PREPAREDNESS EXERCISE MESSAGE For Controller Use Only: CONTROLLER INFORMATION: , I EXPECTED ACTIONS: l O O m
t C 1987 Evaluated Exercise Time - 1130 Message Number: 29 t - 04/00-COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Message for: Control Room Simulated Plant Conditions: See attached' Plant Data Message: ,
***THIS IS A DRILL ***
4 4 1 l l ( b i
/ 987 Evaluated Exercise Time - 1130 ' y .nessage Number 29 COOPER NUCLEAR STATION t -
04/00 EMERGENCY PREPAREDNESS EXERCISE PLANT DATA
. PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 900 SRM RER A UNAVAIL 0 0 REACTOR LEVEL 35"* VR _
RHR C STBY 50 REACTOR PRESSURE __ 170 RHR B TRS. CLG 100 14,000 CORE D/P (psig) - 0.3 6 RHR D TRS. CLG 100 CORE FLOW (10 lbm/hr) 0.1 0 CS A STBY 50 0 FLOW _(10 lbs/hr) CS B STBY '50 0 FEEDWATER A 0 l HPCI OPER 360 As Reo'd FEEDWATER B 0 Drywell Pressure .3 (psig) MAIN STEAM A 0 Torus Level 0.3 (inches) MAIN STEAM B 0 C OPEN CLOSED MAIN.. STEAM C 0 v MSIV 0 8 MAIN STEAM D 0 j FLOW PANEL 9-4 CRD A 50 (gpm) STATUS PR'ESS(psig) FI'0W(gpm) CRD B AVAIL (gpm) RCIC OPER 325 400 LEVEL PRESS SQUIB PUMPS RWCU A ISOL 0 0 SLC 75 % 0 (psig) 'ON UNAVAIL RNCU B ISOL 0 0 RRPA 0 % SPD MISCELLANEOUS PANELS RRPB 0 % SPD DIESEL GEN A OPER DIESEL CEN B OPER SBGT A OPER SBGT B STBY DRYWELL COOLING NORMAL O TORUS WATER TEMP 87 'F
7 y I g
= = 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 4 0 8 6 4 2 0 ) 2 0 8 6 e i ) .1 12 1 1 1 '
F m ig 0 O i s ( T p e ( r e u r t u a r s s e e p r P 5 m e r T t R o c a e N1 - T s u r o E N 0 3 S I C R % 3 N E g O X 0 0 5 0 0 5 0 5 0 0 3 0 0 - T E I 1 1 + - 1 2 4 2 0 2
+ + - 3, - 2 1 1
+
A SS ) 0
+ -
T E n ) - S ( i n N A l ( i R D T e v l e A E A e v E. R D L , e I A r L - C P S o s U E DP t c u r N R S a 5 o R P e 1
- T E Y R -
P C O N O E C G R E 0 M 3 E . 3
)
0 0 0 0 0 0 M 0 8 6 4 2 0 0 0 0 0 0 0 R 1 7 6 5 4 3 2 1 P 0 A
)
% g G is p
V ( ( A e r e r u s i s e . 5 s c w 1 e r o - - r e P - P x r E o l l t e d t c - w t e a a y a e - r l u R - 3 0 D a - - ' E v e g a 7 s s 8 9 e 1 M
Time - 1130 () RADIATION MONITOR DATA t - 04/00 AREA RADIATION MONITORS READING STATION DESCRIPTION (mr/hr). 1 Rx Bldg Fuel Pool Area (SE 5th Floor) 90 2 Rx Bldg Fuel Pool Area (SE 5th Floor) 2 3 Rx Bldg New Fuel Area (SE Sch Floor) 0.03 4 Rx Bldg Rx Water Cleanup Demineralized Area 175 * (SW 3rd Floor) 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 50 6 Rx Bldg Neutron Monitor System Index Area 150 (TIP Room 1st Floor) 7 Rx Bldg Neutron Monitor System Drive Mech Ares 15 (SE lst Floor) 8 Rx Bldg Control Rod Hydraulic Equipment Area 15 (S ist Floor)
- 9 Rx Bldg Control Rod Hydrauli Equipment Area 15 l (N lst Floor)
! 10 Rx Bldg HPCI Pump Reom (SW Quad) OS
- l 11 Rx Bldg RHR Pump Room (SW Quad) OS
- 12 Rx Bldg RHR Pump Room (NW Quad) OS
- 13 Rx Bldg RCIC/CS Pump Room (NE Quac) OS
- 1 14 Rx Bldg CS Pamp Room (SE Quad) , OS
- l \ 15 Turbine 31dg Turbine Front Standaro 2 l 16 Turbine Eldg Turbine Bldg Mezz Control Corridor 0.2 I 17 Turbine Bldg Turbine Bldg Basement Control Corridor 0.04 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 8 19 Turbine Bldg Turbine Bldg Condensate Pump Area 0.1 20 Control Room Main Control Room 0.015 21 Grade Level Control Corridor 0.25 22 Radwaste Control Room 0.02 23 Radwaste Pump Room 7 -
24 Radwaste Basement Equipment Area 3 25 Radwaste Demin Valve Room 2 ! 26 Radwaste Conveyor Aisle Operating Area 0.03 l 27 SPARE l 28 Radwaste Lab Area 0.2 29 Centrifuge East 10 1 30 Centrifuge West 9 ; Panel 9-02 Personnel Airlock Area 903' l.9 R/hr I Panel 9-02 Ladder 903' to 2nd Level 1.4 R/hr
- Alarm OS Offscale ,
1
\
(s. / 1 l i
s N RADIATION MONITOR DATA Time - 1130 ( t - 04/00 ; PROCESS AND VENT MONITORS PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) ..O uCi/sec ERP Stack Normal Eff (RMP-RM-3A) 6.0 E-1 uCi/sec ERP Stack High Range (RMP'RM-3B) 0' uCi/sec 4 Turbine Bldg Vent Eff (RMV-RM-20A) 1.5 E-3 uCi/sec l Turbine Bldg High Range (RMV-RM-20B) 0 uCi/sec l RW/ARW Bldg Combined'Eff (RMV-RM-30A) 1.0 E-3 uCi/sec l RW/ARW Bldg High Range (RMV-RM-308) 0 uCi/see j PANEL 9-10 Mn. Stm. Rad Monitor Ch. A1, B1 45 mR/hr 40 mR/hr Ch. A2, B2 40 mR/hr 45 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, 8 1 mR/hr 1 mR/hr , Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hr 0.7 mR/hr j Service Water 10 cps j
, Reactor Equipment Cooling 20 cps 1
i a l I . ! l i l
[' 1987 Evaluated Exercise Time - 1130 t Message Number: 29 t - 04/00 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE For Controller Use Only: CONTROLLER INFORMATION: o Data indicatra that both EDGS have been shutdown, and returned to Standby. EXPECTED ACTIONS: t - ______.__ _.___ _ _ _____m____.m_.____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ . _ _ _ __ __ _ _ . _ _ . _ _ _ _ _ .___m.._.
g 1987 Evaluated Exercise Time - 1145
\'/' Message Nwnber: 30 t - 04/15 COOPER NUCLEAR STATION EMERCENCY PREPAREDNESS EXERCISE MESSAGE Message for: Control Room Simulated Plant Conditions: See attached Plant Data Message:
***THIS IS A DRILL ***
i e P 4 e 1 - -
l i l i i [
^ 1987 g
Evaluated Exercise Time - 1145 ( Jessage Number 30 COOPER NUCLEAR STATION t - 04/15 .] i EMERGENCY PREPAREDNESS EXERCISE PLANT DATA . _ _ _ PANEL 9-3 PANEL 9 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 900 SPJi j l RHR A UNAVAIL 0 0- REACTOR LEVEL 35"* WR ! l RHR C STBY 50 REACTOR PRESSURE 120 PJiR B TRS. CLC 100 14,000 CORE D/P (psig) 0.3 6 l RHR D, TRS. CLG 100 CORE FLOW (10 lbm/hr) 0_.1 6 CS A STBY 50 0 FLOW (10 lbs/hr) CS B STBY 50 0 FEEDWATER A 0 HPCI ISOL 0 0. FEEDWATER B 0 Drywell Pressure .3 (psig) MAIN STEAM A 0 Torus Level .3 (inches) MAIN STEAM B 0 OPEN CLOSED MAIN STEAM C 0 1 MSIV 0 8 MAIN STEAM D 0 ! FLOW PANEL 9-4 CRD A SO (gpm) STATUS PRESS (psig) FLOW (gpm) CRD B AVAIL (gpm) RCIC' OPER 250 400 LEVEL PRESS SQUIB PUMPS RUCU A 'ISOL 0 0 SLC 75 % 0 (psig) ON UNAVAIL' RWCU B ISOL 0 0 RRPA 0 % SPD MISCELLANEOUS PANELS RRPB 0 % SPD DIESEL GEN A OPER DIESEL GEN B OPER SBGT A OPER SBGT B ._ __ STBY DRYWELL C0 CLING NORMAL LO TORUS WATER TEMP 87 *F l
W f* (
= =
0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 0 2 0 8 6 e t
)
4 1 2 1 0 1 8 6 ) F 1 1 m ig 0 O i s (
~
T p e ( r e u r t u a r s s e e p r P m r 5 1 e o - T t s c u r a e o
. R T 0
3 E - S I C 6 R - 3 5 N E ' O X 0 0 5 0 0 5 0 0 5 0 0 0 0 0 I T E 1 1 + - 1 1 2 4 2 0 2
+ + - - - 2 1 1
+ +
A SS ) 0 T E n ) - S i ( n N A l e ( i R D T v l e A E A e v E R D e
%) L C
U P A E S DP L r o _ L s t _ u r N R c _ P S a 5 o R e _ 1
- T E Y R _
P C _. O N . O E C G R E 0 M 3 E 3
)
0 0 0 , 0 0 M 0 8 6 , 2 0 0 0 0 0 0 0 0 R 1 7 6 5 4 3 2 1 P 0 - - . A - -
)
% g G isp V (
A e ( r e u r - i s e , 5 s s c w 1 e r o . r e P P x E r l t o l e d e c w e a y t 3 a e r l u R _. 3 0 D
' a , -
v e E ga 7 s s 8 9 e 1 M
I i j i /9 RADIATION MONITOR DATA Time - 1145 t - 04/15 l
)
AREA RADIATION MONITORS READING STATION DESCRIPTION (mr/hr) 1 Rx Bldg Fuel Fool Area (SE 5th Floor) .90 2 Rx Bldg Fuel Pool Area (SE 5th Floor) 2 3 Rx Bldg New Fuel Area (SE Sch Floor)- 0.03 4 Rx Bldg Rx Water Cleanup Demineralized Area 190
- j (SW 3rd Floor) j 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 55 l 6 Rx Bldg Neutron Monitor System Index Area 180 (TIP Room 1st Floor) 7 Rx Bldg Neutron Monitor System Drive Mech Ares 18 (SE ist Floor) 8 Rx Bldg Control Rod Hydraulic Equipment Area 18
, (S lst Floor) 9 Rx Bldg Control Rod Hydraulic Equipment Area 18 (N lst Floor) I 10 Rx Bl'gd HPCI Pump Room (SW Quad) OS
- l 11 Rx Bldg RHR Pump Room (SW Quad) OS
- 1 12 Rx Bldg RHR Pump Room (NW Quad) OS
- 13 Rx Bldg RCIC/CS Pump Room (NE Quad) OS *
- 14 Rx Bldg CS Pump Room (SE Quad) OS *
( 15 Turbine Bldg Turbine Front Standard 2 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.2 , 17 Turbine Bldg Turbine Bldg Basement Control Corridor 0.04 1 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 8 19 Turbine Bldg Turbine Bldg Condensate Pump Area 0.1
~
20 Control Room Main Control Room 0.015 21 Grade Level Control Corridor 0.25 22 Radwaste Control Room 0.02 23 Radwaste Pump Room 7 24 Radwaste Basement Equipment Area 3 j 25 Radwaste Demin Valve Room 2 26 Radwaste Conveyor Aisle Operating Area 0.03 , 27 SPARE i 28 Radwaste Lab Area 0.2 j 29 Centrifuge East 10 30 Centrifuge West 9 i Panel 9-02 Personnel Airlock Arca 903' l.9 R/hr . Panel 9-02 Ladder 903' to 2nd Level 1.4 R/hr i
- Alarm j OS Offscale I O ;
i i
l i
/ RADIATION MONITOR DATA Time - 1145 i t - 04/15 I
l l PROCESS AND VENT MONITORS PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 0 uC1/sec ERP Stack Normal Eff (RMP-RM-3A) 6.0 E-1 uCi/sec ERP. Stack High Range (RMP-RM-3B) ,0 uCi/sec Turbine Bldg Vent Eff (RMV-RM-20A) 1.5 E-3 uC1/see Turbine Bldg High Range (RMV-RM-20B) 0 uCi/sec RW/ARW Bldg Combined Eff (RMV-RM 30A) 1.0 E-3 uCi/sec j RW/ARU Bldg High Range (RMV-RM-30B) 0 -uCi/sec l PANEL 9-10 Mn. Stm. Rad Monitor Ch. A1, B1 45 mR/hr 40 mR/hr. ! Ch. A2, B2 40 mR/hr 45 mR/hr {
'SJAE Off Gas Log Rad Monitor Ch. A, B 1 mR/hr' 1 mR/hr ]
Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hr 0.7 mR/hr 1 Service Water 10 cps Reactor Equipment Cooling 20 cps' i I
)
4 l l l i O
x h ! l
.O _ 1987 Evaluated Exercisa Time - 1145 x' -): Message Number: 30 , t - 04/15 .
COOPER NUCLEAR STATION j EMEl'.pENCY PREPAREDNESS EXERCISE MESSAGE I For Controller Use only: CONTROLLER INFORMATION: -3 l Reactor temperature and pressure are approaching permissives for o-initiation of Shutdown Cooling, i EXPECTED ACTIONS: I o Operators should begin making preparations to enter Shutdown Cooling j Mode at this time-. If they have not; use message x, i l l I l I s ! l
'l I
i l i i a- - - - _ - _ _ _ - - - - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - _ _ _ . __ _- _ _ ___. . - _ _
x '
, l "gl'-
!I ., jl } , ,b
- p) ,i s c - (c
,p - I_ h , f, ! 9987~ Evaluated Exercise ', Time - 1150 ( j. 1
\ Message Number: 31X l' ,
t - 04/20 I t 9 i J' COOPER NUCLEAR STATION l - EMERGENCY PREPAREDNESS EXERCISE MESSAGE I 7j Message for: Control Room - Simulated Plant Condicions: Message:
/
'y -
***THISISADPik.L***
f Commence preparations for entering Shutdowri'Coolf.;ng Mode. c 1 D 'a
.(. 1 % i l
1 ( 8 t' i
)
1 .i i
1 I i i
'"~'s 1987 Evaluated Exercise Time - 1150
- Message Number: 31X t - 04/2C .
COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSACE For Controller Use Only: CONTROLLER INFORMATION: o Delive; this message if Operations personnel have not commenced prepe ations to initiate Shutdown Cooling or if a management decision is made not to implement a forced cooldown at this time, o Data sheets reflect selection of 'B' loop for Shutdown Cooling. Actual loop selected is arbitrary. If operators select 'C' or 'D' pumps, controller may request a change in order to comply with data sheets or note the changes on the appropriate manages. . EXPECTED ACTIONS: o Commence system preparations pe,r procedures. h a i
4 I 1987 Evaluat2d Exercise Time - 1200 Message Number: 32- t - 04/30 . COOPER NUCLEAR STATION t a EMERGENCY PREPAREDNESS EXERCISE MESSAGE Message for: Control Room Simulated Plant Conditions: See attached Plant Data Message: 1
***THIS IS A DRILL ***
6 e i i l
/\1987 Evaluated Exercise Time - 1200 \,, tessage Number 32 COOPER NUCLEAR STATION t - 04/30 EMERGENCY PREPAREDNESS EXERCISE PLANT DATA '
PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 900 SRM RHR A UNAVAIL 0 0 REACTOR LEVEL 35"4 WR RHR C STBY 50 REACTOR PRESSURE 80 RHR B TRS. CLG 100 14,000 CORE D/P (psig) 0.3 0 RHR D TRS. CLG 100 CORE FLOW (10 lbm/hr) 0.1 6 CS A STBY 50 0 FLOW (10 lbs/hr) .. CS B STBY 50 0 FEEDWATER A 0 HPCI- ISOL 0 0 FEEDWATER B 0 Drywell Pressure .3 (psig) MAIN STEAM A O Torus Level 0.3 (inches) MAIN STEAM B 0 OPEN CLOSED MAIN STEAM C 0 MSIV 0 8 MAIN STEAM D 0 FLOW PANEL 9-4 CRD A - 50 (gpm) STATUS PRESS (psig) FLOW (gpm) CRD B AVAIL (gpm) RCIC OPER 200 400 LEVEL PRESS 90UIB PUMPS RWCU A ISOL ' O O SLC _75_% 0 (psig) ON UNAVAIL RWCU B ISOL 0 0 RRPA 0 % SPD MISCELLANEOUS PANELS RRPB 0 % SPD DIESEL CEN A OPER DIESEL GEN B OPER SBGT A OPER SBCT B STBY DRYWELL COOLING NORMAL O TORUS WATER TEMP 87 'F i
-_ _ _ _ _ .-- _ A
" 7
= =
0 0 0 0 0 0 0 0 0 0 0 0 0 0 e t'
)
4 1 2 1 0 1 8 2 0 ) F 2 1 0 1 8 6 m g 0 i i O s ( T p e ( _ r e _. u r t u _. a r s s e e - p r P m r 5 e t o %1
- T s
e u s r e o R T 0 3 E - S I C R N E 3 O X 0 0 5 0 0 5 O 0 0 0 5 0 0 T E I 1 1 + 1 1 2 ' 4 2 0 2
+ + - - - 2 1 1 A SS )
0
+ +
~
T n S E
) -
i ( n N A i ( R A E D T A l e v l e e v E L A R D L e (C C P U E N R S D P t r o e L s u r S s 5 o R P e 1
- T E Y R P C O N O E C G R
E 0 M 3 E . 5
)
0 0 0 0 0 M 0 8 6 4 0 0 0 0 0 0 0 R 1 7 6 5 4 3 2 1 P 0 - A
)
ig G - s p V ( ( A e r e r u i s e , 5 s s c w 1
- e r o r
_ e P P x _ E r o l l d t e c w te 7 y 5 a a e - r l u R - 0 3 D a . - D E v e g a 7 s s 8 9 e 1 M
'W j} RADIATION MONITOR DATA Time - 1200
(~-) t - 04/30 AREA RADIATION MONITORS READING STATION DESCRIPTION (mr/hr) 1 Rx Bldg Fuel Fool Area (SE Sth Floor) 90 2 Rx Bldg Fuel Fool Area (SE 5th Floor) 2 3 Rx Bldg New. Fuel Area (SE Sch Floor) 0.03 4 Rx Bldg Rx Water Cleanup Demineralized Area 200 * (SU 3rd Floor) 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 60
- 6 Rx Bldg Neutron Monitor System Index Area 200 *
(TIP Room ist Floor) 7 Rx Bldg Neutron Monitor System Drive Mech Ares . 20 (SE lst Floor) 8 Rx Bldg Control Rod Hydraulic Equipment Area 20 (S lst Floor) 9 Rx Bldg Control Rod Hydraulic Equipment Area 20 (N 1st Floor) . 10 Rx Bldg HPCI Pump Room (SW Quad) OS
- 11 Rx Bldg RHR Pump Room (SW Quad) OS
- 12 Rx Bldg RHR Pump Room (NW Quad) OS
- f-~s 13 Rx Bldg RCIC/CS Pump Room (NE Quad) OS *
) 14 Rx Bldg CS Pump Room (SE Quad) OS *
-d 15 Turbine Bldg Turbine Front Standard 2 16- Turbine Bldg Turbine Bldg Mezz Control Corridor 0.2 17 Turbine Bldg Turbine Bldg Basement Control Corridor 0.04 l
18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 8 1 19 Turbine Bldg Turbine Bldg Condensate Pump Area 0.1 20 Control Room Main Control Room 0.015 21 Crade Level Control Corridor 0.25 22 Radwaste Control Room 0.02 , 23 Radwaste Pump Room 7 l 24 Radwaste Basement Equipment Area 3 25 Radwaste Demin Valve Room 2 26 Radwaste Conveyor Aisle Operating Area 0.03 27 SPARE 28 Radwaste Lab Area 0.2 29 Centrifuge East 10 30 Centrifuge West 9 Panel 9-02 Personnel Airlock Area 903' 2.0 R/hr Panel 9-02 Ladder 903' to 2nd Level 1.5 R/hr
- Alarm OS Offscale l
U_-____________________________-_-___-_-__-_____
[]
\ /
RADIATION MONITOR DATA Time - 1200 t - 04/30 PROCESS AND VENT MONITORS PANEL VBDG l Rx Bldg Vent Eff.(RMV RM-40) 0 uCi/sec l ERP Stack Normal Eff-(RMP-RM-3A) 6.0 E 1 uCi/sec ERP Stack High Range (RMP-RM-3B) 0 uCi/sec Turbine Bldg Vent Eff (RMV-RM-20A) 1.5 E-3 uCi/see Turbine Bldg High Range (RMV RM-208) 0 uCi/see RW/ARW Bldg Combined Eff (RMV-RM-30A) 1.0 E-3 uCi/see RW/ARW Bldg High Range (RMV-RM-30B) 0 uCi/see PANEL 9-10 . Mn. Stm. Rad Monitor Ch. A1, B1 45 mR/hr 40 mR/hr , Ch. A2,.32 40 mR/hr 45 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 1 mR/hr 1 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hr , 0.7 mR/hr' gg Service Water 10 cps-
) Reactor Equipment Cooling ,20 cps ,b 1
1987 Evaluated Exercise Time - 1200 ( Message Number: 32 e - 04/30 , COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE For Controller Use Only: CONTROLLER INFORMATION: 1
. 1 i
EXPECTED ACTIONS: i e I l I i i l,
)
\ 1 I
O 1987' Evaluated Exercise Time - 1210-
^
Y Message Number: 33 .c - 04/40 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Message for: Control Room Simulated Plant Conditions: See attached Plant Data Message:
***THIS IS A DRILL *** \
f l
l i l i [~'987EvaluatedExercise Time - 1210 tassage Number 33 COOPER NUCLEAR STATION t - 04/40 EMERCENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATU3 PRESS _(psig) FLOW (gpm) REACTOR POWER 900 SRM l RHR A UNAVAIL 0- 0__, REACTOR LEVEL 35"* WR RHR C STBY 50 _ REACTOR PRESSURE 70 RHR B S.D. CLC 150 14,000 CORE D/P (psig) 0.3 j 6 RER D S.D. CLG 50 CORE FLOW (10 lbm/hr) 0.1 6 CS A STBY 50 0 FLOW (10 lbs/hr)
~
CS B STBY 50 0 FEEDWATER A 0 l HPCI ISOL 0 , O FEEDWATER B 0 J l
~
Drywell Pressure .3 (psig) MAIN STEAM A- O d Torus Level 0.3 (inches) MAIN STEAM B 0 O OPEN CLOSED MAIN STEAM C 0 b MSIV 0 _L MAIN STEAM D 0
]
FLOW PANEL 9-4 CRD A 50 (gpm) l STATUS PRESS (psig) FLOW (gpm) CRD B AVAIL (gpm) RCIC ISOL 0 _ 0 LEVEL PRESS SQUIB PUMPS 1 RWCU A ISOL 0 0 SLC 75 % 0 (psig) _ _ ON UNAVAIL RWCU B JSOL 0 0 RRPA 0 % SPD MISCELLANEOUS PANELS RRPB 0 % SPD DIESEL GEN A STBY DIESEL CEN B STBY SBGT A OPER SBGT B STBY
* . PRYWELL COOLING NORMAL TORUS WATER TEMP 87 'F I
j l l
' )I i.,
1 1 f as /< /
& 2s f.
C, c P' 7 f r- -
= = o 0 0 0 0 0 0 6 0 0 0 0 0 0 0 0 0 0 4 2 0 8 6 4 2 0 ) 2 0 8 6 e t ) 1 1 1 F
1 1 m ig , 0 O 0 i s ( T ( p _ e r e u r t u a r s s e e r p .- m - P 5 1 e 5 1 r - T - t o s c u r a e o R T
- u s
0 3 , 0 3 .n E , 1 S I .A C .z R M 5 - N E O X 0 0 5 0 0 5 0 0 0 0 5 0 0 I T E 1 1 + 1 1 2 4 2 2 1 D 2 1
'+ + + + -
A SS ) 0 - 0 T E n ) - S i ( n N A l ( i R D T e v l e 3 A E A e v E L R A D L L e C P S - r U E DP t o s u N R c r P S a 5 o 5 R e 1
- T 1 E Y R P C O N O E C G .
R - .a E i 0 0 . v 3 , 3 i - - E 3 -
)
M 0 0 0 0 0 0 0 8 6 4 0 0 0 0 0 0 0 o . R 1 7 6 5 4 3 2 1
~.
P 0 _ _ . 0 A .
)
6" i g G s p V ( A e . ( r . e r u s s e 5 s 5 i c w 1
- e - 1 r o r -
e P P x - n E r l t o l e - d c w ~ e 3 a y t 3 r a e l u R 0 3 D 3 0 - a - - e f v E ga 7 ss
~
- 8 9 e 1 M -
/ 1987 Evaluated Exercise Time - 1210 4'_ ,)
Message Number: 33 t - 04/40 . COOPER NUCLEAR STATION EMERCENCY PREPAREDNESS EXERCISE MESSACE For Controller Use Only: CONTROLLER INFORMATION: o Data indicates that Shutdown Cooling Mode has been initiated by the Control' Room through the 'B' RHR Heat Exchanger. l EXPECTED ACTIONS: o Monitor and adjust cooldown rates to average 100*F/hr. 1 ('~ . ( l' 4 I J i
i I l s 1
/~~N 1987 Evaluated Exercise Time - 1215 I i \
Message Number: 34 t - 04/45 COOPER NUCLEAR STATION . 1 EMERGENCY PREPAREDNESS EXERCISE MESSAGE
]
1 1 Message for: Control Room Simulated Plant Conditions: See. attached Plant Data
]
Message: I
***THIS IS A DRILL ***
Annunciators in the Control Room include; j i Reactor Low Water 2 Reactor Level High/ Low Reactor Vessel Channel A/B Low Low Water Level Rx Vessel Low Level Trip-High Area Temperature Reactor BLDG High Radiation ! [\ Reactor Building Vent High High Radiation - 3 SGTS Auto Start Auto Scram Trip System A/B RHR Pump 1B Pump Trip Indications in the Control Room include: l 1
- 1 l
Process Computer Points , , ; 275'F, 278'F, 276* F .) Group 2, 3, 6 Isolations l RHR M0-25A, B green light on RRR MO-18 green light on, red light on RHR MO-17 green light on, red light blinking intermittently, then both red and green lights off. l 1 1 I { 1 ; i
/O 987 Evaluated Exercise Time. - 1215 ! ; L .
U dessage Number 33 COOPER NUCLEAR STATION t - 04/45-EMERGENCY PREPAREDNESS EXERCISE PLANT DATA - PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 900 SRM RHR A UNAVAIL 0 0 REACTOR LEVEL -404 WR RHR C STBY 0 REACTOR PRESSURE 50 RHR B TRIPPED 0 0 CORE.D/P.(psig) 0.3 6 RHR D STBY 0 CORE FLOW (10 lbm/hr) 0.1 6 CS A STBY 0 0 FLOW (10 lbs/hr)
~
CS B STBY 0 0 FEEDWATER A 0 HPCI ISOL 0 0 FEEDWATER B 0 Drywell Pressure .3 (psig) MAIN STEAM A 0 Torus Level .3 (inches) MAIN STEAM B 0
.,Og . OPEN CLOSED MAIN STEAM C ,
0 MS1V 0 8 MAIN STEAM D 0 J l FLOW ; I PANEL'9-4 CRD A 50 (gpm) STATUS PRESS (psig) FLOW (gpm) CRD B AVAIL-(gpm) RCIC ISOL 0 0 LEVEL PRESS SQUIB PUMPS RWCU A ISOL 0 0 SLC 75 % 0 (psig) ON UNAVAIL I RWCU B ISOL 0 0 RRPA 0 % SPD MISCELLANEOUS PANELS RRPS 0 % SPD DIESEL CEN A STBY DIESEL GEN B STBY SBGT A OPER SBGT B OPER f DRYWELL COOLING NORMAL ( ( TORUS WATER TEMP 87 *F
-__--__-_________-_-_____a
't ^ [
Y "t
= = -
0 0 0 0 0 g 0 0 0 0 0 0 g 0 0 0 0 0 8 , 2 0 2 0 8 6 e t
)
4 1 2 1 0 1 6
)
F 1 1 m g _ O O , i is ( T p e ( r e u r t u s a r s e e p r P m
' _ 5. 1 e r .
- T t
o s . c - u r a - o e
~
T R
% 0 3
_ E - _ S I _ C N E R 4 3, - O X 0 0 5 0 0 5 0 0 5 0 0 5 0 0 I T E 1
+ +
1 + - 1 1 2 4 2 2 1 0 2 1
+
_ A SS )
+ .
n 0 {< _ T S E i ( _l ) n N A i ( R A E A D T l e v l e _ e v E R D L e L A r L _ C P S o s _ U E DP t c - u r N R S a 5 o _ R P e T 1 _ E Y R P C O N O E _ C G R E 0 M 3 E 3
)
0 0 0 9 0 0 M _ 0 8 6 4 0 0 0 0 0 0 0 _ R 1 7 6 5 4 3 2 1 P _ 0 A
)'
g _ G _ isp V _ ( ( A _ e _. r e r _ u s i s e _ 5 s c w _ - 1 e r o r e P P x r E o _ l l e _ t d c w _ e / a y a 3' t _ e r _ l u R 0 3 D a e - _ v j E ga 7 s _ s 8 9 e _ 1 M
i RADIATION MONITOR DATA Time - 1215 'I f'~ t - 04/45 AREA RADIATION MONITORS READING STATION DESCRIPTION (mr/hr) 1 Rx Bldg Fuel Pool Area (SE Sth Floor) 1000 3 2 Rx Bldg Fuel Pool Area (SE Sth Floor) OS
- 3 Rx Bldg New Fuel Area (SE 5th Floor) 20 4 Rx Bldg Rx Water Cleanup Demineralized Area 2000 *
(SW 3rd Floor) 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) OS
- 6 Rx Bldg Neutron Monitor System Index Area OS *
(TIP Room ist Floor) 7 Rx Bldg Neutron Monitor System Drive Mech Ares OS * (SE 1st Floor) l 8 Rx Bldg Control Rod Hydraulic Equipment Area OS
- l (S 1st Floor) l 9 Rx Bldg Control Rod Hydraulic Equipment Area OS *
(N lst Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) OS
- 11 Rx Bldg RHR Pump Room (SW Quad) OS
- 12 Rx Bldg RHR Pump Room (NW Quad) OS
- 13 Rx Bldg RCIC/CS Pump Room (NE Quad) OS * -
14 Rx Bldg CS Pump Room (SE Quad) . OS *
\ 15 Turbine Bldg Turbine Front Standard 2 16 Turbine Bldg Turbine Bldg Mezz Control Corridor OS
- 17 Turbine . Bldg Turbine Bldg Basement Control Corridor OS
- 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 100
- 19 Turbine Bldg Turbine Bldg Condensate Pump Area 5 20 Control Room Main Control Room 0.015 21 Grade Level Control Corridor OS
- 22 Radwaste Control Room 0.02 23 Radwaste Pump Room 7 24 Radwaste Basement Equipment Area 3 25 Radwaste Demin Valve Room 2 i 26 Radwaste Conveyor Aisle Operating Area 0.3 l l 27 SPARE I l 28 Radwaste Lab Area 0.2 !
29 Centrifuge East 10 j 30 Centriftuge West 9 i Panel 9-02 Personnel Airlock Area 903' 2.0 R/hr Panel 9-02 Ladder 903' to 2nd Level 1.5 R/hr I
- Alarm !
OS Offscale ! j
.l l (
1 i _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ _ _ ._.______..____._._____._______a
l i
/'"'g RADIATION MONITOR DATA Time - 1215 i t - 04/45 4
PROCESS AND VENT MONITORS PANEL VBDC i
, Rx Bldg Vent Eff (RMV-RM-40) 0 uCi/sec 1 ERP Stack Normal Eff (RMP-RM-3A) 0 uCi/sec )
ERP Stack High Range (RMP-RM-3B) 2.1 E+8 uCi/sec * /
. Turbine Bldg Vent Eff (RMV-RM-20A) 1.5 E-3 uCi/sec j Turbine Bldg High Range (RMV-RM-20B) 0 uCi/sec I RW/ARW Bldg Combined Eff (RMV-RM-30A) 1.0 E-~3 uCi/sec RW/ARU Bldg High Range (RMV-RM-30B) 0 uCi/sec PANEL 9-10 -
Mn. Stm. Rad Monitor Ch. A1, B1 45 mR/hr 40 mR/hr Ch. A2, B2 40 mR/hr 45 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 1 mR/hr 1 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B OS mR/hr
- OS mR/hr
- I Service Water 10 cps ,
Reactor Equipment Cooling 20 cps 1 l l , l l l l tx l l
i
,A 1987 Evaluated Exercise Time - 1215 t \ ~A Message Number: 34 t - 04/45 COOPER NUCLEAR STATION-EMERGENCY PREPAREDNESS EXERCISE MESSACE For Controller Use Only:
CONTROLLER INFORMATION: o Water hammer in the RHR Shutdown Cooling (SDC) suction line causes a 20" tee connection outside the drywell, on the suction side of the pumps.to rupture. Reactor water level drops very rapidly be ,w- the j low and low low ' level set points causing Groups 2, 3, and 6 i isolations. The inboard (MO-18) and outboard (MO-17) SDC isolation valves fail to fully close, resulting in a -500 gpm leak to the Reactor Building. Reactor Building ARMS begin to alarm and a l release to the environment begins via SCTS and the- Elevated Release I Point as the hot water (~300?F) flashes to steam and entrained noble gases are released. o The AC inboard isolation valve (MO-18) has stroked partially shut and is mechanically bound, a o- The DC outboard isolation valve (MO 17) has a blown fuse in the DC power supply to the valve motor. o "B" pump trips due to loss of suction head. EXPECTED ACTIONS: o Verify Automatic Actions. Implement E0P-1, RC/L. o Identify leak source, location and rate. Attempt to isolate. l o Declare a General Emergency per EPIP 5.7.1, Initiating Condition 2.6; loss of two of three fission product barriers, o Perform dose projections and recommend Protective Actions to offsite authorities. l l l l l l l i O
1 l l sSg '1987 Evaluated Exercise Time - 1220
~
Message Number: 35 t'- 04/50 COOPER NUCLEAR STATION EMERGENCY' PREPAREDNESS EXERCISE MESSACE Message for: Control Room I Simulated Plant Conditions: See attached Plant Data Message:
***THIS IS A DRILL *** -
i Annunciators in the Control Room include: Reactor Vessel Channel A/B Low Low Water Level Group 1 Isolation Channel A/B RHR System A/B Actuated RHR Pump 1C Pump Trip RHR A Valves Overload j -- Core Spray System A/B Actuated
- A Suppression Chamber Level Hi/Lo (N.R.)
\s_ High Area Temperature Reactor BLDG High Radiation Indications in the Control Room include:
Computer points , , : 295'F, 294*F, 296*F i RHR Mo-13 B, D red lights on
]
RHR M0-13C green light out, red light out l RHR MO-25 A, B red lights on . Both Diesels auto Start Successfully ! l i l i i i i l ( l
l A 1987 Evaluated Exercise Time - 1220 fessage Number 35 COOPER NUCLEAR STATION t - 04/50 EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 900 SRM l RHR A UNAVAIL 0 0 REACTOR LEVEL -155t RHR C TRIPPED 0 REACTOR PRESSURE 40 RHR B LPCI 150. 14,000 CORE D/P (psig) 0.3 6 RHR D LPCI 150 CORE FLOW (10 lbm/hr) 0.1 l 0 l CS A OPER 180 4,700 , FLOW (10 lbs/hr) CS B OPER 180 4,700 FEEDWATER A 0 HPCI ISOL 0 0 FEEDWATER B 0 Drywell Pressure .3 (psig) MAIN STEAM A 0 Torus Level 0 (inches) MAIN STEAM B 0
, OPEN CLOS $D MAIN STEAM C 0 MSIV 0 8 MAIN STEAM D 0 FLOW l
l PANEL 9-4 CRD A 50 (gpm) l STATUS PRESS (psig) FLOW (gpm) CRD B AVAIL (gpm) RCIC ISOL 0 0 LEVEL PRESS SQUIB PUMPS RWCU A ISOL 0 0 SLC 75 % 0 (psig) ON UNAVAIL RWCU B ISOL 0 0 RRPA 0 % SPD MISCELLANEOUS PANELS 1 RRPB 0 % SPD DIESEL GEN A OPER l DIESEL GEN B OPER SBGT A OPER SBGT B OPER DRYWELL COOLING NORMAL TORUS WATER TEMP 87 'F
O E 7 s
= = 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 o 2 0 8 6 e t
)
4 1 2 1 0 1 8 ) F 1 1 - m ig O O s ( iT p _ e ( _ r e u r _ t u _ a s r s e e p r m P 5 e 1 r - T o ' t s c u R a e
~
T r o _ 0 _ 3 _ E - S I C R O f _ N E O X 0 5 0 0 0 5 0 0 0 5 0 0 0 T E _ I _ 1 1 + 1 1 2 4 2 0 2 _ + + - - 2 1 1
+
_ A SS ) 0
+ -
n _ T E S ( i
)
n g N A ( i R D T _ l _ e l A E A v e e v OU E R D L e ~ _ L A L ~
~
C P S r o s - E D P t c u r - N R S a 5 o R P e 1 T _ E Y R P C _ O N O E - _ C G _ R E 0 _ M 3 E _ ) M 0 0 0 8 6 0 0 4 o 0 0 0 0 0 0 0 _ R 1 7 6 5 4 3 2 1 _ P 0 . A
)
ig G _ s _ p _ V _ ( ( A _ e _ r e r . u s i s e , 5 s c w 1
- e
_ r e o ._ r x P _ P E r l _ t o l e d c w _ t e 5< a y a . e _ r _ l u R _ 3 0 D - a e _ v _ ' E ga 7 s _ s 8 9 e 1 M
A 1 i L : i i
-1987 Evaluated Exercise Time - 1220 l
'i I
\s-- Message Number: 35 t - 04/50 !
l l COOPER NUCLEAR STATION D4ERCENCY PREPAREDNESS ' EXERCISE MESSACE For Controller Use Oniv: CONTROLLER'INFORMATION: l o Reactor Vessel level drops below triple low level (-145.5") causing ehe RHR pumps and Core Spray pumps to Auto Start and all RHR valves to align for LPOI inj ection. RHR suction valve MO-13B, D open normally aligning suction from the torus for pumps-B and D. MO-13C i does not open normally due to a breaker problem, indicated by the ! position lights going out, causing RHR C pump to trip on low suction pressure. o Diesel Generator Auto starts are successful. o Reactor level drops to -155" before increasing very rapidly due to l i
,_s -
injection of 2 LPCI and 2 Core Spray pumps. t%) 1 1 EXPECTED ACTIONS: o Verify Automatic Actions o Throttle injection flow as vessel level increases l o Assess location of break from area temperature alarms J l o Attempt to close RHR MO-17 or MO-18 to stop leak, dispatch team to MCC to repair 1 l 1 l 1 l l
. I
{ 1 \~- i
- _ - _ _ _ . . _ - _ _ _ . _ _ _ - - . . - . _ . - - _ _ _ _ _ . - _ - _ . _ _ _ . _ . - _ _ . _ _ - _ a
1987 Evaluated Exercise Time - 1225 Message Number: 36 t - 04/55 l COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE i I Messar,e for: Control Roorn ,
.I l, Simulated Plant Conditions: See attached Plant Data l J
Message:
***TilIS IS A DRILL *** s O
i i l, I l i 0
l I [ N 987 Evaluated Exercise Time - 1225 ) 4essage Number 36 COOPER NUCLEAR STATION t - 04/55 EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 'a i STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 900 SPL RHR A UNAVAIL 0 0 REACTOR LEVEL 354 WR-RHR B TRIPPED 0 REACTOR' PRESSURE 35 RHR C LPCI 150 500 CORE D/P (psig) 0.3 6 RHR D STBY 50 CORE FLOW (10 lbm/hr) 0.1 CS A . STBY 50 0 FLOW (106 lbs/hr) CS B STBY 50 0 FEEDWATER A 0 HPCI ISOL 0 0 FEEDWATER B 0 I Drywell Pressure .3 (psig) MAIN STEAM A. O I l Torus Level .1 (inches) MAIN STEAM B 0 l l OPEN CLOSED MAIN STEAM C 0 MSIV , 0 8- MAIN STEAM D 0 l FLOW PANEL 9-4 CRD A 50 (gpm) 4 J STATUS PRESS (psig) FLOW (gpm) CRD B AVAIL (gpm) RCIC ISOL 0 0 LEVEL PRESS SQUIB PUMPS RWCU A ISOL 0 0 SLC 75 % 0 (psig) ON UNAVAIL RUCU B ISOL 0 0 RRPA 0 % SPD MISCELLANEOUS PANELS RRPB 0 % SPD DIESEL GEN A OPER DIESEL CEN B OPER : I SBGT A OPER i SBGT B OPER ; D.".YWELL COOLING NORMAL
\
i b TORUS WATER TEMP 87 'F 1 l L________________________________ ___:-_-.________
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l l fN '1987 Evaluated Exercise Time - 1225
\
Message Number: 36 t - 04/55 q l i COOPER NUCLEAR STATION ] EMERGENCY PREPAREDNESS EXERCISE MESSACE 1 l i i i For Controller Use Only: 1 i CONTROLLER INFORMATION: ) o LPCI/CS have recovered RPV water level. With 7, solation Valve RHR MO 17 partially shut, the leak rate out the ruptured SDC suction piping has steadied out at approximately 500 gpm. I o Operators will make preparations' for initiating alternate shutdown cooling per procedures, raise RPV level to the main steam lines and ; dump coolant to the torus by way of an open SRV. Decay heat is then i dissipated by operating RHR in Suppression Pool Cooling mode. Make up to the RPV is provided by either a Core Spray or LPCI pump. o RHR/LPCI "D" and CS A&B, have been returned to Standby status; Reactor level being maintained by RHR/LPCI "B" I EXPECTED ACTIONS: o Adjust LPCI injection flow to balance leak rate, o Commence preparations for ASDC pcr procedures. 1 i I
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_ _ . _ _ . _ _ _ _ _ _ _ . J____...________.__________________ _ ______b
j i i 1987' Evaluated Exercise Time - 1230 ) Message Number: 37 t - 05/00 { 1 COOPER NUCLEAR STATION l l EMERGENCY PREPAREDNESS EXERCISE MESSACE l 1 i Message for: Control Room Simulated Plant Conditions: See attached Plant Data Message: .
***THIS IS A DRILL ***
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/ 987 Evaluated Exercise Time - 1230 tessage Number 37 COOPER NUCLEAR STATION t - 05/00 EMERCENCY PREPAREDNESS EXERCISE PLANT DATA-PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 900 SPJ4 RHR A UNAVAIL 0 0 REACTOR LEVEL 3 5 "-* VR RHR B 0 REACTOR PRESSURE 28 TRIPPED _
RHR C LPCI 150 500 CORE D/P (psiS ) 0.3 6 RHR D STBY 50 CORE FLOW (10 lbm/hr) 0.1 6 CS A STBY 50 0 FLOW (10 lbs/hr) CS B STBY 50 0 FEEDWATER A 0 i l HPCI ISOL 0 0 FEEDWATER B 0 ' l i Drywell Pressure .3 (psig) MAIN STEAM A 0 ) l l Torus Level .1 (inches) MAIN STEAM B 0 l l 8 O OPEN CLOSED MAIN STEAM C 0 , 1 MSIV O 8 MAIN STEAM D 0 FLOW PANEL 9-4 CRD A 50 (gpm) STATUS PRESS (psig) FLOW (gpm) CRD 5 AVAIL ('gpm) RCIC ISOL 0 0 LEVEL PRESS SQUIB PUMPS KCU A ISOL O_ 0 SLC 75 % 0 (psig) ON UNAVAIL 1 RWCU B ISOL 0 0 RRPA 0 % SPD MISCELLANEOUS PANELS RRPB 0 % SPD DIESEL GEN A OPER DIESEL GEN B OPER SBGT A , OPER SBGT B STBY , DRYWELL COOLING NORMAL h TORUS WATER TEMP 87 *F
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('~'g RADIATION MONITOR DATA Time - 1230 t
.v/ t - 05/00 AREA RADIATION MONITORS READING STATION DESCRIPTION (mr/hr) 1 Rx Bldg Fuel Pool Area (SE 5th Floor) 1800 2 Rx Bldg Fuel Pool Area (SE Sch Floor) OS
- 3 Rx Bldg New Fuel Area (SE Sth Floor) 35 4 Rx Bldg Rx Water Cleanup Demineralized Area OS *
(SW 3rd Floor) 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) OS
- 6 . Rx Bldg Neutron Monitor System Index Area OS *. -
(TIP Room 1st' Floor) , 7 Rx Bldg Neutron Monitor System. Drive Mech Ares OS
- l (SE 1st Floor) 8- Rx 31dg Control Rod Hydraulic Equipment Area OS *
(S 1st Floor) 9 Rx Bldg Control Rod Hydraulic Equipment Area OS * (N ist Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) OS *- 11 Rx Bldg RER Pump Room (SW Quad) OS
- 12 Rx Bldg RHR Pump Room (NW Quad) OS
- p) 13 14 Rx Bldg RCIC/CS Pump Room (NE Quad)
Rx Bldg CS Pump Room (SE Quad) OS
- OS *
.(s_/
15 Turbine Bldg Turbine Front Standard 2 16 Turbine Bldg Turbine Bldg Mezz Centrol Corridor OS
- 17 Turbine Bldg Turbine Bldg Basement Control Corridor OS
- 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 100
- 19 Turbine Bldg Turbine Bldg Condensate Pump Area 5 20 Control Room Main Control Room 0.015 ;
21 Grade Level Control Corridor OS
- j 22 Radwaste Control Room 0.02 1 23 Radwaste Pump Room 7 l 24 Radwaste Basement Equipment Area 3 !
l 25 Radwaste Demin Valve Room 2 26 Radwaste Conveyor Aisle Operating Area 0.3 27 SPARE 28 Radwaste Lab Area 0.2 ] 29 Centrifuge East 10 30 Centrifuge West 9 Panel 9-02 Personnel Airlock Area 903' 2.0 R/hr Panel 9-02 Ladder 903' to 2nd Level 1.5 R/hr
- Alarm .
OS Offscale V
RADIATION MONITOR DATA Time - 1230
- % ) t - 05/00 PROCESS AND VENT MONITORS PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 0 uCi/sec "ERP Stack Normal Eff (RMP-RM-3A) -
0 'uCi/sec I ERP Stack High Range (RMP RM-3B) 2.05 E+8 uCi/sec Turbine Bldg Vent Eff (RMV-RM-20A) 1.5 E-3 uC1/sec Turbine Bldg High Range (RMV RM-20B) 0 uCi/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 1.0 E-3 uCi/see RW/ARW Bldg High Range (RMV;-RM-30B) 0 uCi/sec PANEL 9-10 Mn. Stm. Rad Monitor Ch. A1, B1 45 mR/hr 40 mR/hr Ch. A2, B2 40.mR/hr 45 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B . 1 mR/hr 1 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B OS mR/hr OS mR/hr Service Water 10 cps [ Reactor Equipment Cooling 20 c,ps l i E_______._______.._____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ . _ _ _ __ _ __ __ _ ____.______j
Og 1987 Evaluated Exercise Time - 1230 I
\) ' Message Number: 37 t - 05/00 l
COOPER NUCLEAR STATION , EMERGENCY PREPAREDNESS EXERCISE MESSAGE i For Controller Use Only: CONTROLLER INFORMATION: -
^ . o Leak continues at 500 gpm (approx.)
o Calculations show that the peak projected offsite dose rate is 980 mr/hr (whole body) and 17 Rem /hr (child thyroid) at 2 miles. EXPECTED ACTIONS: - o Prepare to initiate Alternate Shutdown Cooling as soon as the leak is isolated. b d ' l l O U I i l
A 1987 Evaluated Exercise Time - 1230 (approx.) f Message Number: 38X t - 05/00 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Message for: RHR MO-17 Repair Team /RHR MO-18 Repair Team Simulated Plant Conditions: Message: -
***THIS IS A DRILL ***
MO-17 l There is a blown fuse in the DC - power supply for MO-17. The fuse has fused itself into position and must be forcibly removed before replacement. 1 MO-18 g The valve MCC loss normal. , 1 1 l 1 e t ( 1
------.----.----__-----_---a-.---,-,- - - - _ _ - - - -
f'"'N 1987 Evaluated Exercise Time - 1230 (approx.) ( )-
'~/ Message Number: 38X t- 05/00 COOPER NUCLEAR STATION
'l EMERGENCY PREPAREDNESS EXERCISE MESSAGE For Controller Use Only:
, 1 CONTROLLER INFORMATION:
o Deliver this information to the repair team sent to close RHR-MO-17 , when appropriate investigations have been made. ~' o Repairs to MO-17 are to be completed at 1:00 p.m. o Valve will close automatically when power supply is repaired because
. isolation signal is still present. 1 EXPECTED ACTIONS:
s o Make appropriate repairs. 1
)
1 I i i l D
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. j
('g 1987 Evaluated Exercise ' Time - 1235 Message Number: 39X t - 05/05 1 l COOPER NUCLEAR-STATION . EMERGENCY PREPAREDNESS EXERCISE MESSAGE l
)
Message for: Emergency Director ) 1 1 Simulated Plant Conditions: ) J l Message: 1 1
***THIS IS A DRILL ***
-)
i Declare a General Emergency, per EPIP 5.7.1 Initiating Condition 2.6, " Loss of. J two of three fission product barriers". j l'
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i []- 1987 Evaluated Exercise Time - 1235 (approx.) ) i / j
d Message Number: 39X t - 05/05 (approx.)
{ COOPER NUCLEAR STATION I EMERGENCY PREPAREDNESS EXERCISE MESSAGE i For Controller Use Only: CONTROLLER INFORMATION: o -Deliver this message ' only if a General Emergency has not been-declared, and if there are not discussions in progress that would result in that declaration. EXPECTED ACTIONS: i i
/' %
l l i ( : x l
1
\
1987 Evaluated Exercisa Time - 1245
\ 40 Message Number: t - 05/15 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Message for: Control Room Simulated Plant Conditions: See attached Plant Data l
- Message:
***THIS IS A DRILL ***
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f'~N1987 Evaluated Exercice , Time - 1245 (_,IessageHumber 40 COOPER NUCLEAR STATION t - 05/15 EMERGENCY PREPAREDNESS EXERCISE PLANT DATA l'ANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 900 SRM PJIR A UNAVAIL 0 0 REACTOR LEVEL 3 5 "-+ WR RHR C TRIPPED 0 REACTOR PRESSURE 20 PJ1R B LPCI 100 500 CORE D/P (psig) 0.3 6 RHR D STBY 50 CORE FLOW (10 lbm/hr) 'O.1 0 CS A STBY 50 0 FLOW (10 lbs/hr) CS B STBY 50 0 FEEDWATER A 0 HPCI STBY 5,0 0 FEEDWATER B 0 . Drywell Pressure .3 (psig) MAIN STEAM A 0 Torus Level .25 (inches) MAIN STEAM B 0
/~} OPEN CLOSED MAIN STEAM C 0 l MSIV 0 8 MAIN STEAM D 0 l FLOW PANEL 9-4 CRD A 50 (gpm) i l
STATUS PRESS (psig) FLO:i(gpm) CRD B AVAIL (gpm) l RCIC ISOL O 0 LEVEL IRESS SQUIB PUMPS RWCU A ISOL 0 0 SLC 75 % 0 (psig) ON UNAVAIL . 1 i I l RWCU B ISOL 0 0 I i RRPA 0 % SPD MISCELLANEOUS PANELS l RRPB 0 % SPD DIESEL CEN A STBY l DIESEL CEN B STBY SBGT A OPER SBGT B STBY DRYWELL COOLING NORMAL TORUS WATER TEMP 87 'F
M ]'v
= = 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 e t
)
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- 0 3
E - S I C 6 R 3_ 6 N E . . - O X 0 5 0 0 0 5 0 0 5 0 0 0 5 0 0 . T E I 1 1 + - 1 1 2 4 2 , 2
+ 4 - - - 2 1 1 A SS )
- + + -
T E n 0 ) - S ( i in N A ( RDT A E A l e v l c e 7: E L AR D L L t C P S r U E DP o s t u N R c r _ S a o 5 R P _ e 1
- T -
R E Y - _ P C -. - O N _ O E C G R E 0 _ M 3 E 3 _ ) _ M 0 0 0 0 0 0 8 5 4 0 0 0 0 0 0 _ R 1 7 6 $ 4 ,9 2 1 P
. 0 -
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g _ G is p _ V ( ( A e _ _ r _ e r _ u - i s e _.
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pg RADIATION MONITOR DATA. Time - 1245 (w.j . t - 05/15 AREA RADIATION MONITORS READING STATION DESCRIPTION (mr/hr) 1 Rx Bldg Fuel Pool Area (SE 5th Floor) 2300 2 Rx Bldg Fuel Fool Area (SE 5th Floor) OS
- 3 Rx Bldg New Fuel Area (SE 5th Floor) 40 .
4 Rx Bldg Rx Water Cleanup Demineralized Area _ OS
- j (SW 3rd Floor) I 5 Rx r.1dg Sludge and Decant Pump Area (S 2nd Floor) OS
- l 6 Rx Bldg Neutron Monitor System Index Area OS.*
(TIP Room 1st Floor) 7 Rx Bldg Neutron Monitor System Drive Mech Ares OS * (SE lst Floor) 8 Rx Bldg Control Rod Hydraulic Equipment Area OS * (S ist Floor) 9 Rx Bldg Control Rod Hydraulic Equipment Area OS * (N lst Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) OS
- 11 Rx Bldg RHR Pump Room (SW Quad) OS
- 12 Rx Bldg RER Pump Room (NW Quad) OS
- 13 .Rx Bldg RCIC/CS Pump Room (NE Quad) OS *
(3 14 Rx Bldg CS Pump Room (SE Quad) OS * (,/ 15 Turbine Bldg Turbine Front Standard 2 16 Turbine Bldg Turbine Bldg Mezz Control Corridor OS
- 17 Turbine Bldg Turbine Bldg Basement Control Corridor OS
- 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 100
- 19 Turbine Bldg Turbine Bldg Condensate Pump Area 5 20 Control Room Main Control Room 0.015 21 Grade Level Control' Corridor OS
- 22 Radwaste Control Room 0.02 23 Radwaste Pump Room 7 24 Radwaste Basement Equipment Area 3 25 Radwaste Demin Valve Room 2 26 Radwaste Conveyor Aisle Operating Area 0.3 27 SPARE ,
28 Radwaste Lab Area 0.2 29 Centrifuge East 10 30 Centrifuge West 9 Panel 9-02 Personnel Airlock Area 903' 2.0 R/hr Panel 9 02 Ladder 903' to 2nd Level 1.5 R/hr
- Alarm '
OS Offscale j Q v _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ ____._______________________iJ
i []) RADIATION MONITOR DATA Time - 1245 t - 05/15 ; PROCESS AND VENT MONITORS PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 0 uCi/sec ERP Stack Normal Eff (RMP RM-3A) 0 uCi/sec l ERP Stack High Range (RMP-RM-3B) 2.0 E+8 uCi/sec j Turbine Bldg Vent Eff (RMV-RM-20A) 1.5 E-3 uCi/sec Turbine Bldg High Range (PJIV RM-20B) 0 uCi/see RW/ARW Bldg Combined Eff (RMV-RM-30A) 1.0 E-3 uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) 0 uCi/see PANEL 9-10 Mn. Stm. ' Rad Monitor Ch. A1, B1 45 mR/hr 40 mR/hr Ch. A2, B2 40 mR/hr 45 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 1 mR/hr 1 mR/hr l Rx Bldg Vent Ind/ Trip Unit Ch. A, B OS mR/hr OS mR/hr 1
.l 1
1 Service Water 10 cps
; Reactor Equipment Cooling 20 cps V
1 l
l l
^
=1987 Evaluated Exercise Time - 1245 l
\ Message Number: 40 t - 05/15 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE For Controller Use Only:
CONTROLLER INFORMATION: , o Data reflects EDG return to STBY status, l l-EXPECTED ACTIONS: a i r Y ); i.
i
,e 1987 Evaluated Exercise Time - 1255 q k
l Message Number: 41X 't - 05/25 j
-}
1 COOPER NUCLEAR STATION 1 EMERGENCY PREPAREDNESS EXERCISE MESSAGE ) Message for: Repair team working on RHR MO-17 Simulated Plant Conditions: Message: 9
***THIS IS A DRILL ***
, The Power Supply repairs are complete. 'j-l i . I u_--_.___----_-____---_-__--__...-_-_._-_-_---._--.._ _ _ _ . - _ - _ _ . . - _ _ . . _ _ _ _ - - _ _ _ _ _ . - - _ - . _ _ _ . - _
['N 1987 Evaluated Exercise Time - 1255
-Message Number: 41X t - 05/25 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE For Controller Use Only:
CONTROLLER INFORMATION: o Valve will close automatically on restoration of power since the isolation signal is still present. o When information is received in the Control Room, Controller to verify that the green indicating light is on. EXPECTED ACTIONS: U G
['N 1987 Evaluated Exercise Time - 1300 Message Number: 42 t - 05/30 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE l Message for: Control Room Simulated Plant Conditions: See attached Plant Data l Message: 1
***THIS IS A DRILL ***
Indications in the Control Room include: RHR-M017: Green light on. l i l (g) s/ l i i I l
'1 l 'h I
O l987 Evaluated Exercise Time - 1300 cIessage Number 42 COOPER NUCLEAR STATION t - 05/30 EMERGENCY PREPAREDNESS EXERCISE PLANT DATA - PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 900 SRM RER A UNAVAIL 0 0 REACTOR LEVEL 140 RHR C TRIPPED 0 REACTOR PRESSURE 15 l l RHR B TRS. CLG 150 14,000 CORE D/P (psig) 0.3 ; 6 RHR D TRS. CLC _ 150 CORE FLOW (10 lbm/hr) 0.1 6 CS A ASDC 180 4,700 FLOW '(10 lbs/hr) k CS B ASDC 180 4,700 FEEDWATER A 0 j HPCI ISOL 0 0 FEEDWATER B 0 Drywell Pressure .3 (psig) MAIN STEAM A 0
- Torus Level -0.25 (inches) MAIN STEAM B 0 O 4 OPEN CLOSED M IN STEAM C 0 6
MSIV 0 8 MAIN STEAM D 0 FLOW i PANEL 9-4 (gpm) CRD A 50 , STATUS PRESS (psig) FLOW (gpm) CRD B AVAIL (gpm) RCIC ISOL 0 0 LEVEL PRESS SQUIB PUMPS . RWCU A ISOL 0 0 SLC 75 % 0 (psig) ON Avail RWCU B ISOL 0 0 ; RRPA 0 % SPD MISCELLANEOUS PANELS RRPB 0 % SPD DIESEL GEN A STBY DIESEL GEN B STBY
]
i SBGT A OPER ; }
-SBGT B STBY DRYWELL COOLING NORMAL \ TORUS WATER TDIP 85 'F
N 6
= = 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 0 2 0 8 6 e t
)
4 1 2 1 0 1 8 6
)
F 1 1 m g 0 O i T is . ( ( p e r e u r t u a s r s e e r p P 5 m r 1 e o - T t s c u a r e o R T . 0 3 E - - S I C R b 5 2 N E ~ O X 0 5 0 0 0 5 0 0 5 0 0 0 5 0 0 I T E 1
+ +
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+
+
A SS ) p [ 0 T E n ) y S ( i n N A i ( R D T l - e l v e A E A e v ,- E L A R D L L e f C P S r U E DP o s - t u r N R c R P E Y S R a e 5 1
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)
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-i RADIATION. MONITOR DATA Time - 1300
. ,O) 4 t'- 05/30 1 AREA RADIATION MONITORS READING STATION DESCRIPTION (mr/hr) 1 -Rx Bldg Fuel Pool Area (SE Sch Floor) 1500
.2 Rx Bldg Fuel Pool Area (SE Sch Floor) OS-*
3 Rx Bldg New Fuel Area (SE Sch Floor) 30 4 Rx Bldg Rx Water Cleanup Demineralized Area OS * (SW 3rd Floor) 5 Rx Bldg Sludge and. Decant Pump Area (S 2nd Floor) OS .
- 1 6 Rx Bldg Neutron Monitor System Index Area OS'* I (TIP Room 1st Floor) l l 7 Rx Bldg Neutron Monitor System Drive Mech Ares OS
- I (SE lst Floor) l 8 Rx Bldg Control Rod Hydraulic Equipment Area OS *
(S 1st Floor) 9 Rx Bldg Control Rod Hydraulic Equipment Area OS * (N lst Floor) ,
]
10 Rx Bldg HPCI Pump Room (SW Quad) OS
- 11 Rx Bldg RHR Pump Room (SW Quad) OS
- 12 Rx Bldg RHR Pump Room (NW Quad) OS
- q 13 Rx Bldg RCIC/CS Pump Room (NE Quad) OS
- l 14 Rx' Bldg CS Pump Room (SE Quad) OS
- I
(/ 15 Turbine Bldg Turbine Front Standard 2 16 Turbine Bldg Turbine Bldg Mez: Control Corridor OS
- 17 Turbine Bldg Turbine Bldg Basement Control Corridor OS
- 18 Turbine Bldg Turbine Bldg Rx' Feed Pump Area 70 19 Turbine Bldg Turbine Bldg Condensate Pump Area 5 20 Control Room Main Control Room '
O.015 21 Grade Level Control Corridor OS
- 22 Radwaste Control Room 0.02 23 Radwaste Pump Room 7 24 Radwaste Basement Equipment Area 3 25 Radwaste Demin Valve Room 2
! 26 Radwaste Conveyor Aisle Operating Area 0.3 1 27 SPARE 28 Radwaste Lab Area 0.2 . 29 Centrifuge East 10 30 Centrifuge West 9 Panel 9-02 Personnel Airlock Area 903' 2.0 R/hr Panel 9-02 La 6er 903' to 2nd Level 1.5 R/hr l
- Alarm OS Offscale l
l l O)
j'] RADIATION MONITOR DATA Time - 1300
'j x t - 05/30 !
j PROCESS AND VENT' MONITORS 1 PANEL VBDG ! Rx Bldg Vent Eff (RMV-RM-40) 0 uCi/sec ERP Stack Normal Eff (RMP-RM-3A) 0 uCi/sec ERP Stack High Range (RMP-RM-3B) 1.4 E+8'uCi/sec Turbine Bldg Vent Eff (RMV-RM-20A) -1.5 E-3 uCi/sec Turbine Bldg High Range (RMV-RM-20B) 0 uCi/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 1.0 E-3 uCi/sec-RW/ARW Bldg High Range-(RMV-RM-30B) 0 uCi/see PANEL 9-10 . Mn. Stm. Rad Monitor Ch. A1, B1 45 mR/hr 40 mR/hr Ch. A2, B2 40 mR/hr 45 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 1 mR/hr 1 mB/hr i Rx Bldg Vent Ind/ Trip Unit Ch. A, B OS mR/hr OS mE/hr Service Water 10 cps (fw) Reactor Equipment Cooling 20 cps q
%./
l l v
j 1987 Evaluated Exercise Time - 1300 Message Number: 42 t - 05/30 . COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE For Controller Use Only: CONTROLLER INFORMATION: o RHR MO-17 will shut automatically when electrical repairs are completed since the isolation signal is still present. o When word is received of successful repair, give Control Room ; operators information that_the green' position indication light is on 1 for MO-17. o The release will continue until 1345 due to the hot water in sumps vaporizing and being exhausted by SGTS. l EXPECTED ACTIONS: k.) o Line up Core Spray f6r reactor recirculation portion of ASDC and line up RHR for suppression pool cooling. 1 1 l l l l l V i l
l
, 1987 Evaluated Exercise Time - 1305 I
i Message Number: 43 t - 05/35
. COOPER NUCLEAR STATION l EMERGENCY PREPAREDNESS EXERCISE MESSAGE Message for: Control Room i
Simulated Plant Conditions: See attached Plant Data l i Message:
***THIS IS A DRILL ***1 . i 1
e l
D 1987. Evaluated Exercise Time - 1305
\ i ' v itessage Number 423 COOPER NUCLEAR STATION t - 05/35 EMERCENCY PREPAREDNESS EXERCISE PIANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) ' REACTOR POWER 900 SRM RHR A UNAVAIL 0 0 REACTOR LEVEL 330 WRG RHR C TRIPPED 0 REACTOR PRESSURE- 180 RHR B TRS. CLG 150 14,000 CORE D/P (psig) 0.3 6
RER D TRS. CLG 150 CORE FLOW (10 lbm/hr) 0.1 6 CS A ASDC 180 4,700 FLOW (10 lbs/hr) CS B ASDC 180 4,700 FEEDWATER A 0 l HPCI ISOL 0 0 FEEDWATER B 0 Drywell Pressure' .3 (psig) MAIN STEAM A 0 Torus Level -2 (inches) MAIN STEAM B 0 [O OPEN CLOSED MAIN STEAM C 0 MSIV 0 8 MAIN STEAM D 0 FLOW PANEL 9-4 CRD A 50 (gpm) STATUS PRESS (psig) FLOW (gpm) CRD B AVAIL (gpm) RCIC ISOL 0 0 LEVEL PRESS SQUIB PUMPS RUCU A ISOL 0 0 SLC 75 % 0 (psig) ON UNAVAIL RWCU B ISOL 0 0 l RRPA 0 % SPD MISCELLANEOUS PANELS RRPB 0 % SPD DIESEL GEN A STBY DIESEL GEN B STBY SBGT A OPER SBGT B STBY DRYWELL COOLING NORMAL
'L/ TORUS WATER TEMP 85 *F
-_ __J
%U / -
/
f
= = 0 0 0 0 0 0' 0 y 0 0 0 0 0 0 0 0 0 o 0 B 6 e t
)
4 1 2 1 0 1 8 4 2 0 ) F 2 1 0 1 ' m g , 0 iT i ( s p / _ ( e r e u r u _ t a s r e P s e r _. p m r 5 1 e o _ - T s t c _ u a _ r ' e o R T E
' u_. 3 0
S I C e' R H N E O X 0 5 0 0 0 5 0 0 0 0 5 0 0 I T E . 1 1 + 1 1 2 4 2 0 2
+ + - - 2 1 1 A SS )
- + + -
n 0 T S E ( i f' ) n N A l ( i R D T e v l e A E A e v E R D e Cy .C L U A P E S DP L t r o L s u N R c r P S a 5 o R e 1
- T E Y R P C O N O E C G R
E 0 M 3 E f i
)
M 0 0 0 0 o - 0 8 6 4 0 0 0 0 0 0 0 R 1 7 6 5 4 3 2 1 P 0 . . A _
)
% g G
i s p V _ ( A e e ( r _. r u i s e .
,5
. s s
c w 1 e r o _ r e P _ P x _ E r _ l t o _ l e d t e /'3 c a w y a e r l u R 0 3 D a e t v E ga 7 s 8 9 e 1 M
l
/ ~) 1987 Evaluated Exercise . Time - 1305 b Message Number: 43 t - 05/35 '
.iq COOPER NUCLEAR STATION 1
EMERGENCY PREPAREDNESS EXERCISE MESSAGE ' ll i For Controller Use Only:
' CONTROLLER INFORMATION:
o Alternate Shutdown Cooling has been established with CS pumps Recirculating Reactor water through 1SRV to torus to Reactor. . RHR -) pumps B and D are cooling to torus. 1 1 EXPECTED ACTIONS: ) I i o Monitor cooldown rate, do not exceed 100*F/hr I l o Monitor Reactor pressure, do not exceed 280'psig without opening an additional SRV: (D l U 1 4 o U
- _ . _ _ _ _ _ . . _ . . _ _ _ . _ - - - _ . - _ - . . _ _ _ _ _ . . - -_--_-_..a----_----_----.-O
3 s i 1 J
'\ 1987 Evaluated Exercise , Time - 1315 l
Message Number: 44 t - 05/45
*i COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE
'l Message for: Control Room Simulated Plant Conditions: See attached Plant Data Message:
. ***THIS IS A DRILL ***
Annunciators in the Control Room include: RHR B Heat Exchanger Tube to Shell Differential Pressure Low I Indications in the Control Room include: l g- SW-DPIC-130B 14 PSID/ Oscillating ~11-13 PSID I, SU-M089D position oscillating on POM 129B
'r f%
[ ' 1987 Evaluated Exercise Time - 1315 IIessage Number 44 COOPER NUCLEAR STATION t - 05/45 EMERGENCY PREPAREDNESS EXERCISE PIANT DATA PANEL 9-3 PANEL 9-5 STATUF PRESS (psig) FLOW (gpm) -REACTOR' POWER 900 SRM RHR A UNAVAIL 0 0 REACTOR LEVEL 330" WRG RHR C TRIPPED 0 REACTOR PRESSURE 180 RHR B TRS. CLG 150 14,000 CORE D/P (psig) 0.3 0 RHR D TRS. CLG 150 CORE FLOW (10 lbm/hr) _,0.1 6 l CS A
'ASDC 180 4,700 FLOW (10 lbs/hr)
CS B ASDC 180 4,7'00 FEEDWATER A ~0 HPCI ISOL 0 0 FEEDWATER B 0 Drywell Pressure .3 (psig) MAIN STEAM A 0 Torus Level 0 (inches) MAIN STEAM B 0
/ OPEN CLOSED MAIN STEAM C 0
) MSIV t
0 8 MAIN STEAM D 0 ( FLOW PANEL 9-4 CRD A 50 (gpm) STATUS PRESS (psig) FLOW (gpm) CRD B AVAIL (gpm) l RCIC ISOL 0 0 LEVEL PRESS SQUIB PUMPS RWCU A ISOL 0 0 SLC 75 % 0 (psig) ON UNAVAIL RWCU B ISOL 0 0 RRPA 0 % SPD MISCELLANEOUS PANELS RRPB 0 % SPD DIESEL CEN'A STBY DIESEL GEN B STBY SBCT A OPER l SBGT B STBY A DRYWELL C00LINC NORMAL
!t k TORUS WATER TEMP 85 'F
_ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 1
"' 3 I q
= = 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 8
e t
) 41 2
1 0 1 8 6 2 o ) F 2 1 0 1 6 m- g 0 O i T isp ( ( e r e u r t u a s r s e e p r P 5 m e t r o /1 _
- T s
. c u a r e o R T 0
3 E - S I 1 C 0 l R f 6 N E O X 0 5 0 0 0 5 0 0 0 5 0 0 5 0 0 E I 1 + 4 2 0 2 T - 2 1 1 1
+ + - - - 2 1 1 A SS )
- + + -
T E n 0 ) - S ( i in R A E A N A D T l e v e ( l v e ~ E L AR D L L e b P S r o s U E DP t c - u r N R S a 5 o % R P e 1
- T E Y R P C O N O E C G R
E 0 M 3 E 3
)
' M 0 0 0 0 0 0 8 6 0 0 0 0 0 0 0 R 1 7 6 5 4 3 2 1 P 0 .
A
% )
ig G s p V ( ( A - e
- c. r e r u i
s e 5 s s c w 1 e F r e a P o r l P r o _k c d e / t c - e v t 7 a - - y
'a e d r ~
u R 0 D l a e
- 3 v g E a 7 s 5
s 9 e
#t
'1 :
i _ p ( _
Time - 1315.
.(}
/ RADIATION MONITOR DATA
/ t - 05/45 AREA RADIATION MONITORS READING STATION DESCRIPTION (mr/hr) 1 Rx Bldg Fuel Pool Area (SE 5th Floor) 500 2 Rx Bldg Fuel Pool Area (SE 5th Floor) OS
- 3 Rx Bldg New Fuel Area (SE 5th Floor) 10 4 Rx Bldg Rx Water Cleanup Demineralized Area 1000 *
(SW 3rd Floor) 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) OS
- 6 Rx Bldg Neutron Monitor System Index. Area 0S *
(TIP Room ist Floor) 7 Rx Bldg Neutron Monitor System Drive Mech Ares OS * (SE lst Floor) - 8 Rx Bldg Control Rod Hydraulic Equipment Area OS * (S lst Floor) 9 Rx Bldg Control Rod Hydraulic Equipment Area OS * (N lst Floor) 10 Rx Bldg HPCI Pump Room'(SW Quad) OS
- 11 Rx Bldg RER Pump Room (SW Quad) OS
- 12 Rx Bldg RHR Pump Room'(NW Quad) OS
- f- 13 Rx Bldg RCIC/CS Pump Room (NE Quad) OS *
{ 14 Rx Bldg CS Pump Room (SE Quad)'
- OS * -
\s - 15 Turbine Bldg Turbine Front Standard 2 1 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 50 l 17 Turbine Bldg Turbine Bldg Basement Control Corridor OS
- l 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 30 19 Turbine Bldg Turbine Bldg Condensate Pump Area 4 20 Control Room Main Control Room 0.015 21 Crade Level Control Corridor 50 22 Radwaste Control Room 0.02 23 Radwaste Pump Room 7 24 Radwaste Basement Equipment Area 3 25 Radwaste Demin Valve Room 2 26 Radwaste Conveyor Aisle Operating Area 0.3 27 SPARE 28 Radwaste Lab Area 0.2 29 Centrifuge East 10 30 Centrifuge West 9 Panel 9-02 Personnel Airlock Area 903' 2.0 R/hr Panel 9-02 Ladder 903' to 2nd Level 1.5 R/hr
- Alarm OS Offscale v
E
j' RADIATION MONITOR DATA Time - 1315 t - 05/45 PROCESS AND VENT MONITORS PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 0 uCi/sec ERP Stack Normal Eff (RMP-RM-3A) 0 uCi/see ERP Stack High Range (RMP-RM-3B) 6.4 E+7 uC1/sec. 7urbine Bldg Vent Eff (RMV-RM-20A) 1.5 E-3 uCi/sec l Turbine Bldg High Range (RMV-RM 20B) 0 uCi/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 1.0 E-3 uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) 0 uCi/sec PANEL 9-10 kn. Stm. Rad Monitor Ch. A1, B1 45 mR/hr 40 mR/hr Ch. A2, B2 40 mR/hr 45 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 1 mR/hr 1 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B OS mR/hr OS mR/hr Service Water 10 cps [ Reactor Equipment Cooling - 20 cps i 1 i O
4 (Ng 1987 Evaluated Exercise Time - 1315
\j Message Number: 44 t - 05/45 4
COOPER NUCLEAR STATION EMERCENCY PREPAREDNESS EXERCISE MESSACE For Controller Use Only: CONTROLLER INFORMATION: o The Service Water System differential pressure controller, which maintains SW at higher pressuro than RER in order prevent outleakage by modulating SU flow downstream of the RHR Heat Exchanger', has begun to oscillate, causing a low differential pressure alarm in the Control Room. EXPECTED ACTIONS: o Dispatch I&C tech to investigate problem, fs o Attempt to start another RHR SW Booster Pump if.I&C can not solve the problem. - ( l [ ts
F : 1987 Evaluated Exercise Time - 1325 V Message Number: 45X t - 05/55 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Message for: Instrument Technician investigating the differential pressure controller DPIC-130B Simulated Plant Conditions: Message: _. ***THIS IS A DRILL *** (Later) R . V O
e [^ 1987 Evaluated Exercise Time - 1325 \' j Message Number: 45X t - 05/55 j i COOPER NUCLEAR STATION; EMERGENCY PREPAREDNESS EXERCISE MESSAGE 1 For Controller Use Only: CONTROLLER INFORMATION: -i k
. o I&C technician cannot be allowed to fix DPIC 130B at this time, o The final 'fix' will be manual closure of the valve by an operator.
i I EXPECTED ACTIONS: o Instrument tech should continue attempts to regain control of DP i controller. (s - l l i i l 0
- _.. _ _ . . _ _ _ _ _ _ _ _ __._______._.__._.____J
/h 1987 Evaluated Exercise' Time - 1330-Message Number: 46 t- 06/00 !
COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSACE f ( 1 l 1 Message for: Control Room i Simulated Plant Condition.s: See attached Plant Data Message:
***THI5 IS A DRILL ***
J Annunciators in the Control Room include: RHR B Heat Exchanger Tube to Shell Differential Pressure Low 1 RRR Heat Exchanger 2A/2B Out High Conductivity l Liquid Process High Radiation l l
~~x Indications in the Control Room include: )
f
\
sm- SW-DPIC-130B - O psid (oscillating) SW-MO-89B - pesition oscillating on POM 129B , RMP-RM 351 - 900 cps 1 l RHR-CIS-95B - 120 pmhos 1 1
)
i i 0 f i
\s i
_ . _ . _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . . _ . _ _ ._________..____________..__._.__________J
4
/, 9 987 J
Evaluated Exercise Time - 1330 ( 41essage Number 46 COOPER NUCLEAR STATION t - 06/00 EMERGENCY PREPAREDNESS EXERCISE PIANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER- 900 SRM RHR A UNAVAIL 0 0 REdCTOR LEVEL 330" VRG RHR C TRIPPED 0 REACTOR PRESSURE 180 RHR B TRS. CLG 100 lli,000 CORE D/P (psig) ~0.3 6 RHR D TRS CLC 100 CORE FLOW (10 lbm/hr) 0.1 6 CS A ASDC 180 - 4,700 FLOW (10 lbs/hr) CS B ASDC 180 4,700 FEEDWATER A 0 HPCI ISOL 0 0_ FEEDWATER B 0 Drywell Pressure .3 (psig) MAIN STEAM A 0 Torus Level 0 (inches) MAIN STEAM B 0 OPEN: CLOSED MAIN STEAM C 0 MSIV O 8 MAIN STEAM D 0 , FLOW PANEL 9 4 CRD A 50 (gpm) i STATUS PRESS (psig) FLOW (gpm) CRD B AVAIL (gpm) RCIC ISOL 0 0 LEVEL PRESS SQUIB PUMPS - RWCU A ISOL 0 0 SLC 75 % 0 (psig) ON Avail RWCU B ISOL 0 0 l l RRPA 0 % SPD MISCELLANEOUS PANELS l RRPB 0 % SPD DIESEL GEN A STBY l
~
. DIESEL GEN B . STBY j
SBGT A OPER SBCT B STBY D DRYWELL COOLING NORMAL ( b TORUS WATER TEMP 85 *F 1 i 4 L_ __ ._ __ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _
Q U' I q r g
= = '
0 0 0
'0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 8 6 e t 4 2 0 B 6 4 2 0 ) 2 1 1 m'
1 1 1
) .
F . g 0 O i T isp - ( ( e r e u r ' t u a r s s e e p r P 5 m r 1 e o - T t s c u a r e o R T J.
/ 0 3
_ E - _ S I _ C N E
- R N b O X 0 5
0 0 0 5 0 0 0 0 5 0 0 I T E 1 1 + 1 1 2 4 12 0 2
- + + - - 2
+
1 A SS + _ ) n 0 _ T S E ( i
)
n _ N A l e ( i R D T v l e _. A E A e v - E L A R D L L e C P SD r k U E o s _ P t u N R c r P S a 5 o _ R e 1
- T E Y R
_ P C - O N O C E G ._ _ R - _ E 0 _ M 3 E 3
)
0 0 0 0 M 0 0 8 6 4 0 0 0 0 0 0 0 0 R 1 7 6 5 4 3 2 1 P 0 - A
)
% ig G s p
_ V ( A ( e r e r u i s e 5 s s c w 1
- e r o r e P P x
E r l t o l e d , c w t e l t a y a e r l u ' ~ R 0 3 D a e - Ev ga 7 ss 8 9 e 1 M
l I fO RADIATION MONITOR DATA Time - 1330 {/ t - 06/00 AREA RADIATION MONITORS READING STATION DESCRIPTION (mr/hr) 1 Rx Bldg Fuel Pool Area (SE 5th Floor) 90 2 Rx Bldg Fuel Pool Area (SE 5th Floor) 100 . 3 Rx Bldg New Fuel Area (SE Sth Floor) 0.5 <
.4 Rx Bldg Rx Water Cleanup Demineralized Area 200 i (SW 3rd Floor) 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 500 6 Rx Bldg Neutron Monitor System Index Area 800 g (TIP Room ist Floor) l 7 .Rx Bldg Neutron Monitor System Drive Mech Ares OS ]
(SE lst Floor) 3 Rx Bldg Control Rod Hydraulic Equipment Area OS ] (S ist Floor) l 9 Rx Bldg Control Rod Hydraulic Equipment Area OS (N lst Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) OS 11 Rx Bldg RHR Pump Room (SW Quad)
- OS 12 Rx Bldg RHR Pump Room (NW Quad) OS 13 Rx Bldg RCIC/CS Pump Room (NE Quad) OS
[A
\
14 Rx Bldg CS Pump Room (SE Quad) OS , 15 Turbine Bldg Turbine Front Standard 2 l 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 10 I 17 Turbine Bldg Turbine Bldg Basement Control Corridor OS 18 . Turbine Bldg Turbine Bldg Rx Feed Pump Area 15 19 Turbine Bldg Turbine Bldg Condensate Pump Area 2 q 20 Control Room Main Control Room 0.015 21 Crade Level Control Corridor 10 22 Radwaste Control Room 0.02 23 Radwaste Pump Room ' 7 l 24 Radwaste Basement Equipment Area 3 25 Radwaste Demin Valve Room 2 26 Radwaste Conveyor Aisle Operating Area 0.3 27 SPARE 28 Radwaste Lab Area 0.2 29 Centrifuge East 10 30 Centrifuge West 9 Panel 9-02 Personnel Airlock Area 903' 2.0 R/hr Panel 9-02 Ladder 903' to 2nd Level 1.5 R/hr {
- Alarm OS Offscale O
1 RADIATION MON'ITOR DATA Time - 1330 ) (()%
,, . t - 06/00 i PROCESS AND VENT MONITORS
~
PANEL VBDG
. Rx Bldg Vent Eff (RMV-RM-40) 0 uCi/sec ERP Stack Normal Eff (RMP RM-3A) 0 uGi/sec ERP Stack High Range (RMP-RM-3B) 8.2 E+6 uCi/sec {
Turbine Bldg Vent Eff (RMV-RM-20A) 1.5 E-3 uCi/sec l Turbine Bldg High Range (RMV RM 20B) 0 uCi/sec ! RU/ARW Bldg Combined Eff (RMV-RM-30A) 1.0 E-3 uCi/sec ' RW/ARW Bldg High Range (RMV-RM-30B) 0 uCi/sec-i l PANEL 9-10 Mn. Sem, Rad Monitor Ch. A1, B1 LS mR/hr 40 mR/hr Ch. A2, B2 40 mR/hr 45 mR/hr i SJAE Off Gas Log Rad Monitor Ch. A, B 1 mR/hr_ 1 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B OS mR/hr OS mR/hr 1 I f-Service Water 10 cps
? Reactor Equipment Cooling 900 cps i
I
)
l i I L New
'I /~% 1987 Evaluated Exercise Time - 1330 Message Number: 46 t - 06/00 i
COOPER NUCLEAR STATION !
)
EMERCENCY PREPAREDNESS EXERCISE MESSACE l For Controller Use Only: I CONTROLLER INFORMATION: 1 o A catastrophic tube rupture in the 'B' RHR Heat Exchanger while the- , I d/p Controller was fluctuating has caused a major contamination ! problem in the SW system and the discharge flume.
]
o Operators actions to reduce the effluent will be hindered by inability to isolate the Heat Exchanger; however, with the pumps ) tripped the release will be minimized, o At this time there is approximately 25 megawatts of decay heat remaining, so it is mandatory that decay heat removed be re-established by opening the 'C' RHR pump suction valve. c ! l EXPECTED ACTIONS: o Implement EOP-4 o Attempt isolate RHR SW from RHR Heat Exchanger B i o Request SW sample and discharge fiume sample 1 o Trip RHR pumps and RHRSW pumps to prevent further contamination o Attempt to open RHR-MO-13C to provide suction for RHR pump 'C' and l restore suppression pool cooling /ASDC. I O l I
- s. .
l
1987 Evaluated' Exercise Time - 1335 (approx.)
}r"'S , . Message Number: 47X t - 06/05 (approx.)
COOPER NUCLEAR STATION
' EMERGENCY PREPARE 0 NESS EXERCISE MESSAGE i
Message for: Control Room Simulated Plant Conditions: See attached Plant Data Message: . I
***THIS IS A DRILL ***
i SW-MO 89B will not close with the hand switch. D ' N~s l l 1 i i l i 1
.I
)
i V
i 1 j e j987 Evaluated Exercise Time - 1335 I fessageNumber 47X COOPER NUCLEAR STATION t - 06/o5 EMERGENCY PREPAREDNESS EXERCISE PLANT DATA ,I PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 900 SRM
]
RHR A UNAVAIL 0 0 REACTOR LEVEL 330" WRG RHR C TRIPPED 0 REACTOR PRESSURE 180 l PlIR B TRIPPED 0 0 CORE D/P (psig) 0.3
]
6 RHR D TRIPPED 0 CORE FLOW (10 lbm/hr) 0.1 6 CS A ASDC 180 4,700 FLOW (10 lbs/hr) CS B ASDC 180 4,700 FEEDWATER A 0 - 1 i HPCI ISOL 0 0 FEEDWATER B 0 ! Drywell Pressure .3 (psig) MAIN STEAM A 0 Torus Level .1 (inches) MAIN STEAM B 0 i ! OPEN CLOSED MAIN STEAM C 0 l i ,( ' N 0 i MSIV 0 8 MAIN STEAM D FLOW PANEL 9-4 CRD A 50 (gpm) STATUS PRESS (psig) FLOW (gpm) CRD B AVAIL (gpm)
- RCIC ISOL 0 0 LEVEL PRESS SQUIB PUMPS RWCU A ISOL 0 0 SLC 75 % '0 (psig) ON UNAVAIL .
RWCU B ISOL 0 0 RRPA 0 % SPD MISCELLANEOUS PANELS RRPB 0 % SPD DIESEL GEN A STBY I DIESEL GEN B STBY SBGT A OPER SBGT B STBY I DRYWELL COOLING NORMAL (/ TORUS WATER TEMP 85 'F
2 q g c s /
- / - / h O .
l' ,
=.= 0 0 0 0 0 0 0 k
0 0 0 0 0 0 0 0 0 0 0 4 2 0 8 6 8 2 0 ) 2 0 B ' 6 m e t 1 1
)
g 1 1 1 F e m i
, 0 O 0 -
i s ( T p e ( r 9 e u r t u a r s s e e r __ p P m - r 5 1 e 5 1 o - T - s _ t _ c u a r e
=
e o - R T . _ 0 3 0 3 E S I C N E R W l e O XE I 0 0 5 0 0 5 0 0 0 0 5 0 0 1 + 2 4 2 O 2 T 1 ~ 1 1
+ + - - - 2 1 1 A SS )
+ + -
0 e
=.
T n 0 S E
) . -
( i n ,N N A ( i R A E A D T l e v l e e v E L A D R L e _ r L C P S o s U E DP t c u r N R S a 5 o 5 R P e 1
- T 1 E Y R P C -
O N O E C G R
- E 0 0 -
M 3
, 3 E
3
)
M 0 0 0 0 0 . 8 6 4 2 0 0 0 0 0 0 0 g R 7 6 5 4 3 2 1 P 0 - . 0 A -
) -
% i g _
G s . p m V - ( A ( e r e r - u i s e 5 s s 5 c w 1 e , 1 r o - r - e P P m x r E o l l . d y t e . m m e c w y t /' a - _ a '/ e r . _ l u R 0 3 D .~ 0 3 s a e - - - e Ev ga f . v 1 7 ss w 8 9 e M 1
'f 1
l _- g 1987 Evaluated Exercise Time - 1335 (approx.)
-,O /
Messago Number: 47X t - 06/05 (approx.) COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE
.)
1 For Controller Use Only: 'd CONTROLLER INFORMATION: <
)
o Operator attempts to isolate ,the SW discharge from the heat exchanger by. closing the SW discharge valve are unsuccessful 1 o Data reflects that operators'have tripped B&D RHR pumps, and RHR SW j Booster pumps to mitigate the leakage, 1 i EXPECTED ACTIONS: o Dispatch an operator immediately to close the valve manually. l 1 l LJ l l l
*i N.j) '
- . - -------------------_-------o
i i
~~~T 1987 Evaluated Exercise Time - 1340 (approx.) . \ ] j Message Number: 48X t - 06/10 (approx.)
J l COOPER NUCLEAR STATION l l l EMERGENCY PREPAREDNESS EXERCISE MESSAGE , l i Message for: Operator dispatched to close SU-MO-89B Simulated Plant Conditions: J Message: ,
***THIS IS A DRILL ***
Valve MO-89B closes normally using the handwheel.
~
l r~x { k
's .,
/
i i l d# h
\
i _-
)
.y i
I P 1987 Evaluated Exercise Time - 1340 (approx.) I l s , N- Message Number: 48X t - 06/10 (approx.) COOPER NUCLEAR STATION .1
)
EMERGENCY PREPAREDNESS EXERCISE MESSAGE i I For Controller Use only: CONTROLLER INFORMATION: o The. mal. function of the differential pressure controller caused the - 4 valve to cycle and then fail open, The operator dispatched ' to j isolate the system by closing the valve will.be able to do so with the handwheel, as soon as he attempts. 1 EXPECTED ACTIONS: . o Report to Control Room after successfully closing the valve.
^\
I j l i l e bh V , 4 I
,s-~s 1987 Evaluated Exercise -Time - 1345 (approx.) s_- Message Number: 49X t - 06/15-COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Message for: Repair team attempting to open RHR-MO-13C Simulated Plant Conditions: See attached Plant Data Message: -
***THIS IS A DRILL ***
The 42e contactor is stuck closed and will not allow the valve to open on any - open signal (420 contactor cannot open). , e W \ l> l
)
l l p 1987- Evaluated Exercise ' Time .1345 (approx.). l
- ( '
\ Message Number: 49X t - 06/15 (approx.) j l
l COOPER NUCLEAR STATION l EMERGENCY PREPAREDNESS EXERCISE MESSAGE l For Controller 11se Only: CONTROLLER INFORMATION: q
, o The valve control circuit must be repaired at 1430, allowing the j valve to be opened and Suppression Pool Cooling /ASDC to be ;
re-established, 1
.I EXPECTED ACTIONS:
l l , l
)
1 4 1 R. l i 4 i I i l- j l l k (
l 1987 Evaluated Exercise Time - 1345 t ( Message Number: 50 t - 06/15 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Message for; Control Room Simulated Plant Conditions: See attached Plant Data Message:
***THIS IS A DRILL ***
5 4 d k
[ '1987 Evaluated Exereise -Time - 1345
,.essage Number 50 COOPER NUCLEAR STATION t -
06/15 EMERCENCY PREPAREDNESS EXERCISE PLANT DATA - PANEL 9-3 PANEL 9 5 f STATUS PRESS (psig) FLOW (gpm). REACTOR POWER 900 SRM RHR A UNAVAIL 0 0 REACTOR LEVEL 330" WRG RHR C TRIPPED 0 REACTOR PRESSURE 180" RHR B STBY 50 0 CORE D/P (psig) 0.3 , 6 RHR D STBY 50 CORE FLOW (10 lbm/hr) 0.1 6 CS A ASDC 180 4,720 FLOW (10 lbs/hr) ] CS B ASDC 180 4,720 FEEDWATER A 0 HPCI ISOL 0 0 FEEDWATER B 0 i ; l Drywell Pressure .3 (psig) MAIN STEAM A 0 Torus Level .1 (inches) MAIN STEAM B 0 , i
/~T
- OPEN CLOSED MAIN STEAM C 0 MSIV 0 8 MAIN STEAM D 0 FLOW PANEL 9-4 CRD A 50 (gpm) l STATUS PRESS (psig) FLOW (gpm) CRD B AVAIL (gpm) l RCIC ISOL 0 0 LEVEL PRESS ' SQUIB PUMPS RWCU A ISOL 0 0 SLC 75 % 0 (psig) ON UNAVAIL l RWCU B ISOL 0 0 l
l RRPA 0 % SPD MISCELLANEOUS PANELS RRPB 0 0 SPD DIESEL GEN A STBY DIESEL GEN B STBY 1 SBGT A OPER SBGT B STBY ; DRYWELL COOLING NORMAL
\ TORUS WATER TEMP 91 *F
f-
~
~
!' j
= = 0 0 0
~~
0 0 0 0 0 0 0 0 0 0 0 ; 0 0 0 0 0 8 6 e t
)
4 1 2 1 0 1 B 6 4 2 o_ .
)
F 2 1 1 i m ig 0 O s ( T p e ( r e u r t u a s r s e e p r P m r _ 5 1 e o _ - T t _ s c u r a e o R , T 0 _ 3 - _ E - _ S I _ C N E R % ~ I. _ O X 0 5 0 0 0 5 0 0 5 0 5 0 0 I T E 1 1 + - 1 2 4 2 0 2
+ + - - 2 1 1 A SS )
+ + -
_ T E in 0 ) n _ S ( N A l ( i R D T v e l e _ A E A e v E L AR D L L e ' ( _ C P S r U E DP o s t c u r N R S a o P e 5 T .% _ R 1 R E Y P C O N _ O E C G _ R E 0 _ M 3 E 3
)
0 0 0 g 0 M _ 0 8 6 . 0 0 0 0 0 0 0 _ R 1 7 6 5 4 3 2 1 P
- 0 A
)
ig G _ s _ p V ( _ A _ e _ ( r _ e r _. u s i s - e , 5 s _ c w _ 1 e r o r _ e P _ P _ x r E l _ t o l e d c _ w _ t e t a y a$ e _ r D u R 0 l _ 3 a . - ( v e g E a 7 s s 8 9 e 1 M
/~'N RADIATION MONITOR DATA Time - 1345
( v j t - 06/15' AREA RADIATION MONITORS READING STATION DESCRIPTION (mr/hr)- .. 1 Rx Bldg Fuel Fool Area (SE Sth Floor) 90 2 Rx Bldg Fuel Pool Area (SE Sth Floor) 5 3 Rx Bldg New Fuel' Area (SE 5th Floor). 0.03 4 Rx Bldg Rx Water Cleanup Demineralized Area 15-(SW 3rd Floor) 1 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 25 6 Rx Bldg Neutron Monitor System Index Area 90 l (TIP Room 1st Floor) l 7 Rx Bldg Neutron Monitor System Drive Mech Ares 50 1 (SE 1st Floor) 8 Rx Bldg Control Rod Hydraulic Equipment Area
- 50 (S lst Floor)
. 9 Rx Bldg Control Rod Hydraulic Equip' ment Area 50 (N 1st Floor) 10 Rx Bldg HPCI Pump Room (SU Quad) OS 11 Rx Bldg RHR Pump Room (SW Quad) 05 12 Rx Bldg RHR Pump Room (NW Quad) OS 13 Rx Bldg RCIC/CS Pump Room (NE Quad) OS I i 14 Rx Bldg CS Pump Room (SE Quad) . OS \s_,/
15 Turbine Bldg Turbine Front Standard 2 16 Turbine Bldg Turbine Bldg Mezz Control Corridor { 02 1 17 Turbine Bldg Turbine Bldg Basement Control Corridor OS l 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 5 19 Turbine Bldg Turbine Bldg Condensate Pump. Area 1 20 Control Room Main Contr31 Room 0.015 21 Grade Level Control Corridor 0.25 22 Radwaste Control Room 0.02 23 Radwaste Pump Room 7 24 Radwaste Basement Equipment Area 3 25 Radwaste Demin Valve Room 2 26 Radwaste Conveyor Aisle Operating Area 0.3 ; 27 SPARE 28 Radwaste Lab Area 0.2 29 Centrifuge East 10 30 Centrifuge West 9 Panel 9-02 Personnel Airlock Area 903' 2.0 R/hr Panel 9-02 Ladder 903' to 2nd Level 1.5 R/hr j
- Alarm OS Offscale v)
1
/N I
RADIATION MONITOR DATA Time - 1345
~
t - 06/15
- PROCESS AND VENT MONITORS PANEL VBDG )
Rx Bldg Vent Eff (RMV-RM-40) 0 uCi/sec ERP Stack Normal Eff (RMP-RM-3A) 0 uCi/sec ERP Stack High Range (RMP-RM-3B) 2.1 E+4 uCi/sec Turbine Bldg Vent Eff (RMV-RM-20A) 1.5 E 3 uCi/sec l Turbine Bldg High Range (RMV-RM-20B) 0 uCi/sec ) RW/ARW Bldg Combined Eff (RMV-RM-30A) 1.0 E-3 uC1/see I RW/ARW Bldg High Range (RMV-RM-308) 0 uCi/sec l l
)
PANEL 9-10 Mn. Stm. u !- ! tor Ch. A1, B1 45 mR/hr 40 mR/hr Ch. A2, B2 40 mR/hr 45 mR/hr l SJAE Off Gas Log Rad Monitor Ch A, B' 1 mR/hr 1 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B OS mR/hr OS mR/hr Service Water 10 cps ' i Rea,etor Equipment Cooling 100 cps o o 1 I r a l
/N '1987 E' valuated Exercise' Time - 1345
's Message Number: 50 t - 06/15-COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE-For Controller Use Oniv:
CONTROLLER INFORMATION: o Reactor / Suppression Pool System is heating up at approximately 6'F/15 minutes with no decay heat removal, o In plant radiation levels have decreased significantly and the ERP release rate.is near background since SGTS has filtered most of the airborne contamination out of the reactor BLDG.and the hot water in the basement had subcooled such that vapor is no longer escaping the break area. EXPECTED ACTIONS: [ o Continue to expedite re-est.ablishment of decay heat removal. i \s_, o Assess course of action if ASDC cannot be re-established. O V 1
- [^ 1987 Evaluated Exercise Time -.1400 k Message Number: 51 t - 06/30 . COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Message for: Control Room Simulated Plant Conditions: See attached Plant Data Message:
***THIS IS A DRILL ***
i . (> .
;g
[1987EvaluatedExercise
\ l
. Time- - 1400 b dessage Number 51 COOPER NUCLEAR STATION t - 06/30 EMERCENCY PREPAREDNESS EXERCISE PLANT DATA
- PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 900 SRM o RHR A UNAVAIL 0 0 REACTOR LEVEL 330" WRG RHR C TRIPPED 0 REACTOR PRESSURE 180 RHR B' STBY 50 0 CORE D/P (psig) 0.3' 6
RER D STBY 50 CORE FLOW (10 lbm/hr) 0.1 6 CS A ASDC 180 4.710 FLOW (10 lbs/hr). CS B ASDC 180 4,710 FEEDWATER A 0 HPCI ISOL 0 0 FEEDWATER B 0 Drywell Pressure .3 (psig) MAIN STEAM A' O Torus Level .1 (inches) MAIN STEAM B 0
/^ OPEN CLOSED MAIN STEAM C 0 s
MSIV 0 8 MAIN STEAM D' O FLOW 1 PANEL 9-4 CRD A 50 (gpm) STATUS PRESS (psig) FLOW (gpm) CRD B. AVAIL (gpm) RCIC ISOL 0 0 LEVEL PRESS SQUIB PUMPS l RUCU A ISOL 0 0 SLC '75 % 0 (psig) ON UNAVAIL RUCU B ISOL 0 0 i RRPA 0 % SPD MISCELLANEOUS PANELS RRPB 0 % SPD DIESEL GEN A STBY DIESEL GEN B ,STBY SBGT A OPER SBGT B STBY ! DRYWELL COOLING NORMAL TORUS WATER TEMP "97 'F C-
E
- s. -
fi h 1
._ 1
? _
~
' i ;_
e; [e c _ s
]
/
h t h . [ u _ _
. i' _
= = 0 0 . 0 0 0 0 0 E
e t
)
0 4 1 2s 0 0 1 0 1 0 0 8 6 0 4 0 2 0 ) 1 0, 2 0 0 %; 1 0 8 6 0 m g 0 F 0 i i D c- . T ( s p ( e e yr r i t u s a r
]
u s e e r p P m r - 5 1 e 5 1 T o _ t s c a u r R e C T o 0 0 3 ,3 E - - - S I C N E R @ J O X 0 0 5 0 0 5 0 0 0 5 0 3 0 0 T E
~
I 1 1 + - 1 ,2 4 2 0 2
+ + - , 2 1 1 A SS )
+ + -
T n 0 0 S E
) -
i ( n N A i ( R A E A D T l e v l e e v E L R A D L L e C P S r e, U E DP o s t c u r N R S a 5 o 5 R E Y P R e 1
- T 1 P C _
O N _ O E ._ C G _ R E 0 0 M 3
. 3 E _ _
g
)
M 0 0 0 0 0 o 0 8 6 4 2 O 0 0
- 0 0 0 0 _
R 1 T 6 5
- 3 2 1 P 0 - . 0 A _
)
% i g
G s p V ( A ( e r e r u i s e 5 s s 5 _ c w 1 e 1 o - . r r _ e P P ._ x _ E r l t o l e _ d c t e 3 a . w y ._ a 6 e . _. r u R 0 D OE 0 l _ 3 3 a e . v g . 1 a 7 s s 8 9 e 1 M _ r, l ! l l ll ll ! , il t
f'~~'g . RADIATION MONITOR DATA Time - 1400 a
,Q
/ t - 06/30 AREA RADIATION MONITORS READING STATION DESCRIPTION (mr/hr) .
1 Rx Bldg Fuel Pool Area (SE Sch Floor) 90-2 Rx Bldg Fuel Fool Area (SE Sch Floor) 5 3 Rx Bldg New Fuel Area (SE Sch Floor) 0.03 4 Rx Bldg Rx Water Cleanup Demineralized Area 15 (SW 3rd Floor) 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 25 6 Rx Bldg Neutron Monitor System Index Area 90 , (TIP Room ist Floor) 7 Rx Bldg Neutron Monitor System Drive Mech Ares 50 1 (SE 1st Floor) , 8 Rx Bldg Control Rod Hydraulic Equipment Area 50 1 (S 1st Floor) l 9 Rx Bldg Control Rod Hydraulic Equipment Area 50 l (N ist Floor) l 10 Rx Bldg HPCI Pump Room (SW Quad) OS 11 Rx Bldg EUH1 Pump Room (SW Quad) OS l 12 Rx Bldg RHR Pump Room (NW Quad) OS 13 Rx Bldg RCIC/CS Pump Room (NE Quad) OS l O 14 15 16 Rx Bldg CS Pump Room (SE Quad) Turbine Bldg Turbine Front Standard Turbine Bldg Turbine Bldg Mezz Control Corridor OS 2 0.2 17 Turbine Bldg Turbine Bldg Basement Control Corridor OS 18 Turbine Bldg Turbina Bldg Rx Feed Pump Area 5 19 iurbine Bldg Turbine Bldg Condensate Pump Area 1 20 Control Room Main Control Room 0.015 21 Grade Level control Corridor 0.25 . l 22 Radwaste Control Room 0.02 23 Radwaste Pump Room 7 24 Radwaste Basement Equipment Area 3 25 Radwaste Demin Valve Room 2 26 Radwaste Conveyor Aisle Operating Area 0.3 27 SPARE j l 28 Radwaste Lab Area 0.2 l 29 Centrifuge East 10 30 Centrifuge West 9 Panel.9-02 Personnel Airlock Area 903' 2.0 R/hr Panel 9-02 Ladder 903' to 2nd Level 1.5 R/hr
- Alarm OS Offacale f
m Q./ '
i ["]j RADIATION MONITOR DATA Time - 1400 t V t - 06/30 PROCESS AND VENT MONITORS PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 0 _uci/sec ERP Stack Normal Eff.(RMP-RM-3A) 0 uCi/sec ERP Stack High Range (RMP-RM-3B) 5.0 E+1 uCi/sec j Turbine Bldg Vent Eff (RhV-RM-20A) 1.5 E-3 uCi/sec Turbine Bldg High Range-(RMV-RM-20B) 0 uCi/see RW/ARW Bldg Combined Eff (RMV-RM-30A) 1.0 E-3 uCi/see RW/ARU Bldg High Range (RMV-RM-30B) 0 uCi/sec ) PANEL 9-10 Mn. Stm. Rad Monitor Ch. A1, B1 45 mR/hr 40 mR/hr Ch. A2, B2 40 mR/hr 45 mR/hr SJAE Off Cas Log Rad Monitor Ch. A, B 1 mR/hr 1 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B OS mR/hr OS mR/hr f Service Water 10 cps {g Reactor Equipment Cooling 20 cps l
TN 1987 Evaluated Exercise Time - 1400 l
~
Message Number: 51 t - 06/30
*l COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE 1
I l For Controller Use Only: l l CONTROLLER INFORMATION: 4 I o Reactor continues to heat up with no decay, heat removal. l i l l EXPECTED ACTIONS:
- l d['~N i t
b'
R i I. 1
,e 1987 Evaluated Exercise Time - 1415 t,
Message Number: 52 e - 06'45
/
~l COOPER NUCLEAR' STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE
. Message for: Control Room
)
Simulated Plant Conditions: See attached Plant Data Message: ,
***THIS IS A DRILL ***
.i
~
1 I i 4
)
l i
, j -(~ .
i i l l Time - 1415 [1987EvaluatedExercise g (,dessageNumber 52 COOPER NUCLEAR STATION t -
'06/45 )
EMERGENCY PREPAREDNESS EXERCISE PLANT DATA' PANEL 9-3 PANEL 9-5 , STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 900 SPJi RIIR A UNAVAIL 0 0 REACTOR LEVEL 330" WRG RHR C TRIPPED 0 REACTOR PRESSURE 180 I RIIR B STBY 0- 0 CORE D/P (psig) 0.3 g 6 RHR D STBY 0 CORE FLOW (10 lbm/hr) 0.1 6 CS A ASDC 180 4,700 FLOW . (10 lbs/hr) CS B ASDC 180 4,700- 'FEEDWATER A 0 HPCI ISOL 0 0 FEEDWATER B 0 Drywell Pressure .3 (psig) MAIN STEAM A 0 Torus Level 0 (inches) MAIN STEAM B 0 OPEN CLOSED MAIN STEAM C 0 I
\
MSIV O 8 MAIN STEAM D 0-FLOW PANEL 93 CRD A 50 (gpm) STATUS PRESS (psig) FLOW (gpm) CRD B AVAIL (gpm) RCIC ISOL 0 _ 0 LEVEL PRESS SQUIB PUMPS RWCU A ISOL 0 _ 0 SLC 75 % 0 (psin) ON UNAVAIL 1 1 RWCU B ISOL 0 0 RRPA 0 % SPD MISCELLANEOUS PANELS- .j l RRPB 0 % SPD DIESEL GEN A STBY l DIESEL GEN B STBY SBGT A OPER SBGT B STBY DPa'WELL COOLING NOPJiAL f q s TORUS WATER TEMP 103 'F 1 ___._______b
g I p
= =.
0 0 0 0 0 0 0 0 0 0 0 0 0 0 - 0 0 0 0 e t
)
4 1 2 1 0 1 8 6 4 2 0 ) F 2 1 0 3 8 6 m ig 0
/
i O s ( T p e ( r e u r t
. u a s r s
e ep r P m r 5 1 e o - T ' t s c a e u r o R T 0 3 E - S I C N E R M d O X 0 5 0 0 0 5 0 0 5 0 0 0 5 0 0 T E I
+
1 1 - 1 1 2 4 2 0 2 _ + + - - - 2 1 1 _ A SS )
- + + -
T E n 0 ) n S i ( N A ( i _ R A E A DT l e v l e e v E L R D A L L e _, C P S r o s U E DP t c u r N R S a 3 o R P e 1 T E Y R P C _ O N O E C G _ R , E _ 0 _ M 3 E _ } _ ) 0 0 M 0 0
,o 0
_ 0 8 6 0 0 0 0 0 0 0 R 1 7 6 5 4 3 2 1 P 0 - . A
)
_ ig _ G s p V ( ( A e r _ e r u s e s i c w 5 1 s . r o - e r e P P x , . E r H t o e d c e 2 - w t a y a 5 e r l u H 3 0 D A a e - v E ga 7 s 8 9 e 1 M
y I
,/~'% ,
RADIATION MONITOR DATA Time - 1415
- ( t - 06/45 i
AREA RADIATION MONITORS i READING I STATION DESCRIPTION _ (mr/hr) j 1 Rx Bldg Fuel' Pool Area (SE 5th Floor) 90 2 Rx Bldg Fuel Fool Area (SE 5th Floor) 5 i 3 Rx Bldg New Fuel Area (SE 5th Floor)
.0.03 4 Rx Bldg Rx Water Cleanup Demineralized Area 15 i (SW 3rd Floor) 5 -Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 25 6 Rx Bldg Neutron Monitor System Index Area 90 (TIP Room 1st Floor) 7 Rx Bldg Neutron Monitor System Drive Mech Ares 50-(SE 1st Floor) {
8 Rx Bldg Control Rod Hydraulic Equipment Area 50 .) (S lst Floor) . i 9 Rx Bldg Control Rod Hydraulic Equipment Area 50 (N ist Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) OS 11 Rx Bldg RHR Pump Room (SW Quad) OS ) 12 Rx Bldg RHR Pump Room (NW Quad) OS i f-~s 13 Rx Bldg RCIC/CS Pump Room (NE Quad) OS-j (s 14 Rx Bldg CS Pump Room (SE Quad) PS 15 Turbine Bldg Turbine Front Standard 2 15 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.2 17 Turbine Sldg Turbine Bldg Basement Control Corridor OS- J 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 5 19 Turbine Bldg Turbine Bldg Condensate Pump Area 1 l 20 Control Room Main Control Room 0.015 l 21 Grade Level Control. Corridor 0.25 l 22 Radwaste Control Room 0.02 ! 23 Radwaste Pump Room 7 l 24 Radwaste Basement Equipment Area 3 l 25 Radwaste Demin Valve Room 2 26 Radwaste Conveyor Aisle Operating Area 0.3 27 SPARE 28 Radwaste Lab Area 0.2 29 Centrifuge East 10 30 Centrifuge West 9 Panel 9-02 Personnel Airlock Area 903' 2.0 R/hr Panel 9-02 Ladder 903' to 2nd Level 1.5 R/hr
- Alarm .
'OS Offscale l /'~'} ;
, \v/ l l l l l l
I l
.fe"'s RADIATION MONITOR DATA Time - 1415 ;
( ) t - 06/45 1 1 PROCESS AND VENT MONITORS-1 PANEL VBDC l Rx Bldg Vent Eff (RMV-RM-40) 0 uCi/sec ERP Stack Normal Eff (RMP-RM-3A) 0 uCi/see ERP Stack High Range (RMP-RM-3B) 5.0 E+1 uCi/sec Turbine Bldg Vent Eff (IUTV-RM-20A) 1.5 E-3 uCi/see I Turbine Bldg High Range (RMV-RM-20B) 0 - uCi/sec l RW/ARW Bldg Combined Eff (RMV-RM-30A) 1.0 E-3 uCi/sec l RW/ARW Bldg High Range (RMV-RM-30B) 0 uCi/sec l PANEL 9-10 Mn. Stm. Rad Monitor Ch. A1, B1 45 mR/hr- 40'mR/hr Ch. A2, B2 40 mR/hr 45 mR/hr l SJAE Off Cas Log Rad Monitor Ch. A, B. 1 mR/hr 1 mR/hr i Rx Bldg Vent Ind/ Trip Unit Ch. A, B OS mR/hr OS mR/hr ,
)
i Service Water 10 cps ! [ \ Reactor Equipment Cooling 20 cps l
%_sl 1
l 1 I l e y/
'1987 Evaluated Exercise ' Time - 1415 Message Number: 52 t - 06/45 .
COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE For Controller Use Only: ; l I CONTROLLER INFORMATION: o- Reactor.heacup continues - EXPECTED ACTIONS: i l l ! 1 i i I t l
'\
o i i E
1 l l
'~'
1987 Evaluated Exercise Time - 1425
\w- Message Number: 53X t - 06/55 l COOPER NUCLEAR' STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Message for: Repair team working on RHR-MO-13C Simulated Plant Conditions:
Message: -
***THIS IS A DRILL ***
Repairs to valve logic are finished, s
)
l i W L_ _ . _ _ _ _ _ _ _ _ . __ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _
1 i l
,] 1987 Evaluated Exercise Time - 1425 ;
Message Number: 53X t- 06/25 COOPER NUCLEAR STATION 1 1
, 1 EMERGENCY PREPAREDNESS EXERCISE MESSACE-1 . 1 For Controller Use Only:
CONTROLLER INFORMATION: 1 1 o Deliver the message prior to 1400, at which time the Control Room will be allowed to re-establish Suppression Pool Cooling. , l EXPECTED ACTIONS:
)
o Notify Control Room l l o Control Room re-establish decay heat removal i i i I l () l
/"~'si. 1987 Evaluated Exercise Time - 1430 )
- / Message Number: 54 t - 07/00 COOPER NUCLEAR STATION EMERCENCY PREPAREDNESS EXERCISE MESSACE i
l Message for: Control Room Simulated Plant Conditions: See attached Plant Data l Message: -
***THIS IS A. DRILL *** '
l l l Indications in the Control Room include: , ) RHR.-MO-13C red lights on l 1 O' ' l \ l l 6, L ..
Time - 1430 f]987 Evaluated Exercise '( ,lessage Number , 54 COOPER NUCLEAR STATION 't - 07/00 EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 900 SRM RRR A UNAVAIL 0 7,600 REACTOR LEVEL 330" WRC RHR C TRS. CLC 100 REACTOR PRESSURE 180 RHR B STBY 50 0 CORE D/P (psig) 0.3 6 RHR D ,STBY 50 CORE FLOW (10 lbm/hr) 0.1 6 CS A ASDC 180 4,600 FLOW (10 lbs/hr) CS B ASDC 180 4,600 FEEDWATER A 0 HPCI ISOL 0 0 i FEEDWATER B 0 Drywell Pressure .3 (psig) MAIN STEAM A 0 Torus Level 0 (inches) MAIN STEAM B 0 OPEN CLOSED MAIN STEAM C 0 MSIV 0 8 MAIN STEAM D 0 FLOW PANEL 9-4 C"lD A 50 (gpm) STATUS PRESS (psig) FLOW (gpm) CRD B AVAIL (gpm) i RCIC ISOL 0 0 LEVEL PRESS SQUIB PUMPS RWCU A Is0L 0 0 SLC 75 % 0 (psig) ON UNAVAIL RWCU B ISOL 0 0 RRPA 0 % SPD MISCELLANEOUS PANELS RRPS 0 % SPD DIESEL GEN A STBY l DIESEL GEN B STBY
]
SBCT A OPER SBGT B STBY
)
n DRYWELL COOLING NORMAL \ l TORUS WATER TEMP 110 *F j 1 4
i a n e, s Oy g
/
/.
s y
#* a h
= =
e m t_ ) g 0 0 4 1 0 0 2 1 0 0 0 1 0 0 0 0 8 6 0 0 2 0 ) F 0 2 1 0 0 1 0 8
'0 6 m i
T i s 0 ( , 0 - p _. e ( - e r t r u - x u a T " s r - s e e p r P m r 5 1 e 5 1 o - T - t s c a u r e o - T R -
~
0 0 3 ,3 E - - - S I
^
C N E R
@ . D , ~
O X 0 0 5 0 0 5 0 0 0 5 0 0 5 0 0 a - T E I 1 1 + - 1 1 2 4 2 0 2
+ +
~ A SS )
- - - 2
+
1
+
1
- m T n 0 x S E ;0
) -
( i n - N A i
'( m R
A E A D T l e v l e OC e v EL R A D L L e - P S r m U E DP o s - t c u r m N R S a 5 o 5 R P e 1
- T 1 R
E Y s w P C O N O E = C G R E 0 0 > M 3
. 3 E u 0
) .-
0 0 0 g - M 0 0 - 0 8 6 g 0 0 0 0 0 0 0 O - R 1 7 6 5 4 2 1 - P 0 . 0 w A .
.c
% )
i g . G s p a V ( - ( A e . r - e r u i s e 5 s s 5 ~ c w 1
- e 1 -
r e o r - x P P E r l - t o l e ~ d / c w te 9 a y - a e r - u R 0 3 D 0 3 tE l a e - - v g a s 7 s ~ 8 9 e 1 M s.
l F- H
/'~'N RADIATION MONITOR DATA Time - 1430_ ,(v) t - 07/00 i
AREA RADIATION MONITORS s READING STATION DESCRIPTION (mr/hr) l I l 1 Rx Bldg Fuel Fool Area (SE Sch Floor) 90 ' 2 Rx Bldg Fuel Pool Area (SE 5th Floor) 5 3 Rx Bldg New Fuel Area (SE 5th Floor) 0.03 4 Rx Bldg Rx Water Cleanup Demineralized Area 15 (SW 3rd Floor) . y 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 25 ) 6 Rx Bldg Neutron Monitor System Index Area 90. -j (TIP Room ist Floor) ! 7 Rx Bldg Neutron Monitor System Drive Mech Ares 50 (SE lst Floor) 8 Rx Bldg Control Rod Hydraulic Equipment Area 50 S lst Floor) 9 h(x Bldg Control Rod Hydraulic Equipment Area- ~50 (N 1st Floor) l 10 Rx Bldg HPCI Pump Room (SW Quad) OS { 11 Rx Bldg RHR Pump Room (SW Quad) OS j 12 Rx Bldg RRR Pump Room (NW Quad) OS l
-~ 13 Rx Bldg RCIC/CS Pump Room (NE Quad) OS l
[sj 14 - Rx Bldg CS Pump Room (SE Quad) OS
\s_ / Turbine Bldg Turbine Front Standard 15 1 l 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.2 1 17 Turbine Bldg Turbine Bldg Basement Control Corridor OS 16 Turbine Bldg Turbine Bldg Rx Feed Pump Arca 5 19 Turbine Bldg Turbine Bldg Condensate Pump Area 1 20 Control Room Main Control Room 0.015 21 Crade Level Control Corridor 0.25 )
Radwaste Control Room 22 0.02 23 Radwaste Pump Room 7 24 Radwaste Basement Equipment Area 3 25 Radwaste Demin Valve Room 2 26 Radwaste Conveyor Aisle Operating Area 0.3 27 SPARE 28 Radwaste Lab Area 0.2 29 Centrifuge East 10 30 Centrifuge West 9 Panel 9-02 Personnel Airlock Area 903' 2.0 R/hr Panel 9-02 Ladder 903' to 2nd Level 1.5 R/hr
- Alarm 05 Offscale A
/O g RADIATION-MONITOR DATA Time - 1430 t - 07/00 PROCESS AND-VENT MONITORS PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 0 uCi/sec-ERP Stack Normal Eff (RMP-RM-3A) 0 uCi/sec ERP Stack High Range (RMI'-RM-3B) 5.0 E+1.uci/see Turbine Bldg Vent Eff (RMV-RM-20A) 1.5~E-3 uCi/see Turbine Bldg High Range (RMV-RM-20B) 0 uCi/sec.
RW/ARW Bldg Combined Eff (RMV-RM 30A). 1,0 E-3.uci/sec RW/ARW Bldg High Range (RMV-RM-308) 0 uCi/see PANEL 9-10 Mn. Stm. Rad Monitor Ch. A1, B1 45 mR/hr 40 mR/hr-Ch. A2, B2 40 mR/hr 45 mR/hr l SJdE Off Gas Log Rad Monitor Ch. A, B 1 mR/hr 1 mR/hr-Rx Bldg Vent Ind/ Trip Unit Ch. A, B OS mR/hr OS mR/hr Servico Water 10 cps
,, Reactor Equipment Cooling 20 eps 1
l l 1 (
.)
i
/' N. 6
-1987 Evaluated Exercise Time - 1430
's /
N- '- Message Number: 54 t - 07/00 l COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE q l' For Controller Use Only: CONTROLLER INFORMATION: o Suppression Pool Cooling / Alternate Shutdown Cooling has been re-established. o Reactor. temperature begins to decrease as expected. l EXPECTED ACTIONS: o Plan Recovery Actions l o Discuss de-escalation of the Emergency Classification
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/'S 1987 Evaluated Exercise Time - 1445 r,
Y Message Number: 55 t 07/15 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Message for: Control Room Simulated Plant Conditions: See attached Plant Data Message:
***THIS IS A DRILL ***
l 1 i I [
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R i l l Time - 1445 f " %987 Evaluated Exercise
\ essage Number 55 COOPER NUCLEAR STATION t - 07/15 EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 900 SRM RER A UNAVAIL 0 7600 REACTOR LEVEL 330" WRC RHR C TRS. CLG 100 REACTOR PRESSURE 180 j
- RHR B STBY 50 0 CORE D/P (psig) 0.3 6
RHR D STBY 50 CORE FLOW (10 lbm/hr) _ 0.1 0 CS A ASDC 180 4,600 FLOW (10 lbs/hr) 1 CS B ASDC 180 4,600 FEEDWATER A 0 -) HPCI ISOL 0 0 FEEDWATER B O' Drywell Pressure .3 (psig) MAIN STEAM A 0 Torus Level 0 (inches) MAIN STEAM B 0
^ OPEN 0 f CLOSED ~ MAIN STEAM C '- MSIV 0 8 MAIN STEAM D 0 l
l FLOW PANEL 9-4 CRD A 50 (gpm) , 1 STATUS PRESS (psig) FLOW (gpm) CRD B AVAIL (gpm) I RCIC ISOL 0 0 LEVEL PRESS SQUIB PUMPS RWCU A ISOL 0 0 SLC 75 % 0 (psig) ON UNAVAIL I l RWCU B ISOL 0 0 RRPA 0 % SPD MISCELLANEOUS PANELS
]
1 RRPB 0 % SPD DIESEL GEN A STBY l DIESEL GEN B STBY SBGT A OPER SBGT B STBY DRYWELL COOLING NORMAL
. TORUS WATER TEMP 100 *F l
e 1
N m
= = 0 0 0 0 0 0 -
0 0 0 0 0 . 0 0 0 0 e t'
)
4 1 2 1 0 1 8 2 0 .
)
F 2 1 0 1 8 6 m g 0 i O is ( T p e ( r e u r t u a s r s e e p r P m r 5 1 e o - T t s c u a r e ~ o R ~~ T
~
- 0 3
_ E - S _ I C _ 6 _ R $ ^ N E 4 h _ O X 0 5 0 0 0 5 0 0 0 0 5 0 0 T E I 1 1 + 1 1 2 4 2 O 2 _ + + - - - 2 1 ' 1 - A SS )
- + + -
_ T E n 0 ) S ( i n N A ( i R D T l e l A E A v e e v E L R D A L L e C P S r U E DP o s t c u r N R S a 5 o R P e T 1 E Y R - _ P C _ O N . O E , _ C G R E 0 M 3 _ E - b _ ) M 0 0 0 8 0 6 0 4 0 0 0 0 0 0 0 0 R 1 7 6 5 4 3 2 10 P 0 A - _ G
)
ig s p V ( A ( e r e r u i s e 5 s s c w 1 e r o - r e P P x E r l t o _ l e d c e w t a & a e - y r _ l u R _ 0 3 D a + v e _ E ga _ 7 s _ s 8 e _ 9 1 M
/A RADIATION MONITOR DATA Time - 1445
(. x. t - 07/15 AREA RADIATION MONITORS READING STATION DESCRIPTION (mr/hr) 1 Rx Bldg Fuel Pool Area (SE'5th Floor) 90 2 Rx Bldg Fuel Pool Area (SE Sch Floor) 5 3 Rx Bldg New Fuel' Area (SE Sch Floor) 0.03 4 Rx Bldg Rx Water Cleanup Demir.eralizer Area 15 (SW 3rd Floor) l 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 25 l- 6 Rx Bldg Neutron Monitor System Index Area 90
- (TIP Room ist Floor) ,
7 Rx Bldg Neutron Monitor System Drive Mech Ares 50 (SE 1st Floor) 8 Rx Bldg Control Rod Hydraulic Equipment Area' 50 (S lst Floor)
,9 Rx Bldg Control Rod, Hydraulic Equipment Area 50-(N 1se Floor) .
10 Rx Bldg HPCI Pump Room (SW Quad) OS 11 Rx Bldg RER Pump Room (SW Quad) OS 12 Rx Bldg RHR Pump Room (NW Quad) OS 13 Rx Bldg RCIC/CS Pump Room (NE Quad) n) OS i ( 14 Rx Bld5 CS Pump Room (SE Quad) OS
\d 15 Turbine Bldg Turbine Front Standard 2 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.2 17 Turbine Bldg Turbine Bldg Basement Control Corridor OS 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 5 19 Turbine Bldg Turbine Bldg Condensate Pump Area 1 20 Control Room Main Control Room- '
O.015 21 Crade Level Control Corridor 0.25 22 Radwaste Control Room 0.02 23 Radwaste Pump Room 7 24 Radwaste Basement Equipment Area 3 25 .Radwaste Demin Valve Room 2 26 Radwaste Conveyor Aisle Operating Area 0.3 27 SPARE 28 Radwaste Lab Area 0.2 , 29 Centrifuge East 10 30 Centrifuge West 9 Panel 9-02 Personnel Airlock Area 903' 2.0 R/hr Panel 9-02 Ladder 903' to 2nd Level 1.5 R/hr
- Alarm OS Offscale O
/ RADIATION MONITOR DATA Time - 1445 I (N t - 07/15 PROCESS AND VENT MONITORS PANEL VBDG l Rx Bidg Vent Eff (RMV-RM-40) 0 uCi/sec~
ERP Stack Normal Eff (RMP-RM-3A) 0 uC1/sec ERP Stack High Range (RMP-PmM-3B) 5.0 E+1 uCi/see Turbine' Bldg Vent Eff (RMV-RM-20A) 1.5 E 3 uCi/sec l Turbine Bldg High Range (RMV-RM-20B) 0 uCi/sec' i RW/ARW Bldg Combined Eff (RMV RM-30A) 1.0 E-3 uCi/sec RW/ARU Bldg High Range (RMV-RM-30B) 0 uCi/sec P_ANEL 9-10 . i Mn. Stm. Rad Monitor Ch. A1, B1 45 mR/hr 40 mR/hr
~
Ch. A2, B2 40 mR/hr 45-mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 1 mR/hr 1 mR/hr 4 Rx Bldg Vent Ind/ Trip Unit Ch. A, B OS mR/hr 'OS mR/hr I l 1 n Service Water 10 cps 4 Reactor Eguipment Cooling , 20 cps 3
1 l 4
)
1987 Evaluated Exercise Time - 1445 : i Message Number: 55 t - 07/15 'l l COOPER NUCLEAR STATION ! 1
)
EMERGENCY PREPAREDNESS EXERCISE MESSAGE For Controller Use Only: i CONTROLLER INFORMATION: l o Cooldown continues 1 EXPECTED ACTIONS: i l l i i i 1 1 i i i i o i ( I l
a I l 1987 Evaluated Exercise
'{'T' l
Time - 1500 , j Message Number: 56 e - 07/30 l COOPER NUCLEAR STATION l EMERGENCY PREPAREDNESS EXERCISE MESSAGE Message for: Control Room Si'mulated Plant Conditions: See~ attached Plant Data-Message:
***THIS IS A DRILL ***' .
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/'"'N1987 Evaluated Exercise Time - 1500 'k,,fessageNumber 56 COOPER NUCLEAR STATION t - 07/30 EMERCENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9 3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 900 SRM RHR A UNAVAIL 0 7600 REACTOR LEVEL 330" WRG RHR C TRS. CLC 100 REACTOR PRESSURE 180 RHR B STBY 50 0 CORE D/P (psig) 0.3 6
RRR D STBY 50 CORE FLOW (10 lbm/hr) 0.1 6 CS A ASDC 180 4,600 FLOW (10 lbs/hr) CS B ASDC 180 4,600 FEEDWATER A 0 HPCI ISOL 0 0 FEEDWATER B 0 Drywell Press ~ure .3 (psig) MAIN STEAM A 0 Torus Level 0 (inches) MAIN STEAM B 0 l
/- OPEN CLOSED MAIN STEAM C 0 MSIV 0 8 MAIN STEAM D 0 FLOW I i
- PANEL 9-4 CRD A 50 (gpm) 'j i
i STATUS PRESS (psig) FLOU(gpm) CRD B AVAIL (gpm) l l RCIC ISOL 0 0 LEVEL PRESS SQUIB PUMPS RWCU A ISOL 0 0 SLC 75 % 0 (psig) ON UNAVAIL , RWCU B ISOL 0 0 i RRPA 0 % SPD MISCELLANEOUS PANELS RRPB 0 % SPD DIESEL GEN A STBY= DIESEL GEN B STBY' i l SBGT A OPER ! I i SBGT B STBY fs DRYWELL COOLING NORMAL-k l s- TORUS WATER TEMP 90 *F ' I t
( I n g
= = 0 0 0 0 0
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0 0 0 0 0 0 0 0 0 e t
)
4 1 12 0 1 8 2 0 ) F 2 1 0 1 - 8 6 m g - 0 i O is ( T p e
~
( r e u r t u a r s s e e p r P - m r 5 1 e o - T t s c u a r e o R T 0 3 E - S C c' R 3 3 a N E O X 0 5 0 0 0 5 0 0 0 5 0 0 0 . T E _ I 1 1 + 1 1 2 4 2 0 2
+ + - - - 2 1 1 A SS )
+ + -
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)
_ S in ( n N A ( i R A E A DT l e v l e e v E L AR D L L e _
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.p RADIATION MONITOR DATA Time - 1500 j (s t - 07/30' j i
i AREA RADIATION MONITORS . O READING- 2 STATION DESCRIPTION (mr/hr)
-c 1 Rx Bldg Fuel Pool Area (SE Sth Floor) 90 l 2 Rx Bldg Fuel Pool Area (SE 5th Floor) 5 3 Rx Bldg New Fuel Area'.(SE 5th Floor) 0.03 .j 4 Rx Bldg Rx Water Cleanup Demineralized Area 15 i (SW 3rd Floor) 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 25 Rx Bldg Neutron Monitor System Index Area 6 90 (TIP Room ist Floor) . q l 7 Rx Bldg Neutron Monitor System Drive Mech Ares 50 3 (SE lst Floor) - ,
8 Rx Bldg Control Rou Hydraulic Equipment Area 50 ; (S ist Floor) 9 Rx Bldg Control Rod Hydraulic Equipment Area 50 (N ist Floor) 10 Rx Bldg HPCI Pump Ro'om (SW Quad) OS 11 Rx Bldg RHR Pump Room (SW Quad) OS 12 Rx Bldg RHR Pump Room (NW Quad) OS
,g 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 05 l l \ 14 Rx Bldg CS Pump Room (SE Quad) OS 1.
() 15 Turbine Bldg Turbine Front Standard Turbine Bldg Turbine Bldg Mezz Control Corridor 2 16 0.2 17 Turbine' Bldg Turbine Bld5 Basement Control Corridor OS 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 5 19 Turbine Bldg Turbine Bldg Condensate Pump Area 1 20 Control Room Main Control Room 0.015 21 Grade Level control Corridor 0.25 22 Radwaste Control Room 0.02 23 Radwaste Pump Room 7 24 Radwaste Basement Equipment Area 3 25 Radwaste Demin Valve Room 2 ! 26 Radwaste Conveyor Aisle Operating Area 0.3 27 SPARE 28 Radwaste Lab Area 0.2 29 Centrifuge East 10 30 Centrifuge West 9 Panel 9-02 Personnel Airlock Area 903' 2.0 R/hr Panel 9-02 Ladder 903' to 2nd Level 1.5 R/hr-
- Alarm OS Offseale O
l ['} RADIATION MONITOR DATA Time - 1500 t t - 07/30 PROCESS AND VENT MONITORS l' PANEL VBD'G j Rx' Bldg Vent Eff (RMV-RM-40) 0 uCi/sec ERP Stack Normal Eff (RMP-RM 3A) 0 uCi/sec l ERP Stack High Range (RMP RM-3B) 5.0 E+1 uCi/sec l Turbine. Bldg Vent Eff (RMV-RM-20A) 1.5 E-3 uCi/see Turbine Bldg High Range (RMV-RM-20B) _0 uCi/sec RW/ARW Bldg Combined Eff (RMV-RM 30A) 1.0 E-3 uCi/see j RW/ARW Bldg High Range (RMV RM-30B) 0 uCi/sec
. PANEL 9-10 Mn. Stm. Raa Monitor Ch. A1, B1 45 mR/hr 40 mR/hr.
Ch. A2, B2 40 mR/hr 45 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 1 mR/hr 1 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch.'A, B OS mR/hr OS mR/hr Service Water _10 cps [ Reactor Equipment Cooling 20 cps
i i i 1987 Evaluated Exerc.ise Time - 1500 j
/
s,
- Message Number:
56 t - 07/30
'1 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE 1 '
For Controller Use Only: i CONTROLLER INFORMATION: . o Cooldown continues i l
=
l EXPECTED ACTIONS: . - 1 l l O - ' ( . s s t
l 1987 Evaluated Exercise Time - 1515 N Message Number: 57 t - 07/45 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Message for: Control Room Simulated Plant Conditions: See attached Plant Data Message: 1 L ***THIS IS A DRILL *** i I
]
1 l l l 1 l i 1,.. ! w____ ._
a j 987 Evaluated Exercise Time - 1515
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v dessage Number 57 COOPER NUCLEAR STATION t - 07/45' f EMERGENCY PREPAREDNESS ~ EXERCISE PLANT DATA - PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 900 SRM RHR A UNAVAIL 0 7600 REACTOR LEVEL 330"~ WRC RHR C TRS. CLC 100 REACTOR PRESSURE 180 RHR B STBY 50 0 CORE D/P (psig) 0.3 6 RHR D STBY 50 CORE FLOW (10 lbm/hr) 0.1 6 CS A ASDC 180 4,600 FLOW (10 lbs/hr)
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CS B ASDC 180 4,600 FEEDWATEP. A' O ) HPCI ISOL 0 0 FEEDWATER B 0 j Drywell Pressure .3 (psig) MAIN STEAM A 0 Torus Level 0 (inches) MAIN STEAM B 0 OPEN CLOSED MAIN STEAM C 0 , MSIV 0 8 MAIN STEAM D 0 FLOW
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PANEL 9-4 CRD A 50 (gpm)
]1 STATUS PRESS (psig) FLOW (gpm) CRD B AVAIL (gpm) f RCIC ISOL 0 0 LEVEL PRESS SQUIB PUMPS ,
i RWCU A ISOL 0 0 SLC 75 %' O (psig) ON UNAVAIL RWCU B ISOL 0 0 RRPA 0 % SPD MISCELLANEOUS PANELS RRPB 0 % SPD DIESEL CEN A STBY DIESEL GEN B STBY SBCT A OPER SBCT B STBY g DRYWELL COOLING NORMAL
\
TORUS VATER TEMP 80 *F 1 i
i* U $ C.
= =.
0 0 n 0 0 0 0 o 0 0 0 0 0 e t 4 2 o g 8 2 o ) 2 0 6
) 1 1 -
1 1 m g . 0 F O i T isp ( ( e r e u r t u a r s s e p e r P m 5 e t r o ~ 1
- T s
c a u r e o R~ T 0 3 E g S I C R O O N E O X 0 0 5 0 0 5 0 0 0 0 5 0 0 E I
+
T 4 2 1 1 1 1 2 2
+ + - - - 2 1 1 A SS )
+ + -
T E n 0 ) - S ( i n N A ( i R A E A D T l e v l e e v E L A R D L L e . . *
- n. C P S r o s U E DP t c
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- T E Y R P C O N O E C G R
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M 0 0 0 0 0 0 0 8 6 4 0 0 0 0 0 0 0 R 1 7 6 5 4 2 1 P 0 A .
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ig G s p V ( A e ( r e r u i s e 5 s s c w 1 e r o - r e P P x r E o
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l l f'~' RADIATION MONITOR DATA Time - 1515 l i N- t - 07/45 ! 1 i
.) 1 AREA RADIATION MONITORS ]
READING STATION DESCRIPTION (mr/hr) l 1 Rx Bldg Fuel Pool Area (SE 5th Floor) 90 2 Rx Bldg Fuel Pool Area (SE Sth Floor) 5 3 Rx Bldg New Fuel Area (SE Sth Floor) 0.03' i 4 Rx Bldg Rx Water Cleanup Demineralized Area 15
]
(SW 3rd Floor) ] 5 Rx Bldg Sludge and Decant. Pump Area (S 2r.d Floor) 25- i 6 Rx Bldg Neutron Monitor System Index Areti 90 (TIP Room ist Floor) l j 7 Rx Bldg Neutron Monitor System Drive Meca Ares 50 (SE 4st Floor) _ 8 Rx Bldg Control Rod Hydraulic Equipment Area 50 j' (S 1st Floor) 9 Rx Bldg Control Rod Hydraulic Equipment Area 50 , (N ist Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) OS 11 Rx Bldg RHR Pump Room (SW Quad) OS-12 Rx Bldg RHR Pump Room (NW Quad) OS gs 13 Rx Bldg RCIC/CS Pump Room (NE Quad) OS F i 14 Rx Bldg CS Pump Room (SE Qudd) - OS 1
\s_s/ 15 Turbine Bldg Turbine Front Standard 2 j 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.2 17 Turbine Bids Turbine Bldg Basement Control Corridor OS 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 5 j 19 Turbine Bldg Turbine Bldg Condensate Pump Area 1 l 20 Control Room Main Control Room 0.015 21 Grade Level Control Corridor 0.25 1 22 Radwaste Control Room 0.02 l
23 Radwaste Pump Room 7 24 Radwaste Basement Equipment Area 3 25 Radwaste Demin Valve Room 2 26 Radwaste Conveyor Aisle Operating Area 0.3. 27 SPARE 28 Radwaste Lab Area 0.2 29 Centrifuge East 10 30 Centrifuge West 9 , 1 Panel 9-02 Personnel Airlock Area 903' 2.0 R/hr Panel 9-02 Ladder 903' to 2nd Level 1.5 R/hr i
- Alarm i OS Offscale
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[ RADIATION MONITOR DATA Time - 1515 ( t - 07/45 PROCESS AND VENT MONITORS PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 0 uCi/sec - ERP Stack Normal Eff (RMP-RM-3A) 0. uCi/sec ERP Stack High Range (RMP-RM-3B) 5.0 E+1 uCi/see Turbine Bldg Vent Eff (RMV-RM-20A) 1.5 E-3 uCi/sec Turbine Bldg High Range (RMV-RM-20B) 0 uci/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 1.0 E-3 uCi/see RW/ARW Bldg High Range (RMV-RM-30B) 0 uCi/ soc
~
PANEL 9-10
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1 l Mn. Stm. Rad Monitor Ch. A1, B1 45 mR/hr 40 mR/hr Ch. A2, B2 40 mR/hr 45 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 1 mR/hr 1 mR/hr-Rx Bldg Vent Ind/ Trip Unit Ch. A, B OS mR/hr OS mR/hr l Service Water 10 cps {s Reactor Equipment Cooling 20 cps t l l 1 r t {
1 i i d 1987 Evaluated Exercise Time - 1515 Message Number: 57 t - 07/45-l h COOPER NUCLEAR STATION EMERCENCY PREPAREDNESS EXERCISE MESSACE For Controller Use Only: CONTROLLER INFORMATION: o Cooldown continues
- EXPECTED ACTIONS:
l l 1 l 1 (s . 1 l l 1 R l 1 I I I i
,d"'s 1987 Evaluated Exercise Time - 1530 (approx.) '- Message Number: 58 t - 08/00 (approx.)
COOPER NUCLEAR STATION EMERGENCY PREPAREDNE.SS EXERCISE MESSAGE Message for: Emergency Director Simulated Plant Conditions: Message:
***TNIS IS A DRILL ***
l You may terminate the 1987 emergency preparedness exercise at your discretion. l' . . t
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- - 1 l /N RADIATION MONITOR DATA- Time - 1530- l L
t - End-f AREA' RADIATION MONITORS l READING STATION DESCRIPTION (mr/hr) 1 Rx Bldg Fuel Pool Area (SE 5th Floor) 90 j 2 Rx Bldg Fuel Fool Area (SE 5th Floor) 5 ) 3 Rx Bldg New Fuel Area (SE Sch Floor) 0.03 j 4 Rx Bldg Rx Water Cleanup _ Demineralized Area 15 (SW 3rd Floor) 5 Rx Bldg. Sludge and Decant Pump Area (S 2nd Floor) 25 6 Rx Bldg Neutron Monitor System Index Area 90 , (TIP Room ist Floor)}}