NLS8500228, Forwards Detailed Description of Exercise Sequence of Events & Cooper Nuclear Station 1985 Annual Emergency Preparedness Exercise, Per 840209 Commitment.Comments Requested by 850913.W/o Detailed Description
| ML20141A037 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 08/28/1985 |
| From: | Pilant J NEBRASKA PUBLIC POWER DISTRICT |
| To: | Martin R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| NLS8500228, NUDOCS 8510240414 | |
| Download: ML20141A037 (228) | |
Text
v GENERAL OFFICE Nebraska Public Power District
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NLS8500228 August 28, 1985 Mr. Robert D. Martin 3[r h i - ! ' \ [/
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Regional Administrator s ! i U.S. Nuclear Regulatory Commission AUG 3 u SS5 0 Region IV 611 Ryan Plaza Drive b Suite 1000 Arlington, Texas 76011
Dear Mr. Martin:
Subject:
Cooper Nuclear Station Emergency Preparedness Exercise Information.
Reference:
Letter from J. T. Collins (USNRC) to J. M. Pilant (NPPD) dated February 9, 1984, subject: Exercise Submission dates.
In accordance with the milestones outlined in the referenced letter, NPPD is hereby submitting two copies of the following items: (1) a detailed description of the exercise sequence of events and (2) complete controller packages for the 1985 Cooper Nuclear Station Emergency Preparedness Exercise. By copy of this letter, duplicate sets including items (1) and (2) are being forwarded to Mr. Jim Jamison of Battelle Northwest Labs (NRC contractor) and Mr. Joe Keller, Exxon Nuclear Idaho Co., Inc. (FEMA contractor) for review of various data in the detailed scenario. Also, two complete sets including items (1) and (2) will be forwarded to Mr. P. J. Brehney, FEMA Region VII.
In order that any necessary changes may be incorporated into the exercise scenario, it is requested that all NRC/ FEMA comments concerning the detailed scenario be submitted to my office no later than Friday, September 13, 1985.
Should you have any questions or comments regarding the enclosed information, please contact me.
Sincerely, k.WA m
. M. Pilant Manager, Technical Staff Nuclear Power Group 8510240414 850828 hDR ADOCK 05000298 ACM/rg .
Enclosures cc P. J. Brehney w/ Item (1) and (2) - 2 copies J. Keller w/ Item (1) and (2) - 1 copy FEMA-Region VII Exxon Nuclear Idaho Co., Inc.
] E. L. Jordan w/ Item (1) only - I copy Jim Jamison w/ Item (1) and (2) - 1 cop:
h U.S. Nuclear Regulatory Commission Battelle Northwest Labs [
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( ,) NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION 1985 ANNUAL EMERGENCY PREPAREDNESS EXERCISE l
FOREKORD
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i This exercise package has been developed to provide the basis for the conduct I
of a simulated radiological accident at the Cooper Nuclear Station, located in Nemaha County, Nebraska, Through this exercise, the capabilities and effectiveness of the emergency response plans for the Nebraska Public Power District, the states of Nebraska and Missouri and their respective counties vill be evaluated. This package is to be utilized by the Exercise Controllers and the Observer / Evaluators from Federal, State and local agencies, and from the utility. The information contained herein will allow for the initiation and control of the exercise as well as the evaluation of participant activities. The Nebraska Public Power District and the states of Nebraska and Missouri approve this document as the standard for conduct in performance of the October 16, 1985. Emergency Preparedness Exercise.
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Nebraska Public Power District State of Missouri State of Nebraska i
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l Information to be provided later:
Public Information questions.
- i Controller / Evaluator evaluation packages. :
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PASS Results i
Meteorological forecast contingency messages (in the event
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University of Missouri Sample Analysis results in the form !
of message to FCP. !
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- - Some Control Room indications as denoted by Blanks on Messages.
Finali::ed Meteorological Data Chart. ;
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Ingestion Pathway information.
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NEBRASKA PUBLIC POWER DISTRICT
\ ,j COOPER NUCLEAR STATION 1985 EMERGENCY PREPAREDNESS EXERCISE INTRODUCTION The Cooper Nuclear Station Emergency Plan describes the emergency response capabilities for a nuc1 tar 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 exercise.
The purpose of the Exercise is 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 accordance with Nuclear Regulatory Co= mission (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 emergen'cy response plans, as required by Federal Emergency Management Agency (FEMA)
Regulation 44CFR350.9(b). The conduct and evaluation of the Exercise provide additional training for emergency response organization personnel and a means to further enhance Nebraska Public Power District's emergency response capability.
) This Exercise Manual has been developed to provide the basis for the conduct of a simulated radiological accident at the Cooper Nuclear Station locatol 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 and Missouri and their respective counties, can be evaluated. This manual is to be utilized by the exercise controllers and observers of the Federal, State and local agencies, as well as the Utility, to initiate, control, 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 consists of two parts. Part I (white tabs) provides a general description and overview of an emergency exercise. Part II (red tabs) contains the scenario and time schedule of simulated plant conditions and is subject to a limited, controlled distribution.
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COOPER NUCLEAR STATION
) 1985 EMERGENCY PREPAREDNESS EXERCISE 4
TABLE OF CONTENTS t
- FOREWORD INTRODUCTION TABLE OF CONTENTS
', LIST OF FIGURES
. PART I GENERAL INFORMATION (WHITE TABS) 1.0 SCOPE AND OBJECTIVES I
1.1 Scope 1.2 Objectives l.2.1 Nebraska Public Power District Objectives 1.2.2 State of Nebraska Objectives 1.2.3 State of Missouri Objectives 1.2.4 Missouri County Objectives 1.3 FEMA Objectives Cross-Reference _
2.0 EXERCISE INFORMATION 2.1 Exercise Pa'rticipants g'~' 2.2 Exercise Organization 2.3 Emergency Response Facilities 2.4 Exercise Conduct 2.5 Evaluation and Critique
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l 3.0 TRAVEL INFORMATION 3.1 Directions to Cooper Nuclear Station 3.2 Accommodations
4.0 REFERENCES
/ ABBREVIATIONS / DEFINITIONS i
4.1 References -
4.2 Abbreviations 4.3 Definitions i 5.0 CONTROLLER / EVALUATOR GENERAL INFORMATION 5.1 Precautions and Limitations 5.2 Controller Instructions 5.3 Evaluator Instructions i
l 6.0 SCHEDULE OF EVENTS PART II CONTROLLED INFORM / TION (RED TABS) f-~ 7.0 EXERCISE SCENARIO i s- 7.1 Narrative Summary of the Exercise Scenario 7.2 On-site Sequence of Events t
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, COOPER NUCLEAR STATION 1
1985 EMERGENCY PREPAREDNESS EXERCISE i
TABLE OF CONTENTS i (Continued) I 1
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8.0 MESSAGE FORMS AND PLANT DATA SHEETS l 9.0 ON-SITE RADIOLOGICAL DATA l -
9.1 Radiological and Meteorological Summary l 9.2 In-Plant Radiation Data 9.3 On-site. Radiation Levels
-l 1 ' 10.0 0FF-SITE RADIOLOGICAL DATA i I 1 10.1 Plume Location i j 10.2 Release Rate Information i
- 10.3 Whole Body Dose Rates
- I 10.4 Thyroid Dose Rates g
- 10.5 Maps ,
j 10.6 Off-site Sampling Points and Data j ,
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COOPER NUCLEAR STATION j h 1985 EMERGENCY PREPAREDNESS EXERCISE
!; LIST OF FIGURES l
, I Section 2.0 i !
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FIGURE 2.1 Control Room and Technical Support Center j FIGURE 2.2 Emergency Operations Facility ;
i FIGURE 2.3 Alternate Emergency Operations Facility
- FIGURE 2.4 General Office Emergency Center L
, FIGURE 2.5 Media Release Center l l
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l 4 Se.ction 6.0 i e FIGURE 6.1 Schedule of Events 4
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1.0 SCOPE AND OBJECTIVES 1.1 SCOPE The 1985 Cooper Nuclear Station Emergency Preparedness Exercise, to be conducted on October 16, 1985, will test and provide the opportunity to evaluate the Nebraska Public Power District, the states of Nebraska and Missouri and their respective county's 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.
Whenever practical, the exercise will incorporate provisions for
" Free Play" on the part of the participants.
The scenario will depict a simulated sequence of events, resulting in a radiological release of sufficient magnitude to warrant mobilization of State and local agencies to respond to the emergency.
1.2 OBJECTIVES The Cooper Nuclear Station (CNS) 1985 Emergency Preparedness-Exercise Program objectives are based on the Nuclear Regulatory Commission (NRC) requirements delineated in 10CFR50.47 Appendix E.
[ Additional guidance provided in NUREG-0654, FEMA-REP-1, Revision 1 NUREG-0696 and NUREG-0737 Supplement I was also utilized in developing these objectives.
The exercise vill have partial participation from the State of Nebraska and full-scale participation by the State of Missouri. The warning system sirens and EBS notifications for the emergency planning zone will not be activated during the exercise.
The major objective of the Exercise is to evaluate the integrated "
capability of a major portion of the basic elements existing within the on-site and off-site 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 Alternate Emergency Operations Facility.
- 2. Demonstrate the reliability and effective use of emergency communications equipment and procedures.
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- 3. Demonstrate proficiency in recognizing and classifying emergency-conditions.
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- 4. Demonstrate the notification of Federal, State, local, corporate, and plant emergency response personnel.
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,,/ 5. Demonstrate the ability to coordinate the available emergency response resources of NPPD, State and local organizations.
' 6. Demonstrate the ability to perform dose calculations utilizing radiological and meteorological information to determine the magnitude of, and for continuously assessing the impact of, the release of radioactive materials to the environment.
- 7. Demonstrate the transition of responsibilities between emergency facilities as a result of escalating accident classification.
- 8. Demonstrat, knowledge of Protective Action Guides-(PACS), the recommendation of protective actions to off-site authorities, and determination of the subsequent implementation of protective actions by off-site agencies.
- 9. Demonstrate the capabili.ty to obtain and analyze samples utilizing the post-accident sampling system.
- 10. Demonstrate the mobilization of on-site and off-site radiological monitoring teams and the appropriate use
g of equipment, procedures, and communication to effectively track the plume,
- 11. Demonstrate the capability of off-site radiological monitoring teams to collect sample media.
- 12. Demonstrate the ability to perform site assembly, maintain accountability and evacuate as appropriate.
- 13. Demonstrate the ability to monitor and control emergency worker exposure within the plant.
- 14. Demonstrate adequate equipment and procedures for decontamination of emergency workers and equipment, as required.
- 15. Demonstrate the capability to obtain, coordinate and assemble emergency information for timely dissemination to the public via the media.
- 16. Demonstrate the capability of the NPPD spokesperson to reply to inquiries of both a technical and political nature.
- 17. Demonstrate the capability of NPPD IAC personnel to
's respond directly to (simulated) input from the public concerning real versus rumoured events occurring at
) Cooper Nuclear Station or within the 10 mile EPZ.
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- 18. Demonstrate the ability to plan recovery operations
-[~Ng and identify the need for additional resources.
b 19. Demonstrate decision-making and coordination with off-site agencies in de-escalating and terminating the emergency and in planning re-entry to evacuated areas.
1.2.2 State of Nebra ka Objectives Objectives of the Exercise.
Test the Cooper Nuclear Power Plant Emergency Plan to include:
- 1. Interface with off-site government agencies.
- 2. Initial notification to State government.
- 3. Coordination of dose assessment activities.
4 Public warning interface.
- 5. Jointly conducted public information.
- 6. Recovery and re-entry activities.
The following State support capabilities as listed in the O Nebraska Radiological Emergency Response Plan for Nuclear Power Plant Incidents will be tested.
- 1. Activation of staff with subsequent deployment and operation of the State Field Command Post to include local and long-range communications. If plant i scenario permits, test relocation of State Field Command Post to support local government implementation of appropriate protective actions.
Participation of Nebraska State Patrol BLUEBIRD will be simulated.
- 2. Notification and follow-up contacts with State,
- Federal, and private agencies having responsibilities described in the Nebraska Plan.
- 3. Operational status and functioning of State EOC as well.as coordination with agencies and field elements. Includes State EOC interstate coordination. With the exception of the Health Department, Agency representation at the State EOC will be simulated. State EOC will implement appropriate protective actions as approved oy the i
Governor and/or the Governor's Authorized Representative.
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- 4. State field radiological monitoring activities.
_ off-site dose assessment, and coordination of
[\s j/i protective action recommendations with Governor's r
Authorized Representa*.ive and State EOC.
Coordination will also be effected with the utility and Missouri. This will include timely mobilization, deployment and operation of State field radiological monitoring teams as well as management of team activities, appropriate briefings and information flow. Field monitoring team equipment and communications capabilities will also be demonstrated. State aerial radiological monitoring mission to roughly track and define the parameters of the airborne plume as well as transport samples to the State lab will be simulated.
- 5. Decision-making provisions for the use and distribution of radioprotective drugs for emergency workers.
- 6. The collection and transport of samples to the State Laboratory in Lincoln may be simulated. Timely processing of samples and other techniques at the
, State Laboratory will be demonstrated.
, 7. State EOC coordination of simulated Federal technical and non-technical support under the Federal
' Radiological Emergency preparedness Plan (FREPP),
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s including message flow and simulated support by such agencies as NRC, DOE, FEMA.
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- 8. State CD support of the jointly operated Information Authentification Center (IAC) and Media Release Center (MRC). Demonstrate IAC. coordinated dissemination of information simulated throughout the EBS. Operations at the MRC will include news media briefings as well as the appropriate use of zone designators/ local terms in briefing media and the State of Nebraska use of visual displays for briefing and operacions.
The transmission of selected emergency information by means of portable data terminals will also be demonstrated. Rumor Control functions at the ':AC and MRC will be tested.
- 9. Support for and-supervision of two decontaminscion stations; one at Auburn for emergency workers and the other at Nebraska City for evacuees.
- 10. State and local communication including primary and supporting capabilities.
- 11. Decision-making and coordination for re-entry and recover *.
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- 12. State's capability to provide and distribute
{T sufficient dosimetry to include self-reading and s ,/ pe rmanent record devices (TLSs) for the initial distribution to emergency workers operating in radiation areas. Most TLDs used during the exercise will be simulated. Actual TLDs will be available for inspection at the State EOC.
The following local support capabilities, as listed in appropriate local plans, will be demonstrated:
- 1. Initial notification receipt and alerting of key people.
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2 ', Communications and coordination with all involved agencies.
- 3. Activation and staffing of local Emergency Operation Center (EOC) and appropriate use of Emergency Classification.
4 Coordinated access control and security decision-making by selected law enforcement agencies.
- 5. Increased readiness measures for potential operations at Nebraska City /Otoe County relocation center. This facility will be operated on a training basis but will be subject to observation.
- 6. Decontamination station operations at Auburn to support. emergency workers will be demonstrated.
- 7. Demonstrate capability to activate public alerting system and provide an informational message to the public within 15 minutes. Actual activation of alerting system and EBS will be simulated. However, preparation and handling of public notification messages will be demonstrated. (The public alert and notification procedures will be accomplished during the FEMA 43 test, to be conducted on October 17, 1985.
- 8. Coordination with IAC/MRC where appropriate concerning local public information activities.
Demonstrate capability to define hazard area by referencing local landmarks.
- 9. Provision of fire and rescue support as required by plant. Transport and reception of simulated
. radiation casualty to the Nemaha County Hospital by a 4
local Rescue Squad.
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- 10. Decision-making and coordination planning for
_ recovery and re-entry.
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- 11. The Nebraska City /0 toe County reception registration and decontamination activities in support of Nemaha
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County evacuees will be operated on a training basis but will be subject to observation.
- 12. Demonstrate effective system for distribution and record keeping of dosimetry to include permanent record devices (TLDs).
- 13. Demonstrate timely communication and coordination with community facilities for mobility impaired, disabled, etc. that may require special actions such i
as early notification or other support functions.
- 14. Decision-making will be demonstrated to simulated and control allocation of local resources, and determine need for State support as necessary.
- 15. Decision-making will be demonstrated to simulate allocation of appropriate support for the evacuation of the public with special needs, if required.
See Missouri scenario for objectives and other exercise information. _.
1.2.3 State of Missouri objectives
,m Emergency Operations Center k, , 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 decisions and to coordinate emergency activities.
- 4. Demonstrate adequacy of facilities and displays to support emergency operations.
- 5. Demonstrate ability to communicate with all appropriate locations, organizations, and field personnel.
- 6. Demonstrate ability to identify need for, request, and obtain Federal assistance.
I Forward Command Post
- 1. Demonstrate ability to mobilize staff and activate facilities promptly.
- 2. Demonstrate ability to fully staff facilities and j ~s maintain staffing around the clock.
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- 3. Demonstrate ability to make decisions and to
(} coordinate emergency activities.
- 4. Demonstrate adequacy of facilities and displays to support emergency operations.
S. Demonstrate ability to coimunicate with all appropriate locations, organizations, and field personnel.
- 6. Demonstrate ability to identify need for, request, and obtain Federal assistance.
Forward Command Post
- 1. Demonstrate ability to mobilized staff and activate facilities promptly.
- 2. Demonstrate ability to fully staff facilities and maintain staffing around the clock. ;
- 3. Demonstrate ability to make decisions and to coordinate emergency activities.
- 4. Demonstrate adequacy of facilities and displays to support emergency operations.
- 5. Demonstrate ability to ecmmunicate with all appropriate locations, organizations, and field personnel.
- 6. Demonstrate ability to project dosage to the public
, via plume exposure, based on plant and field data, and to determine appropriate protective measure, based on PAG's, available shelter, evacuation time estimates, and other appropriate factors. ,
- 7. Demonstrate ability to project dosage to the public via ingestion pathway exposure, based on filed data, and to determine appropriate protective measures ,
based on PAG's and on other relevant factors (NUREG-0654, I.10, J.11). I
- 8. Demonstrate ability to alert the public within the 10-mile EPZ, disseminate an initial instructional message within 15 minutes. !
- 9. Demonstrate ability to formulate and distribute appropriate instructions to the public in a timely fashion.
- 10. Demonstrate the organization ability and resources ,
necessary to control access to an evacuated area- ;
s (NUREG-0654, J.10.j).
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- 11. Demonstrate the ability to continuously monitor and
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control emergency worker exposure.
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- 12. Demonstrate the ability to make the decision, based on predetermined criteria, whether to issue KI to emergency workers and/or the general population.
- 13. Demonstrate the ability to supply and administer KI, once the decision has been made to do so.
14 Demonstrate ability to provide advance coordination of information released.
- 15. Demonstrate ability to identify need for, request, and obtain Federal assistance.
- 16. Demonstrate ability to determine and implement appropriate measures for controlled recover and re-entry.
Information Authentication Center
- 1. Demonstrate ability to mobilize staff and activate facilities promptly.
- 2. Demonstrate ability to fully staff facilities and maintain staffing around the clock.
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- 3. Demonstrate adequacy of facilities and displays to support emergency operations.
4 Demonstrate ability to communicate with all appropriate locations, organi:ations, and field personnel.
- 5. Demonstrate the ability to continuously monitor and control emergency worker exposure.
- 6. Demonstrate ability to provide advance coordination of information released.
Dose Assessment
- 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 decisions and to coordinate emergency activities.
- 4. Demonstrate ability to communicate with all appropriate locations, organizations, and field
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. 5.- Demonstrate ability to mobilize and deploy field monitoring teams in a timely fashion.
j 6. Demonstrate appropriate equipment and procedures for determining ambient radiation levels.
- 7. Demonstrate appropriate equipment and procedures for
- measurement of airborne radioiodine concentrations as 2
t low as-10 ' uCi/CC presence of noble gases.
- 8. Demonstrate appropriate equipment and procedures for i collection, transport and analysis of samples of
{ soil, vegetation, snow, water and milk.
- 9. Demonstrate ability to project dosage to the public 3 via plume exposure, based of plant and field data,
{ and to determine appropriate protective measure, based on PAG's, available shelter, evacuation time esticates, and other appropriate factors.
- 10. Demonstrate ability to project dosage to the public j via ingestion pathway exposure, based on field data, ,
i and to determine appropriate protective measure based
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on PAG's and on other relevant factors (NUREG-0654 I.10, J.11).
l 11. Demonstrate the ability to continuously monitor and
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control emergency worker exposure.
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- 12. Demonstrate the ability to make the decision, based i
on predetermined criteria, whether to issue KI to
! emergency workers and/or the general population.
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- 13. Demonstrate adequate equipment and procedures for 4
1 deccntamination of emergency workers, equipment and vehicles (NUREG-0654. K.S.a. b).
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- 1. Demonstrate ability to mobilized staff and activate j
facilities promptly.
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- 2. Demonstrate ability to fully staff and maintain ;
j staffing around the clock.
- 3. Demonstrate ability to make decisions and to +
1 coordinate emergency activities, i
- 4. Demonstrate adequacy of facilities and displays to support emergency operations.
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5.- Demonstrate ability to coamunicate with all appropriate locations, organizations, and field l personnel.
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- 6. Demonstrate the ability to continuously monitor and 4,
control emergency worker exposure.
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('-) 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 decisions and to coordinate emergency activities.
- 4. Demonstrate adequacy of facilities and displays to support emergency operations.
- 5. Demonstrate ability to communicate with all appropriate locations, organizations, and field personnel.
- 6. Demonstrate ability to communicate with all appropriate locations, organizations, and field personnel.
- 7. Demonstrate ability to provide advance coordination or information released.
Medical
~'s 1. Demonstrate ability to communicate with all
) appropriate locations, organizations, and field personnel.
- 2. Demonstrate adequacy of ambulance facilities and procedures for handling contaminated individuals.
- 3. Demonstrate adequacy of hospital facilities and procedures for handling contaminated individuals.
1.2.4 Missouri County Objectives 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 decisions and to coordinate emergency activities.
- 4. Demonstrate adequacy of facilities and displays to support emergency operations.
-~3 5. Demonstrate ability to communicate with all
( ) appropriate locations, organizations, and field
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personnel.
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- 6. Demonstrate appropriate equipment and procedures for
{ determining. ambient radiation levels.
- 7. Demonstrate appropriate equipment and procedures for measurement of airborne radiciodine concentrations as low-as 10 ' uCi/CC presence of noble gases.
- 8. Demonstrate ability to alert the public within the 10-mile EPZ, disseminate an initial instructional message within 15 minutes.
- 9. Demonstrate ability to formulate and distribute appropriate instructions to the public in a timely fashion.
- 10. Demonstrate the organizational ability and resources necessary to manage an orderly evacuation of all or part o'f the plume EPZ (NUREG-0654, J.9, J.10.g).
- 11. Demonstrate the organizational ability and resources necessary to control access to an evacuated area (NUREG-0654, J.10.j).
- 12. Demonstrate the organizational ability and resources necessary to effect an orderly evacuation of mobility-impaired individuals within the plume EPZ (NUREG-0654, J.10.d).
- 13. Demonstrate the organizational ability and resources necessary to effe.ct an orderly evacuation of schools within the plume EPZ (NUREG-0654, J.9, J.'10.g).
- 14. Demonstrate the ability to continuously monitor and control emergency worker exposure.
- 15. Demonstrate the ability to make the decision, based on predetermined criteria, whether to issue KI to emergency workers and/or the general population.
- 16. Demonstrate the ability to supply and administer KI, once the decision has been made to do so.
- 17. Demonstrate ability to provide advance coordination of information released.
- 18. Demonstrate adequate equipment and procedures for decontamination of emergency workers, equipment and vehicles (NUREG-0654. K.S.a. b).
- 19. Demonstrate ability to determine and implement appropriate measures for controlled recovery and and re-entry.
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- 1. Demonstrate adequacy of procedures for registration and radiological monitoring of evacuees (NUREG-0654,
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1.5 FEMA OBJECTIVES CROSS-REFERENCE y ,t L
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- 1. Demonstrate ability to mobilize staf f and activat'e facilities promptly.
- 2. Demonstrateabilitytofullystafffacilitiesandmaintain staffing around the clock. '
- 3. Demonstrate a'ility to make decisions and to coordinate ?
emergency activities.
- 4. Demonstrate adequacy of facilities and displays and to support ! d emergency operations. +
- 5. Demonstrate ab.tlity to communicate with all appropriate >
locations, organizations, and field perscanel.
- 6. Demonstrate ability to mobilize and deploy fie'id monitoring 3 teams in a timely fashion. '
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- 7. Demonstrate appropriate equipment and procedures for r N\
determining ambient radiation levels. (
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- 8. Demonstrate appropriate equipment and procedurea for p measurement of airborne radiciodine concentrations as low as
'l 10 ' uCi/CC in the presence of noble gases. '
- 9. Demonstrate appropriate equipment and procedures for collections, transport and analysis of soil, vegetation, snow.
(. water, and milk.
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- 10. Demonstrate ability to project. dosage to the public via plume exposure, based on plant and field data, and to determine s-appropriate protective measures, based on PAG's, available shelter, evacuation time estimates, and all other appropriate factors.
- 11. Demonstrate ability to project dosage to the public.via i ingestion pathway exposure, based on field data, and to ,
determine appropriate protective measure, based on PAG'e and other relevant factors.
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- 12. Demonstrate ability to implement protective actions f.or .
8 ingestion pathway hazards. , d '
- 13. Demonstrate ability to alert the public within the IO mile EPZ, and disseminate an initial instructional message, within 15 '.
minutes.
- 14. Demonstrate ability ta formulate and distribute appropriate instructions to the public, in a timely fashion.
- 15. Demonstrate the organization ability and resources necessary to p manage an orderly evacuation of all or part of the plume EPZ.
V 1 - 12
e
- 16. ' Demonstrate the organizational ability and resources necessary 4m to deal with impediments to evacuation, such as inclement
( s
.weather or traffic ebstructions.
- f. remonstrate the organizational ability and resources necessary f.o control access to an evacuated area.
O
.18. Nmonstrate the organizational ability and resources necessary to effect an orderly evacuation of mobility-impaired
~
individua.!s within the plume EPZ.
- 19. Demonstrate the organizational ability and resources necessary to effect an orderly evacuation of schools within the plume EPZ.
I
- 20. Demonstrate ability to continuously monitor and control emergency worker exposure.
- 21. Demonstrate ability to make _the decision, based on s' 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 on-site personnel. t i
i 24. Demonstrate ability to brief the media in a clear, accurate, timely manner.
t's I
,; 'ES. Demonstrate ability to provide advance coordination of 1, t/ information released.
- 26. Demonstrate ability to establish and operate rumor control in a coordinated fashion.
t- .
t 4 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.
~
?0. Demonstrate adequacy of ambulance facilities and procedures for 3, handlieg contaminated individuals.
- 31. Demone.trate adequacy of hospital facilities and procedures for handlity contaminated individuals.
- 32. Demotistrate 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.
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\, l' 1 - 13
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- 34. Demonstrate ability to estimate total population exposure.
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- 35. Demonstrate ability to determine and implement appropriate measures for controlled recovery and re-entry.
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I SECTION 2.0 EXERCISE INFORMATION 4
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~2.0 EXERCISE INFORMATION
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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 ,
l a. Control Room (CR)
- c. Operations Support Center (OSC)
- d. Emergency Operations Facility (EOF)
- e. Alternate Emergency Operations Facility (AEOF)
- f. General Office Emergency Center (GOEC)
- g. Media Release Center (MRC) 2.1.2 Off-site Agencies / Organizations
- 1. Federal
- a. Nuclear Regulatory Commission (NRC)
- 2. State of Nebraska
- a. Health Department
- b. Other State agencies simulated at State EOC
- 3. State of Missouri
- a. All State agencies will participate at State EOC 4
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2-1 3
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2.2 EXERCISE ORGANIZATION
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The organization for this exercise will consist of the Exercise s Coordinator, the Lead Exercise Controller, the Controllers, the Evaluators, the Players and the observers, as follows:
2.2.1 The Exercise Coordinator (Bill Keller) is responsible for the conduct of a successful exercise, 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 preparation of a consolidated evaluation package, and prepare and follow up on an itemized list of corrective actions recommended as a result of the evaluatien and critique.
2.2.2 The Lead Exercise Controller (Bill Keller) will ensure the safe conduct of the exercise. The 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 will be the responsibility of the Lead Exercise Controller.
2.2.3 The Controllers (see Figure 5.1) are qualified personnel sele;ted to perform functions as follows:
A. A Lead Controller is assigned to each emergency N _)T response facility. The Lead Controller is responsible for all Controller, Evaluator and Observer activities for that f acility and, as appropriate, its associated teams. Controllers for teams or sub-areas of a facility report to the Lead Controller of that facility.
B. The Controllers will deliver " Exercise Messages" to designated players at specified times and places during the exercise, inject or deliver contingency
- messages as required to prompt the appropriate player response and keep the exercise actions moving according to the scenario, observe the exercise at other assigned locations, and prepare an evaluation, Controllers will submit written recommendations to the Lead Controller, who will summarize all comments for submittal to the Exercise Coordinator. The Controllers are provided with instructions and evaluation forms in Section 5.0 of this manual.
2.2.4 The Evaluators are qualified personnel who are assigned to judge the effectiveness of participating organizations, personnel, and activities in response to the scenario.
Selection of Evaluators is based on their expertise and qualifications to evaluate an assigned activity or area.
f'~'g Persons designated as Controllers for a given function will
\s_-}
2-2
usually be assigned as Evaluators when feasible.
Evaluators will record their observations using the
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evaluation form provided and make recommendations to the Lead Controller in their facility. They will evaluate performance on the basis of standards or requirements contained in the appropriate Emergency Plon, Implementing Procedures, Exercise messages, and as described herein (See Section 5.0).
2.2.5 The Plavers include CNS and other Nebraska Public Power
- District personnel assigned to perform emergency functions as described in the Emergency Plan and Implementing Procedures. Players from off-site organizations and agencies (county, State, and private industry) are participants in the Exercise as described in their respective Emergency Plans and Standard Operating Procedures.
2.2.6 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.
2.3 EMERGENCY RESPONSE FACILITIES During the exercise, following emergency response facilities will be activated to manage, assess and support the response to the f}
simulated emergency as required by the sce.nario.
'~'
- l. 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 following the CR to be habitable during Design Basis Accidents (as defined in the CNS USAR). The CR contains plant instrumentation, required technical drawings, CNS records, and communications equipment.
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 Caitronics intercom and the_1TT intercom (with executive override 4 capabilities).
o Telephone hotlines to the following: NRC (ENS),
, and the Nebraska EOC/ Nebraska State Patrol Headquarters.
/^g o National Warning System (NAWAS).
\
'-/ o High and low band radio communications.
4 2-3
/N The TSC (Figure 2.1) is the focal point for on-site emergency
\
) coordination and for directing and assisting the Control Room (CR) during station emergency conditions. The following functione are performed in the TSC:
o Provide managecent and technical support to station 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) functions for an ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY until the EOF becomes functional and is adequately manned; assumes the role of the EOF in the event the EOF functions must be transferred to the AEOF.
The TSC is located adjacent to the Control Room.
Figure 2.1 provides a layout of the TSC.
As indicated in Figure 2.1, a portion of the TSC is in the Control Room. Accordingly, the habitability of this portion of the TSC is identical to that of the Control Room. The portion of the TSC outside the Control Room is provided with radiological protection and monitoring f} equipment to protect personnel under most conditions. The
\'/ exception being core degradation and leakage to the aren 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 OCS'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.
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 levels, independent of thyroid blocking provisions (potassium 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 additional, the locker contains equipment necessary to provide continued r~~N
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l 2-4
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TSC operation during the presence of low-level airborne radioactivity or radioactive surface contamination.
s ,) If the TSC becomes uninhabitable, the TSC Emergency Response functions will be transferred to the Control Room.
Th'e 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, records needed to perform the functions of the EOF when it is not operational, and a copy of the Updated Safety Analysis Report are available to personnel in the TSC itself or in the adjacent Control Room.
In addition to the above, the TSC is equipped with the following communi:stions 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 NSP Headquarters, (v'~'} 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 on-site and off-site communications and portable radios are also available.
- 3. Operstions Support Center (OSC)
The OSCs are the assembly and staging areas for CNS personnel pooled for emergency response assignments. The OSCs provide a location 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 Support Centers: ;
- 1) Health Physics Office Area - This Operations Support Center will be manned by members of the station Chemistry and Health Physics staff.
. 2) Electrical Shop - This Operations Support Center will be manned by members of the station Electrical and Instrument
& Control staffs.
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- 3) Mechanical Maintenance Shop - This Operations Support Center will be manned by Mechanical Maintenance personnel.
2-5
In an ALERT or a higher classification of emergency, personnel will report to their respective OSCs. If assistance from one
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or more of the OSCs is required by TSC personnel, actions will be coordinated through the 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 Operations Support Center consists of:
o Lincoln Telephone and Telegraph PBX extensions, station -
intercom system, and an alternate emergency intercom system to the other OSCs, TSC, CR, and EOF. Portable radios are also available if required.
In the event any or all of the OSCs become uninhabitable, personnel will be relocated to the Security Euilding Auditorium.
- 4. Emergency Operations Facility (EOF)
The EOF (Figure 2.2) is located adjacent to the Security Building, outside the station security area. The EOF is the emergency response facility where the following functions are carried out:
( _ ,/ o Management of the off-site emergency response functions, o Coordination of radiological and environmental assessment.
o Determination of recommended protective 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.
During SITE AREA or CENERAL EMERGENCY conditions, the EOF will be manned. Off-site 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 locker in the EOF contains material and equipment needed for off-site monitoring and re-entry 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 of off-site rs surveys and sample analyses will be reported to the EOF for
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evaluation and assessment, and to aid in the development of recommendations to off-site authorities..
2-6
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Personnel in the EOF, in addition to those in the TSC, have the capability to access meteorological data (from personnel in the
(' 'T ' Computer Room) and in conjunction with release rate (s)
\s_,/ information (obtained from personnel in the Control Roem) determine the projected downwind doses. All of this data is prominently displayed in the EOF and is readily available to local / state / federal authorities for use in making an independent determination of protective actions, etc.
Communications available in the EOF are as follows:
o Dedicated NRC hotline (ENS) located in the NRC area; the NRC Health Physics Network (HPN) located in the NRC area; sufficient number of additional " plug in" commercial telephones to provide access to on-site and off-site locations (including state and local emergency operation centers).
o Remote control consoles for radio communications with inplant and CNS field monitoring teams. j o CNS station intercom system and alternate emergency intercom to the CR, TSC, and OSCs.
o Dedicated intercom system between the EOF and the Nebraska State Field Command Post.
o Hotline to Nebraska Emergency Operations Center and NSP
/) Headquarters.
L) o Hotline to GOEC and MRC.
Document communication by facsimile transmission equipment between the EOF, the TSC, the NRC operations center, MRC, GOEC, j and the State of Nebraska EOC, is also provided. l Information available in the EOF includes: Station Technical Specifications Operating Procedures, Emergency Operating Procedures Updated Safety Analysis Report, environs radiological monitoring records, and selected as-built drawings. In additional, copies of state and local emergency response plans and information pertinent to evacuation is also maintained.
The Nebraska Field Command Post and the Nebraska 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 vrr.s consists of direct intercom and telephone via external plug-in at the EOF. Radio communication is also available.
- 5. Alternate Emergency Operations Facility (AEOF)
The AEOF (Figure 2.3) is located in the town of Auburn,
(g Nebraska, approximately 10 1/2 miles west of CNS. It is housed
( ) in the Auburn National Guard Armory.
2-7
., If emergency conditions dictate relocation to the AEOF, emergency evaluation and coordination activities will be
(g accomplished from this location. Furthermore, it will serve as (j the alternate assembly point for station personnel. The AEOF also has an emergency locker containing similar amounts and types of emergency equipment as the EOF; however, it does contain a larger quantity of decontamination equipment, should decontamination of evacuated station personnel be required. A list of the general type of this emergency and decontamination equipment is included in Appendix E of the CNS Emergency Plan.
Communications available in the AEOF are as follows:
o 21 LTT Lynch line extensions for AEOF personnel.
o 2 LTT Lynch line extensions for data transfer.
The time required to fully activate the CNS Emergency Response Facilities (ERFs) identified above,-is dependent upon the time of day the event (s) which necessitates activation occurs.
Specifically, if the ERFs were required to be activated during on-shift hours (i.e., 0800-1630), then they could be adequately staffed and placed into operation within 30 minutes of the time an ALERT of higher classification was declared. If the ERFs had to be activated during off-shift hours, manning of the ERFs will require additional time.
The District estimates that the ERFs could be adequately f' 'g staffed within approximately one hour after the notification
( ) process described in EPIP 5.7.6 is executed.
As previously indicated, the AEOF, located in Auburn, Nebraska, serves as the backup for the CNS EOF. In the unlikely event
, that the EOF had to be evacuated, key personnel would, in accordance with EPIP 5.7.11, evacuate the area and relocated to l the AEOF.
Personnel in the TSC would be controlled from the TSC. It is estimated that the transfer to, and activation of, the AEOF would require approximately one hour. It should be_ emphasized that key personnel relocating to the AEOF would maintain contact with CNS via mobile radio. Furthermore, direct communications with the TSC and GOEC would be established.
- 6. General Office Emergency Center (GOEC)
The GOEC (Figure 2.4) 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 r Emergency Director, and his staff, the following support:
s o Engineering and technical support.
o Licensing, logistics, and legal support.
-( ) o Communications and facility equipment support.
. 2 .8 i
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o Public relations support.
/' 'g During a SITE AREA or GENERAL EMERGENCY condition, the COEC
\ _,/ will be manned by senior NPPD personnel and will provide support to the Emergency Director as required.
To assure timely and accurate information is available to the general public, the District has establisl.ed an Information Authentication Center (IAC). The center, located in the GOEC, 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 offices will be referred to the IAC. Additionally, all calls 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 IAC via the General Office switchboard. _
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 k _,g
/ . or correct any misconception, is developed and issued to the media.
Communications, other than normal telephone facilities available in the GOEC, consists of:
o Dedicated line from the EOF and Media Release Center.
- 7. Media Release Center (MRC)
The MRC (Figure 2.5), located in Omaha, Nebraska, serves as the focal point for contact with the media. The MRC will be staffed by NPPD senior management personnel who will act as 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 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
-s available at the MRC, are as follows:
\' / o Dedicated line from EOF and GOEC.
2-9 l
2.4 EXERCISE CONDUCT f)
'J 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 off-site emergency response organizations / agencies. The exercise will also simulate an off-site radiological release which will require deployment of CNS and state radiological monitoring teams.
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 1 procedures. The simulated emergency will then de-escalate, the recovery phase vill be initiated, and the exercise will then be terminated.
- 2.4.2 Actions 4
Emergency response actions during the simulated emergency
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( _,e will include: Recognition and classification of emergency conditions; assessment of on-site /off-site radiological consequences, alert / notification and mobilization of emergency response organizations, implementation of in-plant correct actions, activation /operati'on 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 will 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 backup, unless radio is the only means available. Separate telephone numbers and radio channels will be used for Controller communications to prevent the Players from learning the sequence of events in advance.
Close coordination between Controllers and Evaluators is essential.
2.4.4 Players The success of the exercise is largely dependent upon player reaction, knowledge of appropriate emergency plans g and implementing procedures, and an understanding of the v
) objectives of the exercise. Initial conditions which will 2 - 10
l affect player action or reaction will be provided to the players at the time the exercise begins. However, most of i
( the elemenlEs of the exercise play will be introduced l through the use of message forms. Players, therefore, are responsible for initiating actions during the exercise in l accordance with instructions, responsibilities, and tasks l for their particular function. Each Player will advise his/her Controller prior to performing emergency response actions to ensure that the Player is credited for those actions.
- 1. The Control Room will be the central point for distribution of exercise messages, and is the key to ensuring that the exercise progresses on schedule.
l 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 off-site activities, it will be necessary to postulate noncredible situations. 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 Controller, so that the scenario will progress as designed. The exercise Players are expected to " free play" the scenario to the extent practical. Notifications of, and contact with
( V supervisors, plant management, and off-site agencies will be made in accordance with the Emergency Plan Implementing Procedures.
- 2. The TSC will be the coordination point for on-site emergency response activities. TSC and EOF personnel will be aware that if the Exercise is to proceed as planned, and if the off-site organizations are to be exercised, it will be necessary to postulate noncredible situations. This is done to ensure that -
all aspects of the on-site and off-site emergency response organizations are tested. TSC and EOF l
personnel will accept exercise messages as written.
l 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 Controller.
The exercise Players in the TSC and EOF are expected to " free play" the scenario to the extent practical.
j Notifications of, and contact with supervisors, plant management, and off-site agencies should be made in l accordance with the Emergency Plan Implementing Instructions. The scenario is designed to activate on-site and off-site emergency response capabilities.
v 2 - 11
Players are reminded not to be excessively concerned with
, - - the mechanics or cause of the exercise scenario. This
( exercise is designed to evaluate the Emergency Plan,
\ implementing procedures, and emergency preparedness training program; not the probability, 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 at the conclusion of the exercise.
2.5 EVALL'ATION AND CRITIQUE The exercise will be evaluated by individuals who have expertise in the activity in their assigned location. These Evaluators and Controllers will evaluate exercise performance on the basis of requirements contained in the Emergency Plan Implementing Procedures, and exercise messages. Evaluators and Controllers 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. Deficiencies in the Emergency Plan, implementing procedures, the emergency preparedness training program, facilities, equipment and/or other areas will be identified
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N_ ,f through the critique pro, cess. The deficiencies will be documented by the Exercise Coordinator and corrected by the individuals who have responsibility in the area of the identified deficiency.
The schedule for the critique is included in Section 6.0.
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4 1 i 1 l l l t i i f f 4 SECTION 3.0 l . I TRAVEL INFORMATION s h l A e f i i f i I l 2 - 13 i l- - -- . - - . ..-,___ _ ._ _ _ _ ._,___ __ , _ _ , ,, _ . , _.___ . _ .,__ _,__._.,,_,__ _, _
/S. 3.0 TRAVEL INFORMATION This section of the Exercise Manual provides information to those individuals from Nebraska Public Power District, other utilities, local, state, federal government .and/or other organizations who will attend the exercise. Permission to observe the exercise must be obtained from: P. R. Windham Emergency Planning Coordinator Nebraska Public Power District Cooper Nuclear Station Brownville, Nebraska 3.1 TRAVEL o Air
- Eppley Field (80 miles from Cooper Nuclear Station)
Omaha, Nebraska o Automobile Directions from 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 [s's_ -) Brownville. In Brownville, follow signs to Cooper Nuclear Station entrance.
- Directions from Kansas City, Missouri: Take Interstate 29 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).
[ ) \s_ s / 3-1
3.2 ACCOMMODATIONS o Auburn, Nebraska f Auburn Inn U.S. 73-75 i North Auburn i (402) 274-3143 Friendship Inn Palmer House Motel U.S. 73-75 f South Auburn (402) 274-3193
- Grand Central Hotel 1114 J I Auburn j
(402) 274-3148 \ ! l o Rock Port, Missouri Rock Port Inn (Best Western) l I-29 & U.S. 136 l Rock Port l (816) 744-6282 l 0 i i i r I I n h ltill 3-2
PLANT: COOPER LOCATION: Brownville, NE LICENSEE: Nebraska Public Power District I l d y Dh V DIRECTIONS FROM EPPLEY EPPLEY FIELD 7% 0-
)
FIELD AIRPORT: Take Abbott Onve South to U.S. Hignway 6/ Interstate
- 4eo Take U S. Highway 6/ interstate 480 East to inter state g I 29 Take 1-29 South to U S. H'gnway 13L Take U.S.136
/
West to Brownvule in Brownville, fo!!ow signs south to Cooper Nuclear Station entrance Total approx. distance (n] OMAHA y,# " 80 ""*' E""E ' COUNCIL BLUFFS begammmesmemmamemameman g a g E NEBRASKA - IOWA
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i t i l i S ! 5 I t I t l . i l i l i SECTION
4.0 REFERENCES
/ ABBREVIATIONS / DEFINITIONS l
l t i I r i f i i { 1 0 3-3+
1 l l l
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 CNS License and Technical Specifications 4.1.9 CNS Piping and Instrumentation Drawings 4.1.10
- Nebraska Radiological Emergency Response Plan for Nuclear 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 Incide~nts - Nemaha County Change 1 (3/82) 4.1.15 Radiological Emergency Response Fran 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 Response Plan (9/84) n v
4-1
4.2 ABBREVIATIONS O) ( 4.2.1 4.2.2 A/E AEOF Architect Engineer 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 4.2.8 BLUEBIRD NSP Mobile Communication Center 4.2.9 B0P Balance of Plant 4.2.10 BRH Bureau of Radiological Health 4.2.11 BWR Boiling Water Reactor . 4.2.12 CAM (s) Constant Air Monitor (s) 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 4.2.25 ECCS Emergency Core Cooling System (' 4.2.26 ED Emergency Director 4.2.27 EOC Emergency Operating Center 4.2.28 EOF Emergency Operations Facility 4.2.29 EPA Environmental Protection Agency 4.2.30 EPC Emergency Planning Coordinator 4.2.31 EPl Emergency Plan Information 4.2.32 EPIP(s) Emergency Plan Implementing Procedures (s) 4.2.33 EPZ Emergency Planning Zone 4.2.34 ERF(s) Emergency Response Facility (s) 4.2.35 ERP Elevated Release Point 4.2.36 FEMA Federal Emergency Management Agency 4.2.37 FRRP Federal Radiological Response Plan 4.2.28 CE General Electric 4.2.39 G0 General Office 4.2.40 GOEC General Office Emergency Center 4.2.41 GOG(s) General Of fice Guidelines (s) 4.2.42 HP Health Physicist 4.2.43 HPCI High Pressure Core Injection 4.2.44 HPN Health Physics Network 4.2.45 HVAC Heating Ventilation Air Conditioning 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 4.2.50 LOCA Loss of Coolant Accident
~
4.2.51 LPCI Low Pressure Core Injection 4.2.52 LT&T Lincoln Telephone and Telegraph ('/) s, 4.2.53 LWR Light Water Reactor 4-2
1 4.2.54 MPC Maximum Permissable Concentration ik 4.2.55 Media Release Center O MRC \ 4.2.56 NAWAS National Warning System 9 4.2.57 NPPD Nebraska Public Power District s, y 4.2.58 NRC Nuclear Regulatory Commission 4.2.59 NSP Nebraska State Police 4.2.60 OSC Operations Support Center s' 4.2.61 PAG (s) Protective Action Guide (s) (' 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 4.2.68 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 4.2.73 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 p 4.2.77 TIC Technical 7nformation Center ? 4.2.78 TLD Thermoluminescent Dostmeter 4.2.79 TSC Technical Support Center 4.2.80 USAR Updated Safoty Analysis Report t 4.2.81 VFD Volunteer Fire Department O 4.2.82 WSFO Weather Service Forecast Of fice
,' l 1
O-4-3
I y 1 4.3 DEFINITIONS 4.3.1' ALERT: The level of emergency classification which indicates that events are in progress or have occurred which involve an actual or potential degradation of the level of safety of the. plant. 4.3.2 ff. TERNATE EMERGENCY OPERATIONS FACILITY (AEOF): The AEOF, stich is housed in the Auburn National Guard Armory, is
, , ; located approximately 10 miles west of CNS in Auburn,
< Nebraska. If conditions dictate relocating emergency response personnel from the EOF to the AEOF, emergency evaluation and coordination will be accomplished from this location.
s 4.3.3 ANTICIPATED TRANSIENT WITHOUT SCRAM (ATWS): Failure of the reactor control rods to insert into the core upon demand.
4.3.4 ASSbSSMENTACTIONS
Actions taken during or after an emergency to obtain and process information necessary to determine the character and magnitude of the emergency and u, Y ', to implement specific corrective emergency measures.
4.3.5 CONTAMINATION
Ingestion, inhalation, or direct contact f ~sg with water, air, soil, or tangible objects which are t
\s ') emitting ionizing radiation. A contaminated object has a level of radioactive material adhering to its surface higher than an established limit.
4.3.6 CONTROL ROOM (CR): The CR, operating under the direction of the Control Room Supervisor, is the primary point at 3 which station conditions are monitored and controlled. It is the point where corrective actions are taken to 3 mitigate an emergency situation and where the initial assessment and classification of an emergency are made.
4.3.7 CONTROLLER
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. i, " 4.3.8 C0&RECTIVE ACTIONS: Measures taken to reduce the severity of, or terminate an emergency situation at, or near, the
' I' source of.the problem; to prevent an uncontrolled release V
of.3adioactive material; or to reduce the magnitude of the
, radioactive release.
4.3.9 DE(ONTAMINATION
The proceas by which the body or an
~
, objrtt is relieved of radioactive substances.
[\m']- 4.3.10 DO N ASSESSMENT: The process of estimating the amount of radiation a person will potentially receive as a result of a radiological release.
, 4-4
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9 4.3.11 DRILL: A supervised event aimed at evaluating,
N developing, and maintaining skills in a particular operation.
4.3.12 EMERGENCY ACTION LEVELS (EALs): Parameters used to designate a particular class of emergency. These parameters are indicators of the emergency's severity or potential severity and are guides to aid in determining appropriate emergency response measures. 4.3.13 EMERGENCY OPERATIONS CENTER (EOC): An emergency response facility from which government officials exercise direction and control. 4.3.14 EMERGENCY OPERATIONS FACILITY (EOF): The E0F is the focal point for overall NPPD management of an emergency at CNS, and is used for the coordination of on-site and off-site Q 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. 4.3.15 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 g pathways. 4.3.16 EMERGENCY RESPONSE FACILITY: Any of several on-site and off-site centers which are activated to coordinate emergency 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. 4.3.17 EVALUATOR: A member of the exercise evaluation group. An evaluator may serve in a dual capacity as _ both a Controller and Evaluator. Each Evaluator may be assigned to one or more activities or functions for the purpose of evaluating, recording, critiquing, and making reccomendations for improvements. 4.3.18 EXCLUSION AREA: The area surrounding CNS in which the Nebraska Publi: Power District has the authority to determine all activities, including exclusion or removal of persons and property from the area during accident conditions. 4.3.19 EXERCISE: An event which tests the overall functions and capabilities of organizations involved in responding to an emergency situation. An exercise shall simulate an emergency that results in off-site authorities participating? fsv) 4-5 l
__ __ . _ _ __ _ - _ m 4.3.20 CENERAL EMERGENCY: The most severe level of emergency fg- classification which Indicates that events are in (\') progress. or have occurred, which involve actual or imminent' substantial core degradation or melting with potential for loss of containment integrity. Release of radioactive material can be reasonably expected to exceed PAG exposure
- levels off-site.
4.3.21 GENERAL OFFICE EMERGENCY CENTER (COEC): Located at NPPD Headquarters, Columbus, Nebraska. The COEC will be manned by senior management personnel with authority to commit corporate resources (i.e. , manpower, facilities, equipment, information, funds, etc.) to assist the CNS Emergency Response and Recovery organizations. 4.3.22 INFORMATION AUTHENTICATION CENTER (IAC): That portion of the GOEC, EOF, and MRC where information concerning the emergency is gathered and coordinated. 4.3.23 INGESTION 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 Emergency Planning Zone includes the area within a
, 50-mile radius of CNS.
j-~s 4.3.'24 LOCAL EMERGENCY RESPONSE PLANS: Plans for local 5
) governmental response to radiological emergencies at CNS
'V .(i.e., Nemaha, Otoe, and Richardson counties in Nebraska and Atchison county in Missouri). The plans set forth specific responsibilities and proced.ures for emergency agencies responsible for off-site emergency operations and the protection of the affected population.
4.3.257 MELIA 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. 4.3.26 NOTIFICATION OF UNUSUAL EVENTS: The lowest level of emergency classification,'which indicates that events are in progress or have occurred which indicate a potential degradation of the level of safety of the plant.
'4.3.27 OBSERVER: Any individual who is authorized to observe the Exercise,- but is not authorized to interact with the players.
' 4.3.28 0FF-SITE: All land and water areas outside the Owner-Controlled Area fence surrounding the CNS.
/p T? 4.3.29 ON-SITC: All land and water areas thin the
\s_s/ Owner-Controlled Area fence surrounding the CNS.
2 y 4 - _6 hl .. .
4.3.30 OPERATIONS SUPPORT CENTER (OSC): There are three OSC's at s CNS. In the event of an emergency, these centers will [ serve as staging areas and support bases for emergency
\s 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 3
activities. 4.3.31 PARTICIPANT: An individual who has some part in the Exercise, whether as an Evaluator, Controller, Player or Observer. 4.3.32 PLAYERS: All individuals (CNS, Nebraska Public Power District personnel, and individuals from off-site 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 potential 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.
\ \s_ / 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 4 and controls. 4.3.36 PROTECTED AREA: The area within the Site Boundary
~
encompassed by physical barriers and to which access is 4 controlled for security purposes. 4.3.37 PROTECTIVE ACTIONS: Emergency measures taken to prevent or minimize radiological exposure. These commonly include in-house shelter, evacuation, respiratory protection, and thyroid blocking. 4.3.38 PROTECTIVE ACTION GUIDES (PAGs): 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 P . -ks associated with taking the protective actions. PAGs are guides used as a decision aid in an actual emergency response situation.
/y The PAG does not include the dose that has unavoidably
( _, ) occurred prior to the assessment. (
Reference:
Manual of 4-7
- Protective Action Guides and Protective Actions for gN Nuclear Incidents; as revised June 1980; EPA-520/2-75-001.)
\
4.3.39 RADIATION ACCESS CONTROL AREA '(RACA): Any area in which the general area radiation level is equal to or exceeds 0.25 mrem /hr or radioactive loose gurface contamination is equal to og exceeds 220 dpm/100 cm beta-gamma, or 22 - dpm/100 cm alpha activity. A general REP is required for l entry to this type area. 4.3.40 RADIOLOGICAL MONITORING TEAMS (RMT's): Two-person teams responsible for monitoring radiation levels in the environment and collecting soil, air, and water samples for laboratory analysis. 4.3.41 RECOVERY ACTIONS: Post-emergency actions to restore the station as nearly as possible to its pre-emergency condition. 4.3.42 SITE AREA EMERGENCY: The level of emergency classification which indicates'that events are in progress or have occurred which involve actual or likely major failures of plant functions needed for protection of the public. Any releases of radioactive material are not expected to exceed Protection Action Guide (PAC) exposure levels, except within the Site Boundary. 4.3.43 STATE EMERGENCY RESPONSE PLANS: Plans for governmental
~s 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 off-site emergency operations and the protection of the affected population. i 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. t 4 f% 4 - 8~
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1 l l l l I l l l SECTION 5.0 CONTROLLER / EVALUATOR INFORMATION l b I e d i l l I I l
\
l l 4-9
f) v 5.0 CONTROLLER / EVALUATOR GENERAL INFORMATION Each Controller and Evaluator should be familiar with the following:
- a. The basic objectives of the exercise.
- b. The assumptions and precautions being taken.
- c. The exercise 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.
5.1 PRECAUTIONS AND LIMITATIONS This section provides guidance for all exercise Controllers and Obser.'ers 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 Controllers and Observers identified in this manual.
- 1. Should, at any time during the course of the conduct of this 7 ~3 exercise, an actual emergency situation.trise, all activities
( ) and communications related to the exercise will be suspended. N- / It will be the responsibility of any exercise Controller or Observer that becomes 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 Controllers / Observers to suspend all exercise activities. The Lead Exercise Controller will make a determination at that point whether to continue, place at temporary hold on, or terminate the exercise.
- 2. Shculd, at any time during the course of the conduct of this exercise, an exercise Controller or Observer witness an exercise participant undertake any action which would, in the opinion of the Controller / Observer, place either an individual or component in an unsafe condition, the Controller / Observer is responsible for intervening in the individual's actions and terminatingtheundEleactivityimmediately. Upon termination of the activity, the Controller / Observer is responsible for contacting the Lead Exercise Controller and informing him of the situation. The Land Exercise Controller will make a determination at that point whether to continue, place a temporary hold on, or terminate the exercise.
- 3. Manipulation of any plant operating systems, valves, breakers,
,_, or controls in response to this exercise are only to be
[ j simulated. There is to be no alteration of any plant operating \__,/ equipment, systems, or circuits during the response to this exercise. 5-1
4. ( All repair activities. associated with the scenario will be simulated, with extreme caution emphasized around operating equipment.
- 5. All telephone communications, radio transmissions, and public address announ. cements related to the exercise must begin and end with the stateuent, "This is a drill." Should a Controller or Observer witness an exercise participant not observing this practice, it is the Controller's/ Observer's responsibility to remind the individual of the need to follow this procedure.
- 6. Any motor vehicle response to this exercise, whether it be ambulance, fire fighting equipment, police / security vehicles or field monitoring teams, should observe all normal motor vehicle operating laws including posted speed limits, stop lights / signs, one way streets, etc.
- 7. Should any on-site security actions be required in response 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.
- 8. Exercise participants are to inject as much realism into the exercise as is consistent with its safe performance; however, caution must be used to prevent over-reaction.
- 9. Care must be taken to prevent any non-participating individuals f)'
('"' who may observe exercise activities from believing that an actual emergency exists. Any exercise Controller or Observer who is aware of an individual or group of individuals in the immediate vicinity who may have become alarmed or confused about the s.ituation, should approach that individual or group and explain the nature of the exercise and its intent. 5.2 CONTROLLER INSTRUCTIONS 5.2.1 Controllers will position themselves at their 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. watches and clocks will be synchronized with the Lead Exercise Controller as part of the communications testing. 5.2.3 All Controllers will comply with instructions from the Lead Exercise Controller. 5.2.4 Each Controller will have copies of the messages controlling the progress of the exercise scenario. No message shall be delivered out of sequence or_other than 1 as written unless specifically authorized by the Lead s Exercise Controller. l s_- 5-2 l
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 'I conditions indicated on the message are met. 5.2.6 Each on-site Controller will have copies of plant data sheets. Data sheets will be distributed only in the Control Room. 5.2.7 . Controllers will not 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 l judgement in determining response actions and resolving problems.
5.2.8 Some Players may insist that ce'rtain parts of the scenario are unrealistic. The Lead Controllers have the sole. authority to clarify any questions regarding scenario ' content. 1 5.3 EVALUATOR INSTRUCTIONS Each Evaluator will take detailed notes regarding the progress of
- the exercise and response of the exercise participants at their s assigned locations. Each Evaluator should carefully note the arrival and departure times of participants, the times when major j activities or milestones occur, and problem areas encountered.
(Evaluator Packages and further instructions to be-included later.) i-1 k k f s
\
f k 5-3 m-
l i COOPER NUCLEAR STATION ANNUAL EMERGENCY EXERCISE )
) FIGURE 5.1 CONTROLLER / EVALUATOR ASSIGNMENTS l
FACILITY / ASSIGNMENT CONTROLLER / EVALUATOR ! t Control Room Bob Jansky Bill Keller Technical ' Support Center Garrett Smith (Overall) Verne Wolstenholm (Engineer.) Rick Palazzo (Rad. & D.A.) Emergency Operations Facility Clem Morgan (Overall) Bob Wilbur (Management) Rick Palazzo (Rad & D.A.) Chemistry and Health Physics John Ditto Electrical / Instrumentation and Control Rich Gibson Operations Support Center - Maintenance Chuck Putnam Radiation Monitoring Teams G.O. Environmental Dept, s Repair Teams - Maintenance Chuck Putnam PASS Ken Fike General Office Emergency Center J. E. Flash (Overall) R. L. Gumm (QAP-1900) G. R. Smith (Management) Media Release Center K. C. Walden (Overall) T. E. Hottovy (QA) R. D. Landis (Media Interface) '\ : ,h~ 5-4
i I r I t i i l i l l l l t SECTION 6.0 SCHEDULE OF EVENTS j i i l .1 l l i l l l l l l l t l s I l i 5-5
N COOPER. NUCLEAR STATION-ANNUAL EMERGENCY EXERCISE FIGURE 6.1 SCliEDULE OF EVENTS EVENT DATE TIME LOCATION COMMENT
. Controller / Evaluator-Briefing for Evaluated Exercise Attendance mandatory for all Controllers.
1 NRC Briefing for Evaluated Exercise 10/15/85 Attendance mandatory for all Controllers. 1985 Emergency Preparedness Exercise 10/16/85 Attendance mandatory for all Controllers. Controller / Evaluator.De-Brief , Attendance mandatory for all Controllers. CNS/NRC Critique Attendance mandatory for all Controllers. FEMA Public Critique NRC provides on-site portion of public critique. 6-1
. . - - - . . - - - - - .. ...-..-.- - .--~ -.--- - -- - - - - . - - . - - . . - . - . . - . . . . . . - . . - -
e l 4 5 1 l , 2 I l I i i i 1 ( i !' i i t i r ! l f i 1 SECTION 7.0 ! EXERCISE SCENARIO j t t- 'l i ! i l l i i s L l r i F l t l l l t
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COOPER NUCLEAR STATION (} \s / 1985 EMERGENCY PREPAREDNESS EXERCISE PROGRAM EXERCISE SCENARIO SEQUENCE OF EVENTS Approximate Scenario Tine Time Key Events 0730 00/00 The Shift Supervisor is notified that the mechanic performing Maintenance Procedure 7.2.41 in the RWCU Filter Roem has been seriously injured in a highly contaminated area. First Aid team believes that injury warrants transportation to the hospital. Because the site ambulance is unavailable, the Auburn Rescue Squad is called to respond to the plant. (This injury is simulated for plant response, but the Rescue Squad response must occur in real time.) 0735 00/05 Health Physics personnel at the scene of the incident confirm that the injured individual is contaminated. . UNUSUAL EVENT An UNUSUAL EVENT should be declared in accordance
' with EPIP 5.7.1. EAL 6.5.1; Transportation to -
off-site facilities of contaminated, injured C,j)/ personnel. 0745 0C/15 Health Physics / Security verify that the injured individual has been moved to the plant gates. Health Physics awaits arrival of the Auburn Rescue Squad. The Shift Supervisor ensures that assignments are made to complete Maintenance Procedures 7.2.41. 0800 00/30 During the RWCU filter cartridge change out, the
" filter cartridge is dropped, spreading contamination over a large area. ARMS and CAM near the Filter Room alarm. ARM readings increase to 1000 times normal readings in the area near the incident.
ALERT An ALERT should be declared per EPIP 5.7.1, EAL 1.2.1; The control of radioactive material. The Shif t Supervisor insures that the area is evacuated and initiates plans for clean up of area contamination. 0815 00/45 Safety valve RV-70A may be weeping as indicated by elevated tailpipe temperature. O v)
Approximate Scenario Time Time Key Events
\s_/ 0845 01/15 The TSC and OSC have been fully activated.
Additional augmentation of the Health Physics staff may be considered. 0915 01/45 Safety valve RV-70A continues to indicate some intermittent weeping, howe ter drywell conditions remain stable indicating that the leak is not serious. 0930 02/00 Control Room operators performing Surveillance Procedure 6.2.4.1 notes some irregularity in core flow instrumentation readings. RRP SPD is adjusted in an attempt to balance the loop flows. Jet pump 6 has~ begun to deteriorate. 1000 02/30 Flow irregularities continue as jet pump 6 begins to degrade more seriously. Core DP shows marked increase while loop flow decreases. 1015 02/45 Off gas pre-treatment radiation monitors show some increase in off gas radiation. Flow irregularities continue, but do not warrant rapid shutdown of the reactor . I 1030 03/00 The condition of the jet pump deteriorates O' rapidly. Pieces of the jet pump ramshead have broken off and impinged on the core and lodged in the flow channels, causing degradation of cladding and local loss of core flow and high core differential pressure. Main Steam radiation monitors increase rapidly to 3 times normal values, causing group I/VII isolations, subsequent reactor scram and turbine trip and feed pump trip. The reactor level transient causes Group II, III, VI isolation. SRVs lift to control reactor pressure. HPCI/RCIC control level. Reactor instrumentation indicates that 30 control rods are not full in. Operators respond by attempting manual insertion of control rods. Power drops to 3%. SITE AREA A SITE AREA EMERGENCY should be declared in EMERGENCY accordanca with~EPIP 5.7.1.- EAL 2.5.1; Degraded core with-possible loss of coolable geometry. 1035 03/05 Control Room operators continue attempts to manually insert control = rods. SRVs continue to cycle, controlling pressure, HPCI maintains level within acceptable limits. Suppression pool terperature and radiation monitors begin to increase rapidly. ARMS in HPCI turbine area
'/'~'}
( ,j increase, indicating high steam radiation. Power oscillations cause intermittent APRM downscale alarms. Operators attempt to insert IRMs; however, only 3 will go in fully.
Approximate Scenario (s% Time 1040 Time 03/10 Key Events Operators continue attempts to manually drive rods in. Chemistry is requested to draw and analyze an RCS sample per General Operating Procedure 2.1.22 due to a Group I, VII isolation on Main Steam Hi Rad. In-core detectors (TIP) cannot be inserted completely due to blockage in channels. LPRM upscale. 1045 03/15 SRVs continue to control pressure, HPCI/RCIC control level. However, at every peak of reactor pressure there is indication that safety valve RV-70A weeps until the SRVs decrease the pressure. Power has been reduced to approximately 3% by_ manual insertion of control rods. 1100 03/20 Reactor is in subcritical condition with 13 rods not fully in. Operators continue to attempt manual insertion of control rods. SRVs continue to control reactor in cycle. The HPCI turbine trips and steam line isolates. There are indications of an rupture in the turbine steam supply line. 1115- 03/45 All control rods have been successfully inserted. 1130 04/00 Safety valve RV-70A fails open at peak of reactor pressure cycle. Drywell pressure increases rapidly. Containment atmospheric monitors indicate radiation levels rapidly increasing. _ Drywell humidity and temperature increase. Reactor level drops but is restored by RCIC. 1145 04/13 Drywell pressure increases very rapidly. Accident range monitors increase rapidly. Containment spray valve F031B fails to open When operators attempt to realign system.8iesels start on 2 psig in drywell. Diesel B trips. High oil _DP on filter.
' GENERAL A GENERAL EMERGENCY should be' declared in EMERGEFCY with EPIP 5.7.1, EAL 2.6.1 c)S: Loss of two of three fission product barriers with potential for loss of the third.
1200 04/30 Lighting strikes (the) transformers providing power to EOF. A team is sent to investigate problems. Plant essential buses are not affected. The EOF has lost all AC power. A decision is made to move EOF operations to the Alternate EOF O) I in Auburn. Control of the emergency is transferred back to the TSC temporarily.
r 9 Approximate. Scenario Time Time Key Events ; 4 1230 05/00 Diesel Generator B is successfully started by OSC ! teams in the plant. , 1300 05/30 -
-The Alternate EOF has been activated and is declared functional. ARMS alarm in area of CRD i hatch, indicating that the containment has been breached.. SBGT and ERP monitors indicate a .
j significant release has commenced. l } 1330 06/00 OSC. teams are still unable to open containment i
- spray valve F0318. The release continues.
i 1 1445 07/15 Containment spray is successfully initiated. ; .i Drywell pressure drops rapidly and release rate ; decreases to near background. ' i 1515 07/45 Meteorological conditions change and the remaining radioactive gases are_ dispersed in the '
- atmosphere.
1530 08/00 A recovery organization is established and re-entry planning is initiated. De-escalation of the emergency is discussed. 1630 09/00 The exercise is terminated. t I I 4 i r k
- a
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. _ - _ - - .. - . . . - - . . . . - - . . _ _ . . . - - . . - . - . - - - . . . - . . . . . - . ~ . - . . . - - - - . . .-. ..----.-.
1 1 i 4 i i i 1 l I I i i ! i I . I I t i i 1 I
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- ' SECTION 8.0 j MESSAGE FORMS AND PLANT DATA SEETS l
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1985 Evaluated Exercise Time = 0715
, Message Number IC t- -00/15 v
COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Message For: Control Room Simulated Plant Conditions: See attached Plant Data and Rad Monitoring Sheets Measage: * *
- THIS IS A DRILL * *
- O CNS is operating at 100% power. The core is near end of life and has 300 equivalent full power days. The unit has been operating for one month at steady state.
o containment Spray valve 10" 511 MV is tagged out due to repairs being performed on operator M031A. The valve is locked closed. A seven day LCO has been in effect since noon yesterday. o Sit'e ambulance is in Nebraska City for periodic maintenance and will be back on site tomorrow. o Maintenance procedure 7.2.41 is underway. SW-XXX, Attached, has been appropriately signed and posted. o The mechanic in the RWCU filter room has just been reported injured (simulated). The First Aid Team has responded to the incident (simulated). For Controller Use Only: CONTROLLER INFORMATION: o Discuss this inforeation with the drill operating shif t crew. Note care-fully that inplant response to the medical emergency is simulated, but that all other actions must be demonstrated. EXPECTED ACTIONS: O
1985. Evaluated Exerciss Tims = 0715
. Massage Number Ic t= -00/15 i \
COOPER NUCLEAR STATION l' EMERGENCY PREPAREDNESS EXERCISE PLANT DATA i i PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 100% APRM RHR A STBY 0 0 REACTOR LEVEL 35" + NR RHR B STBY 0 0 REACTOR PRESSURE 1000 psig ^ RHR C STBY 0 0 CORE D/P (psig) 17.25 RHR D STBY 0 0 CORE FLOW 71.0 6 CS A STBY 0 0 (0 lbm/hr) 0 FLOW (10 lbs/hr) CS B STBY 0 0 FEEDWATER A 4.8 HPCI STBY 0 0 FEEDWATER B 4.8 Drywell Pressure 16 (PSIA) MAIN STEAM A 2.4 Torus Level 0 (inches) MAIN STEAM B 2.4
.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) FLOW (gpm) CRD B Avail (gpm) RCIC 'STBY 0 0 LEVEL PRESS SOUIB PUMPS RWCU A OPER SLC 75 % 0 (psig) ON Avail i RWCU B Unavail j RRPA 92 % SPD MISCELLANEOUS PANELS RRPB 88 % SPD DIESEL GEN A STBY DIESEL GEN B STBY SBGT A STBY i i SBGT B STBY C Q) DRYWELL COOLING NORMAL TORUS WATER TEMP 80 'F i
. . . , . , , _ , ~ . _ _ _ . _ , , . . . . . .,_._,,e.,.. ., - . _ , = , . _ .
Tina = oms RADIATION MONITOR DATA t= 00/00 I AREA RADIATION MONITORS
; STATION DESCRIPTION READING 1 Rx Bldg Fuel Pool Area (SE Sch Floor) 150 mR/hr :
2 Rx Bldg Fuel Pool Area (SE Sch Floor). 7 mR/hr t 3 Rx Bldg New Fuel Area (SE Sth Floor)_ 0.1 mR/hr ! 4 Rx Bldg Rx Water Cleanup Demineralizer Area , (SW 3rd Floor) 8 mR/hr 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 1 mR/hr 6 Rx Bldg Neutron Monitor System Index Area (TIP Room ist Floor) 30 mR/hr 7 Rx Bldg Neutron Monitor System Drive Mech Area (SE ist Floor) 1 mR/hr Rx Bldg Control Rod Hydraulic Equipment Area 8
-(S ist Floor) 0.7 mR/hr i 9 lbc Bldg Control Rod Hydraulic Equipment Area
- (N ist Floor) 8 mR/hr
. 10- Rx Bldg HPCI Pump Room (SW Quad) 0.5 mR/hr 11 Rx Bldg RHR Pump Room (SW Quad) 7 mR/hr 12 Rx Bldg RHR Pump Room (NW Quad) 10 mR/hr
) 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 2 mR/hr j -14 Rx Bldg CS Pump Room (SE Quad) - 3 mR/hr i 15 Turbine Bldg Turbine Front Standard 0.6 mR/hr [ 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.02 mR/hr ! 17 Turbine Bldg Turbine Bldg Basement Control Corridor 0.01 mR/hr l l O 18 19 20 Turbine-Bldg Turbine Bldg Rx Feed Pump Area Turbine Bldg-Turbine Bldg Condensate Pump Area Control Room Main Control Room 0.04 mR/hr 0.01 mR/hr 2 mR/hr { 21 Grade Level Control Corridor- 0.2 mR/hr .i
- Panel 9-02 Personnel Airlock Area 903 0.3 R/hr l Panel 9-02 Ladder 903 to 2nd Level 0.29 R/hr l
- PROCESS AND VENT MONITORS l
PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 2.1El uCi/sec
- j. ERP Stack Normal Eff (RMP-RM-3A) 1.7El uCi/sec
- ERP Stack High Range (RMP-RM-3B) 0.0 uci/see Turbine Bldg Vent Eff (RMV-RM-20A) 4.0E0 uCi/see Turbine Bldg High Range (RMV-RM-20B) 0.0 uCi/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 3.7E0 uCi/see RW/ARW Bldg High Range (RMV-RM-30B) 0.0 uCi/sec
'i PANEL 9-10 Mn. Stm.-Rad Monitor.Ch. A2, B1 300 mR/hr 300 mR/hr Ch. A2, B2 302 nR/hr 300 mR/hr SJAE Off Gas Log' Rad Monitor Ch. A, B 22 mR/hr 22 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.7 mR/hr 0.7 mk/hr o- All other monitors display normal readings
- Alarm 0S Offscale t
l t 1.
.-.--.-_.--_-_-_-.---n.-.- -..__.. - . -.. ,. - --_. __. - . ._. . . . _ , - . . _ . . . ~ . . . - - - - . . _ ..a
1985 Evaluated Exercise Time = [d
'\ Message Number t= -00/05 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Message For: Control Room Simulated Plant Conditions:
Message: * *
- THIS IS A DRILL * *
- Make the following PA announcement:
" Attention all personnel - We are now commencing the CNS 1985 Emergency Preparedness evaluated drill. 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."
w For Controller Use Only: CONTROLLER INFORMATION: Direct the operations crew and make the following announcement. EKPECTED ACTIONS:
e 1985 Evaluated Exercise Time = 0730 b Message Number t= 00/00 V COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE
~
Message For: Control Room Simulated Plant Conditions: See attached Plant Data and Rad Manit7r Sheets Message: * *
- THIS IS A DRILL * *
- The First Aid Team at the scene of the incident has reported that (Victim's Name) has sustained serious injuries in the RWCU filter demin-eralizer room, and that an ambulance will be required to transport the victim to the hospital. An HP at the scene reports that the victim is contaminated.
O For Controller Use Only: CONTROLLER INFORMATION: o Inplant response to this emergency situation is sir.ulated. Ability of Auburn Rescue Squad to respond to a contaminated injured individual at CNS must be demonstrated. Two HPs and a victim will be stationed at the plant docr for transport to the hospital via the Auburn Rescue Squad. i EXPECTED ACTIONS: o SS should call Auburn Rescue Squad and identify that the injured individual is contaminated. Phone message must commence with "This is a drill...". o An Unusual Event should be declared in accordance with EPIP 5.7.1,
" EAL 6.5.1; Transportation to off-site facilities of contaminated, injured individual.
o SS should notify hospital of arrival of contaminated victim and inform CAS that the Rescue Squad will be arriving. l l t
1985 Evaluated Exarciss Tima = 0730 Massage Number t= -00/00 O COOPER NUCLEAR STATION LJ EMERCENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 100% APRM RHR A STBY 0 0 REACTOR LEVEL 35" + NR RHR B STBY ,_ 0 O REACTOR PRESSURE 1000 psig RHR C STBY 0 0 CORE D/P (psig) 17.25 RHR D STBY 0 0 CORE FLOW 71.0 0 CS A STBY 0 0 (10 lbm/hr) 6 FLOW (101bs/hr) CS B STBY 0 0 FEEDWATER A 4.8 HPCI STBY 0 0 FEEDWATER B 4.8 Drywell Pressure 16 (PSIA) MAIN STEAM A 2.4 Torus Level 0 (inches) MAIN STEAM B 2.4 OPEN CLOSED MAIN 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 0 0 LEVEL PRESS SOUIB PUMPS RWCU A OPER SLC 75 '% 0 (psig) ON Avail RWCU B Unavail RRPA 92 % SPD MISCELLANEOUS PANELS RRPB 88 % SPD DIESEL CEN A STBY DIESEL GEN B STBY SBGT A STBY SBGT B STBY DRYWELL COOLING NORMAL TORUS WATER TEMP 80 'F t
r time = 0730 RADIATION MONITOR DATA t= 00/00 s AREA RADIATION MONITORS
/ \
's_,) STATION DESCRIPl?ON READING 1 Rx Bldg Fuel Pool Area (SE Sch Floor) 150 mR/hr 2 Rx Bldg Fuel Pool Area (SE 5th Floor) 7 mR/hr 3 Rx Bldg New Fuel Area (SE Sch Floor) 0.1 mR/hr 4 Rx Bldg Rx Water Cleanup Demineralizer Area (SW 3rd Floor) 8 mR/hr 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 1 mR/hr 6 Rx Bldg Neutron Monitor System Index Area (TIP Room 1st Floor) 30 mR/hr 7 Rx Bldg Neutron Monitor System Drive Mech Area (SE 1st Floor) 1 mR/hr 8 Rx Bldg Control Rod Hydraulic Equipment Area (S lst Floor) 0.7 mR/hr 9 Rx Bldg Control Rod Hydraulic Equipment Area (N lst Floor) 8 mR/hr 10 Rx Bldg HPCI Pump Room (SW Quad) 0.5 mR/hr 11 Rx Bldg RHR Pump Room (SW Quad) 7 mR/hr 12 Rx Bldg RHR Pump Room (NW Quad) 10 mR/hr 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 2 mR/hr 14 Rx Bldg CS Pump Room (SE Quad) 3 mR/hr-15 Turbine Bldg Turbine Front Standard 0.6 mR/hr 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0,.02 mR/hr 17 Turbine Bldg Turbine Bldg Basement-Control Corridor 0.01 mR/hr
[T
\s_,/
18 Turbine Bldg Turbine Bldg Rx Feed Pump Area Turbine Bldg Turbine Bldg Condensate Pump Area 2 mR/hr 19 0.04 mR/hr 20 Control Room Main Control Room 0.01 mR/hr 21 Grade Level Control Corridor 0.2 mR/hr Pan.' 9-02 Personnel Airlock Area 903 0.3 R/hr Panel 9-02 Ladder 903 to 2nd Level 0.29 R/hr PROCESS AND VENT MONITORS PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 2.lEl uC1/sec ERP Stack Normal Eff (RMP-RM-3A) 1.7El uCi/sec ERP Stack High Range (RMP-RM-3B) 0.0 uCi/sec Turbine Bldg Vent Eff (RMV-RM-20A) 4.0E0 uCi/sec Turbine Bldg High Range (RMV-RM-702) 0.0 uCi/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 3.7E0 uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) 0.0 uCi/sec PANEL 9-10 Mn. Stm. Rad Monitor Ch. A2, B1 300 mR/hr 300 mR/hr Ch. A2, B2 302 mR/hr 300 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 22 mR/hr 22 mR/hr f'~N) Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.7 mR/hr 0.7 mR/hr
! 'i
'~
o All other monitors display normal readings
- Alarm OS Offscale L-_____-_-__-_-__-_____-_-_____-______-__-_---_ . _ _ _ _ _ _ __ __-______- __ _ _ _ _ - - _ _ - .
. _ . . _ _ _ _ . _ . _ . . . _ _ . - _ . _ m._._. .m. _ _ _ . _ _ __ _ ._ _ ._ . . . _ _ . _ . .
-1985 Evaluated Exercise Time = 0735 f' Message Number t= 00/05
- COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE i
Message For: Control Room Simulated Plant Conditions: Message: * *
- THIS IS A DRILL * *
- i 4
Insure that work continues on SWP-4 i [ ' c t
- For Controller Use Only: '
CONTROLLER INFORMATION: I ! o Ensure that work on Maintenance Procedure 7.2.41 continues. I i [ o Deliver this message only if Shif t Supervisor has not arranged for , j work continuation. ! l 7
- EXPECTED ACTIONS
f i e L i s i I
. - ~ . - - . ~ . ~ - - . . - . -- . . -. . . _ , . . _ . . - . - ~ . . - - . .
1985 Evaluated Exercise Time = 07/40 Message Number t= 00/10 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE ! t Message For: - Shift Supervisor Simulated Plant Conditions: Message: * *
- THIS IS A DRILL' * *
- o Call the Auburn Rescue Squad.
i T r L i-For Controller Use Only: CONTROLLER INFORMATION:
-o Deliver this message only if the Shift Supervisor has not performed this- L action at this time. ;
t e
-EXPECTED ACTIONS:
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i i 1 1985 Evaluated Exercise Time = 0745 1-5 Message Number t= 00/15 l 4 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Y Message For: Health Physics personnel with victim at Plant Door . , 2 --
. Simulated Plant Conditions: ,
N w Message: * *
- THIS IS A DRILL * *
- y ,91 ..
Personnel contamination and injury information are detailed on attached map. L l s.
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!. + ! t-4 For Controller Use Only: 4 CONTROLLER INFORMATION: [ Deliver this to the pre-staged HPs at plant-door with victim. This - information is for their use in participating in the Auburn Recue Squad j response. I s EXPECTED ACTIONS: 1 t
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y: BODY >L\P TIME: DATE: INDICATE !!0IRiDS AND/OR CONTAMINATED AREAS:
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i . 1985 Evaluated Exercise Time = 0745' ., L Message Number t= 00/15 - f . !- COOPER NUCLEAR STATION
\ .
EMERGENCY PREPAREDNESS EXERCISE MESSAGE 4 3 Message For: Control Room-f Simulated Plant Conditions: See attached plant data and Rad Monitor Sheets Message: * *
- THIS IS A DRILL * *
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! For Controller Use Only: CONTROLLER INFORMATION: i o Plant conditions remain stable. i l I EXPECTED ACTIONS: i % I i l l-I i
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-c ww h.
x,4 E ,1985 Evaluated Exercise c Tima = 0745 M2ssage Number t= -00/15 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 100% APRM RHR A STBY 0 0 REACTOR LEVEL 35" + NR RHR B STBY 0 0 ' REACTOR PRESSURE 1000 psig RHR C- STBY 0 0 ' CORE D/P (psig) 17.25 s RHR D STBY 0 O CORE FLOW 71.0 6 CS A STBY 0 ' O (10 lbm/hr) 6 FLOW (101bs/hr) CS'B
- a STBY 0 J0- FEEDWATER A 4.8 HPCI STBY 0 0 FEEDWATER B 4.8
! 'g P s, j Drywell Pressure 16 (PSIA) MAIN STEAM A 2.4 Torus Level. 0 (inches) MAIN STEAM B 2.4 _ j' OPEN CLOSED MAIN STEAM C 2.4
\MSIV. 8
~
0' MAIN STEAM D. 2.4 k' ; g t FLOW
~
PANEL 9-4 CRD A 50 (gpm) STATUS PRESS (psig) FLOW (gpm) CRD B -Ada11(gpm)
- RCIC- STBY 0 0 LEVEL PRESS PUMPS SQUIB RWCU A 'OPER .SLC 75 % 0 (psig) ON Avail RWCU B Unavail
- RRPA 92 % SPD MISCELLANEOUS PANELS RRPB' 88 % SPD .
DIESEL GEN A 'STBY ( Y DIESEL GEN B STBY SBGT A .Y STBY l SBGT B STBY O m :4; xWEtt Cee<1 e WeS L l I TORUS WATER TEMP 80 *F s g
= s >
-. s. .# .1. . . , _ _ , , ',.,, .-.r, _. --_.. . _ _ . . . . . ~ . - , _ , _ . -
Tima =- 0745 RADIATION MONITOR DATA t = ,00/15 AREA RADIATION MONITORS [
\s STATION DESCRIPTION- READING 1 Rx Bldg Fuel Pool Area (SE Sch Floor) 150 mR/hr 2 Rx Bldg Fuel Fool Area (SE Sth Floor) 7 mR/hr 3 Rx ' Bldg New Fuel Area (SE Sch Floor) 0.1 mR/hr 4 Rx Bldg Rx Water Cleanup Demineralizer Area I (SW 3rd Floor) 8 mR/hr 5- Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 1 mR/hr 6 Rx Bldg Neutron Monitor System Index Area (TIP Room ist Floor) 30 mR/hr 7 Rx. Bldg Neutron Monitor System Drive Mech Area (SE ist Floor) 1 mR/hr 8 Rx Bldg Control Rod Hydraulic Equipment Area (S 1st Floor) 0.7 mR/hr 9 Rx Bldg Control Rod Hydraulic Equipment Area (N 1st Floor) -8 mR/hr li0 Rx Bldg HPCI Pump Room (SW Quad) 0.5 mR/hr 11 Rx Bldg RHR Pump Room (SW Quad) 7 mR/hr 12 Rx Bldg RHR Pump Room (NW Quad) 10 mR/hr 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 2 mR/hr 14 Rx Bldg CS Pump Room (SE Quad) 3 mR/hr 15 Turbine Bldg Turbine Front Standard 0.6 mR/hr 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.02 mR/hr ;
17 Turbine Bldg Turbine Bldg Basement. Control ' Corridor 0.01 mR/hr
- 18 . Turbine Bldg Turbine Bldg Rx Feed Pump-Area 2 mR/hr 19 Turbine Bldg Turbine Bldg Condensate Pump Area 0.04 mR/hr 20 Control. Room Main Control Room 0.01 mR/hr 21 Grade Level Control Corridor 0.2 mR/hr Panel 9-02 Personnel Airlock Area 903 0.3 R/hr l Panel 9-02 Ladder 903 to 2nd Level - 0.29 R/hr i
! PROCESS AND VENT MONITORS PANEL VBDG E i Rx' Bldg Vent Eff (RMV-RM-40) 2.1El uCi/sec. ERP Stack Normal Eff (RMP-RM-3A) 1.7El uCi/sec ERP Stack High Range (RMP-RM-3B) 0.0 uci/sec Turbine Bldg Vent Eff (RMV-RM-20A) 4.0E0 uCi/sec Turbine Bldg High Range (RMV-RM-20B) 0.0 uCi/sec i RW/ARW Bldg Combined Eff (RMV-RM-30A) 3.7E0 uCi/sec i cRW/ARW Bldg High Range (RMV-RM-30B) 0.0 uci/sec
. PANEL 9-10 Mn. Stm. Rad Monitor Ch. A2, B1 300 mR/hr 300 mR/hr Ch.-A2, B2 302 mR/hr 300 mR/hr l lSJAE Off Gas Log Rad Monitor Ch. A, B 22 mR/hr 22 mR/hr l ('~') ~Rx Bldg Vent Ind/ Trip Unit'Ch. A B . 0.7 mR/hr 0.7 mR/hr U o All other monitors display normal readings
*- Alarm OS Offscale
1985 Evaluated Exercise Time = 0745 Message Number t= 00/15 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSACE Message For: Control Room Shift Supervisor l Simulated Plant Conditions: ' Message: * *
- THIS IS A DRILL * *
- Declare an UNUSUAL EVENT per EPIP 5.7.1, EAL 6.5.1.; any serious radio-logical exposure of plant personnel or the transportation to off-site facilities of contaminated injured personnel. ,
t 1 t I m
- U i
4 f For Controller Use Only: 1 CONTROLLER INFORMATION: I 1 Deliver this message only if an Unusual Event has not been declared at i
- . this time.
j [ i ii EXPECTED ACTIONS: [ e f i t
6 1985 E raluated Exercise Time = 0800 Message Number t= 00/30 v COOPER NUCLEAR STATION DdERGENCY PREPAREDNESS EXERCISE MESSAGE d Message For: Control Room Simulated Plant Conditions: See Attached Plant Data and Rad Monitor Sheets Message: * *
- THIS IS A DRILL * *
- Annunciators in the Control Room include:
Reactor Building High Radiation For Controller Use Only: CONTROLLER INFORMATION: i o The RWCU filter demineralizer cartridge has been dropped spreading gross contamination over a large area. o ARMS in the area alarm. o ARM on attached Radiation Monitor Cheets in reading 1000 times normal reading. 1 EXPECTED ACTIONS: I o Implement HPP - Declare an ALERT per EPIP 5.7.1, EAL 1.2.1; Control or Radioactive ('~') Material: sudden increase by a factor of 1000 over normal radiation readings. I i
1985 Evaluated Exerciss Tims = 0800 4 Massage Number t= 00/30
- COOPER NUCLEAR STATION l EMERGENCY PREPAREDNESS EXERCISE PLANT DATA l
PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 100% APRM ' I RHR A STBY 0 0 REACTOR LEVEL 35" + NR ; 1 j RHR B STBY- 0 0 REACTOR PRESSURE 1000 psig i RHR C STBY 0 0 CORE D/P (psig) 17.25 ' RHR D STPY 0 0 , CORE FLOW 71.0 6 CS A STBY 0 0 (0 lbm/hr) 6 FLOW (10 lbs/hr) CS B STBY 0 0 FEEDWATER A 4.8 HPCI STBY 0 0 FEEDWATER B 4.8 : f Drywell Pressure 16 (PSIA) MAIN STEAM A 2.4 i , i Torus Level 0 (inches) MAIN STEAM B _ 2.4 OPEN CLOSED MAIN STEAM C 2.4 ' i M31V 8 0 MAIN STEAM D 2.4 FLOW r ! i i PANEL 9-4 CRD A 50 (gpm) i
- STATUS PRESS (psig) FLOW (gpm) CRD B Avail (gpm) l I i RCIC STBY 0 0- LEVEL PRESS SQUIB PUMPS I RWCU A OPER SLC 75 % 0 (psig) ON Avail RWCU B Unavail i RRPA 92 % SPD MISCELLANEOUS PANELS
}
i RRPB 88 % SPD DIESEL GEN A STBY ! i DIESEL GEN B STBY t , SBGT A . STBY ! SEGT B STBY I DRYWELL C00 LING' NORMAL ! TORUS WATER TEMP 80 *F i [ t
Time = ~0800 RADIATION MONITOR DATA t= 00/30 i
. ss AREA RADIATION MONITORS
\~/ STATION DESCRIPTION READING 1 Rx Bldg Fuel Pool Area (SE Sch Floor) 150 mR/hr 2 Rx Bldg Fuel Pool Area (SE 5th Floor) 7 mR/hr 3 Rx Bldg New Fuel Area (SE Sch Floor) 0.1 mR/hr 4 Rx Bldg Rx Water Cleanup Demineralizer Area (SW 3rd Floor) 8 mR/hr 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 1250 mR/hr*
6 Rx Bldg Neutron Monitor System Index Area (TIP Room ist Floor) 30 mR/hr 7 Rx Bldg Neutron Monitor System Drive Mech Area (SE 1st Floor) 1 mR/hr 8 Rx Bldg Control Rod Hydraulic Equipment Area (S ist Floor) 0.7 mR/hr 9 Rx Bldg Control Rod Hydraulic Equipment Area (N ist Floor) 8 mR/hr 10 Rx Bldg HPCI Pump Room (SW Quad) 0.5 mR/hr 11 Rx Bldg RHR Pump Room (SW Quad) 7 mR/hr 12 Rx Bldg RHR Pump Room (NW Quad) 10 mR/hr
- 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 2 mR/hr 14 Rx Bldg CS Pump Room (SE Quad) 3 mR/hr 15 Turbine Bldg Turbine Front Standard 0.6 mR/hr 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.02 mR/hr 17 Turbine Bldg Turbine Bldg Basement Control Corridor 0.01 mR/hr 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 2 mR/hr k.
s 19 Turbine Bldg Turbine Bldg Condensate Pump Area 0.04 mR/hr 20 Control Room Main Control Room 0.01 mR/hr 21 Grade Level Control Corridor 0.2 mR/hr Panel 9-02 Personnel Airlock Area 903 0.3 R/hr Panel 9-02 Ladder 903 to 2nd Level 0.29 R/hr PROCESS AND VENT MONITORS PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 2.lEl uCi/sec ERP Stack Normal. Eff (RMP-RM-3A) 1.7El uCi/sec , ERP Stack High Range (RMP-RM-3B) 0.0 uC1/sec Turbine Bldg Vent Eff (RMV-RM-20A) 4.0E0 uCi/sec Turbine Bldg High Range (RMV-RM-20B) 0.0 uCi/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 3.7E0 uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) 0.0 uCi/sec PANEL 9-10 Mn. Stm. Rad Monitor Ch. A2, B1 300 mR/hr 300 mR/hr Ch. A2, B2 302 mR/hr 300 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 22 mR/hr 22 mh/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.7 mR/hr 0.7 mR/hr o All other m,onitors display normal readings
- Alarm OS Offscale
. - . ..=
1985 Evaluated Exercise Time = 0805 Message Number t= 00/35 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Message For: Control Room Simulated Plant Conditions: Message: * *
- THIS IS A DRILL * * *
"This is a drill, this is a drill."
"This is , I'm on elevation , near . The ,
RWCU filter cartridge that's being changed, has dropped. We have gross contamination spread over a large araa." q "This is a drill, thic is a drill." i i For Controller Use Only: CONTROLLER INFORMATION: o This information is to be called in to the Control Room using the plant page by a Controller located near the scene of the simulated incident. o Survey information is attached for use by Controller when plant personnel respond to incident. l l l EXPECTED ACTIONS: o Declare an ALERT in accordance with EPIP 5.7.1, EAL 1-2. 1
1985 Evaluated Exercise Time = 0815 ( V Message Number t= 00/45 COOPER NUCLEAR STATION f EMERGENCY PREPAREDNESS EXERCISE MESSAGE Message For: Control Room Simulated Plant Conditions: See attached Plant Data and Rad. Monitor Sheets Message: * *
- THIS IS A DRILL * *
- o Annunciators in the Control Room include:
Safety or Blowdown Valve Leaking. o Indications in the Control Room include: MS-TR-166, Channel 305'F RV.70A Tailpipe Temperature (Instrument Na.) 130*F Drywell Zone Temperature All other Drywell Zone Temperature indications are normal. 4 For Controller Use Only: CONTROLLER INFORMATION: j o Safety valve RV-70A is weeping. There is no reduction in reactor pressure, power or Main Steam flow rate, indicating a minor leak. Local Drywell temperature monitors show slight increases. RV-70A tailpipe temperature remains high for a normal period of time, then begins to decrease slowly. EXPECTED ACTIONS: i o Shift Supervisor / Control Operator should establish periodic watch of ( g RV-70A indications to insure that conditions do not worsen. d
1985 Evaluatsd Exercisa Tima = 0815 Massage Number t= -00/45 COOPER NUCLEAR STATION
~
EMERGENCY PREPAREDNESS EXERCISE PLANT DATA i . PANEL 9-3 PANEL 9-5 STATUS- PRESS (psig) FLOW (gpm) REACTOR PCWER 100% APRM i RHR A STBY 0 0 REACTOR LEVEL 35" + NR
' RHR B STBY 0 0 REACTOR PRESSURE 1000 psig
. RHR C STBY 0 0 CORE D/P (psig) 17.25
~
RHR D STBY 0 0 CORE FLOW 71.0 i
. CS*A STBY 0 0 ( ' #
6 FLOW (101bs/hr) . CS'B STBY 0 0 FEEDWATER A 4.8 HPCI STBY 0 0 FEEDWATER B - 4.8 Drywell Pressure 16 (PSIA) MAIN STEAM A 2.4 i. Torus Level 0 (inches) MAIN STEAM B 2.4 OPEN CLOSED MAIN STEAM C 2.4 MSIV 8 0 MAIN STEAM D 2.4 FLOW [ PANEL 9-4 CRD A 50 (gpm) 4 STATUS PRESS (psig) FLOW (gpm) CRD B Avail (gpm) l
. l, RCIC STBY 0 0 LEVEL PRESS PUMPS SQUIB ;
i
- _ RWCU A OPER SLC 75 % 0 (psig) ON Avail ;
1 RWCU B Unavail f k 92 RRPA % SPD MISCELLANEOUS PANELS t RRPB 88 % SPD DIESEL GEN A STBY ! DIESEL GEN B -STBY { SBGT A STBY t SBGT B STBY DRYWELL COOLING NORMAL l TORUS WATER TEMP 80 'F f i
, -. - . . - . - -. - -- . . . - - - ..- - - . _ ... ... .)
_. ~ _ _ __ . . . __ _ _ ._ l Tima = 0815 RADIATION MONITOR 9ATA t= 00/45 l AREA RADIATION MONITORS ( ' STATION DESCRIPTION READING 1 Rx Bldg Fuel Pool Area (SE Sch Floor) 150 mR/hr 2 Rx Bldg Fuel Pool Area (SE Sch Floor) 7 mR/hr 3 Rx Bldg New Fuel Area (SE Sch Floor) 0.1 mR/hr 4' Rx Bldg Rx Water Cleanup Demineralizer Area (SW 3rd Floor) 8 mR/hr 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 1260 mR/hr* 6 Rx Bldg Neutron Monitor System Index Area (TIP Room ist Floor) 30 mR/hr 7 Rx, Bldg Neutron Monitor System Drive Mech Area (SE 1st Floor) 1 mR/hr j 8 Rx Bldg Control Rod Hydraulic Equipment Area (S ist Floor) 0.7 mR/hr 9 Rx Bldg Control Rod Hydraulic Equipment Area (N 1st Floor) 8 mR/hr ? 10 Rx Bldg HPCl Pump Room (SW Quad) 0.5 mR/hr 11 Rx Bldg RHR Pump Room (SW Quad) 7 mR/hr i 12 Rx Bldg RHR Pump Room (NW Quad) 10 mR/hr 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 2 mR/hr 14 Rx -Bldg CS Pump Room (SE Quad) 3 mR/hr 15 Turbine Bldg Turbine Front Standard 0.6 mR/hr 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.02 mR/hr 17 Turbine Bldg Turbine Bldg Basement Control
- Corridor 0.01 mR/hr
' [\s,,)
\ 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 2 mR/hr 19 Turbine Bldg Turbine Bldg Condensate Pump Area 0.04 mR/hr
; 20 Control Room Main Control Room 0.01 mR/hr 21 Grade Level Control Corridor 0.2 mR/hr Panel 9-02 Personnel Airlock Area 903 0.3 R/hr 3 Panel 9 Ladder 903 to 2nd Level 0.29 R/hr i 4
PROCESS AND VENT MONITORS PANEL VBDG 4 Rx Bldg Vent Eff (RMV-RM-40) 2.1El uCi/sec ERP Stack Normal Eff (RMP-RM-3A) 1.7El uCi/sec ERP Stack High Range (RMP-RM-3B) 0.0 uci/sec Turbine Bldg Vent Eff (RMV-RM-20A) 4.0E0 uCi/sec Turbine Bldg High Range (RMV-RM-20B) 0.0 uCi/sec l RW/ARW Bldg Combined Eff (RMV-RM-30A) 3.7E0 uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) 0.0 uCi/sec . PANEL 9-10 l Mn. Stm. Rad Monitor Ch. A2, B1 300 mR/hr 300 mR/hr Ch. A2, B2 302 mR/hr 300 mR/hr i SJAE Off Gas Log Rad Monitor Ch. A, B 22 mR/hr 22 mR/hr i Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.7 mR/hr 0.7 mR/hr [ g'
- o All other monitors display normal readings "
- Alarm OS Offscale i ;
i n-- .- n --- -,, , -, , r - , - - - , - - - -
l' l I 1985 Evaluated Exercise Time = 0815 l l Message Number t= 00/45 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE : i
- I Message For: Control Room / Emergency Director !
Simulated Plant Conditions: [ Message: * *
- THIS IS A DRILL * * * ,
Declare an ALERT. per EPIP 5.7.1, EAL 1.2.1; Control of Radioactive Material; sudden increase by a factor over 1000 over normal radiation readings, i r For Controller Use Only: CONTROLLER INFORMATION: Deliver this message only if an ALERT has not been declared.at this time. EXPECTED ACTIONS: l : l i i i
i e
+-
1985 Evaluated Exercise Time = 0830 Message Number t= 01/00 COOPER N1' CLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Message For: Control Room Simulated Plant Conditions: See attached plant data and Rad Monitor Sheets Message: * *
- THIS IS A DRILL * *
- Indications in the Control Room include:
MS-TR-166 Channel 275'F RV-70A Tailpipe Temperature For Controller Use Only: CONTROLLER INFORMATION: o Health Physics personnel continue clean up of: contamination. o Cooling of tailpipe indicates that the valve weeping has temporarily stopped. EXPECTED ACTIONS:- t l
c . 1985 Evaluated Exercise' Time = 0830 Massage Number ~ t= 01/00 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 100% APRM
~RER A STBY' 0 0 REACTOR LEVEL 35" + NR RHR B STBY 0 0- REACTOR PRESSURE 1000 psig RHR C STBY 0 0 CORE D/P (psig) 17.25 RHR D STBY 0 0 CORE FLOW 71.0 CS A STBY 0 0 (10 lbm/hr) 0 OW (10 lbs/hr)
CS B STBY 0 0 FEEDWATER A 4.8
~'
HPCI STBY 0 0 FEEDWATER B 4.8 Drywell Pressure 16 (PSIA) , MAIN STEAM A 2.5 Torus Level 0 (inches) MAIN STEAM B 2.4 OPEN CLOSED MAIN 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 0 0 LEVEL PRESS SOUIB PUMPS RWCU A OPER SLC 75 % 0 (psig) ON -Avail RWCU B Unavail , RRPA 92 % SPD MISCELLA'NEOUS PANELS RRPB' 88 % SPD DIESEL GEN A. STBY DIESEL CEN B STBY SBGT A STBY ! SBGT B STBY DRYWELL COOLING NORMAL TORUS WATER TEMP 80 'F I-
Timm = 0815 RADIATION MONITOR DATA t= 01/00 AREA RADIATION MONITORS STATION DESCRIPTION READING 1 Rx Bldg Fuel Pool Area (SE Sch Floor) 150 mR/hr 2 Rx Bldg Fuel Fool Area (SE Sch Floor) , 7 mR/hr 3 Rx Bldg New Fuel Area (SE Sch Floor) 0.1 mR/hr 4 Rx Bldg Rx Water Cleanup Demineralizer Area (SW 3rd Floor) 8 mR/hr 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 1260 mR/hr* 6 Rx Bldg Neutron Monitor System Index Area (TIP Room 1st Floor) 30 mR/hr 7 Rx Bldg Neutron Monitor System Drive Mech Area (SE 1st Floor) 1 mR/hr 8 Rx Bldg Control Rod Hydraulic Equipment Area (S 1st Floor) 0.7 mR/hr 9 Rx Bldg Control Rod Hydraulic Equipment Area (N 1st Floor) 8 mR/hr 10 Rx Bldg HPCI Pump Room (SW Quad) 0.5 mR/hr 11 Rx Bldg RHR Pump Room (SW Quad) 7 mR/hr 12 Rx Bldg RHR Pump Room (NW Quad) 10 mR/hr 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 2 mR/hr 14 Rx Bldg CS Pump Room (SE Quad) 3 mR/hr 15 Turbine Bldg Turbine Front Standard 0.6 mR/hr 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.02 mR/hr 17 Turbine Bldg Turbine Bldg Basement Control Corridor 0.01 mR/hr ('~') 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 2 mR/hr (,_/ 19 Turbine Bldg Turbine Bldg Condensate Pump Area 0.04 mR/hr 20 Control Room Main Control Room 0.01 mR/hr 21 Grade Level Control Corridor 0.2 mR/hr Panel 9-02 Personnel Airlock Area 903 0.3 R/hr Panel 9-02 Ladder 903 to 2nd Level 0.29 R/hr PROCESS AND VENT MONITORS PANEL VBDG Rx Bldg Vent Eff (MTV-RM-40) 2.1El uCi/sec
.ERP Stack Normal Eff (RMP-RIt-3A) 1.7El uCi/sec ERP Stack High Range (RMP-RM-3B) 0.0 uCi/sec Turbine Bldg Vent Eff (RMV-RM-20A) 4.0E0 uCi/sec Turbine Bldg High Range (RMV-RM-20B) 0.0 uCi/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 3.7E0 uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) 0.0 uCi/see PANEL 9-10 Mn. Stm. Rad Monitor Ch. A2, B1 300 mR/hr 300 mR/hr Ch. A2, B2 302 mR/hr 300 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 22 mR/hr 22 mR/hr 5
Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.7 mR/hr 0.7 mR/hr o All other monitors display normal readings
- Alarm OS Offscale
7.. 1985 Evaluated Exercise Time = 0845
) Message Number t= 01/15 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS. EXERCISE MESSAGE Message For: Control Room Simulated Plant Conditions: See attached Plant Data and Rad Monitor Sheets Message: * *
- THIS IS A DRILL * *
- Annunciators in the Control Room include:
Safety or Blowdown Valve Open , Indications in the Control Room include: MS-TR-166 Channel 315'F RV-70A Tailpipe Temperature Drywell temperature indications are all normal. For Controller Use Only: CONTROLLER INFORMATION: i o The TSC and OSC should be operational at this time. o RV-70A is weeping slightly again. Drywell atmosphere conditions are normal indicating that the leak is minor. EXPECTED ACTIONS: i l_-
'1985 Evaluated Exarciss Time = 0845 Massage Number t= 01/15 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 100% APRM RHR A STBY 0 0 REACTOR LEVEL 35" + NR ' RHR B STBY 0 0 REACTOR PRESSURE 1000 psig RHR C STBY 0 0 CORE D/P (psig) 17.25 RHR D STBY 0 0 CORE FLOW 71.0 0
CS A STBY 0 0 (0 nmar) 6 FLOW (101bs/hr)" CS B STBY 0 0- FEEDWATER A 4.8 HPCI STBY 0 0 FEEDWATER B 4.8 Drywell Pressure 16 (PSIA) MAIN STEAM A 2.4 Torus Level 0 (inches) MAIN STEAM B 2.4 OPEN CLOSED MAIN STEAM C 2.4 MSIV. '8 'O MAIN STEAM D 2.4 FLOW PANEL 9-4 CRD A 50 (gpm) STATUS PRESS (psig) FLOW (gpm) CRD B Avail (gpm) RCIC STBY 0 0 LEVEL PRESS SQUIB PUMPS RWCU A OPER SLC 75 % 0 (psig) ON Avail f RWCU B Unavail-l l RRPA 92 % SPD MISCELLANEOUS PANELS RRPB- 88 % SPD DIESEL GEN A STBY I DIESEL GEN B STBY l SBGT A STBY l SBGT B STBY ! DRYWELL COOLING NORMAL TORUS WATER TEMP 80 'F l L:
r-Timi = 0845 RADIATION MONITOR DATA t = OL/15
-~s AREA RADIATION MONITORS I )
b/ STATION DESCRIPTION READING 1 Rx Bldg Fuel Pool Area (SE 5th Floor) 150 mR/hr 2 Rx Bldg Fuel Pool Area (SE 5th Floor) 7 mR/hr 3 Rx Bldg New Fuel Area (SE Sch Floor) 0.1 mR/hr 4 Rx Bldg Rx Water Cleanup Demineralizer Area (SW 3rd Floor) 8 mR/hr 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 1250 mR/hr* 6 Rx Bldg Neutron Monitor System Index Area (TIP Room 1st Floor) 30 mR/hr 7 Rx Bldg Neutron Monitor System Drive Mech Area (SE 1st Floor) 1 mR/hr 8 Rx Bldg Control Rod Hydraulic Equipment Area (S 1st Floor) 0.7 mR/hr 9 Rx Bldg Control Rod Hydraulic Equipment Area (N ist Floor) 8 mR/hr 10 Rx Bldg HPCI Pump Room (SW Quad) 0.5 mR/hr 11 Rx Bldg RHR Pump Room (SW Quad) 7 mR/hr 12 Rx Bldg RHR Pump Room (NW Quad) 10 mR/hr 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 2 mR/hr 14 Rx Bldg CS Pump Room (SE Quad) 3 mR/hr 15 Turbine Bldg Turbine Front Standard 0.6 mR/hr 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.02 mR/hr 17 Turbine Bldg Turbine Bldg Basement Control Corridor 0.01 mR/hr [\m,/} 18 19 Turbine Bldg Turbine Bldg Rx Feed Pump Area Turbine Bldg Turbine Bldg Condensate Pump Area 2 mR/hr 0.04 mR/hr 20 Control Room Main Control Room 0.01 mR/hr 21 Grade Level Control Corridor 0.2 mR/hr Panel 9-02 Personnel Airlock Area 903 0.3 R/hr Panel 9-02 Ladder 903 to 2nd Level 0.29 R/hr PROCESS AND VENT MONITORS PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 2.1El uCi/sec ERP Stack Normal Eff (RMP-RM-3A) 1.7El uC1/sec ERP Stack High Range (RMP-RM-3B) 0.0 uCi/sec Turbine Bldg Vent Eff (RMV-RM-20A) 4.0E0 uCi/sec Turbine Bldg High Range (RMV-RM-20B) 0.0 uC1/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 3.7E0 uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) 0.0 uCi/sec PANEL 9-10 Mn. Stm. Rad Monitor Ch. A2, B1 300 mR/hr 300 mR/hr , Ch. A2, B2 302 mR/hr 300 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 22 mR/hr 22 mR/hr (Nl Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.7 mR/hr 0.7 mR/hr s
~'
o All other eonitors display normal readings
- Alarm OS Offscale
1985 Evaluated Exercise Time = 0900 ( Message Number t= 01/30 COOPER NUCLEAR STATION' EMERGENCY PREPAREDNESS EXERCISE MESSAGE
, Message For: Control Room i ; Simulated Plant Conditions: See attached plant data sheets Message: * *
- THIS IS A DRILL * *
- Annunciators in the Control Room include:*
- Safety or Blowdown Valve Leaking - Annunciator cleared Indications in the Control Room include
j MS-TR-166 Channel 295'F RV-70A Tailpipe Temperature i i i i I For Controller Use Only: - I j CONTROLLER INFORMATION: l' o Temperature in tailpipe decreases as steam leak again temporarily ! decreases. Alarm is cleared. I i l EXPECTED' ACTIONS: o Continue surveillance ta note any worsening of conditions. C i L
e-~ . 1985 Evaluated Exercise Time = 0900
. Massage Number t= 01/30
'% COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 100% APRM RHR A STBY 0 0 REACTOR LEVEL 35" + NR RHR B STBY 0 0 REACTOR PRESSURE 1000 psig RER C STBY 0 0 CORE D/P (psig) 17.25 RHR D STBY 0 0 CORE FLOW. '71.0 6
CS A STBY 0 0 -( 0 lbm/hr) 6 FLOW (10 1bs/hr) CS B STBY 0 0 FEEDWATER A 4.8 HPCI STBY 0 0 FEEDWATER B 4.8 Drywell Pressure 16 (PSIA) MAIN STEAM A. 2.4 Torus Level 0 (inches) MAIN STEAM B 2.4 0 FEN CLOSED MAIN 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 0 0 LEVEL PRESS SOUIB PUMPS. RWCU A OPER SLC 75 % 0 (psig) ON Avail RWCU B Unavail RRPA 92 % SPD MISCELLANEOUS PANELS RRPB 88 % SPD DIESEL GEN A STBY I
. DIESEL GEN B STBY 4
SBGT A STBY p SBGT B STBY i DRYWELL COOLING NORMAL TORUS WATER TEMP 80 *F L.
[. Timi = 0900 RADIATION. MONITOR DATA t= 01/30 AREA RADIATION MONITORS C STATION DESCRIPTION READING 1 Rx Bldg Fuel Fool Area (SE Sch Floor) 150 mR/hr 2 Rx Bldg Fuel Pool Area (SE Sch Floor) 7 mR/hr 3 Rx Bldg New Fuel Area (SE Sch Floor) 0.1 mR/hr 4 Rx Bldg Rx Water Cleanup Demineralizer Area (SW 3rd Floor) 8 mR/hr 5- Rx Bldg Sludge and Decant Pump. Area (S 2nd Floor) 1265 mR/hr* 6 Rx Bldg Neutron Monitor System Index Area (TIP Room ist Floor) 30 mR/hr 7 Rx Bldg Neutron Monitor System Drive Mech Area
-(SE 1st Floor) 1 mR/hr 8 Rx Bldg Control Rod Hydraulic Equipment Area
, (S 1st Floor) 0.7 mR/hr 9 Rx Bldg Control Rod Hydraulic Equipment Area (N ist Floor) 8 mR/hr 10 Rx Bld-, HPCI Pump Room (SW Quad) 0.5 mR/hr 11 Rr oldg RHR Pump Room (SW Quad) 7 mR/hr 12 Rx Bldg RHR Pump Room (NW Quad) 10 mR/hr 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 2 mR/hr 14 Rx Bldg CS Pump Room (SE-Quad) 3 mR/hr 15 Turbine Bldg Turbine Front Standard 0.6 mR/hr 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.02 mR/hr 17 Turbine Bldg Turbine Bldg Basement-Control Corridor 0.01 mR/hr 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 2 mR/hr 19 Turbine Bldg Turbine Bldg Condensate Pump Area 0.04 mR/hr 20 Control Room Main Control Room 0.01 mR/hr 21 Grade Level Control Corridor 0.2 mR/hr Panel 9-02 Personnel Airlock Area 903 0.3 R/hr-Panel 9-02 Ladder 903 to 2nd Level -
0.29 R/hr PROCESS AND VENT MONITORS PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 2.1El uCi/sec ERP Stack Normal Eff (RMP-RM-3A) 1.7El uCi/sec ERP Stack High Range (RMP-RM-3B) 0.0 uCi/sec Turbine Bldg Vent Eff (RMV-RM-20A) 4.0E0 uCi/see Turbine Bldg High Range (RMV-RM-20B) 0.0 uCi/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 3.7E0 uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) 0.0 uC1/sec PANEL 9-10 Mn. Stm. Rad Monitor Ch. A2, B1 300 mR/hr 300 mR/hr Ch. A2, B2 302 mR/hr 300 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 22 mR/hr 22 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.7 mR/hr -0.7 mR/hr o All other monitors display normal readings
- Alarm OS Offscale l
I t
I 1 S: 1985 Evaluated Exercise Time = 0915 l ssage' Number t= 01/45 J I COOPER NUCLEAR STATION
-DIERGENCY PREPAREDNESS EXERCISE ~ MESSAGE Massage For: . Control Room '
Simulated Plant Conditions: See attached plant data and Rad Monitor Sheets
~
Massage: * *
- THIS I,S A DRILL * * * -
Annunciators in the Control Room' include: Safety or Blowdown Valve Leaking . Indications in the Control: Room include: MS-TR-166 Channel 325*F RV-70A Tailpipe Temperature !
- 130*F Zone Drywell Temperature l
-For Controller Use Only:
CONTROLLER INFORMATION: o Safety Valve RV-70A continues to weep as indicated by. periodic increases in tailpipe temperature'above 300*F. - Drywell level temperature indication remains a few degrees above normal. EXPECTED ACTIONS: 6 h > l l -- l
.,y,4. < . _
_ , , , , , - - , , , ---,---w-,,,,,,,--,--,y,-w.,- , , . . . . * , . . . . , , , , - - , -
-o------,,vm , - , ,, ---.y -'e-, --vc w eeew
rs -
'1985 Evaluated Exarcisa Time = 0915 Massage Number t= 01/45 (D) COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 IANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 100% APRM RHR A -STBY 0 0 REACTOR LEVEL 35" +- NR RHR B STBY 0 0 REACTOR PRESSURE 1000 psig RHR C STBY 0 0 CORE D/P (psig) 17.25 RHR D STBY 0 0 CORE FLOW 71.0 CS A -STBY 0 0 ( " #
0 FLOW (10 lbs/hr) CS B STBY~ 0 0 FEEDWATER A 4.8 HPCI STBY 0- 0 FEEDWATER B 4.8~ Drywell Pressure 16 (PSIA) , MAIN STEAM A 2.4 Torus Level 0 (inches) MAIN STEAM B 2.4 O OPEN
- CLOSED MAIN STEAM C 2.4 MSIV ~8 0 MAIN STEAM D 2.4 FLOW PANEL 9 CRD A 50 (gpm)
STATUS PRESS (psig) FLOW (gpm) CRD B Avail (gpm) RCIC STBY 0 0 LEVEL PRESS SQUIB . PUMPS RWCU A OPER SLC 75 % 0 (psig) ON Avail RUCU B Unava.,_ RRPA 92 % SPD MISCELLANEOUS PANELS RRPB 88 % SPD DIESEL GEN A STBY DIESEL CEN B STBY SBGT A STBY SBGT B STBY O-- DRYWELL COOLING NORMAL TORUS WATER TEMP 80 'F
T Time = 0915 RADIATION MONITOR DATA t= 01/45 AREA RADIATION MONITORS V) STATION DESCRIPTION READING 1 Rx Bldg Fuel Pool Area (SE Sch Floor) 150 mR/hr 2 Rx Bldg Fuel Pool Area (SE Sch Floor) 7 mR/hr 3 Rx Bldg New Fuel Area (SE Sch Floor) 0.1 mR/hr 4 Rx Bldg Rx Water Cleanup Demineralizer Area (SW 3rd Floor) 8 mR/hr 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 1265 mR/hr* 6 Rx Bldg Neutron Monitor System Index Area (TIP Room 1st Floor) 30 mR/hr 7 Rx Bldg Neutron Monitor System Drive Mech Area (SE 1st Floor) 1 mP/hr 8 Rx Bldg Control Rod Hydraulic Equipment Area (S 1st Floor) 0.7 mR/hr 9 Rx Bldg Control Rod Hydraulic Equipment Area (N 1st Floor) 8 mR/hr 10 Rx Bldg HPCI Pump Room (SW Quad) 0.5 mR/hr 11 Rx Bldg RHR Pump Room (SW Quad) 7 mR/hr 12 Rx Bldg RHR Pump Room (NW Quad) 10 mR/hr 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 2 mR/hr 14 Rx Bldg CS Pump Room (SE Quad) 3 mR/hr 15 Turbine Bldg Turbine Front Standard 0.6 mR/hr 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.02 mR/hr 17 Turbine Bldg Turbine Bldg Basement Control Corridor 0.01 mR/hr f'~j 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 2 mR/hr x ,/ 19 Turbine Bldg Turbine Bldg Condensate Pump Area 0.04 mR/hr 20 Control Room Main Control Room 0.01 mR/hr 21 Grade Level Control Corridor 0.2 mR/hr Panel 9-02 Personnel Airlock Area 903 0.3 R/hr Panel 9-02 Ladder 903 to 2nd Level 0.29 R/hr PROCESS AND VENT MONITORS PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 2.1El uCi/sec ERP Stack Normal Eff (RMP-RM-3A) 1.7El uCi/sec ERP Stack High Range (RMP-RM-3B) 0.0 uCi/sec Turbine Bldg Vent Eff (RMV-RM-20A) 4.0E0 uCi/sec Turbine Bldg High Range (RMV-RM-20B) 0.0 uCi/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 3.7E0 uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) 0.0 uCi/sec PANEL 9-10 Mn. Stm. Rad Monitor Ch. A2, B1 300 mR/hr 300 mR/hr Ch. A2, B2 302 mR/hr 300 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 22 mR/hr 22 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.7 mR/hr mR/hr ('~'} 0.7 o All other monitors display normal readings
- Alarm 6 OS Offseale
~
i 1985 Evaluated Exercise Time = 0930
-Message Number t= 02/00 [
COOPER NUCLEAR STATION-EMERGENCY PREPAREDNESS EXERCISE MESSAGE , 8 Message For: Control Room' i t
! Simulated Plant Conditions: See attached plant data and Rad Monitor Sheets 1
Message: * *
- THIS IS A DRILL * *
- i -
Control Room Operator has just completed Procedure 6.2.4.1, Attachment A . page 6 of 15; Daily Jet Pump Operability Check. He has noted some , irregularities in loop B; JP6 flows. Completed sheet is attached. I ! i-( J i ! a e !O i 1 i i t i For Controller Use Only: ! CONTROLLER INFORMATION: k o Jet Pump 6 is beginning to deteriorate as indicated by flow [ irregularities. ' j j o Jet Pump 6 fails portions of surveillance but is still operable. + i I o Handout Daily. Jet Pump Operability Check Surveillance Sheet. ' i EXPECTED ACTIONS: I t I r o Consider Power Reduction. > T j . o Adjust- Recire Pump flows in an attempt to balance loop flows. , ! o Notify TSC/ Engineering for evaluation of Jet Pump 6. I L l l i i
, . _ , _ . . . . _ _ . . , - , . _ _ . - - . _ . - . - _ . - - - - . _ , _ - - _ . _ _ ~ _ - , _ _ _ . . - - - - - - . _ _ . -_--
1985 Evaluatsd Exarcisa Timi = 0930 Massage Number t= 02/00 f~N
) COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 100% APRM RHR A STBY 0 0 REACTOR LEVEL 35" + NR RHR B STBY 0 O REACTOR PRESSURE 1000 psig RHR C STBY 0 0 CORE D/P (psig) 17.25 RHR D STBY 0 0 CORE FLOW 71.0 6
CS A STBY 0 0 (10 lbmAr) 6 FLOW (10 1bs/hr) CS B STBY 0 0 FEEDWATER A 4.8 HPCI STBY 0 0 FEEDWATER B 4.8 Dryvell Pressure 16 (PSIA) MAIN STEAM A 2.4 Torus Level 0 (inches) MAIN STEAM B 2.4 OPEN CLOSED MAIN STEAM C 2.4 MSIV 8 0 MAIN STEAM D 2.4 FLOW CLG WTR DP DR WTR DP PANEL 9-4 CRD A 50 (gpm) 20 (psig) 265 (psig) STATUS PRESS (psig) FLOW (gpm) CRD B Avail (gpm) 0 (psig) 0 (psig) RCIC STBY 0 0 LEVEL PRESS PUMPS SQUIB RWCU A OPER 100 SLC 75 % 0 (psig) ON Avail RWCU B Unavail RRPA 92 % SPD MISCELLANEOUS PANELS RRPB 88 % SPD DIESEL GEN A STBY DIESEL GEN B STBY SBGT A STBY SBGT B STBY
'i 1 d
DRYWELL COOLING NORMAL TORUS WATER TEMP 80 'F t
g _- . Tim 2 = 0930 RADIATION MONITOR DATA ' t= 02/00 AREA RADIATION MONITORS ('~' r Q STATION DESCRIPTION READING 1 Rx Bldg Fuel Fool Area (SE Sch Floor) 150 mR/hr 2 Rx Bldg Fuel Pool Area (SE Sch Floor) / mR/hr 3 Rx Bldg New Fuel Area (SE Sth Floor) 0.1 mR/hr 4 Rx Bldg Rx Water Cleanup Demineralizer Area (SW 3rd Floor) 8 mR/hr , 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 1200 mR/hr* N 6 Rx Bldg Neutron Monitor System Index Area (TIP Room ist Floor) 30 mR/hr 7 Rx Bldg Neutron Monitor System Drive Mech Area (SE 1st Floor) 1 mR/hr 8 Rx Bldg Control Rod Hydraulic Equipment Area (S 1st Floor) 0.7 mR/hr
- 9 Rx Bldg Control Rod Hydraulic Equipment Area (N 1st Floor) 8 mR/hr .
10 Rx Bldg HPCI Pump Room (SW Quad) 0.5 mR/hr 11 Rx Bldg RHR Pump Room (SW Quad) 7 mR/hr 12 Rx Bldg RHR Pump Room (NW Quad) 10 mR/hr 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 2 mR/hr 14 Rx Bldg CS Pump Room (SE Quad) 3 mR/hr _ 15 Turbine Bldg Turbine Front Standard 0.6 mR/hr 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.02 mR/hr 17 Turbine Bldg Turbine Bldg Basement Control Corridor 0.01 mR/hr 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 2 mR/hr ('~')3 ( _, 19 Turbine Bldg Turb,ine Bldg Condensate Pump Area 0.04 mR/hr 20 Control Room Main Control Room 0.01 mR/hr 21 Grade Level Control Corridor 0.2 mR/hr Panel 9-02 Personnel Airlock Area 903 0.3 R/hr Panel 9-02 Ladder 903 to 2nd Level 0.29 P/hr PROCESS AND VENT MONITORS PANEL VBDG
\
Rx Bldg Vent Eff (RMV-RM-40) 2.1El uCijsec ERP Stack Normal Eff (RMP-RM-3A) 1.7El uCi/sec ERP Stack High Range (RMP-RM-3B) 0.0 uCi/sec Turbine Bldg Vent Eff (RMV-RM-20A) , 4.0E0 uCi/sec Turbine Bldg High Range (RMV-RM-20B) 0.0 uCi/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 3.7EO uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) 0.0 uCi/sec PANEL 9-10 Mn. Stm. Rad Monitor Ch. A2, B1 300 mR/hr 300 mR/hr Ch. A2, B2 302 mR/hr 300 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 22 mR/hr 22 mR/hr gss Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.7 mR/hr 0.7 mR/hr
\' '] c All other monitors display normal readings
- Alarm OS Offscale
~
i Procsdure 6.2.4.1 Page 6 of 15 Attechesnt "A" Date p-, OPERATIONS - DAILY SURVEILLANCE LOG (s_ ,/) DAILY JET PUMP OPERABILITY CHECK Do the following tests daily whenever there is recirculation flow with the reactor in the startup or run modes of operation. Checks #1 through #3 are required by Technical Specifications (refer to Page 137). All three of Checks #1 through #3 must prove unsatisfactory to declare a jet pump inoparable. Checks #4 through #6 are performed because of jet pump beam cracking at several oper-cting BWRs. It is the purpose of Checks #4 through #6 to detect significant recirculation system parformance degradation prior to beam failure to the point of jet pump disassembly. PARAMETER CHECKED (UNITS) ' LOOP A l LOOP B JET PUMP SP INDICATION (%)
- l. Computer WTSUB (10' lb/br) JET PUMP LOOP B l JET PUMP LOOP A
- 2. Indicated Core Flow (10' lb/hr) 't #1 #11
- 3. RR Pu=p aP (PSID) - #2 #12
- 4. RR Pump Flow (10 GPM) #3 #13
- 5. RR MG Set Speed (E) . #4 #14
- 6. Jet Pump Flow (10" lb/hr) l F5 #15
- 7. Core Plate SP (PSID) NBI-DPR-95 x 30 , 3 46 #16
- 8. Co=puter WT (10 $1b/hr) _
#7 #17
*9. RR Pump Flow (10' lb/hr) (Computer) _
l #8 #18
#9 #19
'*Avstage computer points B026 and B027 for Loop A and #10 #20 points 3028 ar.d 3029 for Loop B. Loop B Loop A l, Average Average i A
l i #1: Are all jet pump APs within 10% of the average % AP for their respective loops? Y' YES: NO: -
!n0)4 n CHECY. #2: The values of total core flow in 1. and 2. above are within 10%? YES: NO: N If they do differ by 10% is the derived value (1. above) higher: YES: NO: N CHECK #3: Reactor recirculation pump flow from curve using the value of pump AP in 3. above is
- for Loop A and 's / for Loop B. The flow established from the curve is within 10% of the value in 4. above? Loop A - YES: ). NO: ; Loop B - YES: (
NO: CHECK #4: . ire the values of RR Pump Flow (4. above) and RR MG Set Speed (5. above) within the 5% s limits on the curve? Loop A - YES: NO: ; Loop B - YES: NO: CHECK #5: The value of jet pump loop flov (6. above) divided by the RR MG Set Speed (5. above)
~
l for the same loop is . for Loop A and for Loop B. Are these points determinet l to be within the 5% limits on the curves for Loop A and Loop B? Loop A - YES: NO: ; Loop B - YES: NO:
'-CHECK #6: The square root of Core AP (7. above) is '
. Are the values of square root of Core AP and Core Flow (8. above) within the 5% limits on the curve? YES: \ NO:
IF T4E ANSWER TO ANY OF THE ABOVE QUESTIONS IS liO,, NOTIFY THE SHIFT SUPERVISOR. Op; rotor: Time: A ( )cl Room Supervisor /Shif t Supervisor: / Control Room Supervisor Shift Supervisor Engin:ering Review: Date: NOTE: All the curves mentioned above are maintained in the Control Room.
h 1985 Evaluated Exercise Time = 0945 Message Number t= 02/15 i COOPER NUCLEAR STATION
- EMERGENCY PREPAREDNESS EXERCISE MESSAGE b
Message For: Control Room Simulated Plant Conditions: See attached plant data and Rad Monitor Sheets 1 Message: * *
- THIS IS A DRILL * * * !
l i 1 For Controller Use Only: CONTROLLER INFORMATION:
- o Flow irregularities worsen as a result of debris-from Jet Pump 6 obstruct-ing flow.
o Give out jet pump surveillance sheet information only if requested by an ! operator. Only distribute instrument indications. Surveillance checks must be completed by operator in order to determine status. All additional I i information shown on attached sheet-is for Controller information. '-* o Flow b'alancing has been successful. ' EXPECTED ACTIONS:
'{ .
) -o Consider power reduction.
l
* ' t;
k{ 1985 Evaluatsd Exercisa [ Timt = 0945 MadhkgeNumber t= 02/15 fy ? /) a ( COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA
%~ 3 .PANEI. 9-3' PANEL 9-5
\, STATUS PRESS (paig) FLOW (gpm) REACTOR POWER 100% APRM t . .
RHR A STBY ~
'0'- 0 REACTOR LEVEL 35" + NR s ,
RHR B STBYa 0 0 REACTOR PRESSURE 1000 psig RHR C STBY\ - 0 0 CORE D/P (psig) es.s
? a.
RHR D STBY 0 0 CORE FLOW 7o.5 6 CS A STBY 0 0 (10 lbm/hr) 6 g CS B. STBY- 0 0 FEEDWATER A 4.8 HPCI STBY 0 0- FEEDWATER B 4.8 Drywell Pressu e 16 (PSIA) MAIN STEAM A 2.4
% i i Torus Level 0 (inches) MAIN' STEAM B 2.4 OPEN CLOSED MAIN STEAM C 2.4 MSIV '8 0< MLIN STEAM D 2.4
, 4 FLOW CLG WTR DP DR WTR DP PANEL 9-4 CRD A 50 (gpm) 20 (psig) 265 (psig)
STATUS PRESS (psig) FLOW (gpm) CRD B Avail (gpm) 0 (psig) 0 (psig) RCIC STBY 0 0 . LEVEL PRESS SQUIB PUMPS RWCU A OPER 100 SLC- 75 % 0 (psig) ON Avail RWCU. B Unavail 0
,RRPA- 94 % SPD MISCELLANEOUS PANELS' 1 ._ 4 RR?R+ 86 7. SPD DIESEL GEN A :STBY S. DIESEL GEN B STBY rv
' *$ SBGT A STBY a SBGT.B STBY
- .\
,,/ 4 DRYWEL'L COOLING NORMAL
(' ( TORUS WATER TEMP '80 'F I
Tims = 0945 RADIATION MONITOR DATA t= 02/15 AREA RADIATION MONITORS STATION DESCRIPTION READING 1 Rx Bldg Fuel Pool Area (SE 5th Floor) 150 mR/hr 2 Rx Eldg Fuel Pool Area (SE Sch Floor) 7 mR/hr 3 Rx Bldg New Fuel Area (SE Sch Floor) 0.1 mR/hr 4 Rx Bldg Rx Water Cleanup Demineralizer Area (SW 3rd Floor) 8 mR/hr 5 Rx Bldg Sludge and Decan't Pump Area (S 2nd Floor) 1260 mR/hr* 6 Rx Bldg Neutron Monitor System Index Area (TIP Room 1st Floor) 30 mR/hr 7 Rx Bldg Neutron Monitor System Drive Mech Area (SE 1st Floor) 1 mR/hr 8 Rx Bldg Control Rod Hydraulic Equipment Area (S 1st Floor) 0.7 mR/hr 9 Rx Bldg Control Rod Hydraulic Equipment Area (N 1st Floor) 8 mR/hr 10 Rx Bldg HPCI Pump Room (SW Quad) 0.5 mR/hr 11 Rx Bldg RHR Pump Room (SW Quad) 7 mR/hr 12 Rx Bldg RHR Pump Room (NW Quad) 10 mR/hr 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 2 mR/hr 14 Rx Bldg CS Pump Room (SE Quad) 3 mR/hr 15 Turbine Bldg Turbine Front Standard 0.6 mR/hr 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.02 mR/hr 4 17 Turbine Bldg Turbine Bldg Basement Control Corridor 0.01 mR/hr
/~'N 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 2 mR/hr ks ,,) 19 Turbine Bldg Turbine Bldg Condensate Pump Area 0.04 mR/hr 20 Control Room Main Control Room 0.01 mR/hr 21 Grade Level Control Corridor 0.2 mR/hr Panel 9-02 Personnel Airlock Area 903- 0.3 R/hr Panel 9-02 Ladder 903 to 2nd Level 0.29 R/hr 4
PROCESS AND' VENT MONITORS
. PANEL VBDC Rx Bldg Vent Eff (RMV-RM-40) 2.1El uCi/sec ERP Stack Normal Eff (RMP-RM-3A) 1.7El uCi/sec ERP Stack High Range (RMP-RM-3B) 0.0 uCi/sec Turbine Bldg Vent Eff (RMV-RM-20A) 4.0E0 uC1/sec Turbine Bldg High Range (RMV-RM-20B) 0.0 uCi/sec RW/AKW Bldg Combined Eff (RMV-RM-30A) 3.7E0 uCi/sec RW/AFW Bldg High Range (RMV-RM-30B) 0.0 uCi/sec PANEL 9-10 Mn. Stm. Rad Monitor Ch. A2, B1 300 mR/hr 300 mR/hr Ch. A2, B2 302 mR/hr 300 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 22 mR/hr 22 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.7 mR/hr 0.7 mR/hr o All other monitors display normal readings
- Alarm OS Offscale
Procedure 6.2.4.1 Page 6 of 15 Attach =ent "A" Date
~, OPERATIONS - DAILY SURVEILLANCE LOG DAILY JET PUMP OPERABILITY CHECK Do the follcwing tests daily whenever there is recirculation flow with the reactor in the startup or run modes of operation. Checks #1 through #3 are required by Technical Specifications (refer to Page 137). All three of Checks #1 through #3 must prove unsatisfactory to declare a jet pump inoperable. Checks #4 through #6 are performed because of jet pump beam cracking at several oper-ating BWRs. It is the purpose of Checks #4 through #6 to detect significant recirculation systet perfcrmance degradation prior to beam failure to the point of jet pump disassembly.
PARAMETER CHECKED (UNJTS) I LOOP A I LOOP B JET PUMP AP INDICATION (%)
- l. Computer WTSUB (10" lb/br) y JET PUMP LOOP B 4 JET PUMP LOOP A
- 2. Indicated Core Flow (10" lb/hr) #1 - I vil -
- 3. RR Pump SP (PSID) #2 #12 .
4 RR Fump Flow (10' GPM) #3 #13
- 5. RR MG Set Speed (;) I .i #4 #14 .
- 6. Jet Pump Flow (10" lb/hr) l s- I #5 #15
- 7. Core Plate SP (PSID) NBI-DPR-95 x 30 66 #16 .
- 8. Computer WT (10",1b/hr) '
#7 #17 . *9. RR Fump Flow (10" lb/hr) (Computer) l . . ,
l .
#8 #18 .
F9 #19 .
- Average ccmputer points B026 and B027 for Loop A and #10 #20 .
points B028 and B029 for Loop B. Loop B Loop A , ., Average Average _ fp #1: Are all jet pump APs within 10% of the average % AP for the.r respective loops? YES: NO: .s ::;t 2 CHECK #2: The values of total core flow in 1. and 2. above are within 10%? YES: NO: If they do dif fer by 10% is the derived value (1. above) higher: YES: NO: - CHECK #3: Reactor recirculation pump flow from curve using the value of pump AP in 3. above is for Loop A and ~ st for Loop B. The flow established from the curve is within 10% of the value in 4. above? Loop A - YES: 9 NO: ; Loop B - YES: x NO: . CHECK #4: Are the values of RR Pump Flow (4. above) and RR MG Set Speed (5. above) within the 5% limits on the curve? Loop A - YES: < NO: ; Loop B - YES: NO: CHECK #5: The value of jet pump loop flow (6. above) divided by the RR MG Set Speed (5. above) for the same loop is for Loop A and for Loop B. Are these points determined to be within the 5% limits on the curves for Loop A and Loop B? Loop A - YES: NO: ; Loop B - YES: NO: CHECK #6: The square root of Core AP (7. above) is . Are the values of square root of Core AP and Core Flow (8. above) within the 5% limits on the curve? YES: 2L_ NO: IF THE ANSWER TO ANY OF THE ABOVE QUESTIONS IS NO, NOTIFY THE SHIFT SUPERVISOR. Operator: Time: ( ol Room Supervisor /Shif t Supervisor: / Control Room Supervisor Shift Supervisor l Engintering Review: Date: NOTE: All the curves mentioned above are maintained in the Control Room.
4 i f t 1985 Evaluated Exercise Time = 1000 ( Message Number t= 02/30 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE J Message For: Control Room i Simulated Plant Conditions: See attached plant data and Rad Monitor Sheets i Message: * *
- THIS IS A DRILL * *
- 4 4
!O - f i. For Controller Use Only: CONTROLLER INFORMATION: o Data sheet raflects power reduction in response flow irregularities.
- . o Handout appropriate jet pump' surveillance only if requested.
l . I o ' Jet pump fails surveillance and is inoperable. l . . l o RRPA & B will be 94% and 86% if power is not reduced by Recire and power will be 100%. Pull off core d/p and flow off appropriate surveillance sheet (100%. power or 75% power). EXPECTED ACTIONS:
-O i
I
1985 Evaluated Exerciss Time = 1000 Massage Number t= 02/30 l("%} COOPER NUCLEAR STATION ENERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 100% APRM RHR A STBY 0 0 REACTOR LEVEL 35" + NR RHR B STBY 0 0 REACTOR PRESSURE 1000 psig RHR C STBY 0 0 CORE D/P (psig) RHR b STBY 0 0 CORE FLOW 6 CS A STBY 0 0 (10 lbm/hr) 6 FLOW (10 1bs/hr) CS B STBY 0 0 FEEDWATER A 3.6 HPCI STBY 0 0 FEEDWATER B 3.6 Drywell Pressure 16 (PSIA) MAIN STEAM A 1.8 Torus Level 0 (inches) MAIN STEAM B 1.8 Ns OPEN CLOSED MAIN STEAM C 1.8 MSIV 8 0 MAIN STEAM D 1.8 FLOW CLG WTR DP DR WTR DP PANEL 9-4 CRD A 50'(gpm) 20 (poig) 265 (psig) STATUS PRESS (psig) FLOW (gpm) CRD B Avail (gpm) 0 (psig) 0 (psig) RCIC STBY 0 0 LEVEL PRESS SQUIB PUMPS RWCU A OPER 100 SLC 75 % 0 (psig) ON Avail RWCU B Unavail 0 RRPA 78 % SPD. MISCELLANEOUS PANELS RRPB 66 % SPD DIESEL GEN A STBY DIESEL CEN B STBY SBGT A STBY i SBGT B STBY s_ / DRYWELL COOLING NORMAL TORUS WATER TEMP 80 *F i
Tima = 1000 RADIATION MONITOR DATA t = _02/30 AREA RADIATION MONITORS 0f STATION DESCRIPTION ' READING 1 Rx Bldg Fuel Pool Area (SE Sch Floor) 150 mR/hr
, 2 Rx Bldg Fuel Pool Area (SE Sch Floor) 7 mR/hr 4
3 Rx Bldg New Fuel Area (SE Sch Floor) 0.1 mR/hr 4 Rx Bldg Rx Water Cleanup Demineralizer Area (SW 3rd Floor) 8 mR/hr 5 Rx Eldg Sludge and Decant Pump Area (S 2nd Floor) 1255 mR/hr* 6 Rx Bldg Neutron Monitor System Index Area (TIP Room ist Floor) 30 mR/hr 7 Rx Bldg Neutron Monitor System Drive Mech Area (SE 1st Floor) 1 mR/hr 8 Rx Bldg Control Rod Hydraulic Equipment Area (S ist Floor) , 0.7 mR/hr 9 Rx Bldg Control Rod H'/d raulic Equipment Area (N let Floor) 8 mR/hr 10 Rx Bldg HPCI Pump Room (SW Quad) 0.5 mR/hr 11 Rx Bldg RHR Pump Room (SW Quad) 7 mR/hr
. 12 Rx Bldg RHR Pump Room (NW Quad) 10 mR/hr 2
13 Rx Bldg RCIC/CS Pump Room (NE Quad) 2 mR/hr 14 - Rx Bldg CS Pump Room (SE Quad) 3 mR/hr 15 Turbine Bldg Turbine Front Standard 0.6 mR/hr ) 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.02 mR/hr 17 Turbine Bldg Turbine Bldg Basement Control l . Corridor 0.01 mR/hr
\
18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 2 mR/hr [\, 19 Turbine Bldg Turbine Bldg Condensate Pump Area 0.04- mR/hr 20 Control Room Main Control Room 0.01 mR/hr 21 Grade Level Control Corridor 0.2 mR/hr Panel 9-02 -Personnel Airlock Area 903 0.3 R/hr Panel 9-02 Ladder 903 to 2nd Level 0.29 R/hr PROCESS AND VENT MONITORS i PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 2.1El uCi/sec ERP Stack Normal Eff (RMP-RM-3A) 1.7El uCi/sec ERP Stack High Range (RMP-RM-3B) 0.0 uCi/sec Turbine Bldg Vent Eff (RMV-RM-20A) 4.0E0 uCi/sec Turbine Bldg High Range (RMV-RM-20B) 0.0 uCi/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 3.7E0 uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) 0.0 uCi/sec t PANEL 9-10 l Mn. Stm. Rad Monitor Ch. A2, B1 300 mR/hr 300 mR/hr Ch. A2, B2- 302 mR/hr 300 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 22 mR/hr 22 mR/hr Rx Bldg. Vent Ind/ Trip Unit Ch. A, B 0.7 mR/hr 0.7 mR/hr l l o All other monitors display normal readings
- Alarm OS Offscale
ProcGdura 6.2.4.1 Page 6 of 15 Attcch=;nt "A" Date OPERATIONS - DAILY SURVEILLANCE LOG ( \
's _,/ DAILY JET PUMP OPERABILITY CHECK Do th2 fo11cwing tests daily whenever there is recirculation flow with the reactor in the startup or run modes of operation. Checks #1 through #3 are required by Technical Specifications (refer to Page 137). All three of Checks #1 through #3 must prove unsatisf actory to declare a jet pump inop2rable. Checks #4 through #6 are performed because of jet pump beam cracking at several oper-cting BWRs. It is the purpose of Checks #4 through #6 to detect significant recirculation system p2rformance degradation prior to beam failure to the point of jet pucp disassembly.
PARAMETER CHECKED (UNJTS) LOOP A l LOOP B JET PUMP AP INDICATION (%)
- 1. Computer WTSUB (10' lb/br) JET PUMP LOOP B JET PUMP LOOP A
#1 #11
- 2. Indicated Core Flow (10" lb/hr)
- 3. RR Pump SP (PSID) c #2 #12
- 4. RR Pu=p Flow (10' GPM) J i3 #13
- 5. RR MG Set Speed (;) #4 #14
- 6. Jet Pucp Flow (10" lb/hr) I i #5 #15
#6 #16
- 7. Core Plate AP (PSID) NBI-DPR-95 x 30
- 8. Computer WT (10'z1b/hr) #7 #17 o9. RR Pump Flow (10' lb/hr) (Co=puter) l #8 #18
#9 #19 0 Average computer points E026 and B027 for Loop A and #10 #20 points B028 and B029 for Loop B. Loop B Loop A Average Average
( 3 #1: Are all jet purp APs within 10* of the average
- AP for their respective loops?
' r YES: NO:
CHECK #2: The values of total core flow in 1. and 2. above are within 10*? YES: NO: If they do differ by 10% is the derived value (1. above) higher: YES: NO: CHECK #3: Reactor recirculation pump flow from curve using the value of pump AP in 3. above is for Loop A and for Loop B. The flow established from the curve is within 10% of the value in 4. above? Loop A - YES: NO: ; Loop B - YES: e NO: CHECK #4: Are the values of RR Pump Flow (4. above) and RR MG Set Speed (5. above) within the 5% limits on the curve? Loop A - YES: NO: ; Loop B - YES: NO: CHECK #5: The value of jet pump 1,oop, flow (6. above) divided by the RR MG Set Speed (5. above) for the same loop is for Loop A and for Loop B. Are these points determin to be within the 5* limits on the curves for Loop A and Loop B? Loop A - YES: 7 NO: e ; Loop B - YES: NO: CHECK #6: The square root of Core AP (7. above) is . Are the values of square root of Core AP and Core Flow (8. above) within the 5% limits on the curve? YES: NO: IF THE ANSWER TO ANY OF THE ABOVE QUESTIONS IS M, NOTIFY THE SHIFT SUPERVISOR. , rotor: Time: l rol Room Supervisor /Shif t Supervisor: / l Shift Supervisor Control Room Supervisor Engineering Review: Date: NOTE: All the curves mentioned above are maintained in the Control Room.
Proccdura 6.2.4.1 Pcge 6 of 15 Attachment "A" Date
-~ OPERATIONS - DAILY SURVEILLANCE LOG I i E _)
s DAILY JET PUMP OPERABILITY CHECK Do tha following tests daily whenever there is recirculation flow with the reactor in the startup or run modes of operation. Checks #1 through #3 are required by Technical Specifications (refer to Page 137). All three of Checks #1 through #3 must prove unsatisfactory to declare a jet pump inoptrable. Checks #4 through #6 are performed because of jet pump beam cracking at several oper-eting BWRs. It is the purpose of Checks #4 through #6 to detect significant recirculation system parfor=ance degradation prior to beam failure to the point of jet pump disassembly. FARAMETER CHECKED (USJTS) I LOOP A l LOOP B JET PUMP SP INDICATION (%)
- 1. Computer WTSUB (10 lb/br) i JET PUMP LOOP B l JET PUMPI LOOP A
- 2. Indicated Core Flow (10' lb/hr) { . #1 ., #11
- 3. RR Pu=p SP (PSID) 9 l #2 -
! #12 4 RR Pump Flow (10' GPM) w. toa " #3 1 #13
- 5. RR MG Set Speed (*) l #4 . #14 l
- 6. Jet Pump Flow (10' lb/hr) l l F5 #15
- 7. Core Plate aP (PSID) NBI-DPR-95 x 30 1 #6 -
#16
- 8. Computer WT (10Dlb/hr) - #7 -
#17
- 9. RR Pump Flow (10' lb/hr) (Computer) l #8 #18 -
#9 - #19
- Average ce=puter points B026 and B027 for Loop A and #10 #20 points B028 and B029 for Loop B. Loop B Loop A ,, j Average "' Average # ^
gs (' ) #1: Are all jet pump APs within 10% of the average % SP for their respective loops?
YES: NO: a un o se
- CHECK #2: The values of total core flow in 1. and 2. above are within 10%? YES: NO: 7 If they do differ by 10% is the derived value (1. above) higher: YES: NO: (
CHECK #3: Reactor recirculation pump flow from curve using the value of pump AP in 3. above is U for Loop A and .. for Loop B. The flow established from the curve is within 10% of the value in 4. above? Loop A - YES: NO: - ; Loop B - YES: NO: X CHECK #4: Are the values of RR Pump Flow (4. above) and RR MG Set Speed (5. above) within the 5% limits on the curve? Loop A - YES: NO: ; Loop B - YES: NO: - CHECK #5: The value of jet pump. loop flow (6. above) divided by the RR MC Set Speed (5. above) for the same loop is ' 'l > for Loop A and t .for Loop B. Are these points determined to be within the 5% limits on the curves for Loop A and Loop B? Loop A - YES: NO: e ; Loop B - YES: NO: CHECK #6: The square root of Core AP (7. above) is ' ~ < . Are the values of square root of Core AP and Core Flow (8. above) within the 5% limits on the curve? YES: / NO: IF THE ANSWER TO ANY OF THE ABOVE QUESTIONS IS N0, 0 NOTIFY THE SHIFT SUPERVISOR. Op;rator: Time : C bl Room Supervisor /Shif t Supervisor: / Cor.rol Room Supervisor Shift Supervisor Engin;ering Review: Date: NOTE: All the curves mentioned above are maintained in the Control Room.
e 1985 Evaluated Exercise Time = 1015 x ! Message Number t= 02/45 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Message For: Control Room Simulated Plant Conditions: See attached plant data and Rad Monitor Sheets . Message: * *
- THIS IS A DRILL * *
- Annunciators in the Control Room include:
Off Cas Vent Pipe High Radiation Indications in the Control include: RMP-RM-150A/B 175 mR/hr Offgas Radiation Monitor PNL-9-4 i For Controller Use Only: CONTROLLER INFORMATION: o Off Gas pre-treatment radiation monitors indicate some minor increase due-to damage to fuel cladding by debris from jet pump o Limit power reduction to 75%. EXPECTED ACTIONS:
A l
d
, - - . - , , - . . _ , _ , -,.4.. . . - - . - .
1985 Evaluated Exercise Time = 1015 Massage Number t= 02/45
)- COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 75% APRM RHR A STBY 0 0 REACTOR LEVEL 35" + NR RHR B STBY 0 0 REACTOR PRESSURE 1000 psig RHR C STBY 0 0 CORE D/P (psig) 12.5 RHR D STBY 0 0 CORE FLOW 60.7 6
CS A STBY 0 0 (10 lbm/hr) 6 OW (10 1bs/ h) CS B STBY 0 0 FEEDWATER A 3.6 HPCI STBY 0 - 0 FEEDWATER B 3.6 Drywell Pressure 16 (PSIA) MAIN STEAM A 1.8 Torus Level 0 (inches) MAIN STEAM B 1.8 Ci OPEN CLOSED MAIN STEAM C 1.8 MSIV 8 0 MAIN STEAM D 1.8 FLOW CLG WTR DP DR WTR DP PANEL 9-4 CRD A 50 (gpm) -20 (psig) 265 (psig) STATUS PRESS (psig) FLOW (gpm) CRD B Avail (gpm) 0 (psig) 0 (psig) RCIC STBY 0 0 . LEVEL PRESS SQUIB PUMPS RWCU A OPER 100 SLC 75- % 0 (psig) ON Avail RWCU B Unavail RRPA 78 % SPD MISCELLANEOUS PANELS RRPB 66 % SPD DIESEL GEN A STBY DIESEL GEN B STBY SBGT A STBY SBGT B STBY-DRYWELL COOLING NORMAL TORUS WATER TEMP 80 *F
Tima - 1015: RADIATION MONITOR DITA t= 02/45
,, AREA RADIATION MONITORS
- t
(/ STATION DESCRIPTION READING 1 Rx Bldg Fuel Pool Area (SE Sth Floor) 150 mR/hr 2 . Rx Bldg Fuel Pool Area (SE Sch Floor) 7 mR/hr 3 Rx Bldg New Fuel Area (SE Sch Floor) 0.1 mR/hr 4 Rx Bldg Rx Water Cleanup Demineralizer Area (SW 3rd Floor) 7-- 7 mR/hr 5 Rx Bldg Sludge and D$ cant Pump Area (S 2nd Floor) 1200 mR/hr* 6 Rx Bldg Neutron Monitor System Index Area (TIP Room ist Floor) 30 mR/hr 7 Rx Bldg Neutron. Monitor System Drive Mech Area (SE 1st Floor) 1 mR/hr 8 Rx Bldg Control Rod Hydraulic Equipment Area (S 1st Floor) 0.9 mR/hr 9 Rx Bldg Control Rod Hydraulic Equipment Area (N 1st Floor) 8 mR/hr 10 Rx Bldg HPCI Pump Room (SW Quad) 0.6 mR/hr 11 Rx Bldg RHR Pump Room (SW Quad) 7 mR/hr 12 Rx Bldg RHR Pump Room (NW Quad) 10 mR/hr 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 2 mR/hr 14 Rx Bldg CS Pump Room (SE Quad) 3 mR/hr 15 Turbine Bldg Turbine Front Standard 0.7 mR/hr 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.02 mR/hr 17 Turbine Bldg Turbine Bldg Basement Control Corridor 0.01 mR/hr ['
\
18 19 Turbine Bldg Turbine Bldg Rx Feed Pump Area Turbine Bldg Turbine Bldg Condensata Pump Area 2 mR/hr 0.04 mR/hr 20 Control Room Main Control Room 0.01 mR/hr 21 Grade Level Control Corridor 0.2 mR/hr Panel 9-02 Personnel Airlock Area 903 300 R/hr ! Panel 9-02. Ladder 903 to 2nd Level 290 R/hr 1 , PROCESS ~AND VENT MONITORS I PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 2.2E1 uCi/sec ERP Stack Normal Eff (RMP-RM-3A) 1.6El uCi/sec ERP Stack High Range (RMP-RM-3B) 0.0 uCi/sec Turbine Bldg Vent Eff (RMV-RM-20A) 4.lE0 TCi/sec Turbine Bldg High Range (RMV-RM-20B) 0.0 uCi/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 3.7 uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) 0.0 uCi/sec [ PANEL 9-10 Mn. Stm. Rad Monitor Ch. A2, B1 300 mR/hr 310 mR/hr Ch. A2, B2 300 mR/hr 300 mR/hr- , SJAE Off Gas Log Rad Monitor Ch. A, B 60 mR/hr 61 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.7 mR/hr 0.7 mR/hr ['~' o All other monitors display normal readings
- Alarm OS Offscale I-L._.-
e-Procedure 6.2.4.1 Page 6 of 15 Attachment "A" Date OPERATIONS - DAILY SURVEILLANCE LOG V DAILY JET PUMP OPERABILITY CHECK Do the following tests daily whenever there is recirculation flow with the reactor in the startup or run modes of operation. Checks #1 through #3 are required by Technical Specifications (refer to Page 137). All three of Checks #1 through #3 must prove unsatisfactory to declare a jet pump inoperable. Checks #4 through #6 are performed because of jet pump beam cracking at several oper-ating BWRs. It is the purpose of Checks #4 through #6 to detect significant recirculation system parformance degradation prior to beam failure to the point of jet pump disassembly. PARAMETER CHECKED (UNJTS) LOOP A l LOOP B JET PUMP AP INDICATION (%) !
- 1. Computer WTSUB (10' lb/br) JET PUMP LOOP B l JET PUMP LOOP A
- 2. Indicated Core Flow (10' lb/hr) #1 #11
- 3. RR Pu=p AP (PSID) #2 #12
- 4. RR Pump Flow (10' GPM) #3 #13 ;
- 5. RR MG Set Speed (;) l #4 #14 1
- 6. Jet Pump Flow (10" lb/hr) { #5 #15 .
- 7. Core Plate SP (PSID) NBI-DPR-95 x 30 #6 #16
- 8. Computer WT (10',1b/hr) #7 #17 j
*9. RR Pump Flow (10' lb/hr) (Computer) l #8 l #18 :
F9 l #19 {
- Average computer points B026 and B027 for Loop A and #10 l #20 points B028 and B029 for Loop B. Loop B Loop A ;
Average Average K #1: Are all jet pump APs within 10% of the average % SP for their respective loops? V YES: NO: * ' 2 ' :- CHECK #2: The values of total core flow in 1. and 2. above are within 10%? YES: NO:
- If they do differ by 10% is the derived value (1. above) higher: YES: NO: ;
CHECK #3: Reactor recirculation. pump flow from curve using the value of pump AP in 3. above is
. for Loop A and "o for Loop B. The flow established from the curve is within 10% of the value in 4. above? Loop A - YES: NO: ; Loop B - YES:
l NO: ' CHECK #4: Are the values of RR Pump Flow (4. above) and RR MG Set Speed (5. above) within the 5% limits on the curve? Loop A - YES: NO: ; Loop B - YES: 7 NO: < CHECK #5: The value of jet pump loop flow (6. above) divided by the RR MG Set Speed (5. above) for the same loop is for Loop A and for Loop B. Are these points determine to be within the 5% limits on the curves for Loop A and Loop B? Loop A - YES: ! NO: ; Loop B - YES: NO: CHECK #6: The square root of Core AP (7. above) is . Are the values of square root of Core AP and Core Flow (8. above) within the 5% limits on the curve? YES: NO: IF THE ANSWER TO ANY OF THE ABOVE QUESTIONS IS NO, NOTIFY THE SHIFT SUPERVISOR. l Operator: Time: O rol Room Supervisor / Shift Supervisor: / Control Room Supervisor Shift Supervisor Engineering Review: Date: NOTE: All the curves mentioned above are maintained in the Control Room.
( 1985 Evaluated Exercise Time = 1030 ['\ I,
. s,/.
) Message Number t= 03/00 COOPER NUCLEAR STATION DiERGENCY PREPAREDNESS EXERCISE MESSAGE Message For: Control Room Simulated Plant Conditions: See attached plant data and Rad Monitor Sheets Message: * *
- THIS IS A DRILL * *
- Annunciators in the Control Room include:
Main Steam Line high radiat' ion trip Main Steam Isolation Valves ~not full of open trip Group 1 Isolation Channel A (B) Auto Scram Trip System A (B) RFP Turbine 1A (IB) trip Recire Pump A (B) flow limit Reactor Water Level Channel A (B) Low Low Level Low Low Set Logic A or B Armed () Indications in the Control Room include: Valve position lights for Group I, II, III, VI, VII isolation valve t indicate successful isolations. Rod position indications on Panel 9-5 are shown on attached map. ( ( For Controller Use Only: CONTROLLER INFORMATION: l o Damage to cladding resulting from jet pump debris has caused steam line , radiation levels.co increase to greater than three times normal full power levels, causing a Group I isolation. The Group I isolation causes a Reactor j scram and a subsequent reactor feed pump turbine trip. l l o Reactor level transient causes Group II, III, VI and VII isolations. l Relief valves control reactor pressure; HPCI/RCIC control reactor level after transient. i o Operator Check isolations, control rod position indications. EXPECTED ACTIONS: L \s. / -
, r- - . ,---.e,,
r- 3 l 1985 Evaluated Exercisa Time = 1030 l Message Number t= 03/00 I O COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLAh~f DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 37. APRM RHR A STBY 0 0 REACTOR LEVEL -55" t WR RHR B STBY 0 0 REACTOR PRESSURE 1060 psig RHR C STBY 0 0 CORE D/P (psig) RHR D STBY 0 0 CORE FLOW 6 CS A STBY 0 0 (0 lbmM 6 FLOW (10 1bs/hr) CS B STBY 0 0 FEEDWATER A 0 HPCI OPER 1160 4250 FEEDWATER B 0 Drywell Pressure 16 (PSIA) MAIN STEAM A 0 S 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 CRD A 160 (gpm) STATUS PRESS (psig) FLOW (gpm) CRD B Avail (gpm) RCIC OPER 1160 400 LEVEL PRESS SQUIB PUMPS RWCU A Tripped 0 SLC 75 % 0 (psig) ON Avail RWCU B Tripped 0 RRPA Tripped % SPD MISCELLANEOUS PANELS RRPB Tripped % SPD DIESEL GEN A STBY DIESEL GEN B STBY SBGT A OPER p SBGT B OPER DRYWELL COOLING l TORUS WATER TEMP 80 'F l
_ ~ _ . __ _ _. Tima = 1030 RADIATION MONITOR DATA t= 03/00 AREA RADIATION MONITORS I
\s_,/ STATION DESCRIPTION READING 1 Rx Bldg Fuel Pool Area (SE Sch Floor) 149 mR/hr , 2 Rx Bldg Fuel Pool Area (SE Sth Floor) 6 mR/hr 3 Rx Bldg New Fuel Area (SE Sch Floor) 0.1 mR/hr 4 Rx Bldg Rx Water Cleanup Demineralizer Area (SW 3rd Floor) 8 mR/hr 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 1000 mR/hr*
6 Rx Bldg Neutron' Monitor System Index Area (TIP Room'Ist Floor) 30 mR/hr 7 Rx Bldg Neutron Monitor System Drive Mech Area (SE ist Floor) 1.2 mR/hr 8 Rx Bldg Control Rod Hydraulic Equipment Area (S 1st Floor) , _ 3.5 mR/hr 9 Rx Bldg Control Rod Hydraulic Equipment Area (N 1st Floor) 26 mR/hr 10 Rx Bldg HPCI Pump Room (SW Quad) 0.6 mR/hr 11 Rx Bldg RHR Pump Room (SW Quad) 8 mR/hr 4 12 Rx Bldg RHR Pump Room (NW Quad) 10 mR/hr 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 2.5 mR/hr 14 - Rx Bldg CS Pump Room (SE Quad) 3 mR/hr , 15 Turbine Bldg Turbine Front Standard 0.5 mR/hr 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.02 mR/hr 17 Turbine Bldg Turbine Bldg Basement Control Corridor 0.01 mR/hr f'T
\,,,/
18 19 Turbine Bldg Turbine Bldg Rx Feed Pump Area Turbine Bldg Turbine Bldg Condensate Pump Area 0.04 mR/hr 1 mR/hr 20 Control Room Main Control Room 0.01 mR/hr 21 Grade Level Control Corridor 0.1 mR/hr Panel 9-02 Personnel Airlock Area 903 350 R/hr Panel 9-02 Ladder 903 to 2nd Level 350 R/hr PROCESS AND VENT MONITORS PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 2.2E1 uCi/sec ERP Stack Normal Eff (RMP-RM-3A) 1.7El uCi/sec ERP Stack High Range (RMP-RM-3B) 0.0 uCi/sec Turbine Bldg Vent Eff (RMV-RM-20A) 3.9E0 uCi/sec
. Turbine Bldg High Range (RMV-RM-20B) 0.0 uCi/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 3.5 uC1/sec RW/ARW Bldg High Range (RMV-RM-30B) 0.0 uCi/sec PANEL 9-10 Mn. Stm. Rad Monitor Ch. A2, B1 1200 mR/hr 1220 mR/hr Ch. A2, B2 1250 mR/hr 1200 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 22 mR/hr 22 mR/hr ,/g Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.7 mR/hr 0.7 mR/hr \ )
o All other monitors display normal readings
- Alarm OS Offscale i
I
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01 03 05 07 09 11 13 15 17 19 21 23 25 27 29 31 33 35' 37 39 41 43 45 47 49 51 51 i LPRM Lot ation (Letter indicates TIP machine) S LPRM Location (Common location for all TIP ' ! machines) 35 l l l l QD 31 I l l IRM Locations (Letter indicates IRM channel) j~j j A SRM Locations (Letter indicates SRM channel)
- Source Locations
' jj ll l l l 07 [ l l l l Dummy Fuel Assenibly Locations _ 03 l l ! I 2 r. In la ia ?? ?c in 34 38 42 46 50
-1985. Evaluated Exercise Time - 1035 Message Number e= 03/05 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Message For: Control Room Simulated Plant Conditions: See attached plant data and Rad Monitor Sheets Message: * *
- THIS IS A DRILL *'*
- Annunciators in the Control Room include:
APRM Downscale (Intermittent) Low-Low set logic A or B armed Relief. Valve open Reactor-Building high radiation Safety or blowdown valve leaking Indications in the Control Room inclu'e:d RV-71D. F Blue Lights Off MS-TR-166 Channel 375'F RV-70A Ta11 pipe Temperature N
- Drywell temperature indications normal j For Controller Use Only:
l-j CONTROLLER INFORMATION: o Reactor Power Remains at
- 3% because 30 rods are not full in.
o Reactor. water level restored by HPCI and RCIC. o SRVs cycle normi.lly and maintain pressure. d-o Reactor Building afi rad alarm due to HPCI/ECIC steem lines. ! EXPECTED ACTIONS: } ( o Attempt to insert ccneral rods by resetting scram a.td/or man;: ally driving them in. d o Operators may elect to insert IRMs. .If so, only three will fully insert. l l L
F 1985 Evaluated Exercism Tima = 1035 Massage Number t= 03/05
,, m k COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-3 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER ___3 % APRM RnR A STBY 0 0 REACTOR LEVEL 40" + NR RHR B STBY 0 0 REACTOR PRESSURE 1000 psig RHR C STBY 0 0 CORE D/P (psig) _ _ _
RHR D STBY 0 0 CORE FLOW _ CS A STBY 0 0 (10 lbmMr) 6 FLOW (10 lbs/hr) CS B STBY 0 _ 0 FEEDWATER A 0 HPCI OPER 1100 4250 FEEDWATER B 0 Drywell Pressure 16 (PSIA) 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 CRD A 50 (gpm) STATUS PRESS (psig) FLOW (gpm) CRD B Avail (gpm) RCIC OPER 1100 400 LEVEL PRESS SQUIB PUMPS l RWCU A Tripped 0 SLC 0 (psig) ON _7L% Avail l I RWCU B Tripped 0 RRPA Tripped % SPD MISCELLANEOUS PANELS l l _RRPB Tripped % SPD DIESEL GEN A STBY DIESEL GEN B STBY SBGT A OPER q SBGT B OPER ___ DRYWELL COOLING TORUS WATER TEMP S2 *F l
c Tima = 1035 RADIATION MONITOR DATA t= 03/05
, AREA RADIATION MONITORS
( STATION DESCRIPTION READING 1 Rx Bldg Fuel Pool Area (SE Sch Floor) 150 mR/hr 2 Rx Bldg Fuel ?ool Area (SE 5th Floor) 6 mR/hr 3 Rx Bldg New Fuel Area (SE Sch Floor) 0.1 mR/hr 4 Rx Bldg Rx Water Cleanup Demineralizer Area (SW 3rd Floor) 8 mR/hr 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 10 mR/hr* 6 Rx Bldg Neutron Monitor System Index Area (TIP Rocm ist Floor) 30 mR/hr 7 Rx Bldg Neutron Monitor System Drive Mech Area (SE ist Floor) 1 mR/hr 8 Rx Bldg Control Rod Hydraulic Equipment Area (S 1st Floor) 3.5 mR/hr 9 Rx Bldg Control Rod Hydraulic Equipment Area (N 1st Floor) 27 mR/hr 10 Rx Bldg HPCl Pump Room (SW Quad) 1.8 mR/hr 11 Rx Bldg RHR Pump Room (SW Quad) 8 mR/hr 12 Rx Bldg RHR Pump Room (NW Quad) 11 mR/hr 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 8 mR/hr 14 'Rx Bldg CS Pump Room (SE Quad) 4 mR/hr 15 Turbine Bldg Turbine Front Standard 0.5 mR/hr 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.02 mR/hr 17 Turbine Bldg Turbine Bldg Basement Control Corridor 0.01 mR/hr 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 1 mR/hr Og i 19 Turbine Bldg Turbine Bldg Condensate Pump Area 0.04 mR/hr 20 Control Room Main Control Rcem 0.02 mR/hr 21 Grade Level Control Corridor 0.2 mR/hr Panel 9-02 Personnel Airlock Area 903 370 R/hr Panel 9-02 Ladder 903 to 2nd Level 380 R/hr PROCESS AND VENT MONITORS PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 2.1El uCi/sec ERP Stack Normal Eff (RMP-RM-3A) 1.7El uCi/sec ERP Stack High Range (RMP-RM-3B) 0.0 uCi/sec l Turbine Bldg Vent Eff (RMV-RM-20A) 3.8E0 uCi/sec Turbine Bldg High Range (RMV-RM-20B) 0.0 uC1/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 3.5 uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) 0.0 uCi/sec PANEL 9-10 Mn. Stm. Rad Monitor Ch. A2, B1 650 mR/hr 630 mR/hr Ch. A2, B2 630 mR/hr 640 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 21 mR/hr 21 mR/hr i jN Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.7 mR/hr 0.7 mR/hr i . \'~') o All other monitors display normal readings
- Alarm OS Offscale
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- Source Locations jy ll l lR: Dummy Fuel Assembly Locations 07 l_ l l 03 l l l i
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r- , 1985 Evaluated Exercise Time = 1045 ( Message Number t= 03/15 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Message For: Control Room Simulated Plant Conditions: See attached plant data and Rad Monitor Sheets Message: * *
- THIS IS A DRILL * *
- Annunciators in the Control Room include: '
LPRM upscale Safety or Blowdown Valve leaking Low-Low Set A or B armed Relief Valve open (Valves cycling normally) APRM Downscale (Intermittent) Indications in the Control Room include: g- s1 RV-71D, F Blue Lights Off (Intermittent) g MS-TR-166, Channel 305*F RV-76A Tailpipe temperature N- / 130*F Drywell zone Temperature All other Drywell zone temperature indications Normal For Controller Use Only: CONTROLLER INFORMATION: o Data sheets reflect initiation of.RHR in Suppression Pool cooling mode due to increasing torus temperature. o RV-70A is leaking by the seal at peaks in reactor pressure cycles, o Only two control rods have been inserted since the scram. EXPECTED ACTIONS: o Operations may elect to insert TIP-to verify "LPRM Upscale" annunciator. If so, the TIP will NOT fully insert due to blockage. This provides
-s additional indication of degraded core geometry.
s_ -) I
,c . .-
. - .. , . -. - - , - . , , . . ,~ .,
~ . , . _ . . _ . . ._ _ .. .._
I _1985 Evaluated Exercise Time = 1045
.Jessage. Number t= 03/15 3 COOPER NUCLEAR STATION I
I EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 3% APRM , RHR A SUP PL CLG 0 0 REACTOR LEVEL 40" + FR RHR B STBY 0 0 REACTOR PRESSURE 970 psig RHR C STBY 0 0 CORE D/P (psig) RHR D STBY 0 0 CORE FLOW 6 CS A STBY 0 0 (10 lbm/hr) 6 FLOW (10 1bs/hr) ! CS B -STBY 0 0 FEEDWATER A 0 HPCI OPER 1070 4250 FEEDWATER B 0 Drywell Pressure 16.3 (PSIA) MAIN STEAM A' 0 Torus Level +0.25 (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 50 (gpm) i { RCIC OPER 1070 400 LEVEL PRESS PUMPS SQUIB i RWCU A Tripped 0 SLC 75 % 0 (psig) ON Avail ; ! RWCU B Tripped 0 , l RRPA Trfpped % SPD MISCELLANEOUS PANELS i s RRPB Tripped % SPD DIESEL GEN A STBY l i DIESEL GEN B STBY f SBGT A OPER l SBGT B OPER DRYWELL COOLING TORUS WATER TEMP 88 *F ;
.1
- , - - , _ _ , . . . . ~ . - - . - - . . - . . . _ - _ . . , _ . , , _ . , . . . - , - , , ,
Time = 1045 RADIATION MONITOR DATA t= 03/15 AREA RADIATION MONITORS Q STATION DESCRIPTION READING 1 Rx Bldg Fuel Pool Area (SE Sch Floor) 150 mR/hr 2 Rx Bldg Fuel Pool Area (SE Sth Floor) b mR/hr 3 Rx Bldg New Fuel Area (SE Sch Floor) 0.1 mR/hr 4 Rx Bldg Rx Water Cleanup Demineralizer Area * (SW 3rd Floor) 8 mR/hr 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 10 mR/hr* 6 Rx Bldg Neutron Monitor System Index Area (TIP Boom ist Floor) 30 mR/hr 7 Rx Bldg Neutron Monitor System Drive Mech Area (SE 1st Floor) 1 mR/hr 8 Rx Bldg Control Rod Hydraulic Equipment Area (S 1st Floor) 4 mR/hr 9 Rx Bldg Control Rod Hydraulic Equipment Area (N 1st Floor) 30 mR/hr* 10 ,Rx Bldg HPCI Pump Room (SW Quad) 2.2 mR/hr 11 Rx Bldg RHR Pump Room (SW Quad) 9 mR/hr 12 Rx Bldg RHR Pump Room (NW Quad) 36 mR/hr* 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 10 mR/hr 14 Rx Bldg CS Pump Room (SE Quad) 5 mR/hr 15 Turbine Bldg Turbine Front Standard 0.5 mR/hr 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.02 mR/hr 17 Turbine Bldg Turbine Bldg Basement Control Corridor 0.01 mR/hr /} 18 Turbine Bldg Turbine Bldg Rx Feed Pump Arca l mR/hr ( ) 19 Turbine Bldg Turbine Bldg Condensate Pump Area 0.04 mR/hr 20 Control Room Main Control Room 0.02 mR/hr 21 Crade Level Control Corridor 0.2 mR/hr Panel 9-02 Personnel Airlock Area 903 380 R/hr Panel 9-02 Ladder 903 to 2nd Lev'el 380 R/hr PROCESS AND VENT MONITORS PANEL VBDC Rx Bldg Vent Eff (RMV-RM-40) 2.0E1 uCi/sec ERP Stack Normal Eff (RMP-RM-3A) 1.7El uCi/sec ERP Stack High Range (RMP-RM-3B) 0.0 uC1/sec Turbine Bldg Vent Eff (RMV-RM-20A) 3.7E0 uCi/sec Turbine Bldg High Range (RMV-RM-20B) 0.0 uC1/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 3.5EO uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) 0.0 uCi/sec PANEL 9-10 Mn. Stm. Rad Monitor Ch. A2, B1 630 mR/hr 630 mR/hr Ch. A2, B2 630 mR/hr 630 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 22 mR/hr 22 mR/hr gx s Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.7 mR/hr 0.7 mR/hr \
'- '] o All other monitors display normal readings
- Alarm OS Offscale
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g l t I 01 03 05 07 09 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 45 47 49 51 51 l l @ I!! LPRM Location (Letter indicates TIP machine) 43 l l j G LPRM Location (Common location for all TIP ' ' ! machines) 35 l1 ! Z) 31 I I IRM Locations (Letter indicates IRM channel) j i j i p & SRM Locations (Letter indicates SRM channel) 23 l I
,;4
$ 15 Il Source Locations jj jj l Dummy Fuel Assembly Locations 07 l' l l 03 l l li 2 6 10 14 1R 72 26 30 34 38 42 46 50
r "1985 Evaluated Exercise Time = 1045 Message Number t= 03/15 ! COOPER NUCLEAR STt. TION EMERGENCY PREPAREDNESS EXERCISE MESSAGE i t Message For: Control Room Simulated Plant Conditions: Message: * *
- THIS IS A DRILL * *
- IRM indication is as follows:
40 os Range 8 I 1 I- . I l < For Controller Use Only: CONTROLLER INFORMATION: !. -Deliver this message only if IRMs have been inserted and if operators sub-l sequently check IRM indication (Only 3 of 8 IRMs were inserted due to l blockage by jet pump debris). ., i l l i i EXPECTED ACTIONS: i
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i l- .
r 1985 Evaluated Exercise Time = 1050 Message Number t= 03/20 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Message For: Emergency Director a Simulated Plant Conditions: Message: * *
- THIS IS A DRILL * * * ,
A Site Area Emergency should be declared in accordance with EPIP 5.7.1, EAL 2.5.1; Degraded core with possible loss of coolable geometry. i 1 For Controller Use Only: i CONTROLLER INFORMATION: i Deliver this message only if the decision has not already been made to upgrade to a General Emergency. 1 { EXPECTED ACTIONS: V 4 , l s i 4 l I n j.
rj i
\,_,) 1985 Evaluated Exercise Time = 1100 Message Number 25 t= 03/30 COOPER NUCLEAR' STATION EdERGENCY PREPAREDNESS EXERCISE MESSAGE Message For: Control Room Simulated Plant Conditions: See attached Plant Data sheets and Rad Monitor Sheets Message: * *
- THIS IS A DRILL * *
- Annunciators in the Control Room include:
APRM Downscale HFCI Turbine Trip HPCI Isolation Signal Logic A/B Initiate HPCI Steam Line Differential Pressure Hi Main Steam LIne Steam Leak, Augmented Radwaste Building
)
~J Indications in the Control Room include:
MS-TR-166 Ch. 00 275* Valves and Caud . Lights For Controller Use Only: CONTROLLER INFORMATION: s.
- 1) The reactor is suberitical even through 13 rods are still not full-in.
s, s 'i) HPCI turbine steam supply line has isolated due to rupture line of isolation valve in HPCI Pump Room, h EXPECTED ACTIONS:
- 1) Verify HPCI turbine isolation.
i O- . d . _Y _
. _ . - - , _ - . ~ - _ . - - - . - . . . . . -
r--
+_
1985 Evalutted Exercisa Time = 1100 Missage Number 25 t= 03/30 O COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 s STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 0% APRM' RHR A SUP PL CLG 100 7,000 REACTOR LEVEL 35" + NR RHR B AVAIL 0 0 REACTOR PRESSURE 940 psig RHR C SUP PL CLG 100 7,000 CORE D/P (psig) 2.8 RHR D AVAIL 0 0 CORE FLOW 7.1 CS A AVAIL 0 (
- 0 6 FLOW (10 1bs/hr)
CS B AVAIL 0 0 FEEDWATER A 0 HPCI ISOLATED 1070 4250 FEEDWATER B 0 Dryvell Pressure 16.3 (PSIA) MAIN STEAM A 0 i Torus Level +0.25 (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) STATUS PRESS (psig) FLOW (gpm) CRD B 50 (gpm) RCIC OPER 1040 400 LEVEL PRESS SQUIB PUMPS RWCU A Tripped 0 SLC 75 % 0 (psig) ON Avail 1 RUCU B Tripped 0 RRPA Tripped % SPD MISCELLANEOUS PANELS RRPB Tripped % SPD DIESEL GEN A STBY DIESEL GEN B STBY > SBGT A OPER SBGI B OPER O () DRYWELL COOLING NORMAL l TORUS WATER TEMP 88 *F r
-~ . ._
~ 'i Time = 1100 RADIATION MONITOR DATA t= 03/30 AREA RADIATION MONITORS
- (~
g ,
~ STATION DESCRIPTION -t READING 1 Rx Bldg Fuel Fool Area (SE Sch Ffoor) 150 mR/hr 2.. Rx Bldg Fuel Pool Area (SE Sch Floor) 6 mR/hr 3 Rx Bldg New Fuel Area (SE-5th Floor) 0.1 mR/hr 4 Rx Bldg Rx Water Cleanup Demineralizer Area (SW 3rd Floor) 8 mR/hr 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 7 mR/hr*
6N Rx Bldg Neutron Monitor System Index Area (TIP Room ist Floor) 30 mR/hr 7 Rx Bldg . Neutron Monitor System Drive Mech Area (SE 1st Floor) 1 mR/hr 8, Rx Bldg Control Rod Hydraulic Equipment Area
'), 's (S 1st Floor) 5 mR/hr
/' l9 Rx Bldg Control Rod Hydraulic Equipment Area (N 1st Floor) 33 mR/hr*
10 Rx Bldg HPCI Pump Room (SW Qu'd) a x, 2.8 mR/hr 11 Rx Bldg RHR Fump Room (SW Quad) s 10 mR/hr 12 Rx Bldg RHR Pump Room (NW Quad) 40 mR/hr* 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 13 mR/hr 14 Rx Bldg CS Pump Room (SE Quad) 6 mR/hr 15 Turbine Bldg Turbine Front Standard . 0.4 mR/hr 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.02 mR/hr l[, 17. 17 Turbine Bldg Turbine Bldg Basement Control '
< Corridor O.01 mR/hr
[ 18' , Turbine Bldg Turbine Bldg Rx Feed Pump Area 0.5 mR/hr 19 Turbine Bldg Turbine Bldg Condensate Pump Area
' 0.04 mR/hr
- 20 Control Room Main Control Room 21 0.01 mR/hr Grade Level Control Corridor 0.1 mR/hr
- Panel 9-02 Personnel Airlock Area 903 390 R/hr Panel 9-02; Ladder ~903'to 2nd Level 385 R/hr
~
4
'PNCESS AND VENT MONITORS .
PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) , 2.1El uCi/sec ERP Stack Normal Eff (RMP-RM-3A) l.7El uCi/sec ERP Stack High Range (RMP-RM-3B) 0.0 uCi/sec Turbine Bldg Vent Eff (RMV-RM-20A) 3.6E0 uCi/sec Turbine Bldg High Range (RMV-RM-203) 0.0 uCi/sec
, RW/ARW Bldg Combined Eff (RMV-RM-30A) 3.4E0 uCi/sec RW/AR{31,dgHighRange(RMV-RM-30B) 0.0 uCi/sec PANEL 9-10 Mn. Sem. Rad Monitor Ch. A2, B1 620 mR/hr 620 mR/hr Ch. A2, B2 620 mR/hr 620 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 12.mR/hr 22 mR/hr
<~ Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.7 mR/hr 0.7 mR/hr o All other monitors display normal readings
- Alarm OS Offscale ,
s-
't 4
_~ , - L m m_ , -, ,
I 1 l 1985 Evaluated Exercise Time = 1115 Message Number 26 t= 03/45 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Message For: Control Room Simulated Plant-Conditions: See attached Plant Data and Rad Monitor Sheets Message: * *
- THI'S IS A DRILL * *
- Annunciators in the Control Room include:
o Relief Valve Open (Valves cycling normally) o Safety or Blowdown Valve Leaking Indications in the C'ntrol o Room include: o MS-TR-166 Ch. 00 305' RY-70A tailpipe temperature o 135* Drywell Zone temperature, o All other drywell zone temperatures normal.
. Au. % . gaus us rs Amt .4 . m q-s O
For Controller Use Only: . CONTROLLER INFORMATION: All control rods are fully inserted. EXPECTED ACTIONS: v.) I L
. - _ . _ , - . . . , . ~ - . . - . . - , . . - - -.. . . . . - - . - -
. - - . . - - ~ ~ . - . - - - - - - . - - -
1985 Evaluated Exercise Tica.= _ 1115 Massage Number 26 t= 03/45 COOPER NUCLEAR STATION
\
EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5
- STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 40R3 IRM RHR A SUP PL CLG 100 7,000 REACTOR LEVEL 34" + NR RHR B AVAIL 0 0 REACTOR PRESSURE 980 psig RHR C SUP PL CLG 100 7,000 CORE D/P (psig) 2.8 RHR D AVAIL 0 0 CORE FLOW 7.1 .
CS A AVAIL 0 0 (
- 6 FLOW (10 1bs/hr)
CS B AVAIL 0 0 FEEDWATER A 0 HPCI ISOLATE _D 0 0 FEEDWATER B 0 . . . Dryvell Pressure 16.3 (PSIA) MAIN STEAM A 0 Torus Level +0.25 (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 (gpa) STATUS PRESS (psig) FLOW (gpm) CRD B 50 (gpm) RCIC OPER 1080 400 LEVEL' PRESS SQUIB PUMPS RWCU A Tripped 0 SLC 75 % 0 (psig) ON Avail RUCU B Tripped 0 RRPA 0 % SPD MISCELLANEOUS PANELS RRPB 0 % SPD DIESEL GEN A STBY DIESEL GEN B STBY SBGT A OPER SBGT B OPER 1 O ( DRYWELL COOLING NORMAL , j TORUS WATER TEMP 87 *F l l i
f Tina = 1115 RADIATION MONITOR DATA t = 03/45 p-s AREA RADIATION MONITORS l ) y/ STATION DESCRIPTION READING 1 Rx Bldg Fuel Pool Area (SE Sch Floor) 150 mR/hr 2 Rx Bldg Fuel Pool Area (SE Sch Floor) 6 mR/hr 3 Rx Bldg New Fuel Area (SE 5th Floor) 0.2 mR/hr 4 Rx Bldg Rx Water Cleanup Demineralizer Area (SW 3rd Floor) 8 mR/hr 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 6 mR/hr 6 Rx Bldg Neutron Monitor System Index Area (TIP Room ist Floor) 31 mR/hr 7 Rx Bldg Neutron Monitor System Drive Mech Area (SE 1st Floor) 1 mR/hr 8 Rx Bldg Control Rod Hydraulic Equipment Area (S 1st Floor) 6 mR/hr* 9 Rx Bldg Control Rod Hydraulic Equipment Area (N 1st Floor) 35 mR/hr*. 10 Rx Bldg HPCI Pump Room (SW Quad) _,3 . 4 mR/hr 11 Rx Bldg RHR Pump Room (SW Quad) .2 mR/hr 12 Rx Bldg RHR Pump Room (NW Quad) 42 mR/hr* 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 16 mR/hr 14 Rx Bldg CS Pump Room (SE Quad) 7 mR/hr 15 Turbine Bldg Turbine Front Standard 0.3 mR/hr 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.02 mR/hr 17 Turbine Bldg Turbine Bldg Basement Control Corridor 0.01 mR/hr ('"'\, 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 0.5 mR/hr ( ,,/ 19 Turbine Bldg Turbine Bldg Condensate Pump Area 0.04 mR/hr
.0 Control Room Main Control Room 0.01 mR/hr
't Grade Level Control Corridor 0.1 mR/hr Panel 9-02 Personnel Airlock. Area 903 390 R/hr Panel 9-02 Ladder 903 to 2nd Level 385 R/hr PROCESS AND VENT MONITORS PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 2.0E1 uCi/sec ERP Stack Normal Eff (RMP-RM-3A) 1.8E1 uCi/sec ERP Stack High Range (RMP-RM-3B) 0.0 uCi/sec Turbine Bldg Vent Eff (RMV-RM-20A) 3.6E0 uCi/sec Turbine Bldg High Range (RMV-RM-20B) 0.0 uCi/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 3.4E0 uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) 0.0 uCi/sec PANEL 9-10 Mn. Stm. Rad Monitor Ch. A2, B1 620 mR/hr 620 mR/hr Ch. A2, B2 620 mR/hr 620 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 22 mR/hr 22 mR/hr gN Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.7 mR/hr 0.7 mR/hr
( ) o All other monitors display normal readings
- Alarm OS Offscale
~1985' Evaluated Exercise' Time = 1130 Message Number 27 c= 04/00 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Message For: Control Rdom Simulated Plant Conditions: See attached Plant' Data and Rad Monitoring Sheets Message: * *
- THIS IS A DRILL * * *
, Annunciators in the Codtrol Room include: o Safety or Blowdown Valve Leaking o High Drywell Pressure o Diesel Generator Trouble (Board "C") Indications in the Control Room include: MS-TR-166 Ch. 00 450' RV-70A tailpipe temperature For Controller Use Only: CONTROLLER INFORMATION:
- 1) Safety valve RV-70A has failed open.After an initial drop. reactor level will be maintained by RCIC.
- 2) Drywell temperature pressure and radiation levels are all increasing rapidly.
- 3) "B " Emergency Diesel Generator failed to start on high drywell pressure. A team should be sent to investigate.
EXPECTED ACTIONS:
- 1) A General Emergency should be declared.
v
1985 Evalustad Exerciss Tiz = 1130 Massage Number 28 t= 04/00 COOPER NUCLEAR STATION ( EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 - STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 30R2 IRM RHR A LPCI 235 MIN FLOW -REACTOR LEVEL 25" + NR RHR B LPCI 235 MIN FLOW - REACTOR PRESSURE 980 psig RER C LPCI 235 MIN FLOW CORE D/P (psig) 2.8 4 RHR D LPCI 235 MIN FLOW CORE FLOW 7.1 CS A OP 250 MIN FLOW FLOW (10 lbs/hr) CS B OP 250 MIN FLOW FEEDWATER A 0 HPCI ISOLATED 0 0 FEEDWATER B 0 < Drywell' Pressure 35 (PSIA) 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 2 FLOW I PANEL 9-4 CRD A 50 (gpm) STATUS -PRESS (psig) FLOW (gpa) CRD B AVAIL (gpm). RCIC OPER 1000 400 LEVEL PRESS SQUIB PUMPS 4- RWCU A Tripped 0 SLC 75 % 0 (psig) ON Avail RWCU B Tripped 0 RRPA 0 % SPD MISCELLANEOUS PANELS RRPB- 0 % SPD DIESEL CEN A OP DIESEL GEN B 0FF i SBGT A OPER SBGT B OPER O(- DRYWELL COOLING NORMAL t TORUS WATER TEMP 89 *F
e-Time = '1130'
' RADIATION MONITOR DATA t= 04/00 AREA RADIATION MONITORS
) _ STATION DESCRIPTION READING 11 Rx Bldg Fuel Pool Area (SE Sch Floor) 150 mR/hr 2 Rx Bldg Fuel Fool Area (SE Sch Floor) 82 mR/hr*
3 Rx Bldg New Fuel Area (SE Sch Floor) 43 mR/hr* 4 Rx Bldg Rx Water Cleanup Demineralizer Area (SW 3rd Floor) 48 mR/hr 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 13 mR/hr* 6 Rx Bldg Neutron Monitor System Index Area (TIP Room ist Floor) 75 mR/hr 7 Rx Bldg Neutron Monitor System Drive Mech Area (SE ist Floor) 70 mR/hr 8 Rx Bldg Control Rod Hydraulic-Equipment Area (S ist' Floor) 65 mR/hr*
- 9. R=. Bldg Control Rod Hydraulic Equipment Area (N ist Floor) 64 mR/hr*
10 Rx Bldg EPCI Pump Room (SW Quad) __,9 5 mR/hr 11 Rx Bldg RHR Pump Room (SW Quad) 78 mR/hr 12 Rx Bldg RHR Pump Room (NW Quad) 84 mR/hr* 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 72 mR/hr 14 Rx Bldg CS Pump Room (SE Quad) 81 mR/hr.
.15 Turbine Bldg Turbine Front Standard 0.3 mR/hr 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.02 mR/hr 17 Turbine Bldg Turbine Bldg Basement Control .
' Corridor 0.01 mR/hr 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 0.5 mR/hr 19 Turbine Bldg Turbine Bldg Condensate Pump Area 0.04 mR/hr 20 Control Room Main Control Room 0.01 mR/hr 21 Grade Level Control Corridor 0.1 mR/hr Panel 9-02 Personnel Airlock Area 903 2.6E3 R/hr Panel 9-02 Ladder 903 to 2nd-Level 2.7E3 R/hr PROCESS AND VENT MONITORS PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 1.9El uCi/sec ERP Stack Normal Eff (RMP-RM-3A). 1.8E1 uCi/sec ERP. Stack High Range (RMP-RM-3B) 0.0 uCi/sec-Turbine Bldg Vent Eff (RMV-RM-20A) 3.7E0 uCi/sec Turbine Bldg High Range (RMV-RM-20B) 0.0 uCi/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 3.4E0 uCi/sec RW/ARW Bldg High Range (RMV-RM-308) 0.0 uCi/sec PANEL 9-10 Mn. Stm. Rad Monitor Ch. A2, B1 620 mR/hr 620 mR/hrf Ch. A2, B2 620 mR/hr 620 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 22 mR/hr 22 mR/hr Rx Bldg Vent Ind/ Trip Unit.Ch. A, B 0.8 mR/hr 0.8 mR/hr o All other monitors display normal readings
- Alarm OS Offscale L_.,----__-_.~_--____ . _ . - . - - , _ _
r-Tima = 1143 RADIATION MONITOR DATA t" 04/13 AREA RADIATION MONITORS O STATION DESCRIPTION READING 1 Rx Bldg Fuel Fool Area (SE Sch Floor) 150 mR/hr 2 Rx Bldg Fuel Fool Area (SE Sch Floor) OS mR/hr* 3 Rx Bldg New Fuel Area (SE Sch Floor) OS mR/hr* 4 Rx Bldg Rx Water Cleanup Demineralizer Area (SW 3rd Floor) OS mR/hr* 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 300 mR/hr* 6 Rx Bldg Neutron Monitor System Index Area (TIP Room ist Floor) 116 mR/hr* 7 Rx Bldg Neutron Monitor System Drive Mech Area (SE 1st Floor) OS mR/hr* 8 Rx Bldg Control. Rod Hydraulic Equipment Area (S ist Floor) OS mR/hr* 9 Rx Bldg Control Rod Hydraulic Equipment Area (N ist Floor) OS mR/hr* 10 Rx Bldg HPCI Pump Room (SW Quad) OS mR/hr* 11 Rx Bldg RHR Pump Room (SW Quad) OS mR/hr 12 Rx Bldg RHR Pump Room (NW Quad). OS mR/hr* 13 Rx Bldg RCIC/CS Pump Room (NE Quad) OS mR/hr* 14 Rx Bldg CS Pump Room (SE Quad) OS mR/hr* 15 Turbine Bldg Turbine Front Standard OS mR/hr* 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.3 mR/hr 17 Turbine Bldg Turbine Bldg Basement Control Corridor . 0.01 mR/hr 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 0.4 mR/hr s, 19 Turbine Bldg Turbine Bldg Condensate Pump Area 0.04 mR/hr 20 Control Room Main Control Room 0.01 mR/hr 21 Grade Level Control Corridor 0.L mR/hr Panel 9-02 Personnel Airlock Area 903 1.4E4 R/hr Panel 9-02 Ladder 903 to 2nd Level . 1.3E4 R/hr PROCESS AND VENT MONITORS PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 1.9El uCi/sec ERP Stack Normal Eff (m4P-RM-3A) 1.8E1 uCi/sec ERP Stack High Range (RMP-RM-3B) 0.0 uC1/sec Turbine Bldg Vent Elf (RMV-RM-20A) 3.6E0 uCi/sec Turbine Bldg High Range (RMV-RM-20B) 0.0 uCi/sec RW/ARW Bldg Combined Eff (RMV-RH-30A) 3.4E0 uCi/sec RW/ARW Bldg High Eange (RMV-RM-30B) 0.0 uC1/sec PANEL 9-10 Mn. Stm. Rad Monitor Ch. A2, B1 620 mR/hr 620 mR/hr Ch. A2, B2 620 mR/hr 620 mR/hr SJAE'Off Gas Log Rad Monitor Ch. A, B 22 mR/hr 22 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.7 mR/hr 0.7 mR/hr o All other monitors display normal readings
- Alarm OS Offscale
r-1985 Evaluated Exercise Time = 1145 Message Number 29 t= 04/15 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Message For: Shift Supervisor Simulated Plant Conditions: Message: * *
- THIS IS A DRILL * * * ,
Direct that a post-accident reactor coolant sample be drawn and analyzed. For Controller Use Only: CONTROLLER INFO'IMATION:' Deliver this message only if a post-accident reactor coolant sample has not c1 ready been requested. l l EXPECTED ACTIONS: O w gwy y -P-=.qu *w gr11-my v--- y -ei vt=y--Ww w --mv,7 -=-- --qg------w--------p9--F--w y- -- yw%eev - %m--- - m ye----,wd w + +we--e- ec -wa- =m a =ewn-wwww-r-w-er e e
1985 Evaluated Exercise ' Time = 1145 Message Number 30 t= 04/15 N/ COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE
- Message For
- OSC Teams Investigating Diesel Generator "B" l
Simulated Plant Conditions: Message: * *
- THIS IS A DRILL * * *
(This message will contain information indicating that an improper i vilve line-up on Diesel Generator "B" fuel oil system is the cause 4 of the Auto Start Failure) i i For Controller Use Only: CONTROLLER INFORMATION: l Deliver this message when team arrives to investigate Diesel Generator-
! "B" Auto Start Failure.
EXPECTED ACTIONS: i i l t i
\
i l l l L.
r: 1985 Evaluated Exercise Time = 1145
. Message Number 31 t= 04/15 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Message For: Control Room Simulated Plant Conditions: See attached plant data and Rad Monitor Sheets Message: * *
- THIS IS A DRILL * *
- O For Controller Use Only: -
CONTROLLER INFORMATION: i If the Control Room attempts to initiate Containment Spray, i valve resia will fail to open. All attempts to initiate spray will be unsuccessful until 1445 (07/45). i EXPECTED ACTIONS: i l Declare a General Emergency (Loss of two out of three fission l product barriers, with potential for loss of the third.) J l 2
. _ . . . _ _ _ . . _ . - - . . _ _ _ _ _ _ _ _ _ _ _ . _ . . _ . . ~ . _ . . _ . . . . _ _ . _ . _ , . ~ . . . . _ _
r 1985 Evaluated Exercisa Tims = 1145 Massage Number 31 t= 04/15 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PAhEL9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER- 20R2 IRM RHR A SUP PL CLG 100 7000 REACTOR LEVEL 34" + NR RHR B SUP PL CLG 100 7000 REACTOR PRESSURE 850 psig RHR C LPCI 235 MIN FLOW CORE D/P (psig) 2.8 RHR D LPCI 235 MIN FLOW CORE FLOW 7.1 . CS A OP 250 MIN FLOW ( ' # 6 FLOW (101bs/hr) CS B OP 250 MIN FLOW FEEDWATER A 0 HPCI ISOLATED 0 0 FEEDWATER B 0 Drywell Pressure 50 (PSIA) MAIN STEAM A 0 Torus Level +0.4 (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 4pe) CRD B AVAIL (gps) RCIC OPER 950 400 LENL PRESS SQUIB PUMPS RWCU A Tripped 0 SLC 75 % 0 (psig) ON Avail RWCU B Tripped 0 RRPA 0 % SPD MISCELLANEOUS PANELS RRPB 0 % SPD DIESEL GEN A OP DIESEL GEN B 0FF SBGT A OP SBGT B OP DRYWELL COOLING NORMAL TORUS WATER TEMP 100 *F
r-Tima = 1145 , RADIATION MONITOR DATA t = 14WI AREA RADIATION MONITORS STATION DESCRIPTION READING-1 Rx Bldg Fuel Pool Area (SE Sch Floor) 151 mR/hr 2 Rx Bldg Fuel Pool Area (SE Sth Floor) OS mR/hr* 3 Rx Bldg New Fuel Area (SE Sch Floor) OS mR/hr* 4 Rx Bldg Rx Water Cleanup Demineralizer Area (SW 3rd Floor) OS mR/hr* 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 305 mR/hr* 6 Rx Bldg Neutron Monitor System Index Area (TIP Room ist Floor) mR/hr* 7 Rx Bldg Neutron Monitor System Drive Mech Area (SE 1st Floor) OS mR/hr* 8 Rx Bldg Control Rod Hydraulic Equipment Area (S 1st Floor) OS mR/hr* 9 Rx Bldg Control Rod Hydraulic Equipment Area (N ist Floor) OS mR/hr* 10 Rx Bldg HPCI Pump Room (SW Quad) OS mR/hr* 11 Rx Bldg RHR Pump Room (SW Quad) OS mR/hr* 12 Rx Bldg RHR Pump Room (NW Quad) OS mR/hr* 13 Rx Bldg RCIC/CS Pump Room (NE Quad) OS mR/hr* 14 Rx Bldg CS Pump Room (SE Quad) OS mR/hr* , 15 Turbine Bldg Turbine Front Standard
- 0.2 mR/hr 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.02 mR/hr 17 Turbine Bldg Turbine Bldg Basement Control Corridor 0.01 mR/hr 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area C.3 mR/hr
~
19 . Turbine Bldg Turbine Bldg Condensate Pump Area 0.04 mR/hr 20 Control Room Main Control Room 0.01 mR/hr 21 Grade Level Control Corridor 0.1 mR/hr Panel 9-02 Personnel Airlock Area 903 3.2E4 R/hr Panel 9-02 Ladder 903 to'2nd Level 3.1E4 R/hr PROCESS AND VENT MONITORS PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 1.9El uCi/sec ERP Stack Normal Eff (RMP-RM-3A) 1.8E1 uCi/sec ERP Stack High Range (RMP-RM-3B) 0.0 uCi/sec-Turbine Bldg Vent Eff (RMV-RM-20A) 3.7E0 uCi/sec Turbine Bldg High Range (RMV-RM-20B) 0.0 uCi/sec. RW/ARW Bldg Combined Eff (RMV-RM-30A) , 3.4E0 uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) 0.0 uci/sec PANEL 9-10 Mn. Stm. Rad Monitor Ch. A2, B1 620 mR/hr 620 mR/hr. Ch. A2, B2 620 mR/hr 620 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 22 mR/hr 22 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.7 mR/hr 0.7 mR/hr o All other monitors display normal readings
- Alarm-OS Offscale i
k
. _ - . . . - _ . . _ . _ . -_ _ _ = _ , . ... _ _ _ . . _
i j' 1985 Evaluated Exercise Time'= 1145 Message Number 32 t= 04/15 2 4 COOPER NUCLEAR STATION , EMERGENCY PREPAREDNESS EXERCISE MESSAGE !. i I \ ( , Message For: Contro-1 Room ' ] Simulated Plant Cond[tions: Message: * *
- THIS IS A DRILL * * *
! Containment spray Valve Fosis indicates Closed . I i i i For Controller Use Only: CONTROLLER INFORMATION: i Deliver only if operators attempt to initiate drywell spray. P , .I ' r t
- l. '
i EXPECTED ACTIONS: , Operators to investigate cause for valve not opening. ~ I I
. . , . . _ . - . . . , _ _ _ . _ - - _ _ _ . - - ._,..__,__...._._._._._--.._._____._____.-...,...,_._.____..J
. -_. - . ~. . ~ . . . . .. - - - . .~ - - .- _ -- -.
4 t i 1985 Evaluated Exercise Time = 1200 Message Number 33 t= 04/30 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE i I. Message For: Control Room Simulated Plant Conditions: See attached plant data and Rad Monitor Sheets l Message: * *
- THIS IS A DRILL * *
- l l (This message will contain information that the auto transformer, d
supplying power to the EOF, is out of service.) l' I-1 f i ! For Controller Use Only: - CONTROLLER INFORMATION: I
- The EOF has sustained a total loss of electrical power.
4 l EXPECTED ACTIONS: I
1985 Evaluated Exerciss Tima = 1200 Massage Number 33 t= 04/30 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTrd POWER 50R1 IRM RHR A SUP PL CLG 100 7000 REACTOR LEVEL 35" + NR RHR B SUP PL CLG 100 7000 REACTOR PRESSURE 800 psig RHR C LPCI 235 MIN FLOW CORE D/P (psig) 2.8 RHR D LPCI 235 MIN FLOW CORE. FLOW 7.1 , CS A OP 250 MIN FLOW 6 FLOW (10 1bs/hr) CS B OP 250 MIN FIAW FEEDWATER A 0 HPCI ISOLATED 0 0 FEEDWATER B 0 Drywell Pressure 52 (PSIA) MAIN STEAM A 0 Torus Level +0.5 (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) I RCIC OPER 900 400 LEVEL PRESS EQUIB PUMPS i i RWCU A Tripped 0 SLC 75 % 0 (psig) ON Avail . j RWCU B Tripped 0 RRPA 0 % SPD MISCELLANEOUS PANELS RRPB 0 % SPD DIESEL GEN A OP , DIESEL GEN B 0FF i SBGT A OP l SBGT B OP DRYWELL COOLING NORMAL TORUS WATER TEMP 93 *F l , . - . - . -
Timm = 1200 j RADIATION MONITOR DATA t = 04/30 1 1 l 7\ AREA RADIATION MONITORS STATION DESCRIPTION READING 1 Rx Bldg Fuel Fool Area (SE Sth Floor) 151 mR/hr 2 Rx Bldg Fuel Pool Area (SE Sch Floor) US mR/hr 3 Rx Bldg New Fuel Area (SE Sth Floor) OS mR/hr 4 Rx Bldg Rx Water Cleanup Demineralizer Area (SW 3rd Floor) OS mR/hr 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 307 mR/hr 6 Rx Bldg Neutron Monitor System Index Area (TIP Room 1st Floor) mR/hr 7 Rx Bldg Neutron Monitor System Drive Mech Area (SE 1st Floor) OS mR/hr 8 Rx Bldg Control Rod Hydraulic Equipment Area (S ist Floor) OS mR/hr 9 Rx Bldg Control Rod Hydraulic Equipment Area (N 1st Floor) OS mR/hr 10 Rx Bldg HPCI Pump Room (SW Quad) OS mR/hr 11 Rx Bldg RHR Pump Room (SW Quad) OS mR/hr 12 Rx Bldg RHR Pump Room (NW Quad) OS mR/hr 13 Rx Bldg RCIC/CS Pump Room (NE Quad) OS mR/hr 14 Rx Eldg CS Pump Room (SE Quad) OS mR/hr 15 Turbine Bldg Turbine Front Standard 0.2 mR/hr 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.02 mR/hr 17 Turbine Bldg Turbine Bldg Basement Control 7 ~s Corridor 0.02 mR/hr
) 18 Turbine Bldg Turbine Bldg Rx Feed Pump, Area
( 0.3 mR/hr \s_ / 19 Turbine Bldg Turbine Bldg' Condensate Pump Area 0.03 mR/hr 20 Control Room Main Control Room 0.02 mR/hr 21 Grade Level Control Corridor 0.1 mR/hr Panel 9-02 Personnel Airlock Area 903 3.2E4 R/hr Panel 9-02 Ladder 903 to 2nd Level 3.2E4 R/hr PROCESS AND VENT MONITORS PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 1.9El uCi/sec ERP Stack Normal Eff (RMP-RM-3A) 1.8E1 uCi/sec ERP Stack High Range (RMP-RM-3B) 0.0 uCi/sec Turbine Bldg Vent Eff (RMV-RM-20A) 3.6 uCi/sec Turbine Bldg High Range (RMV-RM-20B) 0.0 uCi/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 3.4E0 uC1/sec RW/ARW Bldg High Range (RMV-RM-30B) 0.0 uC1/sec PANEL 9-10 Mn. Stm. Rad Monitor Ch. A2, B1 620 mR/hr 619 mR/hr Ch. A2, B2 619 mR/hr 619 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 22 mR/hr 22 mR/hr ('~ Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.7 mR/hr 0.7 mR/hr \ _/ s o All other monitors display normal readings
- Alarm OS Offscale e
a 1985 Evaluated Exercise Time = 1.0 0 l' ge Number 34 t= 04/30 V-COOPER NUCLEAR STATION ., i EMERGENCY PREPAREDNESS EXERCISE MESSAGE 4 Massage For: Emergency Operations Facility Sisulated Plant Conditions: Massage: * *
- THIS IS A DRILL * *
- t The EOF has lost all electrical -power.
1 7 i J i e 4 a
- For Controller Use Only
I l CONTROLLER INFORMATION: i f i
- EXPECTED ACTIONS
l l
- 1. Transfer EOF functions to the TSC until the alternate facility can be activiated.
. Activiate the alternate EOF, and move operations to that facility..
G' i
. ,__ .-. _ _ _ . . . . . . _ . . . - . . , ,, . - . , . . . _ . . , _ , , _ . _ . . . - _ . _ _ . . - ,. . . . . . _ , _ , , , , . . .._.. ~,.- . . . . . _ _
i 1985 Evalustad Exercisa Tima = 1215 Massage Number 36 t= 04/45 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA l. PAhEL9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 40R1 IRM 4 RHR A SUP PL CLG 100 7000 REACTOR LEVEL 35" + NR ! RHR B SUP PL CLC 100 7000 REACTOR PRESSURE 750 psig ) RHR C LPCI 235 MIN FLOW CORE D/P (psig) 2.8 RHR D LPCI 235 MIN FLOW CORE FLOW 7.1 i CS A OP 250 MIN FLOW (10 lba/hr) FLOW (10 lbs/hr) CS B OP 250 MIN FLOW FEEDWATER A 0 HPCI I_SOLATEL 0 0 - FEEDWATER B 0 Drywell Pressure 52 (PSIA) MAIN STEAM A 0 i Torus Level +0.6 (inches) MAIN STEAM B 0 ,
, OPEN CI OSED MAIN STEAM C 0
- MSIV 0 8 MAIN STEAM D -0 1
{ FLOW e
- PANEL 9-4 CRD A 50 (gpm)
STATUS PRESS (psig) FLOW (r,pm) CRD B AVAIL (gpa)
- RCIC OPER 850 , '.00 LEVEL PRESS SQUIB ~ PUMPS i
RWCU A Tripped 0 SLC 75 % 0 (psig) ON Avail RWCU B Tripped 0 i ! RRPA 0 % SPD MISCELLANEOUS PANELS k RRPB 0 % SPD DIESEL GEN A OP f DIESEL GEN B OP SBCT A OP
- - SBGT B OP
! DRYWELL COOLING NORMAL TORUS WATER TEMP 93 *F I i
Time = 1215 RADIATION MONITOR DATA t= 04/45 __
,-~ AREA RADIATION MONITORS
\m,/
) STATION DESCRIPTION READING 1 Rx Bldg Fuel Pool Area (SE Sch Floor) 150 mR/hr 2 Rx Bldg Fuel Poel Area (SE Sch Floor) OS mR/hr 3 Rx Bldg New Fuel Area (SE Sch Floor) OS mR/hr 4 Rx Bldg Rx Water Cleanup Demineralizer Area (SW 3rd Floor) OS mR/hr 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 307 mR/hr 6 Rx Bldg Neutron Monitor System Index Area (TIP Room ist Floor) mR/hr 7 Rx Bldg Neutron Monitor System Drive Mech Area -
(SE 1st Floor) OS mR/hr 8 Rx Bldg Control Rod Hydraulic Equipment Area (S 1st Floor) OS mR/hr 9 Rx Bldg Control Rod Hydraulic Equipment Area (N 1st Floor) OS mR/hr 10 Rx Bldg HPCI Pump Room (SW Quad) OS mR/hr 11 Rx Bldg RHR Pump Room (SU Quad) OS mR/hr 12 Rx Bldg RHR Pump Room (NW Quad) OS mR/hr 13 Rx Bldg RCIC/CS Pump Room (NE Quad) OS mR/hr 14 Rx Bldg CS Pump Room (SE Quad) OS mR/hr 15 Turbine Bldg Turbine Front Standard 0.2 mR/hr 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.02 mR/hr 17 Turbine Bldg Turbine Bldg Basement Control [(-'} 18 19 urbi e Bldg Turbine Bldg Rx Feed Pump Area Turbine Bldg Turbine Bldg Condensate Pump Area b3 mR/ r 0.03 mR/hr 20 Control Room Main Control Room 0.02 mR/hr 21 Grade Level Control Corridor 0.1 mR/hr Panel 9-02 Personael Airlock Area 903 3.2E4 R/hr Panel 9-02 Ladder 903 to 2nd Level 3.2E4 R/hr PROCESS AND VENT MONITORS PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 1.8E1 uCi/sec ERP Stack Normal Eff (RMP-RM-3A) 1.9El uC1/sec ERP Stack High Range (RMP-RM-3B) 0.0 uci/see Turbine Bldg Vent Eff (RMV-RM-20A) 3.6E0 uCi/sec Turbine Bldg High Range (RMV-RM-20B) 0.0 uCi/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 3.4E0 uCi/sec RW/ARW Bldg High Range (RMV-FM-30B) 0.0 uCi/sec PANEL 9-10 Mn. Stm. Rad Monitor Ch. A2, B1 620 mR/hr 620 mR/hr Ch. A2, B2 619 mR/hr 619 mR/hr SJAE Off Cas Log Rad Monitor Ch. A, B 22 mR/hr 22 mR/hr ('~T Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.7 mR/hr 0.7 mR/hr \'] o All other monitors display normal readings
- Alarm OS Offscale
.. =. . . - . . - _ . , . . . - . . . _ . , . . . . _ . . . .. -. . - - _ . . -
1 f j 1985 Evaluated' Exercise Time = 1230-Message Number 37 t= 05/00 COOPER NUCLEAR STATION ! } EMERCENCY PREPAREDNESS EXERCISE MESSAGE Message For: Control Room Simulated Plant Conditions: See attached plant data and Rad Monitor Sheets ! Message: * *
- THIS IS A DRILL * *
- 1 J
i f I i 1 i I 3 . .I 1 r
?
i 4 i ? 4 1 For Controller Use Only: ] 1 i t CONTROLLER INFORMATION: e I a 4 EXPECTED ACTIONS: 4 1 ! + 1 4 .f ? f i t I
. . - .. . . . ..._,..,.- ... .... ,__._-_ .. , ~ _,.--, ,,_.,.. , _ ,. ., _ - ,, - ,_ , .-...-,._ .,- _,, -
1985 Evolustad.Exarcies Time = 1230 Massage Number 37 i t=- 05/00 O COOPER NUCLEAR STATION V EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpa) 3 REACTOR POWER 10 SRM RHR A SUP PL CLG 100 7000 REACTOR LEVEL 35" + NR RHR B SUP PL CLG 100 7000 REACTOR PRESSURE 725 psig RHR C LPCI 235 MIN FLOW CORE D/P (psig) 2.8 RHR D LPCI 235 MIN FLOW CORE FLOW 7.1 CS A OP 250 MIN FLOW ( ' 6 FLOW (10 1bs/hr) CS B OP 250 MIN FLOW FEEDWATER A 0 HPCI ISOLATED 0 0 FEEDWATER B 0 Drywell Pressure 55 (PSIA) MAIN STEAM A 0 Torus Level +0.6 (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 (gym) STATUS PRESS (psig) FLOW (gpa) CRD B AVAIL (gpa) RCIC OPER 825 400 LEVEL PRESS SQUIB PUMPS RWCU A Tripped 0 SLC 75 % 0 (psig) ON Avail RWCU B Tripped 0 RRPA 0 % SPD MISCELLANEOUS PANELS RRPB 0 % SPD DIESEL GEN A OP DIESCL GEN B OP SBCT A OP SBGT B OP DRYWELL COOLING NORMAL TORUS WATER TEMP 93 'F
Tims - 1230 l RADIATION MONITOR DATA t= 05/00 l AREA RADIATION MONITORS
\s_ ,/ STATION DESCRIPTION READING 1 Rx Bldg Fuel Pool Area (SE Sch Floor) 151 mR/hr 2 Rx Bldg Fuel Fool Area (SE Sth Floor) OS mR/hr 3 Rx Bldg New Fuel Area (SE Sch Floor) OS mR/hr 4 Rx Bldg Rx Water Cleanup Demineralizer Area (SW 3rd Floor) OS mR/hr 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 307 mR/hr 6 Rx Bldg Neutron Monitor System Index Area (TIP Room ist Floor) OS mR/hr 7 Rx Bldg Neutron Monitor System Drive Mech Area (SE 1st Floor) OS mR/hr 8 Rx Bldg Control Rod Hydraulic Equipment Area (S 1st Floor) OS mR/hr 9 Rx Bldg Control Rod Hydraulic Equipment Area (N 1st Floor) OS mR/hr 10 Rx Bldg HPCI Pump Room (SW Quad) OS mR/hr 11 Rx Bldg RHR Pump Room (SW Quad) OS mR/hr 12 Rx Bldg RHR Pump Room (NW Quad) OS mR/hr 13 Rx Bldg RCIC/CS Pump Room (NE Quad) OS mR/hr i 14 Rx Bldg CS Pump Room (SE Quad) _
OS mR/hr 15 Turbine Bldg Turbine Front Standard 0.2 mR/hr 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.02 mR/hr 17 Turbine Bldg Turbine Bldg Basement Control
/N 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 03 mR/hr x _, . 19 Turbine Bldg Turbine Bldg Condensate Pump Area 0.03 mR/hr 20 Control Room Main Control Room 0.02 mR/hr 21 Grade Level Control Corridor 0.1 mR/hr Panel 9-02 Personnel Airlock Area 903 3.2E4 R/hr Panel 9-02 Ladder 903 to 2nd Level 3.2E4 R/hr PROCESS AND VENT MONITORP PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 1.9El uCi/sec ERP Stack Normal Eff (RMP-RM-3A) 1.9El uCi/sec ERP Stack High Range (RMP-RM-3B) 0.0 uCi/sec Turbine Bldg Vent Eff (RMV-RM-20A) 3.6E0 uCi/sec Turbine Bldg High Range (miV-RM-20B) 0.0 uCi/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 3.4E0 uC1/sec l RW/ARW Bldg High Range (RMV-RM-30B) 0.0 uCi/see PANEL 9-10 Mn. Stm. Rad Monitor Ch. A2, B1 620 mR/hr 619 mR/hr Ch. A2, B2 619 mR/hr 619 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 22 mR/hr 22 mR/hr
' ') Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.7 mR/hr 0.7 mR/hr
' '}
o All other monitors display normal readings
- Alarm OS Offscale
-1985 Ev. 'ed Exercise Time = 1245 Message Number 38 t= 05/15
.i COOPER NUCLEAR STATION l l ~ EMERGENCY PREPAREDNESS EXERCISE MESSAGE 1 $ t i l Message For: Control Room i-l Simulated Plant Conditions: See attached plant data and Rad Monitor Sheets
- i l Message
- * *
- THIS IS A DRILL * *
- 1 1
1 4 , e - I - i
- +
1 1 i t i i l. i ) l For Controller Use Only: i j 'i' j CONTROLLER INFORMATION: I J .k
- i +
4 i i EXPECTED ACTIONS: i b l 4 ! i ! i t s i
- i t.
- . . , - . . - - - - - - , --,.o,n, n.-- ,,-,m-r..n.,-----,-,. .,...,,_V..n-n-----,,,-,_ _n,-.-r--.,---_---.,-
_- . . - . . .. .-. . - . - - - .. - _ _ = i. i 1985 Evaluntsd Exorcisa Tira = '1245 Massage Number 38 t= 05/15 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA i PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 10 SRM RHR A SUP PL'CLG 100 7000 REACTOR LEVEL 35" + NR
- RHR B SUP PL CLC 100 7000 REACTOR PRESSURE 700 psig RHR C LPCI 235 MIN FLOW CORE D/P (psig) 2.8 I RHR D LPCI 235 MIN FLOW CORE FLOW 7.1 CS A '
l OP 250 MIN FLOW FLOW (10 Ibs/hr) CS B OP 250 _ MIN FLOW FEEDWATER A 0 ! HPCI ISOLATED 0 0 FEEDWATER B 0 4 ' Drywell Pressure 56 (PSIA) MAIN STEAM A 0 ' Torus Level +0.7 (inches) MAIN STEAM B 0 l~ OPEN CLOSED MAIN STEAM C 0
! MSIV 0 8 MAIN STEAM D 0 i
FLOW PANEL 9-4 CRD A 50 (gpm)
- STATUS PRESS (psig) FLOW (gpa) CRD B AVAIL (gpa)
RCIC OPER 825 400 LEVEL PRESS SQUIB PUMPS RWCU A Tripped 0 SLC 75 % 0 (psig) ON Avail I RWCU B Tripped 0 a ! l RRPA 0 % SPD MISCELLANEOUS PANELS I j RRPB 0 % SPD DIESEL CEN A OP i DIESEL CEN B OP SBCT A OP ' i } SBGT B OP DRYWELL COOLING NORMAL i TORUS WATER TEMP 94 F f 4
- . __. . _ , . _ _ . _ . _ _ _ _ . , , _ _ . __ . _ , _ , _ . . _ , . _ , . . , , _ . , . . . _ . _ . _ . ____,..,..,...,_.m _ _ . . . . _ . , _ _ _ . . . , . _ _ . . . . _ . . . . . ,
. -__ m .
.~ __ _. - _ _
Tima - 1245 RADIATION MONITOR DATA t= 05/15 ! s i AREA RADIATION MONITORS , hi STATION DESCRIPTION READING i 1 Rx Bldg Fuel Pool Area (SE Sch Floor) 152 mR/hr 2 Rx Bldg Fuel Pool Area (SE 5th Floor) OS mR/hr , 3 Rx Bldg New Fuel Area (SE Sch Floor) OS mR/hr Rx Bldg Rx Water Cleanup Demineralizer Area 4 (SW 3rd Floor) OS mR/hr 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 308 mR/hr 6 Rx Bldg Neutron Monitor System Index Area (TIP Room ist Floor) OS mR/hr 7 Rx Bldg Neutron Monitor System Drive Mech Area (SE 1st Floor) OS mR/hr 8 Rx Bldg Control Rod Hydraulic Equipment Area (S 1st Floor) OS mR/hr 9 Rx Bldg Control Rod Hydraulic Equipment Area (N 1st Floor) OS' mR/hr l 10 Rx Bldg HPCI Pump Room (SW Quad) . OS mR/hr 1 11 Rx Bldg RHR Pump Room (SW Quad) OS mR/hr i 12 Rx Bldg RHR Pump Room (NW Quad) OS mR/hr 13 Rx Bldg RCIC/CS Pump Room (NE Quad) OS mR/hr i 14 Rx Bldg CS Pump Room (SE Quad) OS mR/hr 15 Turbine Bldg Turbine Front Standard 0.2 mR/hr 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.02 mR/hr l 17 Tus's - e Bldg Turbine Bldg Basement Control i Cort. dor 0.01 mR/hr i 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 0.3 mR/hr k 19 Turbine Bldg Turbine' Bldg Condensate Pump Area i 0.03 mR/hr l 20 Control Room Main Control Room 0.02 mR/hr 21 Grade Level Control Corridor 0.1 mR/hr l Panel 9-02 Personnel Airlock Area 903 3.2E4 R/hr Panel 9-02 Ladder 903 to 2nd Level 3.2E4 R/hr l -* PROCESS AND VENT MONITORS PANEL VBDG 1 Rx Bldg Vent Eff (RMV-RM-40) ' 8E1 uCi/sec ERP Stack Normal Eff (RMP-RM-3A) 1.9El uCi/sec ERP Stack High Range (RMP-RM-3B) 0.0 uC1/sec' i Turbine Bldg Vent Eff (RMV-RM-20A) 3.5E0 uCi/sec i Turbine Bldg High Range (RMV-RM-20B) 0.0 uCi/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 3.4E0 uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) 0.0 uCi/sec I PANEL 9-10 t i Mn. Stm. Rad Monitor Ch. A2, B1 620 mR/hr 620 mR/hr
- Ch. A2, B2 619 mR/hr 620 mR/hr
'~' SJAE Off Gas Log Rad Monitor Ch. A, B 22 mR/hr 22 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.7 mR/hr 0.7 mR/hr o All other monitors display normal readings j
- Alarm '
OS Offscale
-_. - . ~ . _ _ _ _ _ , _ ..- . .- . , . __ _ . , _ _
.-. ~. .... . . . . . . .. __ _
1985 Evaluated Exercise Time = 1300 Message Number 39 t= 05/30 COOPER NUCLEAR STATION f j EMERGENCY PREPAREDNESS EXERCISE MESSAGE 4 ! Message For: Control Room Simulated Plant Conditions: See attached plant data and Rad Monitor Sheets Mes'ava : * *
- THIS IS A DRILL * *
- t,
.;g- %
i s.
~
1 ,
- s -s- -
i t d
\'
l' % s I 4 L For' Controller Use Only: 4 ,
.. CONTROLLER INFORMATION:
I Alternate EOF should be activated and declared functional. ARM's alarm -in area of CRD latch indicating that the the containment
- has been breached.
1 SBGT and ERP monitors indicate a significant release has commenced. EXPECTdACTIONS: Re-evaluate protective action recommendations, based or increased release rates.% , f s e i e
,- , . . _ . , , , . .--..,-.-n- , ,,,~.,e.-,- . - . . . . . , - - . - - , , ,-.-_,.n. , . - - - . . . , , - . , - , , . . - - .
4 1985 Evalustsd Exsreisa Time = 1300 s Massage Number 40 t= 05/30 COOPER NUCLEAR STATION 2 EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 ' 2 ' STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 9x10 SRM 35" + RHR A SUP PL CLG 100 7000 REACTOR LEVEL NR , i RHR B SUP PL CLG 100 7000 REACTOR PRESSURE 650 psig RHR C LDCI 235 MIN FLOW CORE D/P (psig) 2.8 RHR D LPCI 235 MIN FLOW CORE FLOW 7 '.1 CS A
- OP 250 MIN FLOW 6 FLOW (101bs/hr)
CS B OP 250 MIN FLOW FEEDWATER A 0 HPCI ISOLATED 0 0 - FEEDWATER B 0 Drywel) Pressure 50 (PSIA) MAIN STEAM A 0 j
; Torus Level +0.7 (inches) MAIN STEAM B 0 OPEN CLOSED MAIN STEAM C 0 MSIV O 8 MAIN STEAM D 0 -
FLOW i PANEL 9-4 CRD A 50 (gpm) .i STATUS PRESS (psig) FLOW (gpm) CRD B AVAIL (gpm) ' RCIC OPER 750 400 LEVEL PRESS SQUIB PUMPS i RWCU A Tripped 0 SLC 75 % 0 (psig) ON Avail , RWCU B Tripped 0 RRPA 0 % SPD MISCELLANEOUS PANELS RRPB 0 % SPD DIESEL CEN A OP 4 DIESEL GEN B OP SBGT A OP SBCT li OP O\ 4 Q DRYWELL COOLING NORMAL TORUS WATER TEMP 95 *F _ __ ~. . - - - - . _ _ ._ -
l Tims = 1300 RADIATT.ON MONITOR DATA t= 05/30
,, AREA RADIATION MONITORS l \ '\_) STATION DESCRIPTION READING 1 Rx Bldg Fuel Pool Area (SE Sch Floor) 150 mR/hr 2 Rx Bldg Fuel Fool Area (SE Sth Floor) OS mR/hr*
3 Rx Bldg New Fuel Area (SE 5th Floor) OS mR/hr* 4 Rx Bldg Rx Water Cleanup Demineralizer Area (SW 3rd Floor) OS mR/hr* 5 Rx Bldg Sludge and Decant Pump Area'(S 2nd Floor) 305 mR/hr* 6 Rx Bldg Neutron Monitor System Index Area (TIP Room 1st Floor) OS mR/hr* 7 4 Rx Bldg Neutron Monitor System Drive Mech Area - (SE 1st Floor) OS mR/hr* 3 Rx Bldg Control Rod Hydraulic Equipment Area (S 1st Floor) OS mR/hr* 9 Rx Bldg Control Rod Hydraulic Equipment Area (N 1st Floor) OS mR/hr* 10 Rx Bldg HPCI Pump Room (SW Quad) OS mR/hr* 11 Rx Bldg RHR Pump Room (SW Quad) OS mR/hr* 12 Rx Bldg RHR Pump Room (NW Quad) OS mR/hr* 13 Rx Bldg RCIC/CS Purp Room (NE Quad) OS mR/hr* 14 Rx Bldg CS Pump Room (SE Quad) OS mR/hr* 15 Turbine Bldg Turbine Front Standard 0.1 mR/hr 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.02 mR/hr 17 Turbine Bldg Turbine Bldg Basement Control ('(_,)N 18 Turb e Bldg Turbine Bldg Rx Feed Pump Area b3 /h 19 Turbine Bldg Turbine Bldg Condensate Pump Area 20 0.03 mR/hr Control Room Main Control Room 0.01 mR/hr 21 Grade Level Control Corridor 0.1 mR/hr Panel 9-02 Personnel Airlock Area 903 3.2E4 R/hr Panel 9-02 Ladder 903 to 2nd Level 3.2E4 R/hr PROCESS AND VENT MONITORS PANEL VBDG
/ Rx Bldg Vent Eff (RMV-RM-40) 1.9El uCi/sec ERP Stack Normal Eff (RMP-RM-3A) 0.0 uCi/sec ERP Stack High Range (RMP-RM-3B) 8.0E7 uCi/sec Turbine Bldg Vent Eff (RMV-RM-20A) 3.6E0 uCi/sec Turbine Bldg High Range (RKV-RM-20B) 0.0 uCi/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 3.5E0 uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) 0.0 uCi/sec PANEL 9-10 Mn. Stm. Rad Monitor Ch. A2, B1 620 mR/hr 620 mR/hr Ch. A2, B2 620 mR/hr 620 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 22 mR/hr 22 mR/hr /N Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.7 mR/hr 0.7 mR/hr
( ) o All other monitors display normal readings
- Alarm OS Offscale
[
. .. _ . _ _ _ _ . . _ . .__ .__. _ . _ _ _ _ _ _ . _ - . _ _ _ . . . . . _ _ _ _ . ....._.___m._
i 1985 Evalua ted Exercise Time = 1315 Message Number 41 t= 05/45 1 i COOPER NUCLEAR STATION , EMERGENCY PREPAREDNESS EXERCISE MESSAGE ; i
- j. Message For: Control Room i~
Simulated Plant Conditions: See attached plant data and Rad Monitor Sheets ; i
- Message
- * *
- THIS IS A DRILL * *
- I 2
i i i .i 1 i . l 1 4 l l i For Controller Use Only: CONTROLLER INFORMATION: 4 l i 1 ) EXPECTED ACTIONS: I i i k i J.
,__,w...__,--.-,,.-.,,, --
1985 Evaluated Exercisa Tims = 1315 Message Number 41 t= 05/45 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 9x10 SRM
- RHR A SUP PL CLG 100 7000 REACTOR LEVEL 35" + NR RHR B SUP PL CLG 100 7000 REACTOR PRESSURE 580 psig RHR C LPCI 235 MIN FLOW CORE D/P (psig) 2.8 RHR D LPCI 235 MIN FLOW CORE FLOW 7.1 CS A "
OP 250 MIN FLOW 6 FLOW (101bs/hr) CS B OP 250 MIN FLOW FEEDWATER A 0 HPCI ISOLATED 0 0 FEEDWATER B 0 Drywell Pressure 48 (PSIA) MAIN STEAM A 0 Torus Level +0.7 (inches) MAIN STEAM B 0 A 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 680 400 LEVEL PRESS SQUIB PUMPS RWCU A TRIPPED 0 SLC 75 % 0 (psig) ON . Avail RWCU B TRIPPED 0 RRPA 0 % SPD MISCELLANEOUS PANELS RRPB 0 2 SPD DIESEL CEN A OP DIESEL GEN B OP SBGT A OP SBGT B OP f O
) DRYWELL COOLING NORMAL TORUS WATER TEMP 95 *F
Tima = 1315 RADIATION MONITOR DATA t= 05/45 i s AREA RADIATION MONITORS STATION DESCRIPTION READING 2 1 Rx Bldg Fuel Pool Area (SE Sch Floor) 150 mR/hr 2 Rx Bldg Fuel Pool Area (SE 5th Floor) OS mR/hr* 1 3 Rx Bldg New Fuel Area (SE Sch Floor) OS mR/hr* 2 4 Rx Bldg Rx Water Cleanup Demineralizer Area (SW 3rd Floor) OS mR/hr* 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 306 mR/hr* 6 Rx Bldg Neutron Monitor System Index Area (TIP Room ist Floor) OS mR/hr* 7 Rx Bldg Neutron Monitor System Drive Mech Area
- (SE 1st Floor) OS mR/hr*
8 Rx Eldg Control Rod Hydraulic Equipment Area
- (S 1st Floor) OS mR/hr*
9 Rx Bldg Control Rod Hydraulic Equipment Area (N ist Floor) OS mR/hr* 4 10 Rx Bldg HPCI Pump Room (SW Quad) OS mR/hr* 11 Rx Bldg RHR Pump Room (SW Quad) OS mR/hr* 12 Rx Bldg RHR Pump Room (NW Quad) OS mR/hr* 13 Rx Bldg RCIC/CS Pump Room (NE Quad) OS mR/hr* 14 Rx Bldg CS Pump Room (SE Qua'd) -- OS mR/hr* 15 Turbine Bldg Turbine Front Standard 0.1 mR/hr
- 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.02 mR/hr i 17 Turbine Bldg Turbine Bldg Basement Control Corridor 0.01 mR/hr
- 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 0.3 mR/hr l . 19 Turbine Bldg Turbine Bldg. Condensate Pump Area 0.02 mR/hr 20 Control Room Main Control Room 0.01 mR/hr 21 Grade Level Control Corridor 0.1 mR/hr Panel 9-02 Personnel Airlock Area 903 3.2E4 R/hr Panel 9-02 Ladder 903 to 2nd Level 3.1E4 R/hr i
PROCESS AND VENT MONITORS j PANEL VBDG , , Rx Bldg Vent Eff (RMV-RM-40) 1.8E1 uCi/sec i ERP Stack Normal Eff (RMP-RM-3A) 0.0 uCi/sec ERP Stack High Range (RMP-RM-3B) 1.0E8 uCi/sec Turbine Bldg Vent Eff (RMV-RM-20A) 3.5E0 uCi/sec Turbine Bldg High Range (RMV-RM-20B) 0.0 uCi/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 3.6E0 uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) 0.0 uCi/sec PANEL 9-10 Mn. Stm. Rad Monitor Ch. A2, B1 620 mR/hr 620 mR/hr Ch. A2, B2 620 mR/hr 620 mR/hr
! . SJAE Off Gas Log Rad Monitor Ch. A, B 21 mR/hr 22 mR/hr '
Rx Bldg Vent Ind/ Trip Unit Ch. A,-B 0.7 mR/hr 0.7 mR/hr ; o All other monitors display normal readings
- Alarm OS Offscale
-- -. - ..- .- - - - _ _ . . . . . _ . . . . = . . - . . . . . - - - - - . _ - . .-
i 1985 Evaluated Exercise Time = 1330 Message Number ~ 42 t= 06/00 1 COOPER NUCLEAR STATION ! 1 r EMERGENCY PREPAREDNESS EXERCISE. MESSAGE t . l t , Message For: Control Room t i Simulated Plant Conditions: See attached Plant Data and. Rad Monitor Sheets ! i Message: * *
- THIS IS A DRILL * *
- I o
1 1 2 ] l i 1 1 1 l 1 ! 1 i For Controller Use Only: CONTROLLER INFORMATION: r t EXPECTED. ACTIONS: 4 ! 4 l 2 i I
. . . - . , , - . ,e--- 4 - -. _ _ _ .m-- ....--- - .-..--.--.-. _ ,,- ._.._,.- - -.. ..........-. _ , _ __.....,. -.- ...- - .. ,.. - ~,. , .._.
1985 Evalusted Exarciss Tima = 1330 ,
-Massage Number 42 t= 06/00 COOPER NUCLEAR STATION t '
EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 - STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 8x10 SRM RHR A SU.' PL CLG 100 7000 REACTOR LEVEL 35" + NR RHR B SUP PL CLG 100 7000 REACTOR PRESSURE 520 psig I
- RHR C LPCI 235 MIN FLOW CORE D/P (psig) 2.8 RHR D LPCI 235 MIN FLOW CORE FLOW 7.1 6
CS A OP 250 MIN FLOW (10 nm/hr) 6 FLOW (10 1bs/hr) CS B OP 250 MIN FLOW FEEDWATER A _ 0 HPCI ISOLATED 0 0 FEEDWATER B 0 , Drywell Pressure 46 (PSIA) MAIN STEAM A 0 Torus Level- +0.7 (inches) MAIN STEAM B 0 l OPEN CLOSED MAIN STEAM C 0 r MSIV 0 8 MAIN STEAM D 0 I FLOW PANEL 9-4 CRD A '50 (gpm) STATUS PRESS (psig) FLOW (gpm) CRD B AVAIL (gpm) RCIC OPER 620 400- LEVEL PRESS PUMPS SQUIB RWCU A TRIPPED- 0 SLC 75 % 0 (psig) ON Avail RWCU B TRIPPED 0 RRPA 0 % SPD MISCELLANEOUS PANELS
- RRPB 0 % SPD DIESEL GEN A ~OP DIESEL GEN B OP SBGT A OP-
'SBGT B OP DRYWELL COOLING NORMAL-TORUS WATER TEMP- 95 *F.
J 1
--4 -
y r r--n . , r -
-r---- , .<,- -- - 4-w -n.. - & ,_.u-, . - . - ~ - -
Tima - 1330 a RADIATION MONITOR DATA t = 06/00 AREA RADIATION MONITORS STATION DESCRIPTION READING 1 Rx Bldg Fuel Pool Area (SE Sch Floor) 150 mR/hr 2 Rx Bldg Fuel Pool Area (SE Sth Floor) US mR/hr 3 Rx Bldg New Fuel Area (SE 5th Floor) OS rA/hr 4 Rx Bldg Rx Water Cleanup Demineralizer Area (SW 3rd Floor) OS mR/hr 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 290 mR/hr 6 Rx Bldg Neutron Monitor System Index Area (TIP Room ist Floor) OS mR/hr 7 Rx Bldg Neutron Monitor System Drive Mech Area (SE 1st Floor) OS mR/hr 8 Rx Bldg Control Rod Hydraulic Equipment Area (S 1st Floor) OS mR/hr 9 Rx Bldg Control Rod Hydraulic Equipment Area (N 1st Floor) OS mR/hr 7 10 Rx Bldg HPCI Pump Room (SW Quad) OS mR/hr 11 Rx Bldg RHR Pump Room (SW Quad) OS mR/hr 12 Rx Bldg RHR Pump Room (NW Quad) OS mR/hr 13 Rx Bldg RCIC/CS Pump Room (NE Quad) OS mR/hr 14 R; Bldg CS Pump Room (SE quad) OS mR/hr 15 Turbine Bldg Turbine Front Standard 0.1 mR/hr 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.02 mR/hr 17 Turbine Bldg Turbine Bldg Basement Control ( ( 18-19 u bine Bldg Turbine Bldg Rx Fe.ed Pump Area 03 h Turbine Bldg Turbine Bldg Condensate Pump Area 20 0.02 mR/hr Control Room Main Control Room 0.01 mR/hr 21 Grade Level Control Corridor 0.1 mR/hr Panel 9-02 Personnel Airlock Area 903 3.0E4 R/hr Panel 9-02 Ladder 903 to 2nd Level 3.0E4 R/hr PROCESS AND VENT MONITORS PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 1.7El uCi/sec ERP Stack Normal Eff (RMP-RM-3A) 0.0 uCi/sec ERP Stack High Range (RMP-RM-3B) 1.0E8 uCi/sec Turbine Bldg Vent Eff (RMV-RM-20A) 3.5E0 uCi/sec Turbine Bldg High Range (RMV-RM-20B) 0.0 uC1/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 3.6E0 uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) 0.0 aci/sec PANEL 9-10 Mn. Stm. Rad Monitor Ch. A2, B1 620 mR/hr 620 mR/hr Ch. A2, B2 620 mR/hr 620 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 22 mR/hr 22 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.7 mR/hr 0.7 mR/hr o All other monitors display normal readings
- Alarm OS Offscale I_._-- -
t [- < l i 1985 Evaluated Exercise Time = 1345 Message Number 43 t= 06/15 , 4 1 COOPER NUCLEAR STATION i j EMERGENCY PREPAREDNESS EXERCISE MESSAGE i-2
- Message For
- Control Room
- Simulated Plant Conditions: See attached Plant Data and Rad Monitor Sheets F
Message: * *
- THIS IS A DRILL * *
- i f 4
2 i, 4 e i I i t i I ! 1-For Controller Use Only:
- CONTROLLER INFORMATION
) i i r i j. 1 EXPECTED ACTIONS:
)
i-1 !- 1 I I _ _ . - , . . ~ , ~ , _ - - _ , . - _ . - - ... . _ - . - - . - . . _ _ _ - . - . _ . . - - - . _ . - . . = _ _ - . . _ - _ - . _ - - _ - _ .
1985 Evaluat'ad Exerciss ~Timm = 1345 Massage Number 43 t= 06/15 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 8x10 SRM i EHR A SUP PL CLG 100 7000 REACTOR LEVEL 35" + NR RHR B SUP PL CLG 100 7000 REACTOR PRESSURE 460 psig RHR C LPCI 235 MIN FLOW CORE D/P (psig) 2.8 RHR D LPCI 235 . MIN FIDW CORE FLOW 7.1 CS A OP 250 MIN FLOW ( "! # 6 _ FLOW (101bs/hr) CS B OP 250 MIN FLOW FEEDWATER A 0 + HPCI ISOLATED 0 0 - FEEDWATER B 0 4 Drywell Pressure 44 (PSIA) . MAIN STEAM A 0 Torus Level +0.7 (inches) MAIN STEAM B 0 OPEN CLOSED MAIN STEAM C 0 t MSIV 0 8 MAIN STEAM D 0 1 i FLOW i PANEL 9-4 CRD A- 50 (gpm) STATUS PRESS (psig) FLOW (gpm) CRD B AVAIL (gpm) RCIC OPER 560 400 LEVEL PRESS PUMPS SQUIB RWCU A TRIPPED 0 SLC 75 % 0 (psig) ON Avail RWCU B TRIPPED 0 RRPA 0 % SPD MISCELLANEOUS PANELS RRPB 0 % SPD DIESEL GEN A OP 1 DIESEL GEN D OP SBGT A OP SBGT B OP DRYWELL COOLING NORMAL TORUS WATER TEMP 95- *F 1 l
Tims = 1345 RADIATION MONITOR DATA t= 06/15 AREA RADIATION MONITORS Q) STATION DESCRIPTION READING 1 Rx Bldg Fuel Pool Area (SE Sch Floor) 150 mR/hr 2 Rx Bldg Fuel Pool Area (SE Sch Floor) OS mR/hr 3 Rx Bldg New Fuel Area (SE 5th Floor) OS mR/hr 4 Rx Bldg Rx Water Cleanup Demineralizer Area (SW 3rd Floor) OS mR/hr 5 Rx Bldg Sludge and Decant Puup Area (S 2nd Floor) 380 mR/hr 6 Rx Bldg Neutron Monitor System Index Area (TIP Room 1st Floor) OS mR/hr 7 Rx Bldg Neutron Monitor System Drive Mech Area - (SE 1st Floor) OS mR/hr 8 Rx Bldg Control Rod Hydraulic Equipment Area (S 1st Floor) OS mR/hr 9 Rx Bldg Control Rod Hydraulic Equipment Are. (N 1st Floor) OS mR/hr 10 Rx Bldg HPCI Pump Room (SW Quad) OS mR/hr 11 Rx Bldg RHR Pu=p Room (SW Quad) OS mR/hr 12 Rx Bldg RHR Pump Room (NW Quad) OS mR/hr 13 Rx Bldg RCIC/CS Pump Room (NE Quad) OS mR/hr 14 Rx Bldg CS Pump Room (SE Quad) OS mR/hr 15 Turbine Bldg Turbine Front Standard 0.1 mR/hr 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.02 mR/hr 17 Turbine Bldg Ttrbine Bldg Basement Control Corridor 0.01 mR/hr Q 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 0.3 mR/hr
'gj 19 Turbine Bldg Turbine Bldg Condensate Pump Area 0.02 mR/hr 20 Control Room Main Control Room 21 0.01 mR/hr Grade Level Control Corridor 0.1 mR/hr Panel 9-02 Personnel Airlock Area 903 3.0E4 R/hr Panel 9-02 Ladder 903 to 2nd Level 3.0E4 R/hr PROCESS AND VENT MONITORS PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 1.8E1 uCi/sec ERP Stack Normal Eff (RMP-RM-3A) 0.0 uCi/sec ERP Stack High Range (RMP-RM-3B) 1.0E8 uCi/sec Turbine Bldg Vent Eff (RMV-RM-20A) 3.4E0 uCi/sec-Turbine Bldg High Range (RMV-RM-20B) 0.0 uCi/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 3.5E0 uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) 0.0 uCi/sec PANEL 9-10 Mn. Stm. Rad Monitor Ch. A2, B1 620 mR/hr 620 mR/hr l Ch. A2, 32 620 mR/hr 620 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 22 mR/hr 22 mR/hr r] Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.7 mR/hr 0.7 mR/hr o All other monitors display normal readings
- Alarm i l OS Offscale I
)
i. i 1985 Evaluated Exercise Time = 1400 i Message Number 44 t= 06/30 COOPER NUCLEAR STATION i f EMERGENCY PREPAREDNESS EXERCISE MESSAGE i Message For: Control Room /OSS i t j Simulated Plant Conditions: See attached Plant Data and Rad Monitor Sheets l Message: * *
- THIS IS A DRILL * * * !
i I i 1 t d i i f 4 l t l-I l a i i t I i i- l For Controller Use Only:
' CONTROLLER INFORMATION:
i i-l 4 i F EXPECTED ACTIONS: 1 - I l" i I _ _ _ - , , . , . - - . , , - _ ~ - , . . . , _ . . _ . . . ~ . . . - _ _ _ . . , _ . . - . _ . . _ _ _ _ . . _ _ _ . _ _ - _ _ - . _ . - . . _ . . . - . . _ , . - . . _ . ..-
1985 Evaluated Exarcisa Time = 1400 Massage Number 44 t= 06/30 I COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 2 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 7.5x10 SRM RHR A SUP PL CLG 100 7000 REACTOR LEVEL 35" + NR RHR B SUP PL CLG 100 7000 REACTOR PRESSURE 400 psig RHR C LPCI 235 MIN FLOW CORE D/P (psig) 2.8 RHR D LPCI 235 MIN FLOW CORE FLOW 7.1 CS A OP 250
- MIN FLOW 0 FLOW (10 lbs/hr)
. CS B OP 250 MIN FLOW FEEDWATER A 0 HPCI ISOLATED 0 0 FEEDWATER B 0 Drywell Pressure 42 (PSIA) MAIN STEAM A 0 Torus Level +0.7 (inches) MAIN STEAid B 0 OPEN CLOSED MAIN STEAM C 0 MSIV 0 8 MAIN STEAM D 0 FLOW P_ANEL 9-4 CRD A 50 (gpm) STATUS PRESS (psig) FLOW (gpm) CRD B AVAIL (gpm) RCIC OPER 500 400 LEVEL PRESS SQUIB PUMPS RWCU A TRIPPED 0 SLC 75 % 0 (psig) ON Avail RWCU B TRIPPED 0 RRPA 0 % SPD MISCELLANEOUS PANELS RRPB 0 % SPD DIESEL GEN A OP DIESEL GEN B OP SBGT A OP SBGT B OP DRYWELL COOLING NORMAL , TORUS WATER TEMP 94 *F E 4
.m , .._.,w - - . - , , - - . . ~ , _ . . ~ . . , _ _ . -y- --
3 .,_y, _ _ . - - . _ _ ., u__
I Tims = ' 1400-RADIATION MONITOR DATA t -- 06/30 AREA RADIATION MONITORS t O STATION- DESCRIPTION READING l 1 Rx Bldg Fuel Pool Area (SE Sch Floor) 150 mR/hr ' 2 Rx Bldg Fuel Pool Area (SE Sch Floor) OS mR/hr 3 Rx Bldg New Fuel Area (SE Sch Floor) OS mR/hr 4 Rx Bldg Rx Water Cleanup Demineralizer Area (SW 3rd Floor) OS mR/hr , 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 370 mR/hr 6 Rx Bldg Neutron Monitor System Index Area (TIP Room ist Floor) OS mR/hr 7 Rx Bldg Neutron Monitor System Drive Mech Area (SE 1st Floor) OS mR/hr 8 Rx Bldg Control Rod Hydraulic Equipment Area (S 1st Floor) OS mR/hr 3' 9 Rx Bldg Control Rod Hydraulic Equipment Area
' (N 1st Floor) OS mR/hr 10 Rx Bldg HPCI Pump Room (SW Quad) OS mR/hr
., 11 Rx. Bldg RHR Pump Room (SW Quad) 05 mR/hr j 12 Rx Bldg RHR Pump Room (NW. Quad) OS mR/hr 13 Rx Bldg RCIC/CS Pump Room (NE Quad) OS mR/hr 14 Rx Bldg CS Pump Room (SE* Quad) - OS mR/hr ' 15 Turbine Bldg Turbine Front Standard 0.1 mR/hr 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.02 mR/hr 17 - Turbine Bldg Turbine Bldg Basement Control Corridor 0.01 mR/hr 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 0.3 mR/hr 19 Turbine Bldg Turbine B.ldg Condensate Pump Area 20 0.02 mR/hr 3 Control Room Main Control Room 0.01 mR/hr 21 Grade Level Control Corridor 0.1 mR/hr
, Panel 9-02 Personnel Airlock Area 903 3.0E4 R/hr 4
Panel 9-02 Ladder 903 to 2nd Level 3.1E4 R/hr i PROCESS AND VENT MONITORS
-PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 1.8E1 uC1/sec
' ERP Stack Normal Eff (RMP-RM-3A) 0.0 uCi/sec ERP: Stack High Range (RMP-RM-3B) 9.8E7 uCi/sec Turbine Bldg Vent Eff (RMV-RM-20A) 3.4E0 uCi/sec Turbine Bldg High Range (RMV-RM-20B) 0.0 uCi/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 3.5EO uCi/sec 4
RW/ARW Bldg High Range (RMV-RM-30B) 0.0 uC1/se: PANEL 9-10 Mn. Stm. Rad Monitor'Ch. A2, B1 620 mR/hr 620 mR/hr Ch. A2, B2 620 mR/hr 620 mR/br SJAE Off' Gas Log Rad Monitor Ch. A, B 22 mR/hr 22 mR/hr g Rx Bldg Vent Ind/ Trip Unit Ch. A B 0.7 mR/hr- -0.7 mR/hr
' Qs o .All other monitors display normal readings
- Alarm OS Offscale
- - . - , , . . - , - , . - - - - -- . .- ..,__-,:-~-.- - - . _ . - . . . . - . - . - - .
1985 Evaluated Exercise Time = 1415 i i 1 Message Number 45 t= 06/45 i COOPER NUCLEAR STATION i . i EMERGENCY PREPAREDNESS EXERCISE MESSAGE ; i a ! Message'For: Control Room /OSS Simulated Plant Conditions: See attached Plant Data and Rad Monitor Sheets - Message: * *
- THIS IS A DRILL * * *
+ ; {. i i i I l i f ] For, Controller Use Only: , CONTROLLER INFORMATION: i 7 l t t i i i EXPECTED ACTIONS: l 4 1 l I'
., __ , , , . . .,...-~._,-n,, . , , . . , , , , . w .
v,- , .w.. ... -.% .-- . - -- - - + - - - >- - - . . . . - - - e-=----*--+----+~~~-d - - * - - - *~"
1 1985 Evaluated Exercisa Tims.= 14is ' Massage Number 45 t= 06/45 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm)- REACTOR POWER 7x10 SRM RHR A SUP PL CLG 100 7000 REACTOR LEVEL 35" + NR RHR B SUP PL CLG 100 7000 REACTOR PRESSURE 350 psig RHR C LPCI 235 MIN FLOW CORE D/P (psig) 2.8 RHR D LPCI 235 MIN FLOW CORE FLOW 7.1 4 CS A OP 250 MIN FLOW 0 FLOW (10 lbs/hr) CS B OP 250 MIN FLOW FEEDWATER A 0 HPCI ISOLATED 0 0 FEEDWATER B 0 i Drywell Pressure 40 (PSIA) MAIN STEAM A 0 Torus Level +0.7 (inches) MAIN STEAM B 0 OPEN CLOSED MAIN STEAM C 0 MSIV 0 8 MAIN STEAM D 0 FLOW i PANEL 9-4 CRD A 50 (gpm)
; STATUS PRESS (psig) FLOW (gpm) CRD B AVAIL (gpm)
RCIC OPER 450 400 LEVEL PRESS SQhIB PUMPS RWCU A TRIPPED 0 SLC 75 % 0 (psig) ON Avail RUCU B TRIPPED 0 RRPA 0 % SPD MISCELLANEOUS PANELS
- i. RRPB 0 '% SPD DIESEL CEN A OP DIESEL GEN B OP t
SBGT A OP~ SBGT B OP , . DRYWELL COOLING NORMAL TORUS WATER TEMP 94 *F
I Time = 1415 RADIATION MONITOR DATA t= 06/45 AREA RADIATION MONITORS STATION DESCRIPTION READING 1 Rx Bldg Fuel Pool Area (SE 5th Floor) 150 mR/hr 2 Rx Bldg Fuel Pool Area (SE Sch Floor) OS mR/hr , 3 Rx Bldg New Fuel Area (SE Sch Floor) OS mR/hr 4 Rx Bldg Rx Water Cleanup Demineralizer Area (SW 3rd Floor) OS mR/hr 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 346 mR/hr 6 Rx Bldg Neutron Monitor System Index Area (TIP Room ist Floor) OS mR/hr 7 Rx Bldg Neutron Monitor System Drive Mech Area (SE 1st Floor) OS mR/hr 8 Rx Bldg Control Rod Hydraulic Equipment Area (S ist Floor) OS mR/hr 9 Rx Bldg Control Rod Hydraulic Equipment Area (N 1st Floor) OS mR/hr 10 Rx Bldg HPCI Pump Room (SW Quad) ' OS mR/hr 11 Rx Bldg RHR Pu:ap Room (SW Quad) OS mR/hr 12 Rx Bldg RHR Pump Room (NW Quad) OS mR/hr 13 Rx Bldg RCIC/CS Pump Room (NE Quad) OS mR/hr 14 Rx Bldg CS Pump Room (SE Quad) OS mR/hr 15 Turbine Bldg Turbine Front Standard 0.1 mR/hr 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.02 mR/hr 17 Turbine Bldg Turbine Bldg Basement Control Corridor 0.01 mR/hr p 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 0.3 mR/hr \ 19 Turbine Bldg Turbine Bldg C'ndensate o Pump Area 0.02 mR/hr 20 Control Room Main Control Room 0.01 mR/hr 21 Grade Level Control Corridor 0.1 mR/hr Panel 9-02 Personnel Airlock Area 903 2.8E4 R/hr-Panel 9-02 Ladder 903 to 2nd Level 2.7E4 R/hr PROCESS AND VENT MONITORS PANEL VBDG Rx. Bldg Vent Eff (RMV-RM-40) 1.7El uCi/sec ERP Stack Normal Eff (RMP-RM-3A) 0.0 uCi/sec ERP Stack High Range (RMP-RM-3B) 9.6E7 uCi/sec Turbine Bldg Vent Eff (RMV-RM-20A) 3.3E0 uCi/sec Turbine Bldg High Range (RMV-RM-20B) 0.0 uCi/see RW/ARW nldg Combined Eff (RMV-RM-30A) 3.5E0 uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) 0.0 uCi/sec PANEL 9-10 Mn. Stm. Rad Monitor Ch. A2, B1 620 mR/hr 620 mR/hr Ch. A2, B2. 620 mR/hr 620 mR/hr SJAE Off Gas. Log Rad Monitor Ch. A, B 22 mR/hr 22 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.7 mR/hr 0.7 mR/hr o All other monitors display normal readings
- Alarm OS Offscale
..m__._..__. . . _ . _ . .. _ _ . . _ . , _ . . ._ . _ - - . _ _ _ . . _ -
P 4 J
'1985 Evaluated Exercise Time - 1430 Message Number- 46 t= 07/00 f i J
COOPER NUCLEAR STATION ' EMERGENCY PREPAREDNESS EXERCISE MESSAGE I j l i Message For: Control Room i - A _ Simulated Plant Conditions: See attached Plant Data and Rad Monitor Sheets ' j Message: * *
- THIS IS A DRILL * * *
+ . l 1 Z 5 i i
)
c i l' i l r t a . - For Controller Use Only: i, j j CONTROLLER INFORMATION: 4 i i i. EXPECTED ACTIONS: - i 1
- j. L i
0 L .--.-
._.-,.-.._ .- ,_ _.. _-_-..-__, - ..._... ._ _ _._..._...-...;_;...~ ..__ _ . .._-_-._.._._ _ _ _._ _ . _.- _ .;. _ __. _ _ . _
'1985 Evaluated Exercise Tima = 1430
~ Message Number' 46 t= 07/00
"""""^"""*
(D EMERGENCY PREPAREDNESS EXERCISE PLANT DATA 4 T PANtt 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 7x10 SRM 'i RHR A SUP PL CLG 100 7000 REACTOR
- LEVEL 35" + NR RHR B SUP PL CLG 100 7000 REACTOR PRESSURE 300 psig RHR C LPCI 235 MIN FLOW CORE D/P (psig) 2.8 RHR D LPCI 235 MIN FLOW CORE FLOW 7.1 CS A OP 250 " #
MIN FLOW 6 FLOW (10 1bs/hr)
- CS B OP 250 MIN FLOW FEEDWATER A 0 HPCI ISOLATED 0 0 . FEEJWATER B 0 Drywell Pressere 38 (PSIA) MAIN STEAM A 0 Torus Leve~. +0.8 (inches) MAIN STEAM B 0 i
[ PEN CLOSED MAIN-STEAM C 0 MSIV O 8 MAIN STEAM D 0 i FLOW PANEL 9-4 CRD A 50 (gpm) STATUS PRESS (psig) FLOW (gpm) CRD B AVAIL (gpm) RCIC ' OPER 400 400 LEVEL PRESS PUMPS SQUIB , RWCU A TRIPPED 0 SLC 75 1% 0. - (psig) ON Avail RWCU B TRIPPED 0 i REPA 0 % SPD MISCELLANEOUS PANELS , RRPB 0 % SPD DIESEL GEN A OP d DIESEL GEN B OP SBGT A OP SBGT B OP DRYWELL COOLING NORMAL TORUS WATER TEMP 93 *F
Tima = 143o RADIATION MONITOR DATA. t= 07/00
, AREA RADIATION MONITORS STATION DESCRIPTION READING 1 Rx Bldg Fuel Fool Area' (SE Sth Floor) 150 mR/hr 2 Rx Bldg Fuel Fool Area (SE Sth Floor) OS mR/hr*
3 Rx Bldg New Fuel Area (SE Sch Floor) OS mR/hr* 4 Rx Bldg Rx Water Cleanup Demineralizer Area (SW 3rd Floor) OS mR/hr* 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 306 mR/hr* 6 Rx Bldg Neutron Monitor System Index Area (TIP Room 1st Floor) OS mR/hr* 7 Rx Bldg Neutron Monitor System Drive Mech Area . ' (SE 1st Floor) OS mR/hr* 8 Rx Bldg Control Rod Hydraulic Equipment Area (S 1st Floor) OS mR/hr* ! 9 Rx Bldg Control Rod Hydraulic Equipment Area (N 1st Floor) OS mR/hr* 10 Rx Bldg HPCI Pump Room (SW Quad) OS mR/hr* 11 Rx Bldg RHR Pump Room (SW Quad) OS mR/hr* 12 Rx Bldg RHR Pump Room (NW Quad) OS mR/hr* 13 Rx Bldg RCIC/CS Pump Room (NE Quad) OS mR/hr* 14 Rx' Bldg CS Pump Room (SE Quad) OS mR/hr* 15 Turbine Bldg Turbine Front Standard 0.1 mR/hr 16 Turbine Bldg Turbine Bldg Mezz control Corridor 0.02 mR/hr 17 Turbine Bldg' Turbine Bldg Basement Control Corridor 0.01 mR/hr 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 0.3 mR/hr 19 Turbine Bldg Turbine Bldg Condensate Pump Area 4 20 0.02 mR/hr Control Room Main Control Room 0.01 mR/hr 21 Grade Level Control Corridor 0.1 mR/hr Panel 9-02 Personnel Airlock Area 903 2.5E4 R/hr Panel 9-02 Ladder 903 to 2nd Level 2.4E4 R/hr PROCESS AND VENT MONITORS j PANEL VBDG 4 Rx. Bldg Vent Eff-(RMV-RM-40) 1.8E1 uCi/sec ERP Stack Normal Eff (RMP-RM-3A). 0.0 uCi/sec ERP Stack High Range (RMP-RM-3B) 9.4E7 uCi/sec Turbine Bldg Vent Eff (RMV-RM-20A) 3.5E0 uCi/sec Turbine Bldg High Range (RMV-RM-20B) 0.0 uCi/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 3.6EO uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) 0.0 uCi/sec PANEL 9-10 Mn. Stm. Rad Monitor Ch._A2, B1 620 mR/hr 620 mR/hr Ch. A2, B2 620 mR/hr 620 mR/hr
'~'
SJAE Off Gas Log Rad Monitor Ch. A,-B 21 mR/hr 22 mR/hr. { Rx Bldg Vent Ind/ Trip Unit Ch. A 'B 0.7 mR/hr 0.7 mR/hr o- All other monitors display normal readings- '~ ~ Alarm
'0S Offscale l
1985 Evaluated Exercise Time = 1445 Message Number 47 t= 07/15 ' COOPER NUCLEAR STATION j EMERGENCY PREPAREDNESS EXERCISE MESSAGE , Message For: Control Room /OSS Simulated Plant Conditions: See attached Plant Data and Rad Monitor Sheets Message: * *
- THIS IS A DRILL * *
- l t
- i L
r For Controller Use Only: CONTROLLER INFORMATION: . Containment Spray is successfully initiated. Drywell pressure ' drops rapidly and release rate decreases to near background. l r i EXPECTED ACTIONS: I t k i
?
1985 Evalusted Exercise Time = 1445 Massage Number 47 t= 07/15 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 ] STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 7x10 SRM RHR A SUP'PL CLG 100 7000 REACTOR LEVEL 15" + NR RHR B SUP PL CLG 100 7000 REACTOR PRESSURE 250 psig RHR C LPCI 250 4400 CORE D/P (psig) 2.8 RHR D LPCI 250 4400 CORE FLOW 7.1 6 1 CS A OP 250 MIN FLOW (10 lbm/hr) 6 FLOW (101bs/hr) CS B OP '250 MIN FLOW FEEDL' ~4 a 1 0 4 HPCI ISOLATED 0 0 FEEDWATEk B 0 Drywell Pressure 15 (PSIA) MAIN FTEAM A 0 Torus Level +0.9 (inches) MAIN STEAM B 0 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 350 400 LEVEL _ PRESS PUMPS SQUIB
- RWCU A TRIPPED 0 SLC 75 % 0 (psig) ON Avail RWCU B TRIPPED 0 RRPA 0 % SPD MISCELLANEOUS PANELS RRPB 0 _% SPD DIESEL GEN A OP
- DIESEL GEN B OP i
SBGT A OP s SBGT B OP DRYWELL COOLING NORMAL TORUS WATER TEMP 93 'F [-
Time = 1445 RADIATION MONITOR DATA t= 07/15
-~s AREA RADIATION MONITORS k STATION DESCRIPTION READING 1 Rx Bldg Fuel Fool Area (SE 5th Floor) 150 mR/hr 2 Rx Bldg Fuel Pool Area (SE Sch Floor) 58 mR/hr 3 Rx Bldg New Fuel Area (SE Sch Floor) 47 mR/hr 4 Rx Bldg Rx Water Cleanup Demineralizer Area (SW 3rd Floor) 48 mR/hr 5 Rx Bldg Sludge and Decant Pump Area ('S 2nd Floor) 99 mR/hr 6 Rx Bldg Neutron Monitor System Index Area (TIP Room ist Floor) 145 mR/hr 7 Rx Bldg Neutron Monitor System Drive Mech Area (SE 1st Floor) 80 mR/hr 8 Rx Bldg Control Rod Hydraulic Equipment Area (S ist Floor) 78 mR/hr 9 Rx Bldg Control Rod Hydraulic Equipment Area (N 1st Floor) 65 mR/hr 10 Rx Bldg HPCI Pump Room (SW Quad) 95 mR/hr 11 Rx Bldg RHR Pump Room (SW Quad) 80 mE/hr 12 Rx Bldg RHR Pump Room (NW Quad) 92 mR/hr 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 76 mR/hr 2 14 Rx Bldg CS Pump Room (SE Quad) 90 mR/hr 15 Turbine Bldg Turbine Front Standard 0.1 mR/hr 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.2 mR/hr 17 Turbine Bldg Turbine Bldg Basement Control
[ \ 18 rbi e Bldg Turbine Bldg Rx Feed Pump Area O mR/hr
\s l 19 Turbine Bldg Turbine Bldg Condensate Pump Area 0.01 mR/hr 20 Control Room Main Control Room 0.01 mR/hr 21 Grade Level Control Corridor 0.1 mR/hr Panel 9-02 Personnel Airlock Area 903 8.4E3 R/hr Panel 9-02 Ladder 903 to 2nd Level 8.2E3 R/hr PROCESS AND VENT MONITORS PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 1.5El uCi/sec ERP Stack Normal Eff (RMP-RM-3A) 0.0 uCi/sec ERP Stack High Range (RMP-RM-3B) 3.0E7 uCi/sec Turbine Bldg Vent Eff.(RMV-RM-20A) 2.8E0 uCi/sec Turbine Bldg High Range (RMV-RM-20B) 0.0 uCi/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 3.3EO-uC1/sec RW/ARW Bldg High Range (RMV-RM-30B) 0.0 uCi/sec PANEL 9-10
- Mn. Stm. Rad Monitor Ch. A2, B1 618 mR/hr 620 mR/hr Ch. A2, B2 620 mR/hr 619 mR/hr SJAE Off Cas Log Rad Monitor Ch. A, B 4 mR/hr 4 mR/hr
( Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.7 mR/hr 0.7 mR/hr i Q o All other monitors dieplay normal readings
- Alarm OS Offscale
19E5 Evaluated Exercise Time = 1500 i
- - Message Number- 48 t= 07/30 COOPER NUCLEAR STATION i
. EMERGENCY PREPAREDNESS EXERCISE MESSAGE ! Message For: Control Room /OSS Simulated Plant Conditions: See attached Plant Data and Rad Monitor' Sheets
;. . Message: * *
- THIS IS A DRILL * *
- 1 i
1 l t t i i : i . i 1 4 I i i i r i ! 1 t i a For Controller Use Only: -
- j CONTROLLER INFORMATION:
3 i 1 , 4 EXPECTED ACTIONS: ! t i l' l' i. I
-~~~*'=~~-*~c'~**-~'~~' " " * ' ' ' "~ * ' * " *" " ~ ~ ' ' ~ " " ' "' ' ' " ' ' ~ * ~ " ~ ' ~ * * " " " ~ ~ ' ~ ~ ^ "
1 4 1985 Evaluated Exercise Time = 1500 Massage Number 48 t= 07/30 COOPER NUCLEAR STATION EMERGlNCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 7x10 SRM RHR A SUP PL CLG 100 7000 REACTOR LEVEL 35" + NR RHR B SUP PL CLG 100 7000 REACTOR PRESSURE 180 psig RHR C LPCI 250 4400 CORE D/P (psig) 2.8 RHR D LPCI 250 4400 CORE FLOW 7.1 CS A ( " OP 250 MIN FLOW - FLOW (10 lbs/hr) CS B OP 250 MIN FLOW FEEDWATER A 0 , HPCI ISOLATED 0 0 FEEDWATER B 0 Drywell Pressure 15 (PSIA) , MAIN STEAM A 0 Torus Level +1.0 (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) STATUS PRESS (psig) FLOW (gpm) CRD B AVAIL (gpm) RCIC OPER 280 400 LEVEL PRESS PUMPS SQUIB RWCU A TRIPPED 0 SLC 75 % 0 (psig) ON Avail RWCU B TRIPPED 0 RRPA 0 % SPD MISCELLANEOUS PANELS 4 RRPB 0 % SPD DIESEL GEN A OP DIESEL GEN B OP SBGT A OP w SBGT B OP DRYWELL COOLING NORMAL TORUS, WATER TEMP 92 *F ?_ ._ _ _ -
Time = 1500 l RADIATION MONITOR DATA t= 07/30 ! l
,_ AREA RADIATION MONITORS
,, STATION DESCRIPTION READING 1 Rx Bldg Fuel Pool Area (SE 5th Floor) 150 mR/hr 2 Rx Bldg Fuel Pool Area (SE Sch Floor) 6 mR/hr 3 Rx Bldg New Fuel Area (SE Sch Floor) 0.1 mR/hr 4 Rx Bldg Rx Water Cleanup Demineralizer Area (SW 3rd Floor) 9 mR/hr 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 1 mR/hr 6 Rx Bldg Neutron Monitor System Index Area (TIP Room ist Floor) 31 mR/hr 7 Rx Bldg Neutron Monitor System Drive Mech Area (SE 1st Floor) 2 mR/hr 8 Rx Bldg Control Rod Hydraulic Equipment Area (S 1st Floor) 0.9 mR/hr 9 - Rx Bldg Control Rod Hydraulic Equipment Area (N 1st Floor) 9 mR/hr 10 Rx Bldg HPCI Pump Room (SW Quad) 4.5 mR/hr 11 Rx Bldg RHR Pump Room (SW Quad) 65 mR/hr 12 Rx Bldg RHR Pump Room (NW Quad) 92 mR/hr 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 19 mR/hr j 14 Rx Bldg CS Pump Room (SE Quad) 25 mR/hr 15 Turbine Bldg Turbine Front Standard 0.4 mR/hr 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.02 mR/hr 1 17 Turbine Bldg Turbine Bldg Basement Control Corridor 0.01 mR/hr
- 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 0.3 mR/hr 4
\ 19 Turbine Bldg Turbine Bldg Condensate Pump Area 0.02 mR/hr 20 Control Room Main Control Room 0.01 mR/hr 21 Grade Level Control Corridor 0.1 mR/hr Panel 9-02 Personnel Airlock Area 903
- 6.5 R/hr Panel 9-02 Ladder 903 to 2nd Level 6.3 R/hr PROCESS AND VENT MONITORS PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 1.6El uCi/sec ERP Stack Normal Eff (RMP-RM-3A) 2.0E1 uCi/sec ERP Stack High Range (RMP-RM-3B) 0.0 uCi/sec Turbine Bldg Vent Eff (RMV-RM-20A) 2.9E0 uCi/sec Turbine Bldg High Range (RMV-RM-20B) 0.0 uCi/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 3.4E0 uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) 0.0 uCi/sec PANEL 9-10 Mn. Stm. Rad Monitor Ch. A2, B1 618 mR/hr 620 mR/hr 1
Ch. A2, B2 620 mR/hr 619 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 4 mR/hr 4 mR/hr g Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.7 mR/hr 0.7 mR/hr
)
l o All other monitors display normal readings
- Alarm l OS Offscale i
A s
-1985 Evaluated Exercise Time = 1515 i
O Message Number 49 t= 07/45 i. COOPER NUCLEAR STATION > EMERGENCY PREPAREDNESS EXERCISE MESSAGE Message For: Control Room /OSS Simulated Plant Conditions: See attached Plant Data and Rad Monitor Sheets Message: * *
- THIS IS A' DRILL * *
- i l
i For Controller Use Only: CONTROLLER INFORMATION: Meteorological conditions change, dispersing-the remaining radioactive gases in the atmosphere. EXPECTED ACTIONS: i i-
1985 Evaluated Exercise Time = 1515
'ifessage Number 49 t= 07/45 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 7x10 SRM RHR A SUP PL CLG 100 7000 REACTOR LEVEL 35" + - NR RHR B SUP PL CLG 100 7000 REACTOR PRESSURE 100 psig RHR C LPCI 100 7000 CORE D/P (psig) 2.8
,+
RHR D LPCI 100 7000 CORE FLOW 7.1 CS A OP 250 MIN FLOW (
- FLOW (10 lbs/hr)
CS B OP 250 MIN FLOW FEEDWATER A 0 HPCI ISOLATED 0 0 FEEDWATER B 0 Drywell Pressure 15.0 (PSIA) MAIN STEAM A 0 Torus Level +1.0 (inches) MAIN STEAM B 0 OPEN CLOSED MAIN STEAM C 0 MSIV 0 8 MAIN STEAM D 0 FIDW PANEL 9-4 CRD A 50 (gpm) STATUS PRESS (psig) FLOW (gpm) CRD B AVAIL (gpm) RCIC OPER 200 400 LEVEL PRESS PUMPS SQUIB RWCU A TRIPPED 0 SLC 75 % 0 (psig) ON Avail RWCU B TRIPPED 0 RRPA 0 % SPD MISCELLANEOUS PANELS RRPB 0 % SPD DIESEL GEN A OP DIESEL GEN B OP SBGT A OP fh
-( SBGT B OP DRYWELL COOLING NORMAL
- j. TORUS WATER TEMP 91 "F L
- Timt = 1515
' RADIATION MONITOR DATA t= 07/45 AREA RADIATION MONITORS STATION DESCRIPTION READING ,
- 1 Rx Bldg Fuel Pool Area (SE Sch Floor) 150 mR/hr
- 1. 2 Rx Bldg Fuel Pool Area (SE 5th Floor) 6 mR/hr i 3 ' Rx Bldg New Fuel Area (SE Sth Floor) 0.1 mR/hr~
4 Rx Bldg Rx Water Cleanup Demineralizer Area (SW 3rd Floor) 9 mR/hr-5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 1 mR/hr } 6 Rx Bldg Neutron Monitor System Index Area
~
(TIP Room ist Floor) 31 mR/hr i 7 Rx Bldg Neutron Monitor System Drive Mech Area (SE ist. Floor) 2 mR/hr
- 8. Rx Bldg Control Rod Hydraulic Equipment Area (S ist Floor) 0.9 mR/hr 9' Rx Bldg Control' Rod Hydraulic Equipment Area l (N 1st Floor) 9 mR/hr ;
i 10 Rx Bldg HPCI Pump Room (SW Quad) 4.5 mR/hr i 11 Rx Bldg RHR Pump Room (SW Quad) 65 mR/hr 17 Rx Bldg RHR Pump Room (NW Quad) 92 mR/hr ,
-13 Rx Bldg RCIC/CS Pump Room (NE Quad) 19 mR/hr 14 Rx Bldg CS Pump Room (SE Quad) 25 mR/hr
.; 15 Turbine Bldg Turbine Front Standard 0.4 mR/hr i 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.02 mR/hr l 17 Turbine Bldg Turbine Bldg Basement Control i Corridor 0.01 mR/hr
} 18' . Turbine Bldg Turbine Bldg Rx Feed Pump Area 0.3 mR/hr- ,
- (,, 19 Turbine Bldg Turbine Bldg Condensate Pump Area 0.02 mR/hr-1 20 Control Room Main Control Room 0.01 mR/hr '
21 Grade Level Control Corridor 0.1 mR/hr Panel 9-02 ~ Personnel Airlock Area 903 6.5 R/hr Panel 9-02 Ladder 903 to 2nd-Level 6.3 R/hr PROCESS AND VENT MONITORS L j PANEL VBDG I. Rx Bldg Vent Eff (RMV-RM-40) 1.6El uCi/sec 0
.ERP Stack Normal Eff'(M(P-RM-3A) 2.0E1 uCi/sec ERP Stack High Range (RMP-RM-3B) 0.0 uCi/sec
. Turbine Bldg Vent Eff (RMV-RM-20A) 2.9E0 uCi/sec Turbine Bldg High Range (RMV-RM-20B)
~ 0.0 uCi/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 3.4E0 uCi/sec
- RW/ARW Bldg High Range (RMV-RM-30B) 0.0 uCi/sec t
i PANEL 9-10 Mn. Stm. Rad Monitor-Ch. A2, B1 618 mR/hr 620 mR/hr 1 , Ch. A2, B2 620 mR/hr 619 mR/hr : { SJAE Off Gas Log Rad Monitor Ch. A, B. 4 mR/hr 4 mR/hr Rx Bldg Vent Ind/ Trip UnitLCh.~A',.B 0.7 mR/hr 0.7 mR/hr -j 4 f o .All other monitors display normal readings
- Alarm )
OS Offscale I l l l
. _ _ . ._. _ . - . _ . . . . _ _ . . _ _ , _ _ . _ _ _= ,. - _., _ _ m .
i-1985 Eval:sted Exercise Time = 1530 Message Number 50 t= 08/00 2 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE i Message For: Control Room /OSS Simulated Plant Conditions: See attached Plant Data and Rad Monitor Sheets Message: * *
- THIS IS A DRILL * *
- j i-4 e
J .i, t 1 For Controller Use Only: CONTROLLER INFORMATION: i 1
)
i EXPECTED ACTIONS: Recovery organization is established and re-entry ,
. planning is initiated.
s e ?' I
.w.... _ - . . . . _ . . . . _ , , _ _ . _ . . _ , . - , , , , . . . _ _ . , , . . . , _ , . , , . , - ,
l l i 1985 Evaluated Exercise Time = 1530 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig)~ FLOW (gpm) REACTOR POWER 7x10 SRM RHR A SUP PL CLG 100 7000 REACTOR LEVEL 35" + NR RHR B SUP PL CLG 100 7000 REACTOR PRESSURE 50 psig RHR C LPCI 100 7000 CORE D/P (psig) 2.8 RHR D LPCI 100 7000 CORE FLOW 7.1 CS A OP 250
- MIN FLOW 0 FLOW (10 lbs/hr)
CS B OP 250 MIN FLOW FEEDWATER A 0 HPCI ISOLATED 0 0 FEEDWATER B 0 Drywell Pressure 15.0 (PSIA) MAIN STEAM A 0 , Torus Level +1.1 (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 ISOL 200 400 LEVEL PRESS PUMPS SQUIB RWCU A TRIPPED 0 SLC 75 % 0 (psig) ON Avail RWCU B TRIPPED 0 RRPA 0 % SPD MISCELLANEOUS PANELS RRPB 0 % SPD DIESEL GEN A OP DIESEL GEN B , OP SBGT A OP SBGT B OP
%J DRYWELL COOLING NORMAL TORUS WATER TEMP 90 *F
Time = RADIATION MONITOR DATA t= 08/00 AREA RADIATION MONITORS s,) s STATION DESCRIPTION READING 1 Rx Bldg Fuel Pool Area (SE Sch Floor) 150 mR/hr 2 Rx Bldg Fuel Pool Area (SE Sch Floor) 6 mR/hr 3 Rx Bldg New Fuel Area (SE Sch Floor) 0.1 mR/hr 4 Rx Bldg Rx Water Cleanup Demineralizer Area (SW 3rd Floor) , 9 mR/hr 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) _ 1 mR/hr 6 Rx Bldg Neutron Monitor System Index Area (TIP Room ist Floor) 31 mR/hr 7 Rx Bldg Neutron Monitor System Drive Mech Area (SE lst Floor) 2 mR/hr 8 Rx Bldg Control Rod Hydraulic Equipment Area (S 1st Floor) 0.9 mR/hr 9 Rx Bldg Control Rod Hydraulic Equipment Area (N 1st Floor) 9 mR/hr 10 Rx Bldg HPCI Pump Room (SW Quad) 4.5 mR/hr 11 Rx Bldg RHR Pump Room (SW Qcad) 65 mR/hr 12 Rx Bldg RRR Pump Room (NW Quad) 92 mR/hr 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 19 mR/hr 14 Rx Bldg CS Pump Room (SE Quad) 25 mR/hr 15 Turbine Bldg Turbine Front Standard 0.4 mR/hr 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.02 mR/hr 17 Turbine Eldg Turbine Bldg Basement Control Corridor 0.01 mR/hr 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 0.3 mR/hr Os 19 20 Turbine Bldg Turbine Bldg Condensate Pump Area Control Room Main Control Room 0.02 mR/hr 0.01 mR/hr 21 Grade Level Control Corridor 0.1 mR/hr Panel 9-02 Personnel Airlock Area 903 6.5 R/hr. Panel 9-02 Ladder 903 to 2nu Level 6.3 R/hr PROCESS AND VENT MONITORS PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 1.6El uCi/sec ERP Stack Normal Eff (RMP-RM-3A)- 2.0E1 uCi/sec ERP Stack High Range (RMP-RM-3B) 0.0 uCi/sec , Turbine Bldg Vent Eff (RMV-RM-20A) 2.9E0 uC1/sec Turbine Bldg High Range (RMV-RM-20B) ^ 0.0 uCi/sec-RW/ARW Bldg Combined Eff (RMV-RM-30A) 3.360 uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) 0.0 uC1/sec PANEL-9-10 Mn. Stm. Rad Monitor Ch. A2, B1 618 mR/hr 620 mR/hr Ch.-A2, B2 620 mR/hr 619 mR/hr SJAS Off Gas Log Rad Monitor Ch. A, B 4 mR/hr 4 mR/hr s Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.7 mR/hr 0.7 mR/hr N' , o All other monitors display normal readings
- Alarm OS Offscale
- . ,=_ .,,
1985 Evaluated Exercise Time = 1545 1 . . l Message Number - 51 e= 08/15 COOPER NUCLEAR STATION' i EMERGENCY PREPAREDNESS EXERCISE MESSAGE i ! e Message For: Control Room /OSS i Simulated Plant Conditions: See attached Plant Data and Rad Monitor Sheets 3 Message: * *
- THIS IS A DRILL * *
- i i
i i i i a 1 For Controller Use Only: . CONTROLLER INFORMATION:
+
i. J
- EXPECTED ACTIONS:
ygw p g&
- s, r y ' w Te e t-9+-+-- ---eA-*r-P-Ma-- c's m 7g.ie'.gr -9+-e- t *s459- 'N-e--P'T*eme--=e ete= -eD + e- ,%%+ w.-a-w.e
1985 Evaluated Exercise Time = 1545
%sssage Number 51 t= 08/15 \
COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA , PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 6x10 SRM i RHR A SUP PL CLG 100 7000 REACTOR LEVEL 35" + NR
- RHR B SUP PL CLG 100 7000 REACTOR PRESSURE 50 psig RHR C LPCI 100 7000 CORE D/P (psig) 1.0 RHR D LPCI 100 7000 , CORE ELOW 3.5-CS A OP 250 MIN FLOW (
- 6 FLOW (10 1bs/hr)
CS B OP 250 MIN FLOW FEEDWATER A 0 HPCI ISOLATED 0 0 FEEDWATER B 0 i Drywell Pressure 15.0 (PSIA) MAIN STEAM A 0 Torus Level +1.1*(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 50 (gpm) STATUS PRESS (psig) FLOW (gpm) CRD B AVAIL (gpm)- RCIC ISOL 200 400 LEVEL PRESS SQUIB PUMPS RWCU A TRIPPED 0 SLC 75 % 0 (psig) ON Avail RWCU B TRIPPED O RRPA 0 % SPD MISCELLANEOUS PANELS RRPB 0 % SPD DIESEL GEN A OP
GEN B OP Slut A OP SBGT B OP J
DRYUELL COOLING NORMAL TORUS WATER' TEMP 90 'F I' -
Time = 1545 RADIATION MONITOR DATA t= 08/15
, AREA RADIATION MONITORS
~'
STATION DESCRIPTION READING 1 Rx Bldg Fuel Pool Area (SE Sch Floor) 150 mR/hr 2 Rx Bldg Fuel Pool Area (SE 5th Floor) 6 mR/hr 3 Rx Bldg New Fuel Area (SE Sth Floor) 0.1 mR/hr 4 Rx Bldg Rx Water Cleanup Demineralizer Area (SW 3rd Floor) 9 mR/hr 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 1 mR/hr 6- Rx Bldg Neutron Monitor System Index Area (TIP Room ist Floor) 31 mR/hr 7 Rx Bldg Neutron Monitor System Drive Mech Area (SE 1st Floor) 2 mR/hr 8 Rx Bldg Control Rod Hydraulic Equipment Area (S ist Floor) 0.9 mR/.hr 9 Rx Bldg Control Rod Hydraulic Equipment Area (N 1st Floor) 9 mR/hr 10 Rx Bldg HPCI Pump Room (SW Quad) 4.5 mR/hr 11 Rx Bldg RHR Pump Room (SW Quad) 65 mR/hr 12 Rx Bldg RHR Pump Room (NW Quad) 92 mR/hr 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 19 mR/hr 14 Rx Bldg CS Pump Room (SE Quad) 25 mR/hr 15 Turbine Bldg Turbine Front Standard 0.4 mR/hr 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.02 mR/hr 17 Turbine Bldg Turbine Bldg-Basement Control Corridor 0.01 mR/hr 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 0.3 mR/hr 19 Turbir.e Bldg Turbine Eldg Condensate Pump Area
, , 0.02 mR/hr 20 Control Room Main Control Room 0.01 mR/hr 21 Grade Level Control Corridor 0.1 mR/hr Panel 9-02 Personnel Airlock Area 903 , 6.5 R/hr Panel 9-02 Ladder 903 to 2nd-Level 6.3 R/hr PROCESS AND VENT MONITORS PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 1.6El uCi/sec ERP Stack Normal Eff (RMP-RM-3A) 2.0E1 uCi/sec ERP Stack High Range.(RMP-RM-3B) -0.0 uci/see Turbine Bldg Vent Eff (RMV-RM-20A) 2.9E0 uCi/sec Turbine Bldg High Range (RMV-RM-20B) 0.0 uCi/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 3.4E0 uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) 0.0 uCi/sec PANEL 9-10 Mn. Stm. Rad Monitor Ch. A2, B1 618 mit/hr 620 mR/hr Ch. A2, B2 620 mR/hr 619 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, 3 4 mR/hr 4 mR/hr Rx Bldg Vent Ind! Trip Unit Ch. A, B 0.7 mR/hr 0.7 mR/hr
.o All other monitors display normal readings
- Alurm .
OS Offscale
. .- . - . . .. - . . . .. . . . ~ . .. -
a r 2 1985. Evaluated Exercise Time = 1600 Message Number 52 t= 08/30 4 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE
. Message For: Control Room /OSS '
4 ^ Simulated clant Conditions: See attached Plant Data and Rad Monitor Sheets i Message: * *
- THIS IS A DRILL * *
- I l
4 i i i e i t 4 i f . For Controller Use Only: } CONTROLLER INFORMATION: l i i i ! i-i 1 i EXPECTED ACTIONS: i t i i, (
._. . . . , _ . _ . _ . _ -_ . _ - , - ._ _ . , _ . . . -- . . - . ___.,__m- . . . . - ..._-_. .
1985 Evaluated Exercise Time = 1600 O *tassage Number 52 08/30 U COOPER NUCLEAR STATION t= EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 6x10 SRM RHR A TORUS CLG 100 7000 REACTOR LEVEL 35" + NR RHR B TORUS CLG 100 7000 REACTOR PRESSURE 50 psig RHR C STBY 100 0 CORE D/P (psig) 1.0 RHR D STBY 100 0 CORE FLOW 3.5 0 CS A STBY 250 0 (0 nmM 6 FLOW (101bs/hr) CS B STBY 250 0 FEEDWATER A 0 HPCI ISOLATED 0 0 FEEDWATER B 0 Drywell Pressure 15.0 (PSIA). MAIN STEAM A 0 Torus Level +1.1 (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 PPISS(psig) FLOW (gpm) CRD B' AVAIL (gpm) RCIC ISOL 0 0 LEVEL PRESS SQUIB PUMPS RWCU A TRIPPED 0 SLC - 75 % 0 (psig) ON Avail RWCU B TRIPPED 0 RRPA 0 % SPD MISCELLANEOUS PANELS RRPE O % SPD DIESEL GEN A OP DIESEL GEN B OP SBGT A OP SBGT B OP DRYWELL' COOLING NORMAL t TORUS WATER TEMP 90 'F 1 [ ( ._ .- .- _ . . . ~ - - - - -- - - -----
t
'Tima = 1600 RADIATION MONITOR DATA t= 08/30 STATION RI ION READING 1 Rx Bldg Fuel Pool Area (SE' 5th Floor) 150 mR/hr , 2 Rx Bldg Fuel Pool Area (SE Sch Floor) 6 mR/hr 3 Rx Bldg New Fuel Area (SE Sch Floor) 0.1 mR/hr 4 Rx Bldg Rx Water Cleanup Demineralizer Area i
(SW 3rd Floor) 9 mR/hr 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 1 mR/hr 6 Rx Bldg Neutron Monitor System Index Area { (T1P Room ist Floor) 31 mR/hr , 7 Rx Bldg Neutron Monitor System Drive Mech Area (SE 1st Flocr) 2 mR/hr i 8 Rx Bldg Control Rod Hydraulic Equipment Area 1 (S 1st Floor) 0.9 mR/hr ; 9 Rx Bldg Contrc3 Ec.d Hyd .ulic Equipment Area (N-1st Floor) 9 mR/hr 10 Rx Bldg HPCI Pump Room (SW Quad) 4.5 mR/hr 11 Rx Blds RHR ? ump Room (SW Quad) 65 mR/hr 12 Rx Bldg RHR Pump Room (NW Quad) 92 mR/hr
; 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 19 mR/hr 14 Rx Bldg CS Pump Room (SE-Quad) 25 mR/hr ! 15 Turbine Bldg Turbine Front Standard 0.4 mR/hr j 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.02 mR/hr 17 Turbine Bldg Turbine Bldg Basement Control Corridor 0.01 mR/hr j 18 Turbine, Bldg Turbine Bldg Rx Feed Pump Area 0.3 mR/hr y,,/ 19 Turbine Bldg Turbine Bldg Condensate Pump Area 0.02 mR/hr 20 Control Room Main Control Room 0.01 mR/hr j 21 Grade Level Control Corridor 0.1 mR/hr Panel 9-02 Personnel Airlock Area 903 6.5 R/hr Panel 9-02 Ladder 903 to-2nd Level 6.3 R/hr 4
PROCESS AND VENT MONITORS i PANEL VBDG Rx Bldg Vent Eff.(RMV-RM-40) 1.6El uCi/sec ERP Stack Normal Eff (RMP-RM-3A) 2.0E1 uCi/sec ERP Stack High Range (RMP-RM-3B) 0.0 uC1/sec
- Turbine Bldg Vent-Eff (RMV-RM-20A) 2.9E0 uCi/sec
) Turbine Bldg High Range (RMV-RM-20B) -0.0 uC1/sec , RW/ARW bldg Combined Eff (RMV-RM-30A) 3.4E0 uCi/se: ) RW/ARW Bldg High Range (RMV-RM-30B) 0.0 uCi/mec PANEL 9-10 Mn. Stm. Rad Monitor Ch. A2, B1 618 mR/hr 620 mR/hr 3 Ch. A2, B2 620 mR/hr 619 mR/hr
- SJAE Off Cas Log Rad Monitor Ch. A, B 4 mR/hr 4 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.7 mR/hr 0.7 mR/hr k-- o All other monitors display normal readings
- Alarm OS Offscale
_ . . . . _ _ . . . . _ . _ _ . . _ - . _ . . . _ _ ._ m_. - _ _ _ _ . . _ . . _ . . . J
, ~ 1985 Evaluated Exercise Time = 1615 Message Number 53 e= 08/45 i
COOPER NUCLEAR STATION f I EMERGENCY PREPAREDNESS EXERCISE ~ MESSAGE -
-i Message For: Control-Room /OSS f Simulated Plant Conditions: See attached Plant Data and Rad Monitor Sheets ;- i
- l. Message: * *
- THIS IS A DRILL * * * !
1 1 1 i I j i 4 1-t t t i i i : i ! I For Controller Use Only: l CONTROLLER INFORMATION: l i i i l
- EXPECTED ACTIONS
g. 4 L l r I-l l n l
. . . . , , , .. - , - - , , , . . - - . . . . . - - , . . - . . . . + . , , , .
,e. ~ , . . , , _ , , , , _ . ~ . . . _ , . . , - - _ , - , . . . . . , _ , . _ , . , - . . . - . _ _ _ . , . . . . , _ . . . . , . . . - , _ . _ . ~ _ - ~ . .
o 1985 Evaluated Exercise Time -- 1615
!assage Number -53 e= 08/45 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA , PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 6x10 SRM RHR A SUP PL CLG 100 7000 35" +
REACTOR LEVEL NR j RHR B SUP PL CLG 100 7000 REACTOR PRESSURE O psig i RER C STBY 0 0 CORE D/P (psig) 1.0
, RHR D STBY 0 0 CORE FLOW 3.5 CS A STBY 0 0 6 ; FLOW (101bs/hr) i CS B STBY 0 0 --
_ FEEDWATER A 0 HPCI ISOLATED 0 0 FEEDWATER B 0 Drywell Pressure 15.0 (PSIA) MAIN STEAM A 0 Torus Level +1.2 (inches) MAIN STEAM B 0 i OPEN CLOSED MAIN STEAM C 0 MSIV 0 8 MAIN STEAM D 0 FLOW t PANEL 9-4 CRD A 50 (gpm) STATUS PRESS (psig) FLOW (gpm) CRD B AVAIL (gpm) l RCIC ISOL 0 0 LEVEL FRESS PUMPS SQUIB I RWCU A TRIPPED 0 SLC 75 % 0 (psig) ON Avail i
. .RWCU B T"IPPED 0 RRPA 0 % SPD l MISCELLANEOUS PANELS j RRPB -0 % SPD DIESEL GEN A OP DIESEL GEN B OP SBGT A OP j SBGT B OP DRYWELL COOLING NORMAL 7
I TORUS WATER TEMP 89 'F E
Time = - 1615 RADIATION MONITOR DATA t= 08/45 AREA RADIATION MONITORS (O,) STATION DESCRIPTION READING 1 Rx Bldg Fuel Pool Area (SE Sch Floor) 150 mR/hr 2 Rx Bldg Fuel Pool Area (SE Sch Floor) 6 mR/hr 3 Rx Bldg New Fuel Area (SE Sth Floor) 0.1 mR/hr 4 Rx Bldg Rx Water Cleanup Demineralizer Area , (SW 3rd Floor) , 9 mL/hr 5 Rx Bldg Sludge and Decant Pump Area (S 2nd Floor) 1 mR/hr 6 Rx Bldg Neutron Monitor System Index Area (TIP Room 1st Floor) 31 mR/hr 7 Rx Bldg Neutron Monitor System Drive Mech Area (SE 1st Floor) 2 mR/hr 8 Rx Bldg Control Rod Hydraulic Equipment Area (S 1st Floor) 0.9 mR/hr 9 Rx Bldg Control Rod Hydraulic Equipment Area (N 1st Floor) 9 mR/hr 10 Rx Bldg HPCI Pump Room (SW Quad) 4.5 mR/hr il Rx Bldg RHR Pump Room (SW Quad) 65 mR/hr 12 Rx Bldg RHR Pump Room (NW Quad) 92 mR/hr 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 19 mR/hr 14 Rx Bldg CS Pump Room (SE Quad) 25 mR/hr 15 Turbine Bldg Turbine Front Standard 0.4 mR/hr 9 16 Turbine Bldg Turbine Bldg Mezz Control Corridor 0.02 mR/hr 17 Turbine Bldg Turbine Bldg Basement Control Corridor 0.01 mR/hr
/'~'s 18 Turbine Bldg Turbine Bldg Rx Feed Pump Area 0.3 mR/hr
( ,) 19 Turbine Bldg Turbine Bldg Condensate Pump Area 0.02 mR/hr t 20 Control Room Main Control Room 0.01 mR/hr 21 Grade Level Control Corridor 0.1 mR/hr Panel 9-02 Personnel Airlock Area 903 6.5 R/hr Panel 9-02 Ladder 903 to 2nd Level 6.3 R/hr a PROCESS AND VENT MONITORS PANEL VBDG 4 Rx Bldg Vent Eff (mfV-RM-40) 1.6El uCi/sec ERP Stack Normal Ef f (RMP-RM-3A) 2.0E1 uCi/sec ERP Stack High Range (RMP-RM-3B) 0.0 uCi/sec Turbine Bldg Vent Eff (RMV-RM-20A) 2.9E0 uCi/sec Turbine Bldg High Range (RMV-RM-20B) 0.0 uCi/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 3.4E0 uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) 0.0 uCi/sec PANEL 9-10 Mn. Stm. Rad l'.onitor Ch. A2, B1 618 mR/hr 620 mR/hr Ch. A2, B2 620 mR/hr 619 mR/hr SJAE Off Cas Log Rad Monitor Ch. A, B 4 mR/hr 4 mR/hr l Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.7 mR/hr -0.7 mR/hr 4 i o All other monitors display normal readings <
- Alarm OS Offscale L
. . .m_-_... _ , _ . _ . _ . . _ _ __ _ _ _ _ . . . ..-_. . ._ _ _ . . _ _ . _ _ _.. _..
I I
- 1985 Evaluated Exercise Time = 1630 -J
} -- Message Number '54 t*= 09/00 d j i COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE , 4 Message For: Control Room /OSS i Simulated Plant Conditions: Message: * *
- THIS IS A DRILL-* *
- i The drill is terminated.
i b i i i i I i I I i ! For Controller Use Only? - I CONTROLLER INFORMATION: I l t l I l
- EXPECTED ACTIONS
i
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- SECTION 9.0 ONSITE RADIOLOGICAL AND t RADI0 CHEMISTRY DATA i -
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f-~s Onsite Radiological Data
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All readings art background prior to 1300. From 1300 to 1445, contact readings of the ERP will be approximately 600 R/hr, dropping to 200 R/hr at 1500 and to background at 1515. Readings upwind (south) of the ERP are the result of gamma shine from the ERP. Concentric rings labled B, C, D, E, and F represent distances of 100, 200, 300, 400, and 500 feet , respectively, from the ERP. The following are readings at distances B - F: B = 60 mR/hr (20 mr/hr C = 15 mR/hr 5 mr/hr 1300 - 1445 D= 6 mR/hr 1515 }} 2 mR/hr E= 3 mR/hr i 1 mr/hr e F= 2 mR/hr ( 0.6 mR/hr Readings downwind of the ERP, beyond the Miasouri River, are the result to gamma shine from the plume. Centerline (A) dose rates of approximately 24 mR/hr will be present from 1300 to 1500. Subsequent readings will be reported as background. Dose rates should be reported as approximately 1/10 of the centerline for each isopleth crossed, i.e., 24 mR/hr directly under centerline, 2.4 mR/hr along isopleth C, 0.24 mR/hr along isopleth D, etc. The plume does not touch down onsite, therefore all air samples taken onsite should be reported :a background. All dose rates will be the same, regardless of whether the shield is open or closed, n v u>
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i l i 1 1 I I 1 1 t i i 1 ) SECTION 10 I METEOROLOGICAL AND OFFSITE RADIOLOGICAL DATA i 1 l 1 l
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_.y. . I y 4 TABLE 10.2 - RELEASE RATES USED TO CALCULATE FIELD DATA
- Downwind Distance (Miles) i.
1 - Scenario 4
- Time .0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 6.0 7.0' 8.0 '9.0 -10.0.
t 5 1 05/00 05/15 l 05/30
- . 05/45 'A A 06/00 B B A. A 06/15 C C B B A. A- -
. 06/30 D D 'C .C B B A A 06/45 .E E D- D C C B B A A '
I '07/00 F F E E D -D C C. B B A
. .07/15 C C' F F E' E D D C ,C B A
' 07/30 H 11 G G F F E E D D D B A 07/45 I H G F E o 08/00 I 08/15
? NOBLE CAS RELEASE RATE (pCi/sec). . IODINE RELEASE RATE (pCi/sec) 1
! A: 8.00E7 A: 2.00E5
[- B: 1.00E8 B: 2.50E5 ! C: 1.00E8 C: 2.50E5
- D
- 1.00E8 D: 2.50E5
- .E
- 9.80E7 E: 2.45ES l F: 9.60E7 F: 2.40E5 i G:' .9.40E7 C: 2.35E5. '
I H: 3.00E7 - H: 7.50E4 l' I: 2.0E1 I: 5.0E2 3 4 1
- i
O O O TABLE 10.3A - WHOLE. BODY DOSE RATES AT PLUM'E CENTERLINE (mrem /hr) - OPEN WINDOW Downwind Distance (Miles) Scenario Time 0.5 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 10.0 05/15 05/30 05/45 371 1484 06/00- 463 1612 975 700 06/15 462 1608.1213 680 602 472 06/30 462 1612 1240 885 729 602 409 340
.06/45 454 1580 1239 880 718 606 508 424 300 260 07/00 445 1548 1225 864 726 588 -509 424 375 328 234 208
.07/15 436 .1516 1190 844 720 576 506 423 376 329 300 260 194 172 07/30 139 484 1172 828 700 564 501 416 370 328 288 262 240 216 160 144 07/45
- 25 '16 50 40 44 36 40 32 32 28 08/00
- 08/15 o.These are open window readings.
- Background readings are 0.02 mrem /hr.
~
~
- . j
~
i l l TABLE'10.3B - WHOLE BODY DOSE RATES AT PLUME CENTERLINE (mrem /hr) - CLOSED WINDOW i i l Downwind Distance (Miles) ! Scenario 2.0 3.0 4.0 5.0 6.0 7.0 8.0 Time 0.5 1.0 9.0 10.0 05/15
- l l 05/30
- 05/45 371 323 .
i 06/00 463 403 250 176 ! 06/15 462 402. 311 220 147 .118 l 06/30 462 403 310 221 184 147 102 85
- 06/45 454 395 310 220 182 148 127 106 75 65 .;
- 07/00 445 387 306 216 183 147 127 106 94 82 58 52
- 07/15 436 379 -298 211 180 144 126 106 94 82 74 65 48 43 07/30 139 .121 293 207 176 141 125 104 92 82 72 65 60 54 39 36 j 07/45 6 4 13 10 .11 9 10 8 8 7 [
- - 08/00
- 08/15~
= _ _ _ -
o These'are closed window readings. ]
- Background readings are 0.02 mrem /hr.
l i l i i i i k 4 I t
4 TABLE 10.4A - CHILD THYROID DOSE RATES AT PLUME CENTERLINE (Rem /hr) 1 Downwind Distance (Miles) 1 . Scenario . Time 0.5 .l .0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 10.0 t 05/15 l .05/30 05/45 t 10.5 ; 06/00 t -13.2 8.I 5.7 h
.06/15 t 13.2 10.2 7.2 4.8 3.8 .
i 06/30 + 13.2 10.2 7.2 6.0 4.8 3.3 2.8 06/45 t. 12.9 10.2 7.2 6.0 4.8 4.2 3.5 2.5 2.1 07/00 t 12.6 9.9 7.0 6.0 4.8 ~ 4.2 3.5 3.1 2.7 1.9 1.7 .i
! 07/15 t 12.4 9.8 6.9 5.9 4.7 4.2 3.5 3.1 2.7 2.4 2.1 1.6 1.4
. 07/30- t 3.9 9.6 6.8 5.8 4.6 4.1 3.4 ,3.1 2.7 2.4 2.1 2.0 1.8 ,1.3 1.2 07/45
- 0.1 0.4 0.3 -0.4 0.3 0.3 0.3 0.1 0.2
- 08/00- *
, 08,115 1
i .t Plume from elevated release point does not touch down until after site boundary. ! 1 l
- Less than 0.1 Rem /hr 4
ti l 4
.e 4
?
~
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TABLE 10.4B - IODINE CONCENTRATION AT PLUPE CENTERLINE (pC1/cc) Downwind Distance (Miles) Scenario Time 0.5 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 10.0
~
C5/15 - 05/30 -05/45 t 2.8E-6 06/00 .t 3.5E-6 2.2E-6 06/15 t 3.5E-6 2.7E-6 1.9E-6 -1.3E-6 1.0E-6 06/30 t 3.5E-6 2.6E-6 1.9E-6 1.6E-6 1.3E-6 8.8E-7 7.5E-7 06/45 - t 3.5E-6 2.7E-6 '1.6E-6 1.6E-6 1.3E-6 1.1E-6 9.3E-7 6.6E-7 5.7E-7 C7/00 - t 3.4E-6 2.6E-6 1.9E-6 1.6E-6 1.3E-6 1.1E-6 9.3E-7 8.3E-7 7.2E-7 5.2E-7 4.6E-7 07/15 t 3.3E-6 .2.7E-6 1.9E-6 1.6E-6 1.2E-6 1.1F-6 9.3E-7 8.3E-7 7.2E-7 6.5E-7 5.7E-7 4.2E-7 3.8E-7 07/30 t 1.1E-6 2.6E-6 1.8E-6 1.6E-6 1.2E-o 1.0r-6 9.1E-7 8.3E-7 7.2E-7 6.5E-7 5.7E-7 5.2E-7 4.7E-7 3.5E-7 3.2E-7 07/45-
- 4.2E-8 3.4E-8 8.0E-8 8.9E-8 8.3E-8 7.6E-8 7.1E-8 6.7E-8 6.2E-8 5.9E-8
.08/00
- 08/15 .
t Plume from elevated release point does not touch down until af ter site boundary.
- Minimum detectable activity t
s r.. . . . . _ - a
r O 6 TABLE 10.4C - GROSS IODINE CONCENTRATION FOR E-140 WITil 177c PROBE OR RO-2 WITil DPEN WINDOWN (FIEl.1) TECilNIQUE) *. (mR/hr) Downwind Distance (Miles) Scanario-
. Time 0.5 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 10.0 i
.05/15s t 05/30 t 05/45 t 0.45- i 06/00 . t. 0.60 0.38 0.25 06/15' t 0.60 0.46 0.34 0.22 0.18
.06/30 t 0.60. 0.46 0.34 -0.22 0.18 06/45 t 0.60 0.45 0.35 0.28 0.22 0.15 0.12 t 07/00 t 0.60 0.46 0.34 0.28 0.22 .0.20 0.16 0.11 0.10 07/15 t 0.57 0.45 0.34 0.28 0.22 0.20 0.16 0.14 0.12 0.09 0.08 07/30 t 0.55 0.46 0. 3 '4 0.28 .0.20 0.20 0.16 0.14 0.12 0.11 0.10 0.07 0.06 07/45- t 0.20 0.45 0.30 0.28 0.20 0.18 0.15 0.14 0.12 0.11 0.10 0.09 0.08 0.06 0.05 08/00 -* *
- 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.01 08/15
- o All concentrations are for samples taken at plume centerline.
* < 0.01 mR/hr i
p 0 0 0 0* 1 1 0 0 1 O 0 9 0 0 1 d n a m p 0 0 c 1 n i E 0 00 s N 00 i I 8 31 L e R t E a T 00 r N 00 E 51 t C . n u E o M 0 000 c U 000 L 7 571 . e P , r e T h A 000 w 000 N 671' , . E ] y K 1 r A 3 a T ) 0 0000 1 d
) s 0005 - n SE e 6 788 I u ET l [ o LU i b PN M 9 MI ( 0000 E e AM 0006 9~ t S e 899 9 i R c s EE n 7 NP a 000 . e I t 0 0000* = ]h O DS s 0000 et OT i 5 81 1 1 e . n I N D t ir U . a d e RO d 0000 f R ot OC n 0000 l If F i 0222 e t a T w 1 1 1 1 h n l SE n s u al GN w o ti N( o 00000 h C ot I D 0 00000 t Tn D 1 3333 r n [ u A
E 4 1 1 1 1 1 u o o' p 8 n R f u 1 w 00000 . o 2 00000 e , d 0d
- 36664 hr e M 1 1 1 1 1 t e s eh A l a bc S np b u
- 0 000000 000000 oma . oo sct t D 3 499977 1 1 1 1 1 1 ,de s i c
/dt 4 d cr nieo eai oC mn 0 000000 ml a i p u 1 000000 up ss E.
933333 1 22222 s ssosriao ntanse l ae et d B l et nss A 0000000 rpt ueiid T 0 0000000 omanc n 2777776 rarinnna 2 2222222 rs e mooo w ciid ro5 t t a 0000000 0000000 f ol off sorrh maae 2989898 i rt t r 3333333 nem i rf e f nne eev gacmncco 0 00000000 r i onn 00000000 as2ti oos 1 00000986 mg scci 45555441 neer
%i ml e11 e 0d upv33 m 5 -
1 asmn11 u ttttttttt esao- l 0 iRASCIIP ( ooooo ot - o i r a 5050505050505 - ne 1 3401 34013401 em ci
/////////////
5556666777788 ST 0000000000000
/*%
/
kg) (Ai sj. TABLE 10.5 - STATE OF MISSOURI SAMPLING POINTS: j W110LE BODY DOSE RATES (mR/hr) {- Actual Time / Scenario Time 1300 1315 1330 1345 1400 1415 1430 1445 1500 1515 1530 A 05/30 05/45 06/00 06/15 06/30 06/45 .07/00 07/15. .07/30 07/45 08/00 i , - C-2 *
- 176 220' 221 220 216 211 207 * *~
- C-11 7 9 9 9 9 9 *
- i C-12 5 6 6 6 6 *
- s C-13 80 100 100 100 98 * *
- C-14 58 74 72 6
- I C-15 3' 3 3 0.2
- C-3 52 65 65 0.2
- C-16 2 3 0.5 * *
{ C-17 40 50 8 *
- I C-18 2 3' O.5 *
- i C8-4 36 9'
- j C8-5 18 5
- C8-7 2 0.5
- i C-19 8 *
; C-20 0.8 *
! C-21 0.8
- i C10-3 0.4
- C10-6 3.5
- l r
- i
- *- Background readings are less than 0.02 mR/hr t o Plume boundaries are assumed to be 5% of centerline; linear j interpolation is assumed for points between centerline and the
; plume boundary. ,
J.. a i
g r- % TABLE 10.6 - STATE OF HISSOURI SAMPLING POINTS: LUDLUM MODEL 2218 READINGS FOR AIR SAMPLES (CDUNTS PER HINUTE) Actual Time / Scenario Time 1300 1315 1330 1345 1400 1415 1430 1445 1500 1515 1530 ION 05/30 05/45 06/00 06/15 06/30- 06/45 07/00 07/15 07/30 07/45 08/00 C-2 * *
- 7200 7200 7200 7200 7200 7000 *
- C-Il 300 400 300 400 400 300 *
- C-12 150 200 200 200 200 *
- C-13 3000 3500 3500 3500 3400 *
- C-14 2000 2500 2500 150
- C-15
- 100 100 *
- C-3 1700 2200 2700 100
- C-16 * * * *
- C-17 1300 1600 300
- C-18 * * * *
.C8-4 1200 300
- C8-5 600 150
- C8-7 * *
- C-19 300
- C-20 150
- C-21 120
- C10-3 *
- C10-6 100
- o z 10% margin of error is assumed.
o Assume 2.0 cfm flow rate on sampler, o Sample time is 5 minutes. . o Conversion from concentration is based upon Count Rate = 2.1 x 1010 [ Iodine] where count rate is in eps and Iodine, o I-131 concentration is assumed to be 0.18 [ Total Iodine]. o Plume boundaries are assumed to be 0.05 [ plume centerline]; values between centerline and plume boundaries are derived by means of linear interpolation. o . Background (<.100 cpm).
7
;~ ~
,s (v v
)
TABLE 10.7 - IODINE DEPOSITION - REENTRY / RECOVERY PilASE Plume Centerline Plume Boundary Distance Plume Center 11ne Plume Boundary Survey Heading at Survey Reading at 2 2 from ERP (Miles) Deposition (pCi/cm ) Deposition (uC1/cm ) 3" from ground 3" from ground (mR/hr) 1.0 8.9E-6 0 0.18 Background 1.5 6.4E-6 0 0.14 Background 2.0 3.9E-6 0 0.09 Background 2.5 3.3E-6 0 0.05 Background 3.0 2.6E-6 0 0.05 Background 3.5 1.9E-6 0 0.04 Background 4.0 1.6E-6 0 0.03 Background 4.5 1.lE-6 0 0.02 Background 5.0 9.7E-7 0 0.02 Background 5.5 6.8E-7 0 0.01 Background 6.0 5.7E-7 0 0.01 Background 6.5 3.6E-7 0 Background Background 7.0 3.4E-7 0 Background Background 7.5 1.5E-7 0 Background Background 8.0 1.4E-7 0 Background Background 8.5 2.5E-8 0 Background Background 9.0 2.4E-8 0 Background Background 9.5 2.2E-8 0 Background Background 10.0 2.lE-8 0 Background Background For Soil Samples: Deposition x 0.47 = pCi of Iodine For Water Samples: Deposition x 0.40 = pCi of Iodine cc of soil ml of water Deposition x 0.53 = pCi of Iodine To compute values for specific isotopes: gm of soil 0.02 I-134 For Vegetation: Deposition x 0.35 = pCi of Iodine Total Iodine 0.05 g , I-132 gm of vegetation Concentration 0.21 , I-135 f 0.27 I-133 0.45 I-131
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