ML20125B656
| ML20125B656 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 11/28/1984 |
| From: | NUTECH ENGINEERS, INC. |
| To: | |
| Shared Package | |
| ML20125B635 | List: |
| References | |
| FOIA-84-896 PROC-841128, NUDOCS 8506110491 | |
| Download: ML20125B656 (748) | |
Text
{{#Wiki_filter:. . Attachment 5 t ). THE CLEVELAND ELECTRIC ILLUMINATING COMPANY PERRY NUCLEAR POWER PLANT EMERGENCY PREPAREDNESS EXERCISE MANUAL i
, 1984 EMERGENCY PREPAREDNESS EXERCISE i
CCNTROLLED COPY NO. N t 4 Prepared by: NUTECH ENGINEERS BETHESDA, MARYLAND 8506110491 B50124 PDR FOIA HIATTB4-896 PDR 5[
PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TABLE OF CONTENTS
' u FOREWORD
? INTRODUCTION TABLE OF CONTENTS Y TJ . LIST OF FIGURES Si' PART I GENERAL INFORMATION [ ' 1.0 SCOPE AND OBJECTIVES
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1 1.1 Scope
"] 1.2 Onsite Objectives 1.3 Offsite Objectives
[; ' 1.4 Precautions and Limitations
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'j 2.0 EXERCISE INFORMATION 4
D 2.1 Exercise Participants _2.2 . Exercise Organization
,i - 2.3 Emergency Response Facilities
, ]j . 2.4 Exercise Conduct 2.5 Evaluation and Critique u..;
5 3.0 TRAVEL INFORMATION 3.1 Directions to the Perry Plant
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3.2 Accommodations m
4.0 REFERENCES
/ ABBREVIATIONS / DEFINITIONS V7.1 '
N]'s . 4.1 References 4.2 Abbreviations
.If k. 4.3 Definitions
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'?.-4 5.0 SCHEDULE OF EVENTS
.3 PART II CONTROLLED INFORMATION (RED TABS)
'id 6.0 EXERCISE SCENARIO
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6.1 Initial Conditions ari
~' 6.2 Narrative Summary - Onsite Sequence of Events 6.3 Narrative Summary - Offsite Sequence of Events 6.4 Written Summary of the Exercise Scenario
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( PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TABLE OF CONTENTS . (Continued) s 7.0 MESSAGE FORMS AND PLANT DATA SHEETS g !] 8.0 RADIATION / CHEMISTRY AND METEOROLOGICAL DATA
'8.1 Radiological and Meteorological Summary 8.2 Site Radiological Data A. Contaminated Injured Person Data
' .] B. Post-Accident Sampling System Results C. In Plant Radiation Data 3 D. Onsite Radiation Levels E. MIDAS Inputs 8.3 Offsite Radiological Data
'i' A. Plume Location B. Meteorological Data C. Whole Body Dose Rates D. Thyroid Dose Rates E. Maps
,j F. State of Ohio Sampling Points and Data G. Contaminated Injured Person (Ashtabula County)
-i-9.0 CONTROLLER AND EVALUATOR INFORMATION 9.1 Controller Instructions
- 9.2 Evaluator Instructions 9.3 Personnel Assignments
-i 9.4 Evaluation Packages
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- PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDSESS EXERCISE LIST OF FIGURES Section 2.0 FIGURE 2.1 CONTROL ROOM SIMULATOR LAYOUT , FIGURE 2.2 TECHNICAL SUPPORT CENTER LAYOUT FIGURE 2.3 OPERATIONS SUPPORT CENTER LAYOUT FIGURE 2.4 EMERGENCY OPERATIONS FACILITY LAYOUT
?j-FIGURE 2.5 JOINT PUBLIC INFORMATION CENTER LAYOUT Section 3.0 FIGURE 3.1 PERRY PLANT SITE LOCATION
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DIRECTIONS FROM CLEVELAND HOPKINS INTERNATIONAL AIRPOR
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i. CLEVEL#D ELECTRIC ILI.lMINATIKi(GPANY PERRY MILENt POMR P1./NT . 1984 MCAL EMRI%"Y PREPAREDESS EERCIS y
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ide the basis for the
- l* This exercise package has been d developed to provt at the P conduct of a sinulated radiological acci en Through this exercise Plant Unit I located in Lake County, Chio. y Response Plans for capabilities and effectiveness of theh Brergenc State of G io, and
] The Cleveland Electric illuninating Carpany, t e This. package is to j be evaluated.
I the associated local counties will b rvers of the Federal, be utilized by the exercise controllers andinitiate, o se control i State and local agencies, as well asinthe t Utility to the exercise. 4 and evaluate the activities of the participan s h State of Chio The Cleveland Electric illuninating Carpany and t enduc approve this docurent as the standard for co l Emergency Preparedness Exercise.
. the Noverrber '23,1984 -
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.o J. Vice PMsident K. Bi Cole MJclear Group Nuclear Operations Officer Chlo Disaster Services Agency Ferry Nuclear Power PlantTh State of G io
THE CLEVELAND ELECTRIC ILLUMINATING COMPANY PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE INTRODUCTION The Perry Nuclear Power Plant (PNPP) Emergency Plan describes the emergency including q response capabilities for a nuclear emergency at the Perry Plant, support from Federal, State, and local government agencies and private organi-zations. The PNPP Emergency Plan provides. for continuous emergency prepared-g ness, including an annual full-scale exercise.
] The purpose of the Exercise is to activate and evaluate major portions of the y
emergency response capabilities and other aspects of the Emergency Plan and
.] associated Emergency Plan Implementing Instructions, in accordance with i
l Nuclear Regulatory Commission (NRC) Regulation 10CFR50.47(b) and Appendix E. The exercise is conducted jointly with appropriate State and local agencies in
.; order to assess State and local government emergency response plans, as required by Federal Emergency Management Agency (FEMA) Regulation 44CFR350.9(b)
; The conduct and evaluation of the Exercise provide additional training for
,J emergency response organization personnel and a means to further enhance The Illuminating Company's emergency response capability.
}
'I This Exercise Manual has been developed to provide the basis for the conduct of a simulated radiological accident at the Perry Nuclear Power Plant Unit 1
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facility located in North Perry Village, Ohio, through which the capabilities
- and effectiveness of the Emergency Response Plans for The Cleveland Electric I
Illuminating Company, the States of Ohio and Pennsylvania, and Ashtabula,
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Geauga and Lake Counties can be evaluated.
.This manual is to be utilized by
.4 the exercise controllers and observers of the Federal, State and local j agencies, as well as the utility, to initiate, control, and "evaluate Exercise players" the will not U
activities of the participants in the exercise. have prior knowledge of the nature of the simulated incident or anytimes, including parts thereof such as, radiological plume release information, i content, size and weather pattern used. This Exercise Manual is the Partcontrol mechanism I provides a general for the conduct description of the Exercise and overview and consists of two parts. of an emergency exercise. Part II contains the scenario and time schedule of simulated plant conditions and is subject to a limited, controlled distri-bution, NOTE: As exercise efforts progress, minor changes may be required to this f., scenario package. Any changes will be identified during pre-i exercise meetings. I a i [ m
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PART I GENERAL INFORMATION l
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; SCOPE AND OBJECTIVES I -1 ,
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y . 1.0 SCOPE AND OBJECTIVES 1.1 l Scope U ~ The 1984 Emergency Preparedness Exercise, to be conducted on ' November 28, 1984, will simulate accident events culminating in a radiological accident with resultant off-site releases from the Perry Nuclear Power Plant, located in North Perry Village,
- Lake County, Ohio. The Exercise will involve events that test the effectiveness of the Perry Emergency Preparedness Program and the j,l integrated capabilities of the Perry emergency organization and the emergency organizations of the State of Ohio and Lake, Ashtabula, and Geauga Counties. The Exercise will include the mobilization of state and local resources adequate to verify their capability to respond to an accident.
1 1.2 On-Site Obiectives The exercise objectives are provided as separate sections, divided into the objectives for the Plant (this section) and those of each state / local agency (following section). The major objective of the exercise is to demonstrate the integrated -- capabilities and a major portion of the basic elements defined
- within the emergency plans and organizations for PNPP. The specific j objectives for the PNPP portions of the exercise are as follows:
- 1. EMERGENCY PLAN
- a. Demonstrate the ability of PNPP to implement the Emergency Plan in a manner that protects the general public, the plant staff, and the plant.
- b. Demonstrate an effective exercise critique program, to
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. include participating plant staff, controllers, and observers.
- 2. CLASSIFICATION AND NOTIFICATION
- a. Demonstrate the ability of the PNPP staff to recognize and classify simulated abnormal plant conditions in accordance with established instructions.
- b. Demonstrate the ability of the PNPP staff to notify and update Federal, state, and local governments in accordance with Federal guidelines and established procedures and
- instructions.
- c. Demonstrate the ability of PNPP to notify and activate emergency response personnel.
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- 3. COMMUNICATIONS
;. a. Demonstrate the ability-to communicate between Emergency j Response Facilities.
3 . l b. Demonstrate the ability to share technical information j with the NRC, state, and counties.
- c. Demonstrate the ability of PNPP emergency communications q to:
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Transmit instructions to essential staff.
- Disseminate essential information to assisting agencies. ],
Operate a 24 hour / day alert and notification system.
- d. Demonstrate the ability to communicate with Radiation Monitoring Teams.
;j e. Demonstrate coordinated communications with the Perry ,j Township Ambulance and Lake County Memorial Hospital, l East.
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- 4. EMERGENCY RESPONSE FACILITIES I a. Demonstrate the adequacy, effectiveness, and proper j ,
utilization of the following facilities for the management j of a radiological emergency: Control Room (Simulator)
- Technical Support Center l' - Operations Support Center Emergency Operations Facility 1
Joint Public Information Center
. b. Evaluate the ability of the PNPP staff to operate Emer-gency Response Facilities.
l c. Demonstrate access control at Emergency Response Facil-4 ities. i 5. DIRECTION AND CONTROL 1 -d a. Demonstrate at.all PNPP emergency response facilities the Si ability to establish and maintain solid accident manage-ment command and control authority, and maintain continuity of authority throughout the exercise. I
- b. Demonstrate effective organizational control, including deployment of field teams, receipt and analysis of field data, and effective sharing of data between facilities for assessment.
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- c. Demonstrate the ability to assess the need for and to identify additional resources.
- 6. PUBLIC INFORMATION
- a. Demonstrate timely activation and staffing of the Joint Public Information Center by state, county, and PNPP personnel.
- b. . Demo'nstrate the coordination of state, county, and PNPP public information activities.
- c. Demonstrate the ability to provide timely public informa-tion releases and rumor control.
- d. Demonstrate the ability to interact effectively with the media during simulated emergency conditions.
- 7. ACCIDENT ASSESSMENT AND EVALUATION
- a. Demonstrate the activation, operation, and reporting f procedures of field and in-plant radiation monitoring teams.
- b. Demonstrate the ability to receive and assess radiological j
3 data from teams. 1l c. Demonstrate the ability to formulate and make protective 1 action recommendations to protect plant personnel and the 1 general public based on plant parameters and/or field monitoring information.
- d. Simulate the ability to assemble personnel and evacuate non-essential personnel.
'< e. Demonstrate the ability to determine the cause of the accident, terminate or limit radioactive releases, and place the plant in a safe condition. f
- f. Demonstrate the ability to obtain, analyze, and assess a Reactor Water Sample using the Post Accident Sampling System.
- g. Demonstrate the ability to develop alternative systems or 1 equipment alterations in response to accident affected
.i plant systems or components and to formulate procedures to accompany these modifications.
- 8. RADIOLOGICAL EXPOSURE CONTROL
- a. Demonstrate the ability to monitor and control the expo-sure of emergency workers.
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.b. Demonstrate the ability of PNPP to implement site access ccatrol procedures.
- c. Demonstrate the use of dosimetry equipment for the pro-tection of emergency workers.
- 9. RE-ENTRY AND RECOVERY
- a. Demonstrate the ability to identify requirements and procedures for re-entering evacuated areas.
- b. Damonstrate the ability to develop a program for damage assessment and plant recovery.
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- 10. IOCAL SUPPORT
- a. Demonstrate the initial treatment of a. contaminated injured person within the Protected Area and transport to and subsequent treatment at Lake County Hemorial Hospital
, East.
- b. Demonstrate the ability of the PNPP fire brigade and the Perry Township Fire Department to respond to and combat a fire at PNPP within the Protected Area.
! 1.3 Off-Site Objectives i The off-site agencies' objectives are found as follows: ' Amency Attachment State of Ohio 1 Lake County 2 Ashtabula County 3 Geauga County 4 FEMA Example Objectives Cross-Reference 5 The off-site exercise objectives are written in reference to the FEMA Example Exercise Objectives. Thus, for example, State of Ohio Exercise Objective No.1 discusses how the State of Ohio will meet FEMA Objective No.1. The state and counties correspond by number to the FEMA Example Objectives. 0
Attache:nt i Page 1 of 4 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE FEMA OBJECTIVE STATE OF OHIO OBJECTIVE (See Attachment 5)
- 1. Demonstrate ability to mobilize staff and. activate facilities promptly.
LIMITING CONDITIONS: None 1
- 2. Demonstrate ability to fully staff facilities and maintain staffing I around the clock.
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'. LIMITING CONDITIONS: None
- 3. Demonstrate ability to make decisions and to coordinate emergency activities. -
LIMITING CONDITIONS: None a 1
- 4. Demonstrate adequacy of facilities and displays to support emergency operations.
LIMITING CONDITIONS: None t
- 5. Demonstrate ability to communicate with all appropriate locations, 4 organizations, and field personnel.
i [j LIMITING CONDITIONS: None 4 6. Demonstrate ability to mobilize and deploy field monitoring teams in f a timely fashion.
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LIMITING CONDITIONS: None . i J 7. Demonstrate appropriate equipment and procedures for determining
. .i ambient radiation levels.
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LIMITING CONDITIONS: None i
Attechm:nt 1 Pago 2 of 4 FEMA OBJECTIVE . STATE OF OHIO OBJECTIVE
- 8. Demonstrate appropriate equipment and procedures for measurement of airborne-radiciodine concentrations as low as 10-' uCi/CC in the presence of. noble gases.
LIMITING CONDITIONS: None
- 9. Demonstrate appropriate equipment and procedures for collection, transport and analysis of samples of soil, vegetation, snow, water, and milk.
LIMITING CONDITIONS: All samples will be returned to the staging area, but will not be flown from the staging area to Columbus. The ability to analyze samples will be demonstrated by the Ohio Depart-ment of Health, out of sequence with the scer.ario.
- 10. Demonstrate ability to project dosage to the public via plume exposure, based on plant and field data, and to determine appropri-ate protective measures, based on PAG's, available shelter, evac-uation time estimates, and all other appropriate factors.
! LIMITING CONDITIONS: None
- 11. Demonstrate ability to project dosage to the public via irgestion pathway exposure, based on field data, and to determine appropriate protective measures, based on PAG's and other relevant factors.
LIMITING CONDITIONS: None
- 12. Demonstrate ability to implement protective actions for ingestion pathway hazards.
LIMITING CONDITIONS: No.te
- 13. Demonstrate ability to alert the public within the 10 mile EPZ, and disseminate an initial instructional message, within 15 minutes.
LIMITING CONDITIONS: The State will initiate the protective actions required and pass those recommendations on to the counties.
- 14. Demonstrate ability to formulate and distribute appropriate instruc-tions to the public, in a timely fashion.
LIMITING CONDITIONS: The State will distribute instructions direct-ly to the public through the JPIC, after counties have initiated EBS. B 4
Attcchm:nt 1 Page 3 of 4 FL% . STATE OF OHIO OBJECTIVE OBJECTIVE-
- 15. Will not be demonstrated, s
- 16. Will not be demonstrated. .
- 17. Will not be demonstrated.
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- 18. Will not be demonstrated.
- 19. Will not be demonstrated.
- 20. Demonstrate ability to continuously monitor and control emergency worker exposure.
1 LIMITING CONDITIONS: This will be demonstrated for State workers only.
- 21. Will not be demonstrated.
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- 22. . Will not be demonstrated.
k- 23. Will not be demonstrated.
- 4 24. Demonstrate ability to brief the media in a clear, accurate and
. timely manner.
jj . ,i LIMITING CONDITIONS: None L, .
. 25. Demonstrate ability to provide advance coordination of information
- released.
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,j LIMITING CONDITIONS: None
,a i 26. Demonstrate ability to establish and operate rumor control in a t coordinated fashion.
- t LIMITING CONDITIONS: None
, .27. Will not be demonstrated.
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Atttchm:nt 1 Pegs 4 of 4 TEMA {BJECTIVE STATE OF OHIO OBJECTIVE
- 28. Will not be demonstrated.
- 29. Will not be demonstrated.
- 30. Will not be demonstrated.
- 31. Will not be demonstrated.
- 32. Demonstrate ability to identify need for, request, and obtain Federal assistance.
LIMITING CONDITIONS: None
- 33. Will not be demonstrated.
- 34. Demonstrate ability to estimate total population exposure. '
LIMITING CONDITIONS: None
- 35. Will not be demonstrated.
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. Atttchm:nt 2 Page 1 of 3 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE FEMA OBJECTIVE LAKE COUNTY OBJECTIVE (See Attachment 5) ,
- 1. Will demonstrate the ability to mobilize, staff and activate the temporary EOC, a reception center (South High School), and an j emergency worker decontamination center (Auburn Career Center).
- 2. The EOC will demonstrate 24 hour staffing.via roster with some double staffing or some positions demonstrating a shift change.
Will' fully staff, have a roster and some double staffing at the y reception center and emergency worker decontamination center.
- 3. Will demonstrate ability to make decisions and to coordinate emer-gency activities.
- 4. From the temporary EOC will demonstrate the adequacy of facilities and displays to include emergency classification levels, status board, plume exposure pathway EPZ map with sectors, evacuation routes, relocation centers, access control points, radiological monitoring points, and population by evacuated area. Bunks, I showers, kitchen will not be addressed since the EOC is a temporary EOC, and also serves as a police station. At the reception center, will identify the areas for registration, sleeping, feeding, and medical support, and monitoring. Backup power in the EOC is svail-able, but will not be demonstrated so that operation of the police station will not be af fected.
I 5. Demonstrate the ability to communicate with all appropriate loca-11 tions, organizations, and field personnel.
- s. 5 way dedicated telephone to Geauga, Ashtabula, PNPP and ODSA.
; b. 3 way dedicated telephone to Geauga and Ashtabula Counties.
- c. Telephone link to the JPIC.
O d. Radio communications from EOC to Sheriff's Department for traffic control and security. 3 7 e. Radio communications to emergency worker decontamination center.
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- f. Amateur radio communication between EOC and reception center.
y 3 Show there is a capability to use commercial telephone as a s backup to the receiption center, emergency worker decontamina-tion center PNPP, ODSA, Lake and Ashtabula Counties. i
m-Attechacnt 2 Page 2 of 3 FEMA OBJECTIVE LAKE COUNTY OBJECTIVE
- 6. Will not be demonstrated.
- 7. Will not be demonstrated.
- 8. Will not be demonstrated.
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- 9. Will not be demonstrated.
- 10. Will not be demonstrated.
- 11. Will not be demonstrated.
- 12. Will not be demonstrated.
- 13. Demonstrate the ability to alert the public within the 10 mile EPZ, and disseminate an initial instructional message within 15 minutes.
LIMITING CONDITIONS: Will not actually sound sirens, will prepare message and contact EBS.
- 14. Will demonstrate within the County EOC, the ability to coordinate EBS messages from the counties for simulated EBS station broadcast.
- 15. Will procedurally demonstrate in the County EOC the ability and resources to manage an orderly evacuation of that portion of the EPZ in Lake County.
- 16. Will procedurally demonstrate organizational ability and resources necessary to deal with impediments to evacuation.
- 17. Will procedurally demonstrate the organizational ability and re-sources necessary to control access,co the affected area and demon-strate activation of a single access control point. No actions will be taken to reroute air, rail, or water traffic.
- 18. Will not be demonstrated.
- 19. Vill procedurally demonstrate organizational ability and resources necessary to effect an orderly evacuation of schools within the plume EPZ.
- 20. ' Will demonstrate ability to continuously monitor and control emer-gency exposures from the EOC for those individuals involved in field activities.
- 21. Will not be demonstrated.
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r_ Attcchm:nt 2 Page 3 of 3 FEMA OBJECTIVE LAKE COUNTY OBJECTIVE
. 2. Will not be demonstrated.
- 23. Will not be demonstrated.
- 24. Demonstrate ability to brief the media in a clear, accurate and timely manner.
- 25. Will demonstrate from the EOC the ability to provide advance coor-dination of information released from the JPIC.
- 26. Will not be demonstrated.
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- 27. Will demonstrate adequacy of procedures for registration and radio-
' logical monitoring of evacuees, at one reception center.
- 28. Will demonstrate adequacy of facilities for mass care of evacuees at one reception center. Will not demonstrate feeding, showering, or sleeping, but will show registration, personnel monitoring, con-trolled access, communications, and adequacy of showers, feeding and sleeping arrangements. Some double staffing.and a roster will show sufficient staff for 24 hour a day operation.
- 29. Will demonstrate adequate equipment and procedures for decontamina-tion of emergency workers and vehicles at one emergency worker decontamination center. Will not require showers, change of clothes, or washing of vehicles, but will procedurally demonstrate those activities.
' 30. Demonstrate adequacy of ambulance facilities and procedures for handling contaminated individuals.
j e LIMITING CONDITIONS: Will demonstrate via treatment of a contam-
" insted/ injured worker from the plant at Lake County Memorial Hospital East.
l 31. Will not be demonstrated. '
. 32. Will not be demonstrated.
j 33. Will not be demonstrated.
.; 34. Will not be demonstrated.
- 35. Will not be demonstrated.
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Attachmtnt 3 Page 1 of 3 PERRY NUCLEAR POWER PLANT , 1984 EMERGENCY PREPAREDNESS EXERCISE FEMA OBJECTIVE ASHTABULA COUNTY OBJECTIVE (See Attachment 5)
- 1. Will demonstrate the ability to mobilize staff, and activate the EOC, a reception center, and an emergency worker decontamination center.
- 2. The EOC will demonstrate 24 hour staffing via roster with'some
! double staffing or some positions demonstrating a shift change. . Will have a roster and some double staffing at the reception center and emergency worker decontamination center. All facilities will be fully staffed.
- 3. Will demonstrate ability to make decisions and to coordinate emer-i' gency activities.
- 4. From the EOC will demonstrate the adequacy of facilities and dis-plays to include emergency classification level, status board, plume exposure pathway EPZ maps with sectors, subareas, evacuation routes, relocation centers, access control points, radiological monitoring points, and population by evacuated area. Bunks, showers, kitchen
-j will not be addressed. At the reception center, will identify the area for registration, sleeping, feeding, medical support, and monitoring. Backup power in the EOC is available, but will'not be demonstrated so that operation of the police station, which shares
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services with the EOC, will not be affected.
- 5. Demonstrate the ability to communicate with all appropriate loca-i tions, organizations, and field personnel.
- a. 5 way dedicated telephone to Lake, Geauga, PNPP, and ODSA.
- b. 3 way dedicated telephone to Geauga and Lake Count,ies,
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i c. Dedicated telephone line to JPIC. i d. Radio communications from EOC to Sheriff's Department for ' traffic control and security.
. e. Radio communications to emergency worker decontamination / center.
- f. Amateur radio communications between EOC and reception center.
- g. Show there is a capability to use commercial telephone as a backup to the reception center, emergency worker decontamina-tion center, PNPP, ODSA, Lake and Geauga Counties, t
. 6. Will not be demonstrated.
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' Attcchm:nt 3 Pags 2 of 3 FEMA s OBJECTIVE ASHTABULA COUNTY OBJECTIVE
- 7. Will not be demonstrated.
- 8. Will not be demonstrated.
Will not be demonstrated. 9. ( 10. Will not be demonstrated. 4 !- 11. Will not be demonstrated. ~i - 12. Will not be demonstrated. ii
- f. 13. Demonstrate ability to alert the public within the 10 mile EPZ, and j disseminate an initial instructional message, within 15 minutes.
i' . .
. LIMITING CONDITIONS: Will not actually sound sirens, will prepare ! , message and contact EBS.
b. >' 14 Will demonstrate within the County EOC, the ability to coordinate EBS messages from the counties for simulated EBS station broadcast.
- 15. Will procedurally demonstrate, in the County EOC, the ability and
- {. resources to manage an orderly evacuation of that portion of
? Ashtabula County in the EPZ.
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- ] 16. Will procedurally demonstrate organizational ability and resources ti necessary to deal with impediments to evacuation.
- 17. Will procedurally demonstrate the organizational ability and re-sources necessary to control access to the affected area and demon- i strate activation of a single access control point. No actions will be taken to reroute air, rail, or water traffic. Demonstration will :
- r take place in the EOC through the use of displays and briefings to !
- . indicate access control.
!t I 18. Will not be demonstrated. , 19.. Will procedurally, within the County EOC, demonstrate the organi-sational ability and resources necessary to effect an orderly evacuation of schools within the plume exposure pathway EPZ.
- 20. Will demonstrate ability to continuously monitor and control emer-
,i gency esposures from the EOC for those individuals involved in field
. activities.
- 21. Will not be demonstrated. -
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Attcchm:nt 3 Page 3 of 3 FEMA OBJECTIVE ASHTABULA COUNTY OBJECTIVE
- 22. Will not be demonstrated.
Will not be demonstrated. 23.
- 24. Will demonstrate ability to brief the media in a clear, accurate and timely manner from the JPIC only, and will demonstrate 24 hour capability with a roster.
. 25. Will demonstrate from the EOC the ability to provide advance coor-dination of information released from the JPIC.
- 26. Will not be demonstrated.
- 27. Will demonstrate adequacy of procedures for cegistration and radio-logical monitoring of evacuees at one reception center.
f 28. Will demonstrate adequacy of facilities for mass care of evacuees at one reception center. Will not demonstrate feeding, showering, or sleeping, but will show registration, persennel monitoring, con-trolled access, communications, and adequac y of showers, feeding and
- sleeping arrangements. Some double staffing and a roster will show j sufficient staff for 24 hours a day operation.
=; . 29. Will demonstrate adequate equipment and procedures for decontamina-
- tion of emergency workers and vehicles at one emergency worker decontamination center. Will not require showers, change of clothes, or washing of vehicles, but will procedurally demonstrate 4
those activities.
- 30. Demonstrate adequacy of ambulance, facilities and procedures for
'j handling contaminated individuals.
1 LIMITING CONDITIONS: Will demonstrate treatment of a contaminated I off-site emergency worker at the Ashtabula County Medical Center.
- 31. Will not be demonstrated. '
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- 32. Will not be demonstrated.
- 33. Will not be demonstrated.
it 34. Will not be demonstrated. P
- 35. Will not be demonstrated.
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Attcchmint 4 Page 1 of 3
., PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE FEMA OBJECTIVE GEAUGA COUNTY OBJECTIVE (See Attachment S)
- 1. Will demonstrate the ability to mobilize, staff and activate the temporary county EOC, a reception center, and an emergency worker decontamination center.
- 2. The EOC will demonstrate 24 hour staffing via roster, with some
. . double staffing or some positions demonstrating a shift change.
Will have a roster and some double staffing at the reception center
. and emergency worker decontamination station.
- 3. Ability to make decisions and to coordinate emergency activities
, will be demonstrated
- 4. From the temporary EOC the adequacy of displays to include emer-gency classification levels, status board, plume EPZ map with sectors, evacuation routes, relocation centers, access control points, radiological monitoring points, and population by evacuated area will be demonstrated. Bunks, showers, kitchen, will not be addressed. At the reception center, the areas for registration, sleeping, feeding, medical support, and monitoring will be iden-tified . A demonstration of the operation of a reception center will occur.
- 5. Demonstrate the ability to communicate with all appropriate loca-tions, organizations, and field personnel.
- s. 5 way dedicated telephone to Lake, Ashtabula, PNPP, and ODSA.
- b. 3 way dedicated telephone to Lake and Ashtabula Counties.
- c. Dedicated telephone to the JPIC.
i Radio communications from EOC to Sheriff's Dept. for traffic d. control and security.
- e. Radio communications to emergency worker decontamination center.
g f. Amateur radio communications between EOC and reception center. 3 Commercial telephone backup to reception center, emergency worker decontamination center, PNPP, 00SA, Lake and Ashtabula Counties.
- 6. Will not be demonstrated.
- 7. Will not be demonstrated.
c: , . , Attech=nt 4 Page 2 of 3 FEMA f*
'0BJECTIVE GEAUGA COUNIT OBJECTIVE
, _8. Will not be demonstrated.
- 9. Will not be demonstrated.
, 10 . Will not be demonstrated.'
1 11. Will not be-demonstrated.
- 12. Will not be demonstrated. .
j 13. Demonstrate the ability to alert the public within the 10 mile EPZ, ,. and disseminate an initial instructional message, within 15 minutes. l LIMITING CONDITIONS: Will not actually sound sirens, will prepare message and contact EBS. S'
.14. Will demonstrate, within the County EOC, the ability to coordinate EBS messages from the counties for simulated EBS station broadcast.
- 15. Ability and resources to manage an orderly evacuation of that portion of Geauga County in the EPE will be procedurally demon-strated in the County EOC.
- 16. Organizational ability and resources necessary to deal with impedi-
. monts to evacuation will be procedurally demonstrated.
J j 17. 'Ihe organizational ability and resources necessary to control access .j ' at a sing 1* Point will actually be demonstrated. Will procedurally demonstrate complete control in the EOC through the use of briefings and displays to indicate access control.
- 18. The organizational ability and resources necessary to effect an i orderly evacuation of mobility-impaired individuals within the plume
; , EPZ will be procedurally demonstrated in the County ECC by using the q list of mobility impaired.
- 19. If required by the scenario, the organizational ability and resources necessary to effect an orderly evacuation of schools within the plume EPZ will be procedurally demonstrated (at the EOC).
- 20. Ability to continuously monitor and control emergency worker expo-l' sures will be demonstrated from the EOC for those individuals in j field activities.
t
- 21. Will not be demonstrated.
(k 22. Will not be demonstrated.
; ~23. Will not be demonstrated.
i 1 t e. 6
Attachmsnt 4 Page 3 of 3 FEMA OBJECTIVE GEAUGA COUNTY OBJECTIVE
- 24. Demonstrate ability to brief the media in a clear, accurate and timely manner at the JPIC.
- 25. Demonstrate the ability to provide advance coordination of informa-
. tion released from the JPIC will be demonstrated from the E0C.
- 26. Will not be demonstrated. ! ';
- 27. The adequacy of procedures for registration and radiological monitoring of evacuees will be demonstrated at one reception center.
F
- 28. The adequacy of facilities for mass care of evacuees will be demon-
'strated at one reception center. Feeding, showering, or sleeping will not be demonstrated but will show registration, personnel
'i. monitoring, controlled access, communications and adequacy of
}
showers, feeding and sleeping arrangements. Double staffing will be j.
~
used to reflect sufficient staff for 24 hour a day operations. I 29. Adequate' equipment and will be demonstrated for decontamination of
; emergency workers and vehicles at one emergency worker decontamina-tion center. Will not require showers or change of clothes or ; washing of vehicles, but will procedurally demonstrate those activ-ities.
i 30. Will not be demonstrated.
- 31. Will not be demonstrated.
Y 32. Will not be demonstrated. [ t 1 33. ~Will not be demonstrated.
- 34. Will not be demonstrated.
if
.* 35- Will not be demonstrated.
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T$' a 4 4
Attachment 5 Page 1 of 3 PERRY NUCIZAR POWER PLAST 1984 EMERGENCY PREPAREDNESS EXERCISE FEMA OBJECTIVE FEMA OBJECTIVES CROSS-REFERENCE
- 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 and to support emergency operations. .
- 5. Demonstrate ability to communicate with all appropriate locations, organizations, and field personnel.
- 6. ' Demonstrate ability to mobilize and deploy field monitoring teams in I a timely fashion.
i
- 7. Demonstrate appropriate equipment and procedures for determining f
ambient radiation levels.
- 8. Demonstrate appropriate equipment and procedures for measurement of
}
i airborne radiciodine concentrations as low as 10"' uC1/CC in the I presence of noble gases.
- s j 9. Demonstrate appropriate equipment and procedures for collection, transport and analysis of soil, vegetation, snow, water, and milk.
j,
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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 appro-
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priate protective measures, based on PAGs, available shelter, evacuation time estimates, and all other appropriate factors.
'll.
Demonstrate ability to project dosage to the public via ingestion
~
i . pathway exposure, based on field data, and to determine appropriate protective measures, based on PAGs and other relevant factors.
- 12. Demonstrate ability to implement protective actions for ingestion e,
SL pathway hazards.
.~ Demonstrate ability to alert the public within the 10 mile EPZ, and 13.
[J- disseminate an initial instructional message, within 15 minutes.
"- 14. Demonstrate ability to formulate and distribute appropriate instruc-tions to the public, in a timely fashion.
.t 9
r . Attachmsnt 5 Pags 2 of 3 FEMA
-0BJECTIVE FEMA OBJECTIVES CROSS-REFERENCE
- 15. Demonstrate the organizational ability and resources necessary to manage an orderly evacuation of all or part of the plume EPZ.
- 16. Demonstrate the organizational ability and resources necessary to deal with impediments to evacuation, such as. inclement weather or traffic obstructions.
- j. ~
- 17. Demonstrate the organizational ability and resources necessary to control access to an evacuated area.
- 18. - Demonstr.afe the organizational ability and. resources necessary to
, effect an orderly evacuation of mobility-impaired individuals within j the plume EPZ.
.q
- 19. Demonstrate the organizational ability and resources necessary to
- effect an orderly evacuatien of schools within the plume EPZ.
,j ~ 20. Demonstrate ability to continuously monitor and control emergency
, worker exposure. . -21. Demonstrate ability to make the decision, based on predetermined . criteria, whether to issue KI to 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.
24' . Demonstrate ability to brief the media in a clear, accurate, timely .i manner.
'.\
- l- 25. Demonstrate ability to provide advance coordination of information j -released.
Y 26. Demonstrate ability to establish and operate rumor control in a coordinated fashion. g 27. Demonstrate adequacy of procedures for registration and radiological monitoring of evacuees.
~ ] 28. Demonstraea adequacy of facilities for mass care of evacuees.
I- 29. Demonstrate adequate equipment and procedures for decontamination of emergency workers, equipment, and vehicles.
- 30. Demonstrate adequacy of ambulance facilities and procedures for handling contaminated individuals.
s 4
^b- J* F
Attechmrnt 5 Pags 3 of 3 FEMA. OBJECTIVE FEMA OBJECTIVES CROSS-REFERENCE
- 31. Demonstrate adequacy of hospital facilities and procedures for handling contaminated individuals.
t
- 32. Demonstrate ability to identify need for, request, and obtain Federal assistance.
; 33. Demonstrate, ability to relocate to and operate the alternate
- EOF /EOC. ll
'4
- 34. Demonstrate ability to estimate total population exposure.
- 35. Demonstrate ability to determine and implement appropriate measures
' - for controlled recovery and re-entry.
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1.4 Precautions and Limitations This section provides information for all Exercise Controllers and Observers related to the rules and guidelines to be followed throughout the conduct of this Exercise. Prior to initiation of the Exercise, a pre-exercise briefing will be held to review the entire Exercise process with all the Exercise Controllers and Observers identified in this manual. , A. Should, at any time during the course of the conduct of this exercise,-an actual emergency situation arise, all activities and communications related to the Exercise will be suspended. 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 deter-j mination at that point whether to continue, place a temporary hold on, or terminate the exercise.
B. Should, at any time during the course of the conduct of this exercise, an Exercise Controller or Observer witness an exer- - cise 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 4 responsible for intervening in the individual's actions and
} terminating the unsafe activity immediately. Upon termination of the activity, the Controller / Observer is responsible for
- contacting the Lead Exercise Controller and informing them of the situation. The Lead Exercise Controller will make a
.p 2 determination at that point whether to continue, place a
',j temporary hold on, or terminate the exercise.
pj C. No pressurization of fire hoses, discharging of fire extin-D guishers, or initiation of any fire suppression systems will be j required for the Exercise.
; D. Manipulation of any plant operating systems, valves, breakers, or controls in response to this exercise are only to be simu-lated. There is to be no alteration of any plant operating equipment, systems, or circuits during the response to this exercise.
b 4 E. All repair activities associated with the scen'ario will be simulated with extreme caution emphasized around operating equipment. F. All telephone communications, radio transmissions, and public address announcements related to the exercise must begin and end with the statement, "This is a drill." Should a Controller i or Observer witness an exercise participant not observing this
- 4 practice, it is the Controller's/ Observer's responsibility to remind the individual of the need to follow this proceddre.
G. 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. I H. 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.
s I. Exercise participants are to inject as much realism into the
- exercise as is consistent with.its safe performance; however,
.l caution must be used to prevent over-reaction. ~ J. Care must be taken to assure that any non participating indivi-
. duals who may observe exercise activities or overhear exercise
, communications are not misled into believing that an actual emergency exists. Any Exercise Controller or Observer who is if aware of an individual or group of individuals in the immediate
'! vicinity who may have become alarmed or confused about the situation, should approach that individual or group and explain the nature of the exercise and its intent. ,
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I SECTION 2.0
.l EXERCISE INFORMATION i
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2.0 EXERCISE INFORMATION 2.1 Exercise Participants The participants in the Exercise will include the following: 2.1.1 The Cleveland Electric Illuminating Company Facilities Management and Support Personnel 1.
- a. Control Room Simulator
' b. Technical Support Center (TSC)
- c. Operations Support Center (OSC)
- d. Emergency Operations Facility (EOF) t 3 e. Joint Public Information Center (JPIC) i j 2. Emergency Response Teams
- a. Radiation Monitoring Teams (RMTs)
, I- b. Fire Brigade
+1 I c. First Aid Team l
- d. Emergency Maintenance Team
- e. Security Force i' f. Post Accident Sampling System (PASS) Team
- g. Health Physics Support
-4
'l 2 2.1.2 Off-Site Agencies / Organizations d 1. Federal
'j ,
- a. Nuclear Regulatory Commission (NRC)
- b. Federal Emergency Management Agency (FEMA) b
- c. United States Coast Guard (USCG) if
- 2. State of Ohio
- a. Adjutant General's Department
- Disaster Services Agency (ODSA)
Ohio National Guard a b. Department of Health
y . . _ . - . m 9
-c. Department of Agriculture
- d. Ohio Highway Patrol
; e. Department of Natura'l Resources
- f. Department of Transportation
, g. Environmental Protection Agency -1
- h. Public Utilities Commission 1
, i. Public Welfare Department J 3. State of Pennsylvania 1-j 4. Local
- a. Lake County Disaster Services Agency and appro-
, priate supporting agencias. )
- b. Geauga County Disaster Services. Agency and appropriate supporting agencies.
,j c. ' Ashtsbula County Disaster Services Agency and
-{ appr.priate supporting agencies.
.t c; d. Perry Township Fire Department
.i i
- e. Lake County Memorial Hospital, East
- f. Ashtabula County Medical Center
- 5. Private (Participation Optional)
J
- a. NUTECH Engineers, Inc.
., b. Duquesne Light Company 3 c. Toledo Edison Company
- d. ECI Corp.
; e. Institute of Nuclear Power Operations 'l 2.2 Exercise Organization ]' ! The organization for this Exercise will consist of the Exercise - Coordinator, the Controllers, the Evaluators, the Players, and the Observers, as follows:
2.2.1 The Exercise Coordinator will coordinate Exercise prepara-tions including the development of the scenario and controller input messages. He will control all aspects of the conduct of the Exercise, prepare a consolidated evaluation and critique report at the conclusion of the 4 9
Exercise, an'd prepare and follow up on an itemized list of corrective actions recommended as a result of the evalua-tion and critique. 2.2.2 Controllers are qualified personnel selected to perform functions as follows:
- 1. A Lead Controller is assigned to each emergency ,
response facility. The Lead Controller is responsible for-all Controller, Evaluator, and Observer activities for.that facility and, if appro-priate,-its associated teams. Controllers for teams
]: ~ or subareas of a facility report to the Lead Con-I troller of that facility.
The Controllers will deliver " Exercise Messages" to j l 2. designated players at various times and places during the Exercise, inject or deliver additional messages L as may be required to initiate the appropriate player response and keep the Exercise action moving f according to the scenario and Exercise objectives, observe the Exercise at their assigned locations, and j' prepara evaluation forms. Controllers submit written
-h' 3,1' recommendations on corrective actions to the Lead Controller, who in turn summarizes all comments for
'j submittal to the Exercise Coordinator prior to the scheduled critique. The Controllers will be provided
,1 4- with a list of instructions in the Exercise Scenario.
- 3. Controllers will act as Evaluators, as described 4
below, 1 i 1,
.{ Controllers will be identified by wearing red arm bands with white lettering stating " Controller."
g 2.2.3 Evaluators are qualified personnel who are assigned to
$i judge the effectiveness of selected organizations, person-
- nel, functions, and activities in response to the simul-L}4 ated emergency situation. Selection of Evaluators is
, y! : based on their expertise and qualifications to evaluate an
- 7 assigned activity or area. Persons designated as Control-I ,~;
lors for a given function may also be assigned as Evalu-l ators of that function when feasible. Evaluators will record their observations using an evaluation form and f, provide recommendations on corrective actions to the Lead ppj Controller in whose facility they. evaluate prior to the jg/ scheduled critique. They will evaluate exercise Lej CD performance on the basis of standards or requirements contained in the appropriate Emergency Plan, Implementing I* Instructions, and Exercise messages and as described ' ,, herein. They will take steps, whenever possible, to f'~ ' collect data on the time and motion aspects of the acti-vity observed for post-Exercise use for implementing l , improvements. C
* " " ' ' ----m.:- s ._ __
.. - . ,~. .-
7 s Evaluators will be identified by wearing red arm bands with white lettering stating " Evaluator." 2.2.4 Players include Perry Plant and other Illuminating Company personnel assigned to perform emergency functions, as described in the Emergency Plan and Implementing Instruc-tions. Players from off-site organizations and agencies (county, State, and private industry) are participants in I the Exercise as described in their respective Emergency Plans and Standard Operating Procedures. f
! Players will be identified by wearing blue arm bands with i white lettering. ; 2.2.5 Observers from The Cleveland Electric Illuminating Company j*
and other organizations may be authorized, on a limited basis, to participate in the Exercise solely for the } purpose of observing Exercise activity for personal j education. Observers will report initially to the PNPP 3 Emergency Planning Coordinator for credential review and l' authorized admittance. They will be provided with orien-i tation information and appropriate exercise publication. j Observers will be identified by wearing green arm bands
+
with white lettering stating " Observer"; Federal agency observers will be identifind by wearing yellow arm bands j with black lettering stating either "NRC" or " FEMA". Requests to participate as an Observer should be made in 'f _ writing and contain the Observer's full name, home address j and phone number, and organizational affiliation. Re-quests to participate as Observers must be submitted to j the Perry Plant Emergency Planning Coordinator no later than one week before the Exercise. j 2.3 Emergency Response Facilities j During the Exercise, special facilities must be activated to manage, assess, and support emergency response. j 2.3.1 On-Site Facilities
! The Cleveland Electric Illuminating Company Emergency Response Facilities are:
. 1. Control Room Simulator l
The PNPP' Control Room will not be used due to poten-tial interference with Unit 1 construction activities. For the Exercise, the PNPP Simulater, i located on the first floor of the PNPP Training and Education Center (TEC), will be utilized (see Figure 2.1). Control Room emergency response
- measures will be exercised from the Simulator under l
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m the direction of the Shift Supervisor, acting as the Emergency Coordinator, until relieved by the Operations Manager.-
- 2. Technical Support Center (TSC)
When emergency conditions escalate to an Alert status . or higher, coordination of the _ emergency response will shift from the Control Room (Simulator] to the , TSC, located in the 603' 6" level of the Service Building (see Figure 2.2). The Operations Manager relieves the Shift Supervisor as Emergency Coordinator and directs activities from the TSC until relieved by the Emergency Coordinator in the EOF.
- The TSC is the location from which technical l management personnel utilize information on plant
- status provided in the TSC to support actions being
; performed in the Control Room. The TSC serves as j the primary communications source to the NRC, OSC,
- j. EOF, and off-site agencies, and will perform other
- j. functions of the EOF until the EOF is activated.
- 3. Operations Support Center (OSC) i 4 The OSC, located on the 574' and 599' elevations of l the Control Complex (see Figure 2.3), provides a
? location where emergency response teams can be assembled and coordinated during an emergency. The OSC will be activated for emergency conditions classified as an Alert or higher, and may be acti-vated for an Unusual Event at the discretion of the Emergency Coordinator. ; 4. Emerzency Operations Facility (EOF) i
- 1. The EOF, located in the Training and Education Center a . (see Figure 2.4), will be activated for emergency conditions classified as a Site Area Emergency or 3:
General Emergency (optional for the Alert status). The Emergency Coordinator (Vice President, Nuclear Group) relieves the Operations Manager as Emergency Coordinator and directs activities from the EOF. The EOF is the command post for coordination of response measures with off-site organizations, assessment of a radiological and environmental conditions and de-
'J- termination of recommended protective actions for the public. The EOF also provides and management of recovery operations under the direction of the Recovery Director.
m , . _ _ _ _ ,
~.
- 5. Joint Public Information Center (JPIC)
The JPIC, located at the Lakeland Community College in Kirtland, Ohio, (see Figure 2.5), provides the point of contact for the coordinated release of news and information to the news media and the general public. The JPIC is staffed by Illuminating Company, county, State, and Federal officials and.will be activated for emergency conditions classified as a Site Area Emergency or General Emergency (optional for the Alert status). 2.3.2 Off-Site Facilities
) 1. Lake County Facilities 3 E:sermency Operations Center (EOC) - The' temporary , Lake County Emergency Operations Center will be located in the basement of the Willoughby Police Department. The Willoughby Police Department Dispatch Center (located on the first floor) is temporarily the 24-hour notification point for Lake 2 County.
y Hospital - Lake County Memorial Hospital East is' F located at Washington and Liberty Streets in
!. . Painesville, Ohio. This is a general hospital which j offers direct support to the Perry Nuclear Power Plant.
Decontamination Facility - The Decontamination
, Station for emergency workers is located at the q Auburn Career Center (a public vocational schoal),
8140 Auburn Road, Painesville, Ohio, !{ j Reception Center - The Reception Center for the i Exercise is located at South High School (Willoughby-Eastlake School District) at 5000 Shankland Road, Willoughby, Ohio. This center includes a congregate care center and a decontamination team that can l survey evacuees for contamination.
- 2. Ashtabula County Facilities Emernency Operations Center (EOC) - A permanent emergency operations center is located in the basement of the Ashtabula County Court House in Jefferson, Ohio. This facility houses the administrative offices of the Ashtabula County Disaster Services Agency and the County Sheriff's Dispatch Center.
f Sheriff - The Sheriff's Dispatch office is located , within the county EOC facility but operated by the Ashtabula Sheriff's Departroent. Hospital - Ashtabula Coun*.y Medical Center is a
, ~ general hospital located at 2420 Lake Street, Ashtabula, Ohio. This hospital is not under contract for services by PNPP; it is a local public hospital capable of providing radiological monitoring and' medical support to a contaminated victim.
l Decontamination Facility - The Decontamination b Station for Emergency Workers is located at the j Saybrook Township Fire Department, 5714 North Ridge 3 Street, Ashesbula, Ohio, t 4 Reception Center - Cont.caut High School. 381 Main
]) Street, Conneaut, Ohio, has been designated as the congregate care facility with a decontamination team 1 to survey evacuees. ;(-
j 3. Geauma County Facilities Emerzency Operations Center (EOC) - A temporary l emergency operations center will be located in the basement of the Geauga County Safety Center,
- 13281 Ravenna Road, Chardon, Ohio. This facility houses the Geauga County Disaster Services Agency administrative offices and communications center.
The Sheriff's offices and dispatch center is on the first floor of the facility. i
' Sheriff - The Sheriff's Offices and Dispatch Center d are located on the first floor of the Geauga County 1- Safety Center. It will be the 24-hour notification M point for Geauga County.
?
Decontamination Facility - The decontamination N station for emergency workers will be located at the c Hambden Fire Department on Route 608, south of Route 6, Hambden, Ohio. l . Reception Center - The congregate care center and
^' - contamination monitoring site for evacuees will be located at the Berkshire High School at Routes 87 and N 608 North, Burton, Ohio. -
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- 4. State of Ohio Facility .
s The State of Ohio Emergency Operations Center is located in the basement of the west wing of the j.. Robert B. Beightler Armory, at 2825 West Granville Road,' Worthington, Ohio. It is a fully equipped - ,
, facility that is the central control site for the i emergency operations of state government.- ,
is 2.4 Exercise Conduct a "1 2.4.1 Overview 1 The Exercise will simulate an abnormal radiological > ()q incident at the Perry Plant which will start with an 4
} Unusual Event and escalate to a General Emergency.
41 . . During the course of the Exercise, in order to evaluate d coordination with appropriate State and local agencies. -? incidents will arise which require response by off-site I emergency response organizations / agencies. Off-site fire
- {'
fighting units will be mobilized to augment the on-site Fire Brigade, and off-site ambulance service personnel
- 3 will be activated to transport a contaminated accident 4 victim to a local hospital. The Exercise will also simulate an off-site radiological release which will required deployment of PNPP and State radiological moni-je toring teams for off-site monitoring.
t !I1 The conduct of the Exercise will demonstrate the effec-tiveness of selected organizations, personnel, functions, t i and/or activities of the appropriate Emergency Plans and t Implementing Instructions. The simulated emergency will then de-escalate. The Recovery Phase will be initiated,
,, and the Exercise will then be terminated.
d 3]- 2.4.2 Actions L1 Emergency response actions during the simulated emergency Ti will include: recognition and classification of emergency ][ [3 conditions; assessment of- on-site /off-site radiological consequences; alert / notification and mobilization of V emergency response organizations; implementation of ri in-plant corrective actions; activation / operation of , )/- emergency response facilities and equipment; preparation . it of reports, messages, and recordkeeping; and recommenda- [ {l tion of protective actions.
; 2.4.3 Communications
<! The Exercise will also demonstrate the effective use of l communications systems. An actual smergency operation
~
t. usually requires the extensive use of both telephone and radios. The telephone'is the primary means of I i- 1 s
)
communication and will be attempted first, with radio as a backup, unless radio is the only means available. Sepa-rate telephone numbers and radio channels will be used for Controller communications to prevent the Players form learning in advance of the situation to which they are to be subjected during the Exercise. Close cooperation and coordination between Controllers and Evaluators is essen-tial due to the number of persons who will be assigned the , dual Controller / Evaluator role. 2.4.4 Controllers I.ead Controllers will be stationed in'the Control Room Simulator, OSC TSC, EOF, JPIC, and County EOCs. Only
' I.ead Controllers can modify exercise messages or initiate b free play messages.
A
- 1. The Control Room Simulator will be the central point T for organization of exercise messages and is the key to ensuring that the Exercise progresses on schedule.
3 Simulated plant parameters will be provided to the 1 Control Room Simulator operators using plant data and
'} status sheets. Since it is required that the emer-j gency escalate to the General Emergency level in 1 order to' exercise off-site activities, it may be I
necessary to postulate non-credible situations. The n operators will accent the exercise messames as j If corrective actions are postulated that written. would terminate the emergency, they should be iden-tified to the I.ead Controller, so that the scenario will progress as designed. 4.i The Exercise Players are expected to " free play" the
, q; scenario to the extent practical. Notifications of, i and centact with, supervisors, plant management, and j off-site agencias will be made in accordance with the i Energency Plan Implementing Instructions.
ij a The TSC will be the coordination point for on-site i 2. emergency response activities. TSC personnel will d_ also coordinate off-site emergency response activi-j ties until activation of the EOF. TSC and EOF personnel will be aware that if the Exercise is to <
'i proceed as planned, and if the off-site organizations 5 1- are to be exercised, it say be necessary to postulate y':$ non-credible situations. This is done to ensure that Ld various aspects of the on-site and off-site emergency F.l ~
response organizations are tested. TSC and EOF oorsonnel will accoot exercise messames as written. l The intended response is not to explain why a situs-
- j. tion could not occur but to react as though it did occur. If corrective actions are postulated that would terminate the emergency, they should be noted t
i to the I.ead Controllers. {
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5 s-4 d' The Exercise Players in the TSC and EOF are expected to " free play".the scenario to the extent practical. Notifications of, and contact with, supervisors, plant management, and off-site agencies should be made in accordance with the Emergency Plan Implemen-T . ting Instructions. The scenario is designed to activate on-site and off-site emergency response
, capabilities.
l The Lead Controllers may inject other information or j )* d change a message to ensure that the Exercise progresses as j planned. - 2.4.5 Players
- J The success of.the Exercise.is largely dependent upon 7 player reaction, player knowledge of their appropriate
,4 Emergency Plan and Implementing Instructions, and an understanding of the purpose of the Exercise. Initial conditions which will affect player action or reaction Q will be provided to the players at the time the Exercise l begins. However, most of the elements of the Exercise
.; play will be introduced through the use of controlled
; Exercise message forms and messages generated by Players
; as a result of the particular emergency activity per-formed. Players, therefore, are responsible for initi-ating actions during the Exercise in accordance with
! instruction, responsibilities, and tasks for their partic-3 ular function. Each Player will . advise his/her Controller prior to performing required emergency actions during the play of simulated activities to ensure that the Player is ,
i credited for his/her actions.
\
i Players are reminded not to be excessively concerned with t]i s the mechanics or cause of the exercise scenario. This Exercise is designed to evaluate the Emergency Plan, j Implementing Instructions, and emergency preparedness . j , training program, and not the probability, feasibility, or i detailed mechanics of the simulated accident. Addition-
- ally the Exercise is a training vehicle for Illuminating l* . Company personnel to practice coordinating with outside
. organizations in a simulated emergency environment.
i Players should note any needed improvements that come to a their attention during the Exercise and submit them to the q- appropriate Controller at the conclusion of the Exercise.
]
2.5 Evaluation and Critique
' The Exercise will be evaluated by Evaluators and Lead Controllers who have expertise in, or qualification to evaluate the activity in their assigned location. Evalustors and Controllers will evaluate exercise performance on the basis of requirements contained in the L.
Emergency Plan Implementing Instructions, and exercise messages. Evaluators and Controllers will prepare evaluation forms and provide recommendations on corrective actions to the Exercise Coordinator. After the Exercise is completed, the Exercise Coordinator will conduct a post-Exercise critique. Deficiencies in the Emergency Plan, Implementing Instructions, the emergency preparedness training program, facilities, equipment and/or other areas will be identified . 4 through the critique process. The deficiencies will be documented i by the Exercise Coordinator and corrected by the individuals who have responsibility in the area of the identified deficiency. The schedule for ,the critiques is shown in Section 5.0. c. e i i 1 I - a i t i 1 Y q , ,t i gi a I* a h
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h e b" SECTION 3.0 TRAVEL INFORMATION + 4 5 k p a s. .1 f.. }. . P t 0 R-r h r. 5 L nv - .- +- - , , , n---__ __ , . - - - _ . - .w,,-- --. _. - ,. . , _ _ . _ , -- , , _ , , , . _ , , . . , . _ _ , , _ , s__ . _ . _,_
3.0 TRAVEL INFORMATION This section of the Exercise Manual provides travel information to those - individuals from the Illuminating Company, other utilities, local / State / Federal government, and/or other organizations who will participate in the Exercise as Observers. Permission to observe the Exercise must be obtained from the Emergency Planning Coordinator, Perry Nuclear Power Plant, SB 312, 10 Center Road, - Perry, Ohio 44081. 3.1 Directions to the Perry Plant The Perry Plant is located on the southeastern shoreline of Lake Erie in Lake County, Ohio, approximately seven miles northeast of Painesville, Ohio, and about 35 miles northeast of downtown Cleveland (see Figure 3.1). 3.1.1 Air Several airlines provide passenger service to Cleveland Hopkins International Airport. 3.1.2 Car
- 1. Several car rental agencies are available at l Cleveland Hopkins International Airport to provide y: rental vehicles for ground transportation to the Perry Plant.
1
- 2. Persons traveling from Hopkins International Airport via auto should take State Road 237 North to Inter-state 71. Follow I-71 North to Interstate 90. Take j I-90 East to State Route 2. Follow State Route 2 4
East (which becomes State Route 20) to Center Road
- (traffic light). Turn left (North) onto Center Road
.i and proceed to the Perry Plant site. Total distance is approximately 50 miles (see Figure 3.2). v
n- - 3.2 Accommodations Hotel / motel accommodations may be obtained at the following locations: a
'j Country Inn of Mentor, Route 2 and Route 306 216/951-7333 1 College Inn, Route 306.and Route 90 216/946-0500 Quail Hollow Inn, I-90 and SR 44 216/946-7990-
; Red Roof Inn, 4166 State Route 306 216/946-9872 4
Knight Inn, Route 306 and Route 90 216/953-8835 Harley Hotel, Route 91 and Route 90 216/944-4300 l 1-A 1 1
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DIRECTIONS TO PERRY NUCLEAR POWER PLANT
^*"'*""
Perry Plant
/
cr . North Perry l2 6ttO** Hotel Key
~ Lake Erie V l*% b f Road #
2.I.akeland Inn d' . 3.Oua5 Hosow kva 4#' _Routg youte
- 4. Red Roof Inn N9 T{te# , g 307 yy 5.6 h ge y pW L Route Rotste 6 Harley Hotel 90 go@*$ 534 46 7.naarviott-Altport 3 i ,
6.Alrport-Sheraton G l Route ! Route
- 9. Sky 5ght inn Downtown Cleveland /[9 6 4 2 g
Lakeland ComsnunNy 528 45
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Route Lake Erie Route Route Lake County 271 306 +Centes Road Temporary EOC l Rt. 2 Rt. 20 T go@a@ 1 Route Ii / rantic ught WMioughby 91 1 Freeway ends... toad continues 2% milea 10 Center flood. Route Geauge Turn notth to Party Plant slie. Cleveland Hopkins 77 County finternational Akport Routy 7 EOC (sann er woon 71 Route 480 Ashtabula County
- "'**'*%* i EOC Jefferson 4o um to La.i.ao W.150th w y cas.e* Street i
Figre '.2
6 i 6 s 0 8 m i i f f SECTION 4.0 j REFERENCES / ABBREVIATIONS / DEFINITIONS l
.I I
!i s N e
"Y
4.0 REFERENCES
/ ABBREVIATIONS / DEFINITIONS 4.1 References 4.1.1 Emergency Plan for Perry Nuclear Power Plant Units 1 and 2 - The Cleveland Electric Illuminating Company, Revision 3, 4/23/84.
4.1.2 PNPP Emergency Plan Implementing Instructions, OMISB: EPI. 4.1.3 Ohio Plan for Response to Radiation Emergencies at Licensed Nuclear Facilities (Revision of 1984).
- 4.1.4 Lake County Radiological Emergency Response Plan for the Perry Nuclear Power Plant.
I 4.1.5 Geauga County Radiological Emergency Preparedness Plan. 4.1.6 Ashtabula County Radiological Emergency Preparedness Plan. 4.1.7 10 CFR Part 50.47, and 10 CFR Part 50, Appendix E. 4.1.8 NUREG-0654 FEMA-REP-1, Criteria for Preparation and
} Evaluation of Radiological Emergency Response Plans and Prapsredness in Support of Nuclear Power Plants.
4.1.9 NUREG-0696, Functional Criteria for Emergency Response .
; Facilities.
1 4.1.10. 44 CFR 350.9
- f .
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m-4.2 List of Abbreviations
. ACP -
Access Control Point ATWS - Anticipated Transient Without Scram CEI - The Cleveland Electric Illuminating Company CR - Control Room ' CFR - Code of. Federal Regulations h ' DOE - Department of Energy DSA - Disaster Services Agency i Lj EAL - Emergency Action Level
! EBS -
Emergency Broadcast System 7! ENS - Emergency Notification System f jJ EOC - Emergency Operations Center j EOF - Emergency Operations Facility 4 EPA - Environmental Protection Agency , j EPZ - Emergency Planning Zone ERF - Emergency Response Facility
- e
'h ERIS - Emergency Response Information System ~
j FEMA - Federal Emergency Management Agency
'l - '
INPO - Institute of Nuclear Power Operations
'i . ; JPIC - Joint Public Information Center LOCA - Loss of Coolant Accident LCO -
Limited Condition of Operation MIDAS- Meteorological Informatmion Dose Acquisition System 1 NRC - Nuclear Regulatory Commission i
.. ODSA - Ohio Disaster Services Agency OSC -
Operations Support Center PAG - Protective Action Guideline D w- ,_ - - - - . - , , , - . , , ,_,.--,- ,_,.,_ . _ _ _,____ ______.,
PASS - Post Accident Sampling System PING - Particulate Iodine Noble Gas Monitor PNPP - Perry Nuclear Power Plant RNTs - Radiation Monitoring Teams SRV - Safety Relief Valve ' TCP - Traffic Control Point TSC - Technical Support Center X/Q - Wind Dispersion Factor (Chi /Q) n
+
1 s e .k s
' 4.2 Definitions
.c ALERT: The level of emergency classification which indicates that events are in progress or have occurred which involve an actual or e - potential degradation of the level of safety of the plant.
L ANTICIPATED TRANSIENT WITHOUT SCRAM (AWS): Failure of the reactor l] control rods to insert into the core upon demand. s ASSESSMENT ACTIONS: Those actions taken during or after an accident
] ,
to obtain and process info ggtion that is necessary to make de-
] cisions to implement specifid emergency measures.
1 j CONTAMINATION: Ingestion, inhalation, or direct contact with water, j' air, soil, or tangible objects which are taitting ionizing radi-Y_ .ation. A contaminated object has a level of radioactive material j adhering to its surface higher than an established limit. j' j
- CONTROL ROON (CR): The principal onsite location from which the f ; reactor is controlled and from which effective emergency control i direction is given. The CR is located on the 654' elevation of the jl Coatroi Complex.
1 .
! CONTROL ROON SIMULATOR: The onsite location which is phyisically i set up to reflect the actual unit control room. The simulator, located in the PNPP Training and Education Center, will be used as the control room for the purposes of the Exercise.
'] ColfrROLLER: A member of the Exercise control group. Each con-- -l- troller may be assigned to one or more activities .or functions for i the purpose of keeping the action going according to a scenario,
; resolving scenario discrepancies, and supervising the actions of the l_ players. p I
CORRECTIVE ACTIONS: Those emergency measures taken to improve or , terminate an emergency situation at or near the ~ source of the problem. '$ DECONTAMINATION: The process by which the body or an object is
.i relieved of radioactive substances.
1" DOSE ASSESSMENT: The process of estimating the amount of radiation .i. ' a person will potentially receive as a result of a radiological release. DRILL: A supervised event aimed at evaluating, developing, and g maintaining skills in a particular operation. j . EMERGENCY ACTION LEVELS (EALs): Radiological dose rates; specific
} contamination levels of airborne, waterborne, or surface-deposited concentrations of radioactivity; or specific instrument readings that may be used as thresholds for initiating specific emergency measures.
,.) 1 i
EMERGENCY OPERATICNS CENTER (EOC): An offsite emergency response facility from which government -officials exercise direction and control in an emergency. . The EOCs are_ located as follows: Lake County - Basement of the Willoughby Police Department at 36700 Euclid Avenue, Willoughby, Ohio. Ashtabula County - Basement of the Ashtabula County Court House, 25 West Jefferson Street, Jefferson, Ohio. . Geauga County - Basement of the Geauga County Safety Center at 13281 Ravenas Road (Route 44 south of Route 322). State of Ohio - Basement of the Robert B. Beightler Armory, g _2825 West Granville Road, Worthington, Ohio. L I EMERGENCY OPERATIONS FACILITY (EOF): An onsite emergency response
' facility from which the offsite energency support activities are controlled. The EOF is located in the Training Center about - one-half mile from the Control Complex along the site access road.
EMERGENCY PLANNING ZONES (EPZs): The land areas encompassed within 10 and 50 mile radii of the Ferry Plant, in which protective actions may be necessary to protect the public in the event of a nuclear
- plant accident. The 10 miles sono is referred to as the Plume I- Exposure Pathway; the 50 mile sono is termed the Ingestion Exposure A Pathway. - +
EMERGENCY RESPONSE FACILITY: Any of several onsite and offsite centers which are activated to coordinate emergency actions. Included in this category are the Control Room. Technical Support
.3 Center, Operations Support Center, Emergency Operations Facility, Joint Public Information Center, and State and local Emergency f
I. Operations Centers. i 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 recommenda-ions for improvement.
EXCLUSION AREA: The area surrounding the Perry Plant in which the Illuminating Company has the authority to determine all activities including exclusion or removal of persons and property from the area
. during accident conditions.
l' EXERCISE: An event which tests the overall functions and capabil-
, ities of organizations involved in responding to an emergency ,! situation. An exercise shall simulate an emergency that results in offsite radiological releases which require response by offsite authorities.
9 I . w s 1
l GENERAL EMERGENCY: The most severe level of emergency classifica- i tion which indicates that events are in progress or have occurred
' which involve actual or imminent substantial core degradation or ;
molting with potential for loss of containment integrity. Release l of radioactive material can be reasonably expected to exceed PAG t p exposure levels offsite. ! i INGESTION EXPOSURE PATHWAY: The principal exposure fros this pathway would be free ingestion of contaminated water or foods, such , [ as milk or fresh vegetables. The time of potential exposure could
- range in length from hours to months. i JOINT PUBLIC INFORMATION CENTER (JPIC): 'An offsite emergency {
response facility, located at the Lakeland Community College, in ' Kirtland, Ohio, which is staffed by Illuminating Company, local, State, NRC and FEMA officials. The JPIC provides a forum and point
.I' of contact for a coordinated release of news and information to the ,
l news media, general public Illuminating Company employees and ' special interest groups. I 's CBSERVER: Any individual who is authorized to observe the Exercise, but is not authorized to interact with the players. OFFSITE: All land and water areas outside the Owner-Controlled Area fence surrounding the Perry Plant.
- l OH813
- All land and water areas within the Owner-Controlled Ares
- j- fence surrounding the Perry Plant.
!t l; OPERATIONS SUPPORT CENTER (OSC): An onsite emergency response ! a facility which provides a location where emergency response teams 1 [ can be assembled and coordinated during an emergency. The OSC is ; g located on the 574' and 599' levels of the Control Complex. l
- q. -
1 "i OWNER-CONTROLLED AREA: The area around the Perry Plant that is ;
~.) . - owned and the access controlled by The Illuminating Company. ;
3 TARTICIPANT: An individual who has some part in the Exercise, l; ,
- whether as an Evaluator, Controller, Player, or Observer.
7 PLAYERS: All individuals (Perry Plant, Illuminating Company person-nel, and individuals from offsite organizations and agencies) who-are assigned to perfore functions of the emergency response organ- ,, isation, as described in the appropriate Emergency Plan and l} Emergency Plan Implementing Instructions. < l
- I' PLUME EXPOSURE PATHWAY: The principal exposure sources for this pathway are (1) whole body external exposure to games radiation from I
L the plume and from deposited esterial and (2) inhalation exposure P from the passing radioactive plume. The time of potential exposure , t, could range from hours to days. ; POPULATION AT RISK: Those persons for whoe protective actions are ; or would be taken. ; l? i t : l s u , [ .
PROTECTED AREA: The area within the Site Boundary encompassed by physical barriers and to which accass is controlled for security purposes. FROTECTIVE ACTION: Those emergency measure taken after an accident or an uncontrolled release of radioactive materials has occurred, for the purpose of preventing or minimizing radiological exposures to personnel that would likely occur if the actions were not taken. PROTECTIVE ACTION GUIDES (PAGs): Projected radiological does or _ dose commitment values to individuals in the general population 1,J which warrant protective action following a release of radioactive material. Protective actions would be warranted provided the reduction individual safety in taking protective action. RADIOLOGICAL CONTROL AREA (RCA): Area for which the Radiation Protection General Supervising Engineer has responsibility for control of access and occupancy for radiation protection purposes.
. RADIOLOGICAL MONITORING TEAMS (RMTs): Two person teams responsible for monitoring radiation levels in the environment and collecting soil, sir, and water samples for laboratory analysis.
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 Protective Action Guide (PAG) exposure levels, except within the Site Boundary. TECHNICAL SUPPORT CENTER (TSC): An onsite emergency response facility which accommodates personnel who will provide informaticn on plant status for use by technical and management personnel in support of the command and control functions executed in the Control Room. The TSC is located on the 603' 6" level of the Service Building. UNUSUAL EVENT: The lowest level of emergency classification which indicates that events are in progress or have occurred which indi-cate a potential degradation of the level of safety of the plant. e 6
I I 1 i SECTION 5.0 SCHEDULE OF EVENTS t
5.0 SCl!EDULE SF EVENTS DAY TIME
- LOCATISN EVENT DATE Monday 1:44 p.m. - 5:00 p.m. TEC-CET ensite Centrollers Briefing /
11/26/84 11/27/84 Tuesday 8:00 a.m. - 9:30 a.m. TEC-CET Gnsite Players Briefing / 14:30 a.m. - II:44 a.m. TEC-248 NRC EntrancA Meeting v 11:00 a.m. - 1:44 p.m. TEC-CET NRC/ Controllers Briefing / 2:44 p.m. - 5:44 p.m. - ensite Facilities Tours (NRC) 9:00 a.m. - 12 noen TEC-249 FEMA Briefing 1:44 p.m. - 4:80 p.m. - effsite Facilities Tours (FEMA) 4:00 p.m. - 5:30 p.m. TEC-268 effsite Centrollers Briefing Wednesday 7:00 a.m. - 4:45 p.m. - Evaluated Exercise 11/28/84 Thursday 12:30 p.m. - 2:44 p.m. TEC-CET ensite players Critique 11/29/84 2:00 p.m. - 3:30 p.m. TEC-CET NRC Exit Meeting 11/30/84 Friday 3:30 p.m. - 5:30 p.m.- Lakeland Public Critique (FEMA) Ceemunity College
*End Times Approximate BWl?6/L/1/jsg
T' O$C - 7: E3 [e F - lo'** C~M" $^' trie - t o o PERRY NUCLEAR POWER PLANT EMERENCY PREPAREDNESS EXERCISE MANUAL ERRATA Please make the following changes to the Exercise Manual LOCATION CHANE f
" ... flanged connection on a valve (ga'rrativeSummary-Onsite Times 0915 upstream of a pump" to "... flanged connection on the Backwash Receiving Tank."
pdessage#2 Message will be called in by a player. vMessage #5 Message will be called into the SAS l by a player.
! pfiessage #6 Message is for a welder.
dessage#18 Message No. is 18X. dessage#19 Controller Note 2 should read in part: " Fuse F4, supplying brake hoist power ..."
! Message #27 Controller Note should read: " ...
leakage from a flanged connection - on the Backwash Receiving Tank resulting in ..." [ Message #38 Controller Note 1 should read: " Fuse F4 has been replaced." p4ea Radiation Monitor Data Monitors D21N320, D21N330 and D21N390 Sheets from Time 1005 to should read 4.0, 4.0 and 3.0 mR/hr., 1155 inclusive. reflecting fuel bundle replacement into the spent fuel storage pool.
u i 2 ERRATA (Continued) 3 LOCATION CHANGE saage #52 Time should read 1130. The shirt change should be completed by 1200.
- Relocate this message.
saage #61 Time should read approximately 1230. Relocate this message sheet and attachment.
)
.5ection 8.2A Contaminationlevelsinareasoutsidg*,
j room should read " < 1000 DPM/100 cm 1
'} /Section8.2A Add the rollowing: " NOTE: to determine CPM, divide DPM by 10."
I Aection 8.2A,. Personnel Con. Add the following to the " Comments" tamination Survey Form section: " Upper lef t ann brcken . " l l . Aable8.68 The reading at 1445 for 1.5 miles should be 1.8ES. t . ., 4 'i O k i
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f e t f L I i f I Y, o 4 e 'i SECTION 6.0 H EXERCISE SCENARIO 7 i l i f'
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- Contents Of This Section I 1
i Section 6.1 Initial Conditions i section 6.2 Narrative Summary - Onsite Sequence of Events - J Section 6.3 Narrative Summary - Offsite Sequence of Events l Section 6.4 Written Summary of Exercise Scenario ,I ?) l I l 't' s i 2 is _i k l 4 m. e
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PERRY NUCLEAR MWER PIET 1984 EMERGENCY PRE?AE~DSESS EXERCISE INITIALS CONDITIONS GIVEN TO PLAYERS ON N0% EMBER 27
- 1. Unit I reactor is operating at 100 percent power. The unit has been operating continuously and has had a capacity factor of over 90 percent since the last refueling outage 17 months ago.
- 2. Emergency Service Water Pump P45-C001A failed to meet its discharge pressure inservice inspection (ISI) at 2200 on November 25. The pump is -
disassembled and is expected to be placed back in service in about 24 4 hours. The following Division 1 Lineup has been established in the daily instructions for the duration of P45-C001A unavailability: RHR Pump A and LPCS Pump Breakers are racked in but are not to be used except if Divisions 2 and 3 are inoperable. RCIC use is allowed but should be limited to a backup to High Pressure Core Spray. Division 1 Diesel Generator is out of service with its output Breaker racked out and is not
; to be used. Emergency Closed Cooling Pump P42 C001A Breaker is also , racked out; ECC Pump A is not to be used until the return of ESW Pump P45-C001A.
f i 3. Preparations continue to ready spent fuel element for shipment to Idaho National Engineering Laboratories to undergo examination and testing of l the new barrier fuel cladding. 4 Annulus Exhaust Gas Treatment System. Train A, is in day two of a seven day Limiting Condition for Operation due to a motor failure on Fan j M15-C001A. The fan is disassembled awaiting a n,ew motor. Train B is in service, t
', 5. All other systems are operable.
- 6. Unit 2 remains under construction; no significant activities are
{ scheduled for today.
- 7. General Electric Company personnel will be onsite Friday to talk with
; Maintenance and Technical Section staff concerning:
1
- a. Intergranular stress corrosion cracking. (IGSCC)
- b. Nes control rod drive seal performance.
- c. Support for the Spent Fuel Element shipment.
- 8. Current weather conditions are as follows:
Wind speed: 10 miles per hour (measured on the 10 meter level]
., Wind direction: 185*
- Temperature: 35'F Tomorrow's forecast calls for sunny and clear but cold weather. Winds will be out of the north-northwest at 10-20 miles per hour for most of the day. High temperatures in the low 40's are expected.
DW176/H/4/kay s
i l PERRY NUCLEAR POWER PLAhT 1984 EMERGENCY PREPAREDNESS EXERCISE INITIAL CONDITIONS
- 1. Unit i reactor is operating at 100 percent power. The unit has been operating continuously and has had a capacity factor of over 90 percent since the last refueling outage 17 months ago.
i 2. Emergency Service Water Pump P45-C001A failed to meet its discharge pressure inservice inspection (ISI) at 2200 on November 25. The pump is disassembled and is expected to be placed back in service in about eight - hours. The following Division 1 Lineup has been established in the daily instructions for the duration of P45-C001A unavailability: RHR Pump A and LPCS Pump Breakers are racked in but are not to be used except if Divisions 2 and 3 are inoperable. RCIC use is allowed but should be l limited to a backup to High Pressure Core Spray. Division 1 Diesel Generator is out of service with its output Breaker racked out and is not to be used. Emergency Closed Cooling Pump P42-C001A Dreaker is also
- racked out; ECC Pump A is not to be used until the return of ESW Pump P45-C001A.
- 3. A spent fuel element is being readied for shipment to Idaho National l Engineering Laboratories for examination and testing of the new barrier fuel cladding.
- 4. Annulus Exhaust Gas Treatment System. Train A, is in day three of a seven day Limiting Condition for Operation due to a motor failure on Fan M15-C001A. The fan is disassembled awaiting a new motor. Train B is in service.
- 5. Backwashing of Fuel Pool Cooling and Cleanup Domineralizers is set to begin at 0900. l l
'{ 6. All other systems are operable.
. 7. Unit 2 remains under construction; no significant activities are scheduled for today.
General Electric Company personnel will be onsite tomorrow to talk with 8. Maintenance and Tachnical Section staff concerning:
- a. Intergranular stress corrosion cracking. (ICSCC)
- b. New control rod drive seal performance.
a
- c. Support for the Spent Fuel Element shipment.
i
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- 9. Current weather conditions are as follows:
Wind speed: 20 miles per hour [ measured on the 10 meter level] ! Wind direction: 200' Temperatures 32*F !' Today's forecast calls for sunny and clear but cold weather. Winds will i be out of the north-northwest at 10-20 miles per hour for most of the day. Nish temperatures in the low 40's are expected.
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PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE NARRATIVE
SUMMARY
- ONSITE SEQUENCE OF EVENTS Approximate Time Key Event 4
0700 Initial conditions are established. Commence exer-cise. 0703 .A fire breaks out in the PPD machine shop. I 0710 The Control Room is notified of the fire; the fire brigade is dispatched. s 0715 The Fire Brigade arrives at the scene. The fire is spreading. The Fire Brigade Leader requests offsite fire fighting assistance. 0717 The Shift Supervisor calls for offsite fire fighting assistance. 0725 The Shift Supervisor declares an UNUSUAL EVENT. i (EPI-A1, Section F.I.1. " Fire within the Protected Area lasting greater than 10 minutes"). I j 0725 Offsite fire fighting assistance arrivos at the Primary Access Control Point Gate, and is escorted to the scene of the fire. 0745 The fire is extinguished. 0755 A spent fuel element is being raised in the Spent a Fuel Pool for loading into the Spent Fuel Transporta-tion Cask. 0800 Offsite fire fighting assistance leaves the site. 0800 The refueling bridge winch position interlock fails as the bundle is raised to the overhoist position. Fuel Handling Building area radiation monitors alarm locally and in the control Room. The bundle cannot be lowered using the winch due to the failure of a fuse in the brake release power. L_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _
p PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE NARRATIVE
SUMMARY
- ONSITE SEQUENCE OF EVENTS Approximate Time Key Event 0805 The Shift Supervisor declares an ALERT (EPI-A1, Section J.II.1, " Fuel handling accident with release
. of radioactivity to Containment or Fuel Handling Building"). The TSC and OSC are activated. Onsite monitoring teams are dispatched.
0900 The TSC and OSC are fully activated. 0915 An operator on rounds in the intermediate building notices water coming from inside the Fuel Pool Cooling and Cleanup Backwash Receiving Tank Room. He slips and falls on a puddle of water, gashes his head and breaks his upper left arm. He radios for help. (The leak is from a flanged connection on stke Back e4
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! 0920 Security dispatches a First Aid Team to treat the injured victim.
0930 An offsite ambulance should be requested for the injured individual. 0940 The offsite ambulance arrives at the Primary Access Control Point Gate. 1 0955 The victim is loaded into the ambulance. 1000 The ambulance leaves the site. Intermediate Building decontaminacion and re-entry operations continue. 1000 Safety-Relief Valve (SRV) B21-F051D inadvertently opens. The operators make preparations for a fast reactor shutdown. 1002 A scram is attempted by placing the mode switch in
" SHUTDOWN": however, there is no inward motion of the control rods. In accordance with PEI-1, the operators attempt to shutdown the reactor using alternate rod insertion. All alternate shutdown methods fail. A manual scram is attempted, but fails.
F
PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE NARRATIVE
SUMMARY
- ONSITE SEQUENCE OF EVENTS Approximate Time Key Event ,
1015 >i. The Suppression Pool temperature reaches 110*F. Standby Liquid Control is activated, but the common , check valve C41-F007 does not open, and SLC does not inject. The operators implement PEI-1, Attachment 5, to lower reactor levnl. Level will reach approxi- .' mately -145 inches in 30 minutes and power will be j approximately 8%. Control Complex ventilation shifts
; to recirculation mode 1
2
-1030 A SITE AREA EMERGENCY is declared. (EPI-A1, Section D.III.2, " Complete loss of any functions needed for i plant hot shutdown").
i 1050 Reactor water level is being maintained at
-145 inches; reactor power remains at 8%.
- l. 1100 The EOF and JPIC are being activated.
! 1115 Suppression Pool temperature reaches a peak of 143*F and remains steady.
j 1120 All upper pool dump valves fail to open automa-q tically. Both trains fail due to a hydraucic lock that exists between the dump valves due to a failure J- of check valves G43-F508A and G43-F508B. Any effort t to open these valves fails. ] 1130 Reactor power remains steady at 8% power. All e efforts to insert the control rods continue to fail. 1155 SRV B21-F051D closes; Suppression Pool Temperature begins to decrease. 1200 - The Turbine Driven Reactor Feed Pump and Feedwater y Booster Pump trip due to Surge Tank Low Level Switch
- ! N21-N335 malfunction; the entire feedwater system is E rendered unavailable. When Reactor water level decreases below -148 inches, an MSIV isolation is
, initiated. , 1201 RCIC is placed in service, but reac' tor water level continues to decrease to seven inches above the top of active fuel.
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PERRY NUCLEAR POWER PIANT 1984 EMERGENCY PREPAREDNESS EXERCISE-NARRATIVE
SUMMARY
- ONSITE SEQUENCE OF EVENTS Approximate Time Key Event 1202 The reactor is being depressurized to the suppgepsion pool by the operators via the safety relief valves (SRVs) in accordance with PEI-1, Attachment 5.
Containment Building Area Radiation Monitors alarm. The Reactor ; ore is uncovered. 1204 Reactor water decreases to 43 inches below the top of the active fuel. 1206, In accordance with PEI-1, Attachment 5, Step 7, the operators direct jumpers to be installed in Panel H13-P618 in order to use RER B to regain reactor water level. The I&C Technician inadver-tently shorts out the Division 2 RHR LOCA logic which realigns RHR B and C in the LPCI mode. When the
, sparks arc, he slips and damages the LPCI B Injection
,i Valve Manual Override Relay E12-K24B in the de-e energized mode. The Reactor Vessel begins to flood rapidly. RHR (LPCI) Pumps B and C are injecting cold water into the vessel at the combined flow rate of 14,000 gpe. Reactor Vessel level peaks at +5 inches Wide Range. Reactor power peaks at 55% and decreases to 40%. i 1208 The operators close LPCI-C injection valve, but ' efforts to close the LPCI-B injection valve fail. Further, when the LPCI B pump control switch is i placed in the "Stop" position, the Breaker Trip ! . Control Power Fuse blows, thus allowing the pump to l run. The pump cannot be tripped from-the Control Room. Reactor power decreases to 20%. 1210 Suppression Pool temperature increases approaching
- 212*F. Containment radiation levels increase.
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-PERRY NUCLEAR POWER PLANT'
.1984 EMERGENCY PREPAREDNESS EXERCISE NARRATIVE
SUMMARY
- ONSITE SEQUENCE OF EVENTS Approximate Time Key Event 1215 An operator successfully opens RHR Pump B breaker locally (Elevation 620 Control Complex). As he completes the task, he becomes aware of the scent of charred paint' and metal. Upon investigation, he discovers the Motor Control Cabinet for Bypass Valve E12-F048B is charred and inoperable. Bypass
! Valve E12-F048B is stuck open. 1220 A GENERAL EMERGENCY is declared (EPI-A1, Sec-tion D.IV.1, " Loss of two fission-product barriers with a potential loss of a third" or Attachment 3, Condition 2, " Transient plus failure of requisite core shutdown systems. Could lead to core melt in several hours with containment failure likely. More severe consequences if reactor Recirculation Pump Trip does not function"). 1230 Suppression Pool temperature reaches 224*F; contain-ment pressure is 5 psig and increasing. RHR B is
, being used for containment spray, but RHR Heat Exchanger Bypass Valve E12-F048B is open, rendering the spray ineffective due to lack of cooling. HPCS .
is maintaining water level. Annulus Exhaust Gas Treatment System (AEGTS) and the Unit 2 vent monitor detect increasing levels of radiation. 1245 Containment pressure and temperature continue to 1 increase. Suppression Pool temperature is 238'F;
, containment pressure is 10 psig and increasing.
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4 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE , NARRATIVE
SUMMARY
- ONSITE SEQUENCE OF EVENTS Approximate-Time Key Event
, 1315 Containment pressure reaches 27 psig. AEGTS and the Unit 2 vent monitor indicate substantially increased
' levels'to radiation. Offsite radiological monitoring teams detect increases in radiation readings.
T NOTE: A release path from the containment to the annulus is available through a crack in the containment dome-to-wall circumferential 4 weld. From the annulus, the radioactive gas is released through the AEGTS. The
. operators should not turn off the AEGTS fan; if they do, the extreme annulus-to-atmosphere pressure could leak out unmoni-tored and unfiltered. Also, the fire dampers do not shut due to a batch of defective fusible links.
1315 Standby Liquid Control System injects into the vessel when Common Check Valve C41-F007 opens. 1325 Containment pressure peaks at 28 psig. t 1330 RER Bypass Valve E12-F048B is closed; Containment Spray Loop B is in full operation. 1335 Maintenance reports that ESW Pump P45-C001A will be able to be racked in at 1340; final coupling. align-ments are in progress. 1340 ESW Pump P45-C001A is started; Containment Spray Loop A is placed in operation?. 1400 Some control rods begin to insert due to spurious rod drifts. 1410 The Reactor is shut down due to completion of SLC injection. 1430 Containment pressure decreases. The release decreases. 4 e ' Mw- v
PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE NARRATIVE
SUMMARY
- ONSITE SEQUENCE OF EVENTS A9 proximate Time Key Event -
' lI 1445 The Shift Supervisor reports that.all control rods-have inserted.
1500 Containment pressure returns to atmospheric pressure. The release stops. 1545 Offsite radiation readings begin to decrease as wind speed and direction changes disperse the plume. l 1615 .Offsite radiation readings return to background. The GENERAL EMERGENCY is downgraded. Commence're-entry !! and recovery operations. 1645 The exercise is terminated. I e i .1 2 ,! e
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e 6 6.3 Narrative Summary - Offsite Sequence of Events k 'h e ? I 3 I f Y
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PERRY NUCLEAR POWER PLANT 1984 EMERCENCY PREPAREDNESS EXERCISE NARRATIVE
SUMMARY
- 0FFSITE SCHEDULE OF EVENTS -
Approximate - Time PNPP Key Events and Actions Ohio Response County Response 0717 PNPP Shif t Supervisor calls Perry Perry Township Fire Department Township Fire Department to assist responds to fire in accordance in fighting'an in-plant fire, with standard procedures. 0725 PNPP declares an UNUSUAL EVENT due Ohio Disaster Services Agency (ODSA) Message is logged. to a fire in the protected area receives notification of an UNUSUAL lasting more than 10 minutes. EVENT from PHPP and from the Sheriff Departments notify their Lake County Radiological Analyst. respective DSA Director and PNPP notifies Counties' Sheriff selected officials as per County Departments and State DSA via Message is logged. procedures. 5-way dedicated line. Lake County Sheriff Department notifies the Perry Township Fire Chief. 0730 Telephone checks are made by the ODSA Response Section to determine the availability of vehicles and
' field monitoring equipment.
The Office of the Governor is notified of the condition. The Lake County Radiological Analyst remains in contact with both the county directors and the utility to receive updates.
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PERRY NUCLEAR POWER PLANT 1984 EMERCENCY PREPAREDNESS EXERCISE NARRATIVE
SUMMARY
- 0FFSITE SCHEDULE OF EVENTS Approximate Time PNPP Key Events and Actions Ohio Response County Response The ODSA Public Information Officer (PIO) and the Communications Officer will be placed on standby.
0805 PNPP declares an ALERT due to a ODSA receives a direct notification spent fuel handling accident. of the Alert from Perry over the The Technical' Support Center 5-way dedicated line. and Operations Support Center are activated. Message is logged. PNPP.uses 5-way line to notify Activate State EOC in Columbus. Message is logged. - County Sheriffs and State DSA of the Alert. Activate field monitoring teams, Sheriff Departments notify DSA dispatch State Public Information Directors and selected officials Officer, Radiological Officer and as per their procedures. Field Monitoring Teams to Perry. County EOCs activate as per plans, and where appropriate, follow DSA Directors' orders. Sheriff Departments transfer monitoring of 5-way dedicated line to County EOCs. Counties test operability of 3-way dedicated line. Send Public Information Officer to the JPIC when JPIC is acti-vated.
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PERRY NUCLEAR POWER PLANT 1984 EMERCENCY PREPAREDNESS EXERCISE NARRATIVE
SUMMARY
- OFFSITE SCHEDULE OF EVENTS i
Approximate Time PNPP Key Events and Actions Ohio Response County Response i Counties notify all agencies per ~ their procedures (police, fire, ambulance, schools, hospitals, nursing homes, prisons, major employers.) Lake County alerts the Ells Central' Program Control Station. EOC staff not yet activated are notified and put on standby. Amateur radio operators notified and put on standby (Ashtabula and Ceauga Counties). Radiological Officer and assistant prepare TLDs for pickup by user agencies.
; EOC security system is activated.
i ' Radiological Officer monitors 5-way dedicated line. Message log initiated. I American Red Cross notified. Reception centers notified. 4
. ... -. . .. - . . - . . - ~ .. .. : -.:....
PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE NARRATIVE
SUMMARY
- 0FFSITE SCHEDULE OF EVENTS Approximate Time PNPP Key Events and Actions Ohio Response County Response Decontamination teams notified.
0815 'The nuclear response section supervisor or his assistant will promptly notify the following:
- a. Supervisor of the ODSA Radiological Instrumentation /
Maintenance and Calibration (RI/M&C) Facility,
- b. State Radiological Officer.
- c. Public Information Officer.
i
- d. Communications Officer.
- e. Ohio Department of Health. ,
- f. Ohio Environmental Protection Agency.
*g. Office of the Covernor.
*h. The Ontario Ministry of the Solicitor General.
- Calls to be made by the Deputy Director of ODSA.
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PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE NARRATIVE
SUMMARY
- 0FFSITE SCHEDULE OF EVENTS Approximate Time PNPP Key Events and Actions Ohio Response ' County Response , , *i. Ohio National Guard (ONG),
Air Support.
*j. ONG Security.
- Calls to be made by the Deputy Director of ODSA.
i 0820 Simultaneously with notification, the following activities will begin:
- a. The radiological section supervisor will alert response personnel.
All response equipment will be loaded into vehicles which will then leave for the staging area at the Chardon Highway Patrol Post.
- b. The ONG will be in the process of preparing air transportation.
- c. The ODSA Communications Officer will dispatch the communications van to the preselected site:
Ledgemont School, 16200 Burrows Rd., Thompson, Ohio. 1 l 1 1
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PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE NARRATIVE
SUMMARY
- OFFSITE SCHEDULE OF EVENTS Approximate Time PNPP Key Events and Actions Ohio Response County Response
- d. The Ohio Department of Health and the Ohio Environmental Protection Agency will proceed to the state Emergency Operations Center (EOC.)
- e. The state PIO and one assistant will prepare to fly to the Joint Public Information Center (JPIC.)
The ODSA Deputy Director will make arrangements for EOC security. The ODSA EOC Controller will verify that the EOC is equipped to function in the event of a Site Area Emergency. 0835 The EOC Controller will dispatch operations and training personnel to the affected counties. 0840 The state dose assessment facility will be staffed by ODSA, Ohio Dept. of Health and the Ohio Environmenthl Protection Agency. Open communi-cations with the three counties and utility Technical Support Center * (TSC) will be ongoing for the remainder of the exercise.
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PERRY NUCLEAR POWER PLANT 1984 EHERGENCY PREPAREDNESS EXERCISE NARRATIVE
SUMMARY
- OFFSITE SCHEDULE OF EVENTS Approximate Time PNPP Key Events and Actions Ohio Response County Response 0845 Ashtabula County Medical Center receives notification of a con-taminated, injured victim.
0905 A contaminated, injured victim arrives at Ashtabula County Medical Center for treatuent. NOTE: The initiating event is , out of sequence; _it occurs at t 1515. 0930 PNPP requests an ambulance to Dispatch ambulance from Perry transport a contaminated, Township Fire Department. injured person to Lake County Memorial Hospital, East. , 1015 The ambulance arrives at Lake The victim is decontaminated and County Memorial Hospital. East. treated for his injuries. 1030 PNPP declares a SITE AREA OSDA receives notification of a Counties' EOCs are fully acti-EMERGENCY due to a complete loss Site Area Emergency over the 5-way vated. of any functions needed for plant dedicated line. ODSA assessment hot shutdown. personnel begin notification Mobilize American Red Cross. of the following agencies with The Emergency. Operations Facility instructions to activate the EOC: Notify hospitals, nursing homes, 1 and Joint Public Information prisons, school districts, recre-Center are activated. a. Ohio Dept. of Natural Resources, ation areas, transportation systems.
. . . . . . . n. . ., , . _ ._ .n . . _ . . , . ~ _ . ~ , . . . _ . . . . . . , .. . s PERRY NUCLEAR POWER PLANT 1984.EMERCENCY PREPAREDNESS EXERCISE NARRATIVE
SUMMARY
- OFFSITE SCHEDULE OF EVENTS Approximate Time PNPP Key Events and Actions Ohio Response County Response PNPP notifies Counties and State b. Ohio State Patrol.
of escalation to SITE AREA EMER- Mobilize police, fire and ambu-CENCY, via the 5-way dedicated c. Public Utility Commission lance, line. of Ohio. . Reception centers and decontam-
- d. American Red Cross. Ination teams are activated or placed on standby as per plans
- e. Ohio Dept. of Agriculture. and DSA Directors' instructions.
- f. Ohio Dept. of Transportation. Establish amateur radio commun-ication links with participants.
- g. State of Pennsylvania.
EBS Message " Site Area Emer-
- h. Ohio Public Welfare, gency; No Action Necessary" -
initiated by Lake County. The ODSA Deputy Director will i notify:
- Radiological dfficer distributes l 1. The Governor's Office. TLDs to agencies as they come to
! the EOC to pick them up. l
- j. The Ohio National Guard Adju-j tant General and Military Response agencies distribute j . Support. dosimetry to individual workers.
- k. Ontario Ministry of the School districta place school bus l Solicitor General. drivers on standly status.
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_ _ . _ _. . . .. ...~ _._ . .. . _ _ - _ - . - . . . . . s - PERRY NUCLEAR POWER PLANT 1984 EMERCENCY PREPAREDNESS EXERCISE NARRATIVE
SUMMARY
- OFFSITE SCHEDULE OF EVENTS Approximate Time PNPP Key Events and Actions Ohio Response County Response Transportation staging areas activated.
Lake County initiates EBS Message " Shelter f arm animals"
- if advised by State.
Notify host schools. 1040 Additional notifications will be made to the Federal Emergency Management Agency and the U.S. Dept. of Energy. This notification will include the request for assistance to include;
- a. field monitoring for noble gas and iodine.
- b. field sampling, including analysis to determine part-iculate and gaseous depositions.
The ODSA Operations Officer will activate the state EOC in support ' of county agencies. 4 L
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PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE-NARRATIVE
SUMMARY
- 0FFSITE SCHEDULE OF EVENTS Approximate Time PNPP Key Events and Actions Ohio Response County Response 1045 The Director of the Ohio Disaster Services Agency will request that the Covernor of Ohio declare a state -
of emergency and authorize active
- duty military support of state field monitoring teams to perform, or prepare to perform, radiation monitoring.
The JPlc will be staffed by state personnel. Lines of communications will be opened to the State EOC and utility EOF for coordination of public information releases. Releases will be made as situations require. The ODSA Public Information Officer-will prepare the state briefing area for press releases from the State EOC. The rumor control line at the State EOC will be manned. Briefings will be held in Room 153 of General Beightler's Armory hourly or as the situation dictates.
. . . . _ , s,L._ _
_ _ _ . a; . 2.:.. ._m. 4 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE NARRATIVE
SUMMARY
- OFFSITE SCHEDULE OF EVENTS Approximate Time PHPP Key Events and Actions Ohio Response County Response
, The Ohio Dept. of Health will make a protective action recommendation to Lake County to: " Shelter and place on stored feed, all lacta-ting animals within two miles of i the plant." 1220 PNPP declares a CENERAL EMERCENCY ODSA receives notification of a Initiate appropriate EBS/NOAA due to a loss of two fission General Emergency. Protective message and simulate siren product barriers with a poten- action recommendations received sounding after coordination tial loss of the third, from the utility are considered among three counties over the
- by the Ohio Dept. of Health 3-way dedicated line.
Personnel, i PNPP notifies State and Counties Activate Traffic Control Points i of escalation via the 5-way and perimeter control points, dedicated line. Activate school bus drivers assemble buses at schools. Mobilize police, fire, ambulance, i hospitals, nursing homes, prisons, j schools, recreation arean, and j transportation systems. Activate reception centers and transportation staging areas if not already done. Activate decontamination teams. I
. - - . ~ . . . u. . :.-. _ _ . . . _ .. . . . .. . _ . . . , , .
1 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE NARRATIVE
SUMMARY
- 0FFSITE SCHEDULE OF EVENTS Approximate Time PNPP Key Events and Actions Ohio Response County Response Direct the relocation of municipal fire station and police department EOCs.
County EOC ensures that local police departments continue security patrols and police / fire
, agencies ensure notification to 100% of population.
Additional protective actions issued as warranted and agreed to via the 3-way dedicated line. Based on plant status, the Ohio Dept. of Health will make an assessment within 15 minutes. Protective action recommenda- - tions will be formulated and approved by the Covernor's repre-sentative. 1235 Protective action recommendations are passed to the county and State representatives at the local EOCs. The State Analyst will remain in consultation with the three County Commissioners until the final protective action recommendation is reached.
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PERRY NUCLEAR POWER PLANT' 1984 EMERGENCY PREPAREDNESS EXERCISE NARRATIVE
SUMMARY
- 0FFSITE SCHEDULE OF EVENTS Approximate
, Time PNPP Key Events and Actions Ohio Response County Response Notification of all county decisions will be made to the State'EOC and utility EOF by the State Analyst. ODSA communicators will maintain communications with counties, adjacent states, field monitoring teams, JPIC, and EOF. 1315 A major release of radiation begins.
, Offsite Radiation Monitoring Teams detect radiation levels.
PNPP upgrades its protective action recommendations. 1330 ODSA receives notification of increased release rates and new protective action recommendations. The Ohio Dept. of Health will analyze the information provided - and make the State recommendations. e
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PERRY NUCLEAR POWER PLANT 1984 EMERCENCY PREPAREDNESS EXERCISE NARRATIVE
SUMMARY
- 0FFSITE SCHEDULE OF EVENTS Approximate Time PNPP Key Events and Actions Ohio Response County Response Based on plant status, the Ohio Dept. of Health will make an assess-ment within 15 minutes. Protective action recommendations will be formulated and approved by the Covernor's representative.
1345 Protective action recommendations are passed to the county and state representatives at the local EOCs. The State Analyst will remain in consultation with the three County Commissioners until the final protective action recommendation is reached. ; Notification of all county decisions
; will be made to the state EOC l and utility EOF by the State Analyst.
Monitoring teams are dispatched i to preselected sites within the pathway of the plume. Assistance is requested from the State of Ohio by one or all of ' the counties involved, to aid i in securing the affected areas.
. - - - . . _ . - _ . - .g- . , , . - _ , . _,.-y PERRY NUCLEAR POWER PLANT.
1984 ENERGENCY PREPAREDNESS EXERCISE NARRATIVE SUIMARY - 0FFSITE SCHEDULE OF EVENTS
. Approximate
- Time PNPP Key Events and Actions Ohio Response County Response
- The Ohio National Cuard dispatches security personnel to Lake, Ceauga, and Ashtabula Counties.
1500 The release of radiation stops. 1515 ODSA receives notification of The counties receive notification the end of the release. of the end of the release. An emergency worker at the , Saybrook Decontamination. Center becomes injured and contaminated. He is loaded into an ambulance. 1615 Offsite levels of radiation return to background. PNPP, in consultation with the Notifications are made to all State and counties, downgradesi response agencies - police.
- the Emergency Classification. fire, ambulance.
PNPP notifies State and counties of downgrade via the 5-way dedicated Notify hospitals, nursing homes, j line. school districts, prisons, recreation areas, transportation systems,
. .. ...:... ,s . m .._. _......, . . :m _ _ . . . s .u ,~ .
PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE NARRATIVE
SUMMARY
- 0FFSITE SCHEDULE OF EVENTS Approximate Time- PNPP Key Events and Actions Ohio Response County Response Issue notice to public via news release at JPIC.
1620 The offsite portion of the Exercise is terminated by the ODSA Nuclear Operations Officer by announcement over the 5-way dedicated line. Field samples will be analyzed by the Ohio Dept. of Health (DOH) to determine ground level concentrations
~~-~
of radionuclides. (DOH analysis --- , will be out of sequence.) -' 1645 The exercise is terminated. 9 DW176/N/16/kay e
J-- L b i 6.4 Written Summary of The Exercise Scenario (, 1 2 se 1 I
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4 4 6.4 Written Summary of The Exercise Scenario The following is a synopsis of the detailed narrative summary NOTE: listed ht Section 6.2 of this package. The Perry Nuclear Power Plant has been operating continuously for the e last 17 months with a capacity factor of over 90 percent. The Plant is , currently operating at 100 percent power and is at the end of core life. Some equipment problems are ongoing but all have been addressed through ' p surveillance activities. Plans are currently underway to ship one fuel element to Idaho National Engineering Laboratories for examination and testing on the new barrier fuel cladding. Weather conditions remain constant with th's forecast indicating a high
, temperature of 45'F for the day with winds out of the Northwest at 10 to 20 miles per hour.
1' At 7:08 a.m. a fire breaks out in the PPD machine shop on Level 599'. 4 The Control Room is notified to activite the Station Fire Brigade. Upon L arrival at the scene, fire fighting operations commence and a request is made for offsite fire fighting a*sistance due to the severe nature of the fire. Based on this situation, at 7:25 a.m. the Shift Supervisor declares an Unusual Event in accordance with EPI-A1, Section F. I. 1 (" Fire within 4 the Protected Area lasting greater than 10 minutes") . Notifications are begun to offsite authorities and the Nuclear Regulatory Commission. U A short while later offsite fire support arrives at the Plant and the fire is extinguished at approximately 7:45 a.m. Initial indications are h that the fire has not affected any Plant safety systems and a decision is made to leave the Plant at full power. j 4 Plant personnel begin damage assessment activities and preliminary reports indicate that no one was injured as a result of the fire. 3 )J . At 8:00 a.m. a spent fuel bundle is raised beyond the normal up limit due c to a winch interlock failure on the Spent Fuel Handling Bridge in the
.; Fuel Handling Building. This action results in the initiation of radiation alarms locally and in the Control Room.
The Fuel Handling Building is evacuated, and the Control Room is notified of the situation. Based on EPI-A1, Section J. II.1 (" Fuel handling 4 accident with release of radioactivity to containment or Fuel Handling
- Building") the Shift Supervisor escalates the emergency classification to an Alert, and notifications are made to required personnel and offsite
>~
agencies. The Technical Support Center and Operations Support Center being activation and other emergency response personnel go on standby. Local Emergency Operations Centers begin notifications and remain in a standby mode. I
, . ~. - - - - . . _ - - - . . - -- -._..- - . - -
Plant assessment activities continue onsite with reports coming in from the work crews who are re-entering the Fuel Handling Building. At 9:15 a.m. an operator on rounds in the Intermediate. Building notices
. water coming from the Fuel Pool Cooling and Cleanup Backwash Receiving Tank Room. While attempting to leave the area, he slips, falls and is
, seriously injured. Later indications will show that he is also l contaminated by the leaking water. The Plant First Aid Team responds
'[
while notifications are made offsite for ambulance support.
- p Lake County Memorial East Hospital is notified to prepare for receipt of
.l a contaminated, injured man.
M Plant conditions remain stable and final reports indicate no serious
- q. damage resulted from the fire. Repair activities are begun in the Spent 3 Fuel Pool Area to return the bundle to safe storage, j- t
- i At 10:00 a.m. Safety Relief Valve (SRV) B21-F051D inadvertently opens and operators prepare to commence a reactor shutdown. During the scram
- j initiation no control rod motion is observed. All alternate attempts to
-
- shutdown fail, resulting in an ATWS (Anticipatory Transient Without
} Scram).
!' The Operations Manager in the Technical Support Center declares a Site Area Emerzency based on EPI-A1, Section D.III, 2 (" Complete loss of any , functions needid for plant hot shutdown"). Offsite notifications are 3; ; made. The Emergency Operations Facility and Joint Public Information l' Center are-activated. State and Local Emergency Operation Centers are j also activated. Operators' attempts to manually scram the reactor continue to fail; and the Standby Liquid Control System fails to initiate upon demand.
;g Due to these failures, the Control Room Operators implement Attachment 5 of PEI-1 to lower reactor water level and reduce reactor power to
, approximately 8% through void formation. Efforts to insert the control ll rods or initiate boron poisoning continue to fail.
, At 12:00 p.m. the reactor's water level is being maintained by only one i, feed pump. A short time later the running feedwater booster pumps and the running feed pump trip due to a low hot surge tank level switch malfunction. Reactor water level control is lost and the water level decreases below the MSIV isolation setpoint resulting in uncovering of the core and fuel clad degradation. j Based on EPI-A1, Attachment 3,1 (" Loss of 2 fission product barriers with a potential loss of third barrier") the Emergency Coordinator declares a General Emergency. e 4 4
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e Offsite authorities are notified and public protective actions are recommended. The Emergency Broadcast system is utilized to notify the public and use of the early warning siren systen is simulated. At 1:15 p.m. increased containment pressure causes the failure of the third fission product barrier (containment) allowing a major release of radioactivity through the Annulus Exhaust Gas Treatment System to the environment. Radiation monitoring teams follow the path of the plume, and onsite efforts continue to attempt to gain control and stabilize the plant. At 2:00 p.m. some of the reactor control rods begin inserting and the Standby Liquid Control System completes injection. Forty-five. minutes later the Control Room reports that the reactor is shutdown and all rods are inserted. Efforts continue to stabilize and improve plant conditions. With the decrease in containment pressure, the release decreases until the containment pressure returns to atmospheric pressure and the release is terminated. Radiation monitoring teams follow the path of the plume and onsite efforts continue to stabilize and improve plant conditions. Due to the long duration of the emergency, turnovers between key onsite response personnel will be occuring to provide a rest period for those initial responders who directed the early phases of the emergency response effort. With all required activities successfully demonstrated onsite and offsite, the emergency is de-escalated so that recovery operations can begin. After all required re-entry activities (plant only) are underway, the Exercise is terminated at 4:45 p.m. i l
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Time: 0700 Message No.: 1 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Messane For: Control Room Simulated Plant Conditions: See Initial Conditions Sheet and Data Sheets Message: ***THIS IS A DRILL *** Commence the 1984 Emergency Preparedness Exercise. Initial Conditions are as specified on the attached sheets. Make the following announcement: " Attention, attention all personnel; we are commencing the 1984 Evaluated Emergency Preparedness Exercise. Only designated participants should respond to drill announcements." FOR CONTROLLER USE ONLY Controller Notes: 1. Ensure that the PA announcement is made.
- 2. Only the Control Room receives annunciator alarm data sheets.
NOTE: The following standard will be utilized for annunciators:
- a. An annunciator alarm which is new is enclosed by a solid line box.
- b. An annunciator which h'as been acknowledged and is cleared is enclosed by a dotted line box. It will not appear on the next annunciator data sheet.
- c. An annunciator which remains lit has no box of any type enclosing it.
Actions Expected: Participants should review initial conditions and plant data sheets. DW176/C/1/ba
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PERRY NUCLEAR POWER PLANT 1984 EMERCENCY PREPAREDNESS EXERCISE TIME: 0700 fit {ll fitRQ CONTAINMENT PARAMETERS SYSTEM INFORMATION REACTOR PARAMETERS' Tempe ra tu re Pressure Pressure Flow Pressure 1018 psig (*Fl f osia l__ Status fosiel . focal Level 31 in. NR Cntet 81 0 RWCU PMP A OP 1350 Neutron Drywe 1 i 120 0.1 B OP 1350 Mon 100 Range APRM HWL PMP A OP 230 Mode SW RUN Tempe ra tu re Level (*F1 fft.) B OP 230 FDW Flw 15.4 Mlb/hr Supr P1 88 18.2 C SS O ST Flw (Total) 15.4 Mlb/hr CBP A OP .__275 Line A 3.8 SYSTEMS INFORMATION B OP 280 Line B 3.8 Pressure Flow Status (psial (com) C SR 150~ Line C 3.8 RHR A SR RFBP A OP 330 Line D 3.8 B SR B OP 330 C SR C OP 330 LPCS SR D SR 160 1 RCIC SR , RFP A OP 1065 15.1 K - HPCS SR B OP 1063 14.9f ECC A 00S MFP SR 0 0 IMREINE-CENERATOR B SR RCIRC A FAST 39254 PARAMETERS ESW A 00S B FAST 39254 Mwatt 1235 B SR MVAR 350 MAJOR VALVE PARAMETERS C SR CNDR Vac 28 In, Hg
. Status Closed Open , CRD A SR Thrt Pr 950 psig
- MSIV NORM 0 8 f
B OP 1900 44 BYP VLV SRV NORM 19 0 Posit 0 % SLC A SR B SR SLC STC TK LVL 4600 gal. k.
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PERRY NUCLEAR PObEH PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 0700 P870 ELECTRICAL DISTRIBUTION P904 CST Level 410.000 eal. Status Load fMW1 Status Status fosial . OFFsite Pwr Sources 2 AV Cont Rm HVAC Supp Fan A OP TBCC PMP A OP 75 Con Breakers 2 CL 8 SR B OP 75 Div 1 DG OOS Cont Rm HVAC Rtn Fan A OP , C SS 18 Div 2 DG SR B SR SA Comp OP 128 Div 3 DG SR Cont Re Eng RCIRC Fan A SR IA Comp SR 120 B SR CIRW PMP A OP 46 Status , P970 B OP 45 Cntet Vsl Cig Fan A OP Pressure Status (DalGI C OP 46 B OP NCC Pump ,A OP 112 8 OP 112 B SS D OP C SS 35 E OP ADDITI O NAL INFORMATION SW Pump A OP 56 - F SS Status Abbreviations: B OP 56 D rywe l l Cool ing Fan I A OP OP Ope ra t ing C SS O 2A OP SS Secured Status . D SS O 3A OP AV Available MTR F i re Pump SR 18 SS SR Standby Readiness DD Fi re Pump SR 2B SS SitTDN Shutdown 3B SS S-SP Slow Speed Cntet Val Purge Supp fan A SS F-SP Fast Speed B SS ISOL 1solated Cptet Val & DW Purge Exh Fan A SS NORM No rma l B SS OOS Out of Service D rywe l l Purge Suppl Fan A SS CL Closed 8 SS OVRD Override AECTS Fan A OOS B OP
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PERRY MUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 0700
, , a PANEL P604 PANELS P669. P670. P671. P672 Process Radiation Main Steam Line RAD 6.8E+2 mR/hr Ala rm Cntet Vent Exh RAD 41.0E-1 mR/hr Orrgas Pre-treatment 2.5E+2 R/hr Offgas Post-treatment A 2 0E+2 Cpm PANEL P902 8 2.0E+2 cpm Common Airborne cas (com) Alarm Eng Service Water A 3.0E+1 cpm RWB Vent Exh 2.0E+1 B 1 QL11 cpm FHB Vent Exh 2.2E+1 OC Carbon Bed Vault A 6.0E+1 mR/hr CR Vent Exh 2.0E+1 8 5.5E+1 mR/hr PANEL P906 PANEL 803 Common Process and Aree gne Af a re Turb Bldg East 2.5E+0 mR/hr UD-MH-73 East Liq 3.0E+1 Turb Bids West 2.5E+0 mR/hr UD-MH-70 West Liq 3.2E+1 NCC Heat HX 3.5E+1 PANEL P804 Radwaste to ESW 3.0E+1 Airborne Radiation Cas (comi Ala rm Radwaste to Sewage 3.6E+1 Annulus Exh A Cas 0,0010 B 3iDE11 Cntat Ata 2,0011 METEOROLOGICAL CONDITIONS D rywe l l - HR (R/hr) 120011 AB Vent ggQLil Wind Speed 20.0 mph OGB Vent Exh 2.DE12 Wind Direction 200 OCB Vent - HR Q 0[10 Tempe ra ture 32 *F OC Vent Pipe 2 pl12 Delta T -0.95 'F U1 Plant Vent 6.0L11 U1 Plant Vent - HR Q 0E10 18/118 Vent 6,0[1]
T8/118 Vent - HR Q,DLiQ ST Packing Exh htDLil U2 Plant Vent 6,0011 U2 Plant Vent - HR 0.0E+0 l DW170C/A/3/ba e
AREA RADIATION $0NITORS Time: 0700 TAG # LOCATION READING (mR/hr) 1D21NO30 Personnel Air Lock, Cntet (600'6") 5.0E+0 1D21N040 CRD HCU West, Cntat (620'6") 5.0E+0 1D21N050 RBRT Area, Cntmt (642') 1.0E+2 I 1D21N060 Tip Drive Area, Cntat (600'6") 3.0E+1 1D21N070 RWCU F/D Area, Cntmt (664'7") 7.0E+0 1D21N080 Upper Pool Area, Cntmt (689'6") 2.0E+0
- 1D21N110 Aux Blda East (574'10") 7.0E+0 1D21N120 Aux Bldg West (574'10") 7.0E+0 1D21N130 Turb Rm East (647'6") 2.5E+0 1D21N140 CRD HCU East, Cntat (620'6") 5.0E+0 1D21N160 Turb Rm West (647'6") 2.5E+0 1D21N170 Turb Blda (605'6") 2.5E+0
[ 1D21N180 Hotwell Pump Area, TB (577'6") 1.0E+1
- . 1D21N190 TB Sump Area, TBC (548'6") 2.0E+1 1D21N200 OGB (584') 1.1E+1 1D21N210 Cnds F1tr Pmp Area, TBC (568'6") 9.0E+0 1D21N220 OG After F1tr Area, OGB (602'6") 2.0E+1
] 1D21N230 HP Fdw Her Area, HB (600'6") 1.0E+1
; 1D21N240 Fdw Pump Area, HB (647'6") 6.6E+0 1D21N400 CR, CC (654'6") 1.6E-1 ' . 1D21N410 OG Hold Up Area, TB (577'6") 1.0E+1 D21N250 RWB West (574'10") 2.5E+1 D21N260 RWB East (574'10") 1.5E+1
- _ D21N270 RWB (602') 5.0E+0 D21N280 Process Sample Rm, RWB (623'6") 4.0E+0 D21N290 RW Evap, RWB (623'6") 4.0E+0
.c D21N310 FPCU F/D Area, IB (599') 6.0E+0 D21N320 Fuel Preparation Pool, IB (620'6") 4.0E+0 D21N330 Spent Fuel Storage Pool IB (620'6") 4.0E+0 D21N420 FPCU Cire Pmp Area, IB (574'10") 9.0E+0 1D21N340 Unit 1 DW, Portable, Cntet (655') -
D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1 D21N370 SR'J Drumming Area, RWB (623'6") 6.0E+0 R'efueling Bridge. Cntmt
~ , 1D21N090 (689'6") 3.0E+0 D21N390 Fuel Serv Hdig Platform, IB (620'6") 3.0E+0 t
1 4 4
* = Alarm OS = Offscale
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Tima: 0710 Message No.: 2 PERRY NUCLEAR POWER PIANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Message For: Control Room Simulated Plant Conditions: Message: ***THIS IS A DRILL *** There is a fire in the welding area (southwest corner) of the Machine Shop. The oxygen and acetylene hoses on the welding rig have been cut, and the fire is spreading rapidly. The hoses are whipping around as pressure is released, and there is heavy smoke in the area. I
- I -
;i O
FOR CONTROLLER USE ONLY l player Controller Notes: This message will be phoned in by a , posing as a welder, using the GAI-TRONICS System. Actions Expected: - - DW176/C/2/ba
Tims: 0712 Massage No.: 3 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Message For: , Secondary Alarm Station (SAS) Simulated Plant Conditions: Message: ***THIS IS A DRILL *** You have a fire alarm indicated in the Machine Shop.
'i -
l, FOR CONTROLLER USE ONLY b Controller Notes: A Walder has severed the acetylene and oxygen hoses on the
; welding rig. The fire initially spreads to Class "A" material (plywood, rags, etc.) and Class "B" material (oil and
, lubricants) in the area.
a Actions Expected: The SAS would inform CAS and a Security Guard should be dispatched to investigate, but once the SAS receives a call corroborating the alarm, he should dispatch the fire brigade, ,: and evacuate the second floor of the Service Building. DW176/C/3/ba l i t t k.
Time: 0712 Hessage No.: 4 PERRY NUCLEAR POWER PIANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Messane For: Control. Room Simulated Plant Conditions: See single attached sheet y
, Messame: ***THIS IS A DRILL ***
n 1, -
, FOR CONTROLLER USE ONLY i.
l. i ! Controller Notes: ," Actions Expected:
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' t[ a DW176/C/4/ba
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W Time: 0712 Message No.: 5' PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM t Messaae For: SAS Simulated' Plant Conditions:
. Messame: ***THIS IS A DRILL ***
ThereisafireandheavysmokeintheweldingareaofthePPD Maintenance Shop. FOR CONTROLLER USE ONLY I ]; playe r. Controller Notes: This message will be called into the SAS by a, - 1 4 Actions Expected: e a b DW176/C/5/ba
Time: 0715 Message No.: 6 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Messaae For: SAS Simulated Plant Conditions: Messame: ***THIS IS A DRILL *** , You have a flow alarm, indicating that the sprinkler system has been activated in the Machine Shop. t j- . I t FOR CONTROLLER USE ONLY (o 1,
~
. Controller Notes: This should start the ten-minute clock for declaration of an UNUSUAL EVENT.
Actions Expected: Inform the Shift Supervisor in the Control Room. u
=V
-{ . DW176/C/6/ba
. . - _ - -.~. .. --..
Tima: 0715 Message No.: 7
- PERRY NUCLEAR POWER PIANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Messaae For: Control Room
. Simulated Plant Conditions: See attached sheets I Messame: ***THIS IS A DRILL ***
bg
- I 1
,ew , 4 d,. . h ' FOR CONTROLLER USE ONLY ! .} ' ,
' Controller Notes:
i j Actions Expected: 7., 4 2.. I 4
+
j .4 DW176/C/7/ba b
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s PERRY NUCLEAR POWER PLA80T ' _1984 EMERGEIICY PREPAREDIIESS EXERCISE TigeE: 0715 CONTR0t. ROOM AlellUIGCI ATORS , P601/P877 P680 P870 as BACK PANELS , S yoIo_n 7L l FIRE AND l SECURITY l lTRSLP802l 1 l l 4 1 i I I J 3 i I l l 1 l 4 ; 5 i
, DW1708/A/8/ba I
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PERRY NUCLEAR POWER PLANT 1984 EMERCENCY PREPAREDNESS EXERCISE TIME: 0715 fit 9.1 fitAQ CONTAINMENT PARAMETERS SYSTEM INFORMATION REACTOR PARAMETERS Tempe ra tu re Pressure Pressu re Flow Pressu re 1018 psig f*F1 fosion Status fosial foon) .
. Level 31 in. NR Cntet 81 0 RWCU PMP A OP 1350 Neut ron Drywe l l 120 0.1 8 OP 1350 Mon 100 Range APRM HWL PHP A OP 230 Mode SW RUN Tempe ra ture Level f*F) fFt.) 8 OP 230 FDW F1w 15.4 Mib/hr Supr Pt 88 18.2 ,
C SS 0 ST Flw (Total) 15.4 Mib/hr CSP A OP 275 Line A 3.8 SYSTEMS INFORMATION 8 OP 280 Line B 3.8 Pre ssu re Flow Status fosion fanal C SR 150 Line C 3.8 RHR A SR RF8P A OP 330 Line D 3.8 8 SR 8 OP 330 C SR C OP 330 LPCS SR D SR 160 RCIC SR RFP A OP 1065 15.18( HPCS SR 8 OP 1063 14.'9 K ECC A DOS MFP SR 0 0 IURSI ME-GENERATOR 8 SR RCIRC A FAST 39254 PARAMETERS ESW A OOS 8 FAST 39254 Mwatt 1235 B SR MVAR 350 MAJOR VALVE PARAMETERS C SR CNDR Vac 28 in. Hg _ Status closed Open CRD A SR Thrt Pr 950 psig MSIV leORM 0 8 8 OP 1900 44 BYP VLV SRV NORM 19 0 Posit 0 % SLC A SR 8 SR SLC STC TK LVL 4600 gal. 7
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PERRY 100 CLEAR POWER PLANT 1984 EMERGENCY PREPAREDeeESS EXERCISE TIME: 0715 P670 ELECTRICAL DISTRIBUTION 220h CST Level 410.000 eat. Status Load fMW) Status Status fosiel Offsite Pwr Sources 2 AV Cont Rm HVAC Supp Fan A OP TBCC Pete A OP 75 Con Breakers 2 CL 8 SR S OP 75 Div 1 DC 00S Cont Rm HVAC Rtn Fan A OP C SS 18 Div 2 DG SR 8 SR SA Comp OP 128 Div 3 DC SR Cont Rm Eng RCIRC Fan A SR IA Camp SR 120 8 SR fA00 CaltW Pree A OP 46 Status f9.10 8 OP 45 Cntet Vsl Cig Fan A OP Pressu re Status fosial C OP 46 8 OP 10CC Pump A OP 112 SJAE A OP C SS S OP 112 8 SS D OP C SS 35 E OP ADOITIONAL INFORMATION SW Pump A OP 56 F SS Status Abbreviations: 8 OP 56 Drywell Cooling Fan 1A OP OP Ope ra ting C SS O 2A OP SS Secured Status D SS O 3A OF AV Available MTR Fire Pump SR 18 SS SR Standby Readiness DD Fire Pump SR 28 SS _ SHTDel Shutdown 38 SS S-SP Slow Speed Cntet Vsl Purge Supp Fan A SS F-SP Fast Speed 8 SS ISOL Isolated Cntet Vsl er DW Purge Exh Fan A SS teORM 900rea I 8 SS DOS Out or Service Drywell Purge Suppl Fan A SS CL Closed 8 SS OVRD Override AECTS Fan A 00S
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PERRY IIUCLEAR POWER PLA81T 1984 EMERCEleCY PREPARE 000ESS EXERCISE TIME: 0715 PANEL P604 PA80ELS P669. P670. P671. P672 - Process Radiation Mein Steam Line RAD. 6.8E+2 mR/hr Alarm Cntet Vent Exh RAD 41.0E-1 mR/hr Offgas Pre-treatment 2.5E+2 R/hr Offgas Post-treatment A L OE+2 cpm PANEL P902 8 2.OE+2 cpm Common A1rborne Gas (comi AIa re Eng Service Water A 3.0E+1 cpm RWS Vent Exh 2.0E+1 8 3.0E+1 cpm FHS Vent Exh 2.2E+1 OG Ca rbon Bed Vaul t ' A 6.OE+1 mR/hr CR Vent Exh 2.0E+1 8 5.5E+1 mR/hr PANEL P906 PANEL 803 Common Process and Area gag Alare Turb Bldg East 2.5E+0 mR/hr 90-MH-73 East Liq 3.0E+1 Turb Bldg West 2.5E+0 mR/hr UO-MH-70 West Liq 3.2E+1 80CC Heat HX 3.5E+1 PAllEL P804 Radweste to ESW 3.0E+1 Airborne Radiation Gas (comi Alare Radweste to Sewage 3.6E+1 Annulus Exh A Cas Dt0E_+9 8 LpE. Catet Atm LDEL METEOROLOGICAL CONDITIONS Drywell - HR (R/hr) L9Q. Wind Speed mph AB Vent L9E_+1 20.0 0C8 Vent Exh L90+2 Wind Direction JO OC8 Vent - HR Q,DE+Q Tempe ra ture 32 *F OG Vent Pipe LQEB Delta T -0.95 *F UI Plant Vent 6 JE+_1 ut Plant Vent - HR D,0(+9 TB/HB Vent 6,DE_+1 TB/HB Vent - HR O_,D dQ ST Packlog Exh A 01:+' U2 Plant Vent ML U2 Plant Vent - HR Q.&[fy DW170C/A/4/ba . O t
AREA RADIATION MONITORS Time: 0715 TAG # LOCATION READING (mR/hr) 4 1D21N030 Personnel Air Lock Cntet (600'6") 5.0E+0 l7 1D21N040 CRD HCU West. Cntet (620'6") 5.0E+0 f.i 1D21N050 RBRT Area. Cntat (642') 1.0E+2 1D21N060 Tip Drive Area. Cntet (600'6") 3.0E+1 1D21N070 RWCU F/D Area. Cntet (664'7") 7.0E+0
-1D21N080 Upper Pool Area. Cntet (689'6") 2.0E+0 1D21N110 Aux Blda East (574'10") 7.0E+0
[ 1D21N120 Aux Blda West (574'10") 7.0E+0
- 1D21N130 Turb Rm East (647'6") 2'.5E+0 3 1D21N140 CRD HCU East Cntet .(620'6") 5.0E+0 1D21N160 Turb Rm West (647'6") 2.5E+0 1D21N170 Turb Blda (605'6") 2.5E+0 1D21N180 Hotwell Pump Area. TB (577'6") 1.0E+1 ' '
1D21N190 TB Sump Area. TBC (548'6") 2.0E+1 .; 1D21N200 OGB (584') 1.IE+1-
, 1D21N210 Cnds Fitr Pop Area. TBC (568'6") 9.0E+0 1D21N220 OG After F1tr Area. OGB (602'6") 2.0E+1
's ID21N230 HP Fdw Htr Area. HB (600'6") 1.0E+1 ] 1D21N240 Fdw Pump Area. HB (647'6") 6.6E+0
- 1D21N400 CR. CC (654'6") 1.6E-1 1D21N410 OG Hold Up Area. TB (577'6") 1.0E+1
~{ D21N250 RWB West (574'10") 2.5E+1 D21N260 RWB East (574'10") 1.5E+1 D21N270 RWB (602') 5.0E+0
; D21N280 Process Sample Rs. RWB (623'6") 4.0E+0
- r. D21N290 RW Evap. RWB (623'6") 4.0E+0
'( D21N310 FPCU F/D Area. IB (599') 6.0E+0 3 D21N320 Fuel Preparation Pool. IB (620 ' 6) 4.0E+0 j D21N330 Spent Fuel Storane Pool. IB (620'6") 4.0E+0 l D21N420 FPCU Cire Pmp Area. IB (574'10") 9.0E+0 1D21N340 Unit 1 DW, Portable. Cntet (655') - 1; D21N380 Waste Cempactor Area.-RWB (623'6") 6.0E+1 3 D21N370 SRW Drumming Area. RWB (623'6") 6.0E+0 1D21N090 Refuelina Bridae. Cntet (689'6") 3.0E+0 * ' I D21N390 Fuel Serv Mdla Platform. IB (620'6") 3.0E+0 3 M. .1
+
i * = Alarm OS = Offscale -) ,
c . Time: 0720 Message No.: 8' PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM
- . Messame Fort AMWelder Simulated Plant Conditions
Messame: ***THIS IS A DRILL ***
. The Maintenance Supervisor reports that all maintenance personnel are accounted for.
s a l na ./ - FOR CONTROLLER USE ONLY 1 A i )-, Controller Notes: Actions Expected: This information should be relayed to the Brigade Leader. a , l* . t 5 Y DW176/C/8/ba
Time: 0725 Message No.: 9
. PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Messane For: . Combat Attack Team (CAT) at Scene Simulated Plant Conditions:
(i Messame: ***THIS IS A DRILL *** You have moderate heat and moderate-to-heavy dark smoke as you enter the door to the Machine Shop. i-i
.i .
8 I.
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it
. FOR CONTROLLER USE ONLY i:
]I Controller Notes: It has now been 10 minutes since the sprinkler system was j- activated. The Shift Supervisor should declare an LNUSUAL
! EVENT (EPI-A1, Section F.I.1, " Fire within the Protected
?; Area lasting more than 10 minutes"). y a. Make notifications. 9 b. Assess the situation. i i Actions Expected: 1. The CAT leader should request that the south door be. opened to provide additional ventilation. I- 2. On receipt of this information, the Fire Brigade Leader d should call for offsite fire fighting assistance. DW176/C/9/ba
Time: 0729 Message No.: 10 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM
>. Messaae For: CAT Leader Simulated Plant Conditions:
Messame: ***THIS IS A DRELL*** You are encountering heavy smoke, but not a lot of flames. The cutting l rig hoses are still whipping around. k J . - i' 3 FOR CONTROLLER USE ONLY 1 1 j Controller Notes: This message is delivered when the CAT approaches the area of
.; the fire.
1 -
- Actions Expected
- DO NOT allow the fire to spread outside the maintenance area i . toward the Control Complex.
T f DW176/C/10/ba
Time: 0730 Message No.: 11 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM 3 Messaae For: Control Room
, Simulated Plant Conditions: See attached sheets t
Messame: ***THIS IS A DRILL *** s i . 1- .
.I ;_ FOR CONTROLLER USE ONLY l
4 .j Controller Notes: g. 1, . Actions Expected: i
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DW176/C/11/ba
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PERRY IIUCLEAR POWER PLANT 1984 EMERGEllCY PREPAREDNESS EXERCISE TIME: 0730 P601 P680 CONTAlllMENT PARAMETERS SYSTEM INFORMATION REACTOR PARAMETERS Tempe ra tu re Pressure Pressure- Flow Pressure 1018 psig (*F1 fosle) Status fosle) feoel Level 31 in. MR Cntet 81 O RWCU PMP A OP 1350 Neutron Drymil 120 0.1 8 OP 1350 Mon 100 Range APRM HWL PMP A OP 230 Mode SW RUN Tempe ra ture Level f*F) (Ft.1 8 OP 230 FDW Flw 15.4 Mib/hr Supr PI 88 18.2 C SS O ST Flw (Total) 15.4 Mib/hr CSP A OP 275 Line A 3.8 SYSTEMS INFORMATION , B OP 280 Line B 3.8 Pressure Flow Status iosial ianel C SR 150 Line C 3.8 RHR A SR RF8P A OP 330 Line D 3.8 B SR S OP 330 C SR C OP 330 LPCS SR D SR 160 RCIC SR RFP A OP 1065 15.1 ( HPCS SR S OP J O63 14.9y . ECC A 00S MFP SR 0 0 ILH!alME-GENLRATOR . 8 SR RCIRC A FAST 39254 PARAMETERS ESW A 005 : 8 FAST 39254 Mwatt 1235 B SR MVAR 350 MAJOR VALVE PARAMETERS C SR CNDR Vac 28 in. Hg Status Closed Open CRD A SR Thrt Pr 950 psig MSIV IIORM O 8 8 OP 1900 44 BYP VLV SRV IIORM 19 0 Posit 0 $ SI_C A SR B SR
> SLC STG TK LVL 4600 gal.
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4 PERRif leUCLEAR POWER PLANT 1984 EMERGE 80CY PREPAREDesESS EXERCISE TIME: D730 P870 FLECTRICAL DISTRIBUTIOff P9048 CST Level 410.000 cal. . Status Load IMW) Status Status fosiel OFFsite Pwr Sources 2 AV Cont Ra IfvAC Supp Fan A OP TBCC PMP A OP 75 Gen Breakers 2 CL 8 SR 8 OP 75 Div 1 DC 00S Cont Rm HVAC Rtn Fan A OP C SS 18 Div 2 DG SR 8 SR SA Coop OP 128 Div 3 DG SR Cont no Eng RCIRC Fan A SR IA comp SR 120 8 SR P800 CIRW PMP A OP 46 . Status
~
E919 8 OP 45 Cntet vsl CIg Fan A OP Pressure Status fosial C OP 46 8 OP IICC Pump A OP 112 SJAE A OP C SS 8 OP 112 8 SS D OP C SS 35 E OP ADDITIOe8AL IItFORMATION SW Pump A OP 56 F SS Status Abbreviations: 8 OP 56 Drywe11 Cooling Fan 1A CP 2A OP SS Secured Status D SS O 3A OP AV Available MTR Fire Pump SR 18 SS SR Standby Readiness DD Fi re Pump SR
. 28 SS SHTDel Shutdown 38 SS S-SP Slow Speed Catet Vsl Purge Supp Fan A SS F-SP Fast Speed ,
8 SS
- ISOL isolated Cntet Vsl & DW Purge Exh Fan A SS Is0RM Iso rua I 8 SS 00S Out or Service Drywell Purge Suppl Fan A SS CL Closed 8 SS OVRD Ove rride AECTS Fan A OOS 8 OP
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N f PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 0730 PANEL P604 Y . PANELS P669. P670. P671. P672 i % Process Radiation
- Main Steam Line RAD 6.8E+2 mR/hr '
Alarm " Cntet Vent Exh RAD 1.0E-1 mR/hr
. \ Offgas Pre-treatment 2.5E+2 R/hr j+ . . 3,. Offgas Post-treatment A 2.0E+2 cpm PAllEL P992 s 8 2.0E+2 cpm Common Alrhorne Gas'Icoal Alsre Eng Service Water A 3.0E+1 cpm RW8 Vent Exh 2.0E+1 8 3.0E+1 cpm fHS vent Exh 2.2E+1
= OG Carbon Bed Vault A 6.0E+1 mR/hr CR Vent Exh 2.0E+1 8 5.5E+1 mR/hr
. PANEL P996 PANEL 803 ca==an Process and Area E23 Alare Turb Bldg East 2.5E+0 mR/hr UD-MH-73 East 1.lg 3.0E+1 Turb Bldg West 2.5E+0 mR/hr UD-MH-70 West Liq 3.2E+1 NCC Heat HX 3.5E+1 PANEL P804 Radweste to ESW 3.0E+1 A1rborne RedIation Gas fcomi A1ere Radwaato to Sewage L.6L+1 Annulus-Exh A Gas Q,D[tQ 8 LD[t.
Cntet Ate 9JQ. METEOROLOGICAL CONDITIONS Drywell - HR (R/hr) L9Q. Wind Speed P0.0__ aph A8 Vent 2OQ.
- OGB Vent Exh ZJE_ + 2 Wind Di rectIon J 0 OG8 Vent - HR QJLig Temperature 32 'F OG Vent Pipe 2 OES Delta T -0.82 *F U1 Plant Vent 6,9EE U1 Plant Vent - HR Q,DEtj}
T8/198 Vent 6,0Q1 T8/188 Vent - HR QJ[tQ ST Packing Exh il nQ1 U2 Plant Vent 6 OEt.1 U2 Plant Vent - HR 0.0E+0 DW170C/A/5/ba l
- e
V AREA RADIATION MONITORS Time: 0730 4 TAG # LOCATION READING (mR/hr)
! 1D21NO30 Personnel Air Lock, Cntat (600'6") 5.0E+0 1* 1D21N040 CRD HCU West. Cntat- (620'6") 5.0E+0 d ID21N050 RBRT Area. Cntat (642') 1.0E+2 a 1D21N060 Tip Drive Area. Cntat (600'6") 3.0E+1 ! 1D21N070 RWCU F/D Area. Cntet (664'7") 7.0E+0 et 1D21N080 Upper Pool Area Cntet (689'6") 2.0E+0 ; . 1D21N110 Aux Blda East (574'10") 7.0E+0 1D21N120 Aux Blda West (574'10") 7.0E+0 l' .1D21N130 Turb Re East (647'6") 2.5E+0 l 1D21N140 CRD HCU East. Cntet (620'6") 5.0E+0 j 1D21N160 Turb Rm West (647'6") 2.5E+0 1D21N170 Turb Blda (605'6") 2.5E+0 i 1D21N180 Hotwell Pump Area. TB (577'6") 1.0E+1 ! 1D21N190 T1 Sump Area. TBC (548'6") 2.0E+1 ! 1D21N200 OGB (584') 1.1E+1 j ID21N210 Cnds F1tr Pep Area. T1C (568'6") 9.0E+0 1D21N220 OG After F1tr Area. OGB (602'6") 2.0E+1 1D21N230 HP Fdw Htr Area. HB (600'6") 1.0E+1
) 1D21N240 Fdu Pump Area. HB. (647'6") 6.6E+0
- j 1D21N400 CR. CC (654'6") 1.6E-1 1 1D21N410 OG Hold Up Area. TB (577'6") 1.0E+1 j D21N250 RWB West (574'10") 2.5E+1 l D21N260 RWB East (574'10") 1.5E+1 D21N270 RWB (602') 5.0E+0 j D21N280 Process Sample Rs. RWB (623'6") 4.0E+0 RW Evap. RWB (623'6") 4.0E+0 D21r290 j D214310 D21I320 FPCU F/D Area. IB Fuel Preparation Pool. IB (599')
(620'6") 6.0E+0
'4.0E+0 i'
D21h .s Spent Fuel Storane Pool. IB (620'6") 4.0E+0 1 D21N420 FPCU Cire Pmp Area. IB (574'10") 9.0E+0 3 1D21N340 Unit 1 DW. Portable. Cntet (655') - 1 D21N380 Waste Compactor Area. RWB (623'6") 6.0E+1 D21N370 SRW Drummina Area. RWB (623'6") 6.0E+0
.' . 1D21N090 Refuelina Bridas. Cntet Fuel Serv Hdla Platform. IB (689'6")
(620'6") 3.0E+0
'3.0E+0 j D21N390 q
'4 i h f* 4 L*
+
A
; * = Alarm OS = Offscale
Time: 0733 Message No.: 12 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE l MESSAGE FORM Messane For: CAT-Leader i Simulated Plant Conditions: Messame: ***THIS IS A DRILL *** The main fire has been confined but the hoses are still whipping y around.
?
i I
- T.
i [ FOR CONTROLLER USE ONLY i 4' , Controller Notes: A'j . Actions Expected: The CAT should make efforts to isolate the oxygen-acetylene ,; bottles. r
?. -
. DW176/C/12/ba
Time: 0739 Message No.: 13 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Message For: CAT Leader [ Simulated Plant' Conditions: { Messaae: ***THIS IS A DRILL *** v The bottles are turned off and the hoses are secured. The fire is now I under control.
'i !?
i i I a- FOR C0!GROLLER USE ONLY
!-f f
F. [, . Controller Notes: Once the bottles are isolated, the main (oxygen-acetylene) 't fire will be extinguished and the brigade can turn their
; . attention to the peripheral fires.
Actions Expected: DW176/C/13/ba a m
- - , w- g y m M -
Time: 0740 Message No.: 14X. PERRY NUCLEAR POWER PLANT
*1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Message For: ' Control Room Simulated Plant Conditions:
I Message: ***THIS IS A DRILL *** Declare an UNUSUAL EVENT (EPI-A1, Section F.I.1, " Fire within the Protected Area lasting greater than 10 minutes"). i I i i J FOR CONTROLLER USE ONLY i Controller Notes: Deliver this message if an UNUSUAL EVENT has not been declared. k Do not deliver this message if Emergency Classification discus-
, sions are underway.
? Actions Expected: See " Actions Expected," Message No. 9. 9 DW176/C/14/ba
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Time: -0743 Message No.: 15 PERRY NUCLEAR POWER PLAW 4 1984 EMERGENCY PREPAREDf2SS EXERCISE 3 MESSAGE FORM a
. Messaae For: CAT Leader Simulated Plant Conditions: ) Messame: ***THIS IS A DRILL *** ' ~
The fire is out. I-b t b P t i 1
,- FOR CONTROLLER USE ONLY
-] ]-e Controller Notes: Actions Expected: The CAT should commence cleanup and overhaul of the affected area, and inspection of the second floor for fire and smoke 3 damage. f 9 L l' DW176/C/15/ba
Tima: 0745 Message No.: 16 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Messane For: Control Room Simulated Plant Conditions: See attached sheets j~ Messaae: ***THIS IS A DRILL *** 4 1 4
?!
1
;l jj, '?
FOR CONTROLLER USE ONLY
- i ff, Controller Notes:
ij -* Actions Expected: d
< 1 b
DW176/C/16/ba
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PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: OT45 P601 P680 CONTAINMENT' PARAMETERS EYfTEM INFORMATION REACTOR PARAMETERS Tempe ra ture Pressure. Pressu re Flow Pressure 1018 psig I'F1 fosial Status.. _ fosle) focal Level 31 in. NR
- Cntet 81 0 RWCU PMP A OP 1350
) Neutron D rywe l l 120 0.1 B OP 1350 Mon 100 Range &fBM HWL PMP A OP 230 Mode SW RUN Tempe ra ture Level f*Fl (Ft.) B OP 230 FDW Flw 15.4 Mlb/hr Supr P1 88 18.2 C SS 0 ST Flw (Total) 15.4 Mlb/hr CBP A OP 275 Line A 3.8 SYSTEMS INFORMATION B OP 280 Line B 3.8 Pressure Flow Status fosial faomi C SR 150 Line C 3.8 RHR A SR RFBP A OP 330 Line D 3.8 8 SR
- 8 OP 330 C SR C OP- 330 LPCS SR D SR 160 RCIC SR RFP A OP 1065 15.1 K HPCS SR S OP 1063 14.9 ( .
ECC A 00S MFP SR 0 0 TUttB l NE-C[M RATOR B SR RCIRC A FAST 39254 PARAMETERS ESW A 00S B FAST 39254 Mwatt 1235 B SR MVAR 350 MAJOR VALVE PARAMETERS C SR CNDR Vac. 28 i n. ' Hg Status Closed Open CRD A __ SR Thrt Pr 950 psig MSIV NORM 0 8 8 OP 1900 44 BYP VLV SRV NORM 19 0 Posit 0 % SLC A SR B SR SLC STG TK LVL 4600 gal.
Os - . . w :. . . .. .- . .t.. . . , . . s. . c- - PERRY NUCLEAR POWER PLANT 1984 EMERCENCY PREPAREDNESS EXERCISE TIME: 0745 M]Q ELECTRICAL DISTRIBUTION DB CST Level 410.000 aal. Status Load fMW) Status Status fosial 0FFsite Pwr Sources 2 AV Cont Rm HVAC Supp Fan A OP TBCC PHP A OP 75 Cen Breakers 2 CL , 8 SR B OP 75 Div 1 DG OOS Cont Rm HVAC Rtn Fan A OP C SS 18 Div 2 DG SR B SR SA Comp OP 128 Div 3 DG SR Cont Re Eng RCIRC Fan A SR IA Comp SR 120 B SR MQQ CIRW PMP A OP 46 Status P970 B OP 45 Cntat Val Clg Fan A OP Pressure Status fosial C OP 46 8 OP NCC Pump A OP 112 SJAE A OP C SS B OP 112 B SS D OP C SS 35 E OP ADDITIONAL 1NFORMATION SW Pump A OP 56 F SS Status Abbreviations: B OP 56 Drywe l l Cool ing Fan I A OP - OP Opera ting C SS O 2A OP SS Secured Status D SS O 3A OP AV Available MTR Fire Pump SR 18 SS SR Standby Readiness DD Fi re Pump SR 28 SS . SHTDN Shutdown 3B SS S-SP Slow Speed Cntet Val Purge . Supp Fan A SS F-SP Fast Speed . B SS ISOL 1solated Cntet Val & DW Purge Exh Fan A SS MORM No rma i B SS OOS Out of Service Drywell Purge ' Suppl Fan A SS CL Closed B SS OVRD Override AEGTS Fan A OOS B OP
e O O
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1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 0745 PERRY NUCLEAR POWER PLANT PANEL P604 PANELS P669. P670. P671. P672 Main Steam Line RAD 6.8E+2 mR/hr Process Radiation Ala re
. Cntet Vent Exh RAD 41.0E-1 mR/hr Offges Pre-treatment 2.5E+2 R/hr PANEL P902 Offgas Post-treatment A 2.0E+2 cpm Common Airborne Gas (cDs) Ala re 8 2.0E42 cpm 3.0E+1 cpm RW8 Vent Exh 2.0E+1 Eng Service Water A 3.0E+1 cpm FHB Vent Exh 2.2E+1 8 .
CR Vent Exh 2.0E+1 DG Carbon Bad Vault A 6.0E+1 mR/hr 8 5.5E+1 mR/hr PANEL P906 Common Process and Area Egg Ala rm PANEL 803 UD-MH-73 East Liq 3.0E+1 Turb Bldg East 2.5E+0 mR/hr UD-MH-70 West Liq 3. 2 Et.1 Turb Bldg West 2.5E+0 mR/hr NCC Heat HX 3.5E+1 Radwaste to ESW 3.0E+1 PANEL P804 Alarm Radweste to Sewage 3.6E+1 Ai rborne Radiation , Cas icDm) Annulus Exh A Cas Q QEfD 8 3,0E_+ 1 2,0Etl METEOROLOGICAL CONDITIONS Cntet Atm Drywell - HR (R/hr) J Q[i.. Wind Speed PQiQ__ sph AB Vent 2,g E t. 0C8 Vent Exh R QE12 Wind Direction __gio Tempe ra ture 32 *F OG8 Vent - HR Q,pE1D -0.82. *F Delta T OG Vent Pipe R QE12 U1 Plant Vent 6,gE11 U1 Plant Vent - HR Q QEt[! 18/118 Vent M EE TB/HB Vent - HR 0 OE1!! ST Packing Exh h,0 DL U2 Plant Vent M 2L. . U2 Plant Vent - HR QAM DW170C/A/6/ba , e 9
_ . -- - ~ . . - . ~ . _ - - - . AREA RADIATION MONITORS Time: 0745
+
i TAG # LOCATION READING (mR/hr) .i 1D21NO30 Personnel Air Lock, Cntet (600'6") 5.0E+0 (( 1D21N040 1D21N050 CRD HCU West, Catet RPRT Area, Cntet (620'6") (642') 5.0E+0 1.0E+2 ]i
'i 1D21N060 Tip Drive Area Cntat (600'6") 3.0E+1
- , 1D21N070 RWCU F/D Area, Cntet (664'7") 7.0E+0 6 1D21N080 Upper Pool Area, Cntet (689'6") 2.0E+0
_1D21N110 Aux Blda East (574'10") 7.0E+0 ij 1D21N120 Aux Blda West (574'10") 7.0E+0 H 1D21N130 Turb Rm East (647'6") 2.5E+0 i 1D21N140 CRD HCU East, Cntet (620'6") 5.0E+0 Ft ID21N160 Turb Rm West (647'6") 2.5E+0 iT 1D21N170 Turb Blda (605'6") 2.5E+0 ! !. 1D21N180 Hotwell Pump Area, TB (577'6") 1.0E+1
,; 1D21N190 TB Sump Area, TBC (548'6") 2.0E+1 1D21N200 OGB (584') 1.1E+1 Ij . 1D21N210 Cnds F1tr Pop Area. TBC (568'6") 9.0E+0 t' ID21N220 OG After Fitr Area. OGB (602'6") 2.0E+1
!i 1D21N230 HP Fdv Htr Area. HB (600'6") 1.0E+1 1D21N240 Fdw Pump Area. HB (647'6") 6.6E+0 1D21N400 CR, CC (654'6") 1.6E-1 1D21N410 OG Hold Up Area,,TB (577'6") 1.0E+1 D21N250 RWB West (574'10") 2.5E+1 !; , D21N260 RWB East (574'10") 1.5E+1 l D21N270 RWB (602') 5.0E+0
} D21N280 Process Sample Ra, RWB (623'6") 4.0E+0 3 D21N290 RW Evap. RWB (623'6") 4.0E+0 l -D21N310 FPCU F/D Area. IB (599') 6.0E+0 1 D21N320 Fuel Preparation Pool IB (620'6") 4.0E+0
?I D21N330 Spent Fuel Storaae Pool. IB (620'6") 4.0E+0
- D21N420 FPCU Cire Pmp Area IB (574'10") 9.0E+0 1 1D21N340 Unit 1 DW, Portable Cntet (655') -
! D21N380 Waste Compactor Area RWB (623'6") 6.0E+1 H. D21N370 SRW Drumming Area, RWB (623'6") 6.0E+0
- I 1D21N090 Refuelina Bridae, Catet (689'6") 3.0E+0
'i D21N390 Fuel Serv Ndla Platform. IB (620'6") 3.0E+0 n; Lg g; y A-l
.i
* = Alarm OS = Offscale
{ 2 4
?? Tims: 0755 Message No.: 17
^
. PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM i Messane For: -Fuel Handling Bridge Operator Simulated Plant Conditions:
i Messame: ***THIS IS A DRILL *** 1 . . . f
- Movement of the spent fuel assambly has commenced.
4 i FOR CONTROLLER USE ONLY Controller Notes: 0
,' Actions Expected: Notify the Control Room.
e e 4 DW176/C/17/ba 4 e
V Time: 0800 Message No.: 18X PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM 6 9 Messane For: Scene Leader (Fire Brigade) Simulated Plant Conditions: l 't Messame: ***THIS IS A DRILL *** h No apparent damage on the second floor, but there is moderate smoke.
] . ?
1 2 1 1 j FOR CONTROLLER'USE ONLY I
] i } . Controller Notes:
l i Actions Expected: 1. The brigade should ventilate the building to remove smoke.
- 2. Notify the SAS.
A t DW176/C/18/ba
Tims: 0800 Message No.: 19 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Message For: Fuel Handling Bridge Operator Simulated Plant Conditions: Message: ***THIS IS A DRILL ***
; The fuel handling bridge winch position interlock has failed, and the fuel bundle has been raised above the NORMAL-UP ILait and the winch has shut down. Operation of the winch was erratic when raising the bundle near the up limit, and the bundle was jostled. ,
The fuel handling bridge ARM is alarming and reading 2 Rem /hr. i i! s I c FOR CONTROLLER USE ONLY Controller Notes: 1. \ttempts to lower the bundle fail. Q_
- 2. .FQsupplying The failure mechanism is as follows: Fuse 44b i: break hoist power, blows shutting down the Refueling
,i Bridge and Hoist. l' 3. The bundle is raised to approximately four feet below h- the top of the water. Actions Expected: 1. Evacuate the area. I
- 2. Notify the Control Room.
f
- 3. Control Room should implement ONI-D17.
DW176/C/19/ba r l
Tima: 0800 Message No.. 20 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM > Message For: Control Room t 1- Simulatid Plant Conditions: See attached sheets i y;, Messame: ***THIS IS A DRILL *** t 3_ f r i ,3 4 FOR CONTROLLER USE ONLY
~~
j 3 Controller Notes: , 'i c Actions Expected: i v . r
. DW176/C/20/ba =
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PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE 11ME: 0800 P601 fnAQ CONTAINMENT PARAMETERS SYSTEM INFORMATION REACTOR PARAMETERS Tempe ra tu re Pressure Pressure Flow Pressure 1018 psig f*F1- fosial Status _losial faomi Level 31 NR in. Cntat 81 0 RWCU PMP A OP 1350 _ Neutrent-D rywe l l 120 0.1 B OP 1350 Mon 100 Range APRM HWL PMP A OP 230 Mode SW RUN Tempe ra ture L. eve l f*F1 fft.) B OP 230 FDW Flw 15.4 Mlb/hr Supr PI 88 18.2 , C SS O ST Flw (Total) 15.4 Mlb/hr CBP A OP 275 Line A 3.8 - SYSTEMS INFORMATION B OP 280 Line B 3.8 Pressure Flow __ Status foslo) local C SR 150 , Line C 3.8 RHR A SR RFBP A OP 330 Line D 3.8 B SR B OP 330 C SR C OP 330 LPCS SR D SR 160 RCIC SR RFP A OP 1065 15.1( HPCS SR B OP 1063 14.9 Y [CC A OOS MFP SR 0 0 TURBINE-GENERATOR B SR RCIRC A FAST 39254_ PARAMETERS ESW A OOS B FAST 39254 Hwatt 1235 B SR MVAR 350 MAJOR VALVE PARAMETERS / C SR CNDR Vac 28 In. Hg Status Closed Ocen CRD A SR Thrt Pr 950 psig MSIV NORM 0 8 B OP 1900 44 BYP VLV SRV NORM 19 0 Posit O % SLC A SR B SR SLC STC TK LVL 4600 gal. w
7 , PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 0800 P870 ELECTRICAL DISTRIBUTION P904
' CST Level 410.000 cal. Status Load (MWI Status Status _ fosial .Orrsite Pwr Sources 2 AV Cont Rm HVAC Supp Fan A OP
- .TBCC PHP A OP 75 Con Breakers 2 CL 8 SR S OP 75' Div 1 DC OOS Cont Rm HVAC Rtn Fan 'A OP C SS 18 Div 2 DC SR B SR SA Comp OP 128 Div 3 DG SR Cont Re EPv ECIRC Fan A SR 1A Comp SR 120 B SR P800 CIRW PMP A OP 46 Status .
. P970 8 OP 45 Cntet Val Cig Fan A OP Pressure Status foslol i C OP 46 B OP NCC Pump A OP 112 SJAE A OP C SS B OP 112 B SS D OP , C SS 35 ADOITIONAL INFORMATION SW Pump A OP 56 F SS Status Abbreviations: B OP 56 Drywel l Cool ing fan 1 A - OP , OP Ope ra t ing C SS O i
2A OP SS Secured Status D *.S O 3A OP AV Available MTR Fire Pump SR IB SS SR Standby Readiness DD Fire Pump SR 28 SS SHTDN Shutdown . 38 SS S-SP Slow Speed Cntet Vs1 Purge Supp Fan A SS F-SP Fast Speed ISOL isolated Cntet Val er DW Purge Exh Fan A SS NORM NoraaI 8 SS OOS Out or Service Drywell Purge Suppl Fan A SS CL Closed i ; B SS OVRD Ove rride AECTS Fan A OOS B. OP l
I . O O o '1
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PERRY 800 CLEAR POWER PLAlli 1984 EMERCEIICY PREPAREDIIESS EXERCISE . TIME: 0800. PANEL P604 PANELS P669. P670. P671. P672 Process Radiation Main Steam Line RAD 6.8E+2 mR/hr Alaru
. Cntot Vent Exh RAD s.1.0E-1 mR/hr Orrgas Pre-treatment 2.5E+2 R/hr Orrgas Post-treatment A 2.0E+2 cpm PANEL P902 j 8 2.0E+2 cpm Common Airborne Gas fcomi Alare Eng Service Water A 3.0E+1 cpm RW8 Vent Exh 2.0E+1 8 3.0E+1 cpm FHS Vent Exh 2.2E+1 OG Carbon Bed Vault A 6.0E+1 mR/hr CR Vent Exh 2.0E+1 8 5.5E+1 mR/hr PANEL P906 PANEL 803 Common Process and Area see Alarm ,
Turb Bldg East 2.5E+0 mR/hr UD-MH-73 East Liq 3.0E+1 , Turb Bldg West 2.5E+0 mR/hr UD-MH-70 West Liq 3.2E+1 NCC Heat HX 3.5E+1 PANEL P804 Radweste to ESW 3.0E+1 , l Airborne Radiation Gas (Coal Afars Radweste to Sewage 3.6E+1 l Annulus Exh A Gas DiDE+Q - 8 Lo[11 j Cntet Ata LQE11 METEOROLOGICAL CONDITIONS Drywel1 - HR (R/hr) MQ A8 Vent 2,D2. . Wind Speed P1.5 mph oc8 Vent Exh 2,9 W 2' O
- Wind Direction Oc8 Vent - HR Q,0Lig Temperature 32 'F OG Vent Pipe 2,002 Delta T -1.20 *F U1 Plant Vent 6,0Q1 U1 Plant Vent - HR Q,0QQ 18/HB Vent 6,0 S !
18/H8 Vent - HR Q,QMQ ST Packing Exh 81 ,Q[11 U2 Plant Vent 6,001.1 , i U2 Plant Vent - HR 0.0E+0 l i DW170C/A/7/ba i i l
m . . . __ _ _ _ _ _ __ 't i AREA RADIATION MONITORS Time: 0800 J 1-R TAG # LOCATION READING (mR/hr) . 1D21NO30 Personnel Air Lock, Cntet (600'6") 5.0E+0
- . 1D21N040 CRD HCU West, Cntat (620'6") 5.0E+0 I' 1D21N050 RBRT Area, Catet (642') 1.0E+2 J 'y E! 1D21N060 Tip Drive Area, Cntet (600'6") 3.0E+1 1D21N070 RWCU F/D Area, Cntat (664'7") 7.0E+0 ,
1D21N080 Upper Pool Area, Cntet (689'6") 2.0E+0 ~' 1D21N110 Aux Blda East (574'10") 7.0E+0 1D21N120 Aux Blda West (574'10") 7.0E+0 1 t 1D21N130 Turb Rm East (647'6") 2.5E+0 9 ID21N140 CRD HCU East, Cntet (620'6") 5.0E+0
!!' 1D21N160 Turb Rm West (647'6") 2.5E+0 1D21N170 _ Turb B1dz (605'6") 2.5E+0
.; 1D21N180 Hotwell Pump Area. TB (577'6") 1.0E+1 !! 1D21N190 TB Sump Area TBC (548'6") 2.0E+1 li 1D21N200 OGB (584') 1.1E+1 1D21N210 Cnds F1tr Pmp Area. TBC (568'6") 9.0E+0 !; 1D21N220 OG After Fitr Area. OGB (602'6") 2.0E+1 1j 1D21N230 HP Fdw Htr Area, HB (600'6") 1.0E+1 }I 1D21N240 Fdw Pump Area. HB (647'6") 6.6E+0 il 1D21N400 CR, CC (654'6") 1.6E-1 il:, 1D21N410 OG Hold Up Area. TB (577'6") 1.0E+1 D21N250 RWB West (574'10") 2.5E+1 lj D21N260 RWB East (574'10") 1.5E+1
- i D21N270 RWB (602') 5.0E+0
-
- D21N280 Process Sample Ra, RWB (623'6") 4.0E+0 l i; D21N290 RW Evan, RWB (623'6") 4.0E+0 ;
!; FPCU F/D Area IB (599') D21N310 6.0E+0 , "! D21N320 Fuel Preparation Pool. IB (620'6") 2.0E+3 * !3 D21N330 Spent Fuel Storage Pool, IB (620'6") 5.8E+2
- D21N420 FPCU Cire Pep Area, IB (574'10") 9.0E+0 1D21N340 Unit 1 DW, Portable Cntat (655') -
D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1 l~ D21N370 SRW Drumming Area, RWB (623'6") 6.0E+0 t ' 1D21N090 .Refuelina Bridge, Cntet (689'6") 3.0E+0 D21N390 Fuel Serv Hdla Platform, IB (620'6") 2.0E+3 * [A 4 _ I l 1 1 . ! i
- * = Alarm OS = Offscale f
Time: 0805 Message No.: 21 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Message For: Controllers t n Simulated Plant Conditions: 2 2 Messame: ***THIS IS A DRILL *** 2
?
4
.FOR CONTROLLER USE ONLY t
2, Controller Notes: 1. The Shift Supervisor should declare an ALERT (EPI-A1, Y Section J.II.1, " Fuel Handling accident with release of radioactivity to Containment or Fuel Handling Building").
- 2. He should implement EPI-A3 " ALERT":
- a. Make notifications.
i' !. b. Activate the TSC and OSC.
- c. Assess the situation.
'?
Actions Expected: DW176/C/21/ba r I-l l
Time: 0815 Message No.: 22 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM
~
Message For: Control Room 1 Simulated Plant Conditions: See attached sheets
; Messame: ***THIS IS A DRILL ***
1 fI~ E' t i "f 4.
~
i i I FOR CONTROLLER USE ONLY s
; Controller Notes:
J ,; Actions Expected: t r. e i DW176/C/22/ba 9 9 - - e 'yy -'yy-
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q PERRY NUCLEAR POWER PLANT 1984 EMERCENCY PREPAREDNESS EXERCISE TIME: 0815 Eg]Q ELECTRICAL DISTRIBUTION M CST Level 410.000 eat. Status Load iMW) Status _ Status __ f os ia l Offsite Pwr Sources 2 AV Cont Rm HVAC Supp fan A OP 18CC PMP A OP 75 Con Breakers 2 CL 8 SR 8 OP 75 Div 1 DC 00S Cont Rm HVAC Rtn Fan A OP C SS 18 Div 2 DC SR 8. SR SA Comp OP 128 Div 3 DG SR Cont Re Eng RCIRC Fan A SR IA Ccap SR 120 , 8 SR CIRW PMP A OP 46 . Status f1ID 8 OP 45 Cntet Vsl Cig Fan A OP Pressure Status foslo) C OP 46 8 OP NCC Pump A OP 112 SJAE A OP . C SS B- OP 112 8 SS D OP C SS 35 E OP ADDIT 1ONAL lNFORMATION SW Pump A OP 56 F SS Status Abbreviations: 8 OP 56 Drywe i I Cooi Ing Fan I A OP OP Operating C SS O 2A OP SS Secured Status D SS O 3A OP AV Avai1able MTR F i re Pump SR 18 SS SR Standby Readiness DD Fire Pump SR 28 SS SHTDN Shutdown 38 SS S-SP Slow Speed Cntet Vsl Purge Supp Fan A SS F-SP Fast Speed 8 SS ISOL isolated Cntet Vsl & DW Purge Exh Fan A SS NORM No rma I 8 SS 00S Out of Service ,Drywell Purge Suppl Fan A SS CL Closed 8 SS OVRO Ove rride AEGTS Fan A OOS B- OP
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J PERRY NUCLEAR POWER PLANT 1988: EMERGENCY PREPAREDNESS EXERCISE TIME: 0815 PANEL P6088 PANELS P669s P670. P671. P672 Process Radiation Main Steam Line RAD 6.8E+2 mR/hr Alarm
.. Cntet Vent Exh RAD 1.0E-1 mR/hr Orrgas Pre-treatment . 2.5E+2 R/hr Orrgas Post-treatment A 2.0E+2 cpm PANEL P902 i 8 2.0E+2 cpm Common Airborne Gas (comi Ala re Eng Service Water A 3.0'E+1 cpm RWB Vent Exh 2.0E+1 B 3.0E+1 cpm FHB Vent Exh 2.2E+1 ,
OG Carbon Bed Vasalt A 6.JE+1 mR/hr CR Vent Exh 2.0E+1 B 5.5E+1 mR/hr - PANEL P906 PANEL 803 Common Process and Area gag Ala re Tairb Bldg East 2.5E+0 mR/hr UD-MH-73 East Liq 3.0E+1 t Turb Bldg West L.1f.iQ mR/hr UD-MH-70 West Liq 3.2E+1
~
NCC Heat HX 3.5E+1 PANEL P80.at Radweste to ESW 3.OE+1 Airborne Radiation 04s (comi Alarm , Radweste to Sewage 3.6E+1 Annulus Exh A Cas Q,0010 B 3 OE_11 Cntet Atm LOLil METEOROLOGICAL CONDITIONS Drywell - HR (R/hr) L DLil mph AB Vent 2AEt1 Wlpd Speed 21.5 OCB Vent Exh 2,DE_t2 Wind Direction J O OCB Vent - HR Q OE_tg Tempe ra ture :i2 *F OG Vent Pipe 2 , 01:t2 Delta T -1.20 *F U1 Plant Vent 6,9 ;.t1 ut Plant Vent - HR h.D ;19 TB/HB Vent 620E11 1B/HB Vent - HR Q,DE_tQ ST Packing Exh $Q ;;11 i U2 Plant Vent nd 11 U2 Plant Vent - HR. QEdQ DW170C/A/8/ba [ m s 9
. , -~ - . . .- - .=. .
AREA RADIATION MONITORS Time: 0815 4
- a
. TAG # LOCATION READING (mR/hr) 1D21NO30 Personnel Air Lock, Cntet (600'6") 5.0E+0 1 1D21N040 CRD HCU West, Cntet (620'6") 5.0E+0 -7 1D21N050 RBRT Area, Cntat (642') 1.0E+2 j 1D21N060 Tip Drive Area, Cntet (600'6") 3.0E+1
'j 1D21N070 RWCU F/D Area Cntat (664'7") 7.0E+0
.. 1D21N080 Upper Pool Area, Cntat (689'6")- 2.0E+0 J! 1D21N110 Aux Blda East (574'10") 7.0E+0 , /-
,7 1D21N120 1D21N130 Aux Blda West Turb Rm East - (574'10") (647'6") 7.0E+0 2.5E+0 Li 1D21N140 CRD HCU East, Cntat (620'6") 5.0E+0
.4 1D21N160 Turb Rm West (647'6") 2.5E+0 ID21N170 Turb Blda (605'6") 2.5E+0 0 1D21N180 Hotwell Pump Area. TB (577'6") 1.0E+1 I."; 1D21N190 TB Sump Area. TBC (548'6") 2.0E+1 )-
1D21N200 OGB (584') 1.1E+1 ID21N210 Cnds F1tr Pmp Area. TBC (568'6") 9.0E+0 1D21N220 OG After Fitr Area, OGB (602'6") 2.0E+1
; 1D21N230 HP Fdw Her Area. HB (600'6") 1.0E+1 1D21N240 Fdw Pump Area. HB (647'6") 6.6E+0 .
N] 1D21N400 CR, CC (654'6") 1.6E-1 3 1D21N410 OG Hold Up Area. TB (577'6") 1.0E+1 41 D21N250 RWB West (574'10") 2.5E+1 -i D21N260 RWB East (574'10") 1.5E+1 D21N270 RWB _ (602') 5.0E+0
'i D21N280 Process %nde % , RWB (623'6") 4.0E+0 (623'6")
D21N290 RW Evap. RWD 4.0E+0 D21N310 FPCU F/D Area, IB (599') 6.0E+0 D21N320 Fuel Preparation Pool, IB (620'6") 2.0E+3 * ~t D21N330 Spent Fuel Storage Pool IB (620'6") 5.8E+2
- j_ D21N420 FPCU Cire Pmp Area, IB (574'10") 9.0E+0 i.. 1D21N340 Unit 1 DW, Portable, Cntet (655') -
+i D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1 i D21N370 SRW Drumming Area, RWB (623'6") 6.0E+0 1D21N090 Refueling Bridge, Cntet (689'6") 3.0E+0 Jl D21N390 Fuel Serv Hdig Platform, IB (670'6"] 2.0E+3 *
.t-
.~ q i
* = Alarm
' OS = Offscale
. - - .-- .. . . _ . . . .-_ . . . - - , . . - , _ - - , - -. .--1
Time: 0820 Message No.: 23X PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM
. Message For: Control Room
~
Simulatsd Plant Conditions: [ Messame: ***THIS IS A DRILL *** 4 Declare an ALERT (EPI-A-1, Section J.II.1, " Fuel handling accident with release of radioact'ivity to Containment or Fuel Handling Building"). 1 i f FOR CONTROLLER USE ONLY-Controller Notes: Deliver this message if an ALERT has not been declared.
- Do not deliver this me ssage if Emergency Classification 1
discussions are underw;.y. Actions Expected: See " Actions Expected,'" Message N'o. 21. B
- DW176/C/23/ba L
Time: 0830 Message No.. 24
~
PERRY NUCLEAR POWER PLANT 9 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM lMessane For: Control Room /TSC i' Simulated Plant Conditions: See attached sheets [ -Messaae: ***THIS IS A DRILL *** t 1 4 5 a
; FOR C0!frROLLER USE ONLY l' Controller Notes: TSC and OSC activation should be underway.
1: Actions Expected: e
}
t - e 9 9 DW176/C/24/ba
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PERRY NUCLEAR POWER Pt. ANT - -1984 EMERCEIICY PREPAREDNESS EXERCISE. TIME:'0830 InQ.1 fitSQ CONTAlle9ENT PARAMETERS SYSTEM INFORMATION REACTOR PARAMETERS Tempe ra ture Pressu re Pressure Flow Pressure 1018 psig i I"F1 fosle) Jtatus InsleL focal Level 31 in. NR Cntet 81 0 RWCU PMP A OP 1350 Neutron DryweIi 120 0.1 8 OP 1350 Mon 100 Range atBtl HWL PMP A OP 230 Mode SW RUN Tempe ra ture Level f*Fl fFt.) 8 OP 230 FDW Flw 15.4 Mlb/hr Supr P1 88 18.2 C SS 0 ST Flw (Total) 15.4 Mlb/hr CSP A OP 275 Line A 3.8 SYSTEMS INFORMATION 8 OP 280 Line B 3.8 Pressure- Flow Status fosial feomi C SR 150 Line C '3.8 RHR A SR RFBP A OP 330 Line D 3.8 8 SR 8 OP 330 C SR C OP 330 LPCS SR D SR 160 RCIC SR RFP A OP 1065 15.1 K HPCS SR 8 OP 1063 14.9K ECC A 00S MFP SR 0 0 IUR81ME-CDlERATOR 8 SR RCIRC A FAST 39254 PARAMETERS ESW A 00S B FAST 39254 Mwatt 1235 8 SR MVAR 350 MAJOR VALVE PARAMETERS C SR CNDR Vac 28 in. Hg Status Closed Ooen CRD A SR Thrt Pr 950 psig 8 OP 1900 44 BYP VLV SRV IIORM 19 0 Posit O % SLC A SR , 8 SR SLC STC TK LVL 4600 gal. 9 9
. .- ~.;-- - - ~ ~ - ~ - ~.~n.---- - ~ - - - - ~ -- - - - -- --
D PERRY leuCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 0830 fAIQ ELECTRICAL DISTRIBUTION 2991 CST Level 410.000 eal. Status. Lead fMW) Status Status Iosie1 Dffaito Pwr Sources 2 AV Cont Rm HVAC Supp Fan A' OP TBCC PMP.A OP 75 Con Breakers 2 CL 8 SR 8 ~OP 75 Div 1 DG OOS Cont Rm HVAC~Rtn Fan A OP C SS 18 Div 2 DG SR 8. SR SA Comp OP 128 Div 3 DG SR Cont Re Eng RCIRC Fan A SR lA Comp SR 120 8 SR EA00 CIRW PMP A OP 46 E stus 2229 8 OP 45 Cntet Val Cig Fan- A OP Pressure Status fosial C OP 46 8 OP NCC Pump A OP 112 SJAE A OP- C SS . 8 OP 112 8 SS D OP C SS 35 E OP ADDITIONAL INFORMATION SW Pump A OP 56 F SS Status Abbreviations: 8 OP 56 Drywell Cool ing Fan 1 A OP OP Ope ra ting C SS O 2A OP SS Secured Status D SS O 3A OP AV Available MTR Fire Pump SR 18 SS SR Standby Readiness DO Fire Pump SR 28 SS SHTON Shutdown 38 SS S-SP Slow Speed Cntet Vs1 Purge-Supp Fan A SS F-SP Fast Speed 8 SS ISOL isolated Cntet Val & DW Purge Exh Fan .A SS NORM Normal 8 SS DOS Out of Service Drywell Purge Suppl Fan A SS CL Closed 8 SS OVRD Ove rride AEGTS Fan A 00S l .8 OP t 0 i r
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.,+.n. . . . - . ., . . - --. - - - - . . ~ - -.- - -- .-
+
PERRY NUCLEAR POWER PLAllT 1984 EMERGEllCY PR'EPAREDNESS EXERCISE TIME: 0830 PANEL P604 PANELS P669. P670. P671. P672 Process Radiation Main Steam Line RAD 6.SE+2.mR/hr Alarm Cntet Vent Exh RAD al.0E-1 mR/hr Orrgas Pre-treatment 2.5E+2 R/hr Orrgas Post-treatment A 2.0E+2. cpm PANEL P902
- 8 2.0E+2 cpm Common Airborne cas (coal Alarm Eng Service Water A 3.0E+1 cpm RW8 Vent Exh 2.0E+1 8 3.0E+1 cpm FH8 Vent Exh 2.2E+1 OG Carbon Bed Vault A 6.0E+1 mR/hr CR Vent Exh 2.0E+1 i 8 5.5E+1 mR/hr PANEL P906 PANEL 803. Common Process and Area Ents Alora Turb Bldg East 2.5E+0 mR/hr UD-MH-73 East Liq 3.0E+1 Turb Bldg West 2.5E+0 mR/hr UO-MH-70 West Liq L2[11 NCC Heat HX 3.5E+1
, fA!!EL P804 Radweste to ESW 3.0E+1 Airborne Radiation Gas tenal Ala rm Radweste to Sewage 3.6E+1 Annulus Exh A Cas 0 001Q 8 LDLil Cntet Ata LQL+1 METEOROLOGICAL CONDITIONS Drywell - HR (R/hr) LQ 1 A8 Vent 2,0 1. Wind Speed 23.0 mph OC8 Vent Exh 2,0 3. Wind Direction J 20
- OG8 Vent - HR QJL+Q Tempe ra ture 35 *F
! OG Vent Pipe 2 OES Delta T -1.20 *F .i U1 Plant Vent 6JE+_1 j U1 Plant Vent - HR Q,DEtQ ! 18/HB Vent (t OE. + 1 1 TB/HB Vent - HR QJEJ , j ST Packing Exh hg{1. U2 Plant Vent 6,0 1. 3 U2 Plant Vent - HR DJ W! DW170C/A/9/ba i l 1 9
AREA RADIATION MONITORS Time: 0830 l TAG # LOCATION READING (mR/hr) Li 1D21NO30 Personnel Air Lock, Cntat (600'6") 5.0E+0 1 ID21N040 CRD HCU West, Cntat (620'6") 5.0E+0 i 1D21N050 RBRT Area, Cntat (642') 1.0E+2 3 1D21N060 Tip Drive Area, Catst (600'6") 3.0E+1 't , 1D21N070 RWCU F/D Area, Cntet (664'7") 7.0E+0 1D21N080 Upper Pool Area, Cntet (689'6") 2.0E+0 1D21N110 Aux Blda East (574'10") 7.0E+0 3 1D21N120 Aux Blda West (574'10") 7.0E+0 3 1D21N130 Turb Re East (647'6") 2.5E+0
! 1D21N140 CRD HCU East, Cntet (620'6") 5.0E+0 l 1D21N160 Turb Rm West (647'6") 2.5E+0 n.
1D21N170 Turb Blda (605'6") 2.5E+0 1D21N180 Hotwell Pump Area TB (577'6") 1.0E+1
'i 1D21N190 TB Sump Area, TBC (548'6") 2.0E+1 . 1D21N200 OGB (584') 1.1E+1 '! 1D21N210 Cnds F1tr Pep Area. TBC (568'6") 9.0E+0 . ID21N220 OG After Fitr Area. OGB (602'6") 2.0E+1 l- 1D21N230- HP Fdw Htr Area. HB (600'6") 1.0E+1 . 1D21N240 Fdw Pump Area HB (647'6") 6.6E+0 1D21N400 CR, CC (654'6") 1.6E-1 1D21N410 OG Hold Up Area. TB (577'6") 1.0E+1
- D21N250 RWB West (574'10") 2.5E+1
/ D21N260 RWB East (574'10") 1.5E+1 i , D21N270 RWB (602') 5.0E+0 D21N280 Process Sample Ra, RWB (623'6") 4.0E+0 j D21N290 RW Evan, RWB (623'6") 4.0E+0 'j D21N310 FPCU F/D Area. IB (599') 6.0E+0 i D21N320 Fuel Preparation Pool. IB (620'6") 2.0E+3
- I D21N330 Spent Fuel Storage Pool, IB (620'6") 5.8E+2
- D21N420 FPCU Cire Pmp Area. IB (574'10") 9.0E+0
! 1D21N340 Unit 1 DW, Portable. Cntat (655') -
D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1-D21N370 SRW Drummina Area, RWB (623'6") 6.0E+0 (689'6") ID21N090 Refuelina Bridae, Cntat 3.0E+0 D21N390 Fuel Serv Hdla Platform. IB (620'6") 2.0E+3 *
* = Alarm OS = Offscale
Time: 0845 Message No.: 25 PERRY NUCLEAR POWER PLANT
,' 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM 4
Messaae For: Control Room /TSC ip
- Simulated Plant Conditions
- See attached sheets 1
Messame: ***THIS IS A DRILL *** C r -i .). I . V - i FOR CONTROLLER USE ONLY I Controller Notes: Actions Expected:
+
9 DW176/C/25/ba
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PERRY NUCLEAR POWER PLAseT 1984 EMERCEIICY PREPAREDelESS EXERCISE TiteE: 0845 Mal M COIITAll8IENT PARApeCTERS SYSTEM INFORMATION REACTOR PARAMETERS Tempe ra ture Pressure Pressure Flow Pressure 1018 psig (*Fl foslo) Status fosle) femel Level 31 in. leR Cntet 81 O RWCU PMP A OP 1350 Neutron Drywe1i 120 0.1 8 OP 1350 Mon '100 Range 6P8tl HWL PMP A OP 230 Mode SW RUN Tempe ra ture Level f*F1 frt.) 8 OP 230 FDW Flw 15.4 Mlb/hr Supr PI 88 18.2 C SS O ST FIw (Total) 15.4 Mib/hr C8P A OP 275 Line A 3.8 SYSTEMS INFORMATl081 . 8 OP 280 Line 8 3.8 Pressure Flow Status fosial femel C SR 150 Line C 3.8 RHR A SR RF8P A OP 330 .Line D 3.8 8 SR 8 OP 330 C SR C OP 330 LPCS SR D SR 160 RCIC SR RFP A OP 1065 15.1 ( HPCS SR 8 OP 1063 14.9 Y ECC A 00S MFP SR 0 0 TUR8INf_.C[3ERATOR 8 SR RCIRC A FAST 39254 PARAMETERS ESW A OOS 8 FAST 39254 Natt 1235 8 SR MVAR 350 MAJOR VALVE PARAMETERS C SR CNOR Vac 28 In, Hg Status Closed Open CRD A SR Thrt Pr 950 psig MSIV IIORM 0 8 8 OP 1900 44 BYP VLV SRV IIORM 19 0 Poait 0 % SLC A SR S SR SLC STC TK LVL 4600 gal. O
~ ~
.i . . ...s.'. . L . . . J.L >. . .s .,.,m.. . ,,~ - ...w.- .n e. ..: - - , - . . - -
s PERRY IIUCLEAR POWER PLAlli 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 0845 P870 ELECTRICAL DISTRIBUTICII 22Qh CST Level 410.000 cal. Status Load IMW) Status
._ Status _ fosiel - OfFsite Pwr Sources 2 AV Cont Rm HVAC Supp Fan A OP
- TBCC PMP A OP 75 Gen Breakers 2 CL 8 SR 8 OP 75 Div 1 DG OOS Cont Rm HVAC Rtn Fan A OP C SS 18 Div 2 DG SR S SR SA Comp OP 128 Div 3 DG SR Cont Re Eng RCIRC Fan A SR IA Comp SR 120 B SR P800 CIRW PMP A OP 46 Status 2220 B OP 45 Cntet Vsl CIg Fan A OP Pressure Status fosial C OP 46 B OP 1 NCC Pump A OP 112 SJAE A OP C SS B OP 112 B SS D OP C SS 35 E OP ADolTIONAL INFORMATION SW Pump A OP 56
, F SS I Status Abbreviations: B OP 56 Drywell Cooling Fan IA OP 2A OP SS Secured Status D SS 0 3A OP AV Available MTR Fire Pump S3 J 18 SS SR Standby Readiness DO Fi re Pump SR I 28 SS . SHTDN Shutdown i 3B SS 1 S-SP Slow Speed Cntet Vsl Purge Supp Fan A SS F-SP Fast Speed 8 SS ISOL Isolated Cntet Vsl k DW Purge Exh Fan A' SS j NORM Norea1 j B SS 00S Out OF Service Drywel l Purge A Suppl Fan SS 4 CL Closed
'R SS OVRD Ove rride AEGTS Fan A OOS B OP
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1984 EMERGEIICY PREPAREDIIESS EXERCISE TIME: 0845 PEstRY leuCLEAR POWER PLA01T PAllEL P604 PAffELS P669. P670. P671. P672 Hein Steam Line RAD 6.8E+2 eft /hr Process Radiation Alare Catet Vent Exh RAD 41.0E-1 aft /hr CfFges Pre-treatment 2.5E+2 R/hr 2.0E+2 cpe PAllEL P902 Offges Post-treatment A 5 2.0E+2 cpe Common Airborne Gas (coal Alam A 3.0E+1 cpe RWB Vent Exh 2.0E+1 Eag Service Water i 3.0E+1 cpe .Fles Vent Exh 2.2E+1 S CR vent Exh 2.0E+1 OG Carbon Sed Vault A 6.0Et1 aft /hr a 5.5E+1 aft /hr PAf0EL P906 Common Process and Aree gag Alare PA80EL 803 US-MH-73 East Lig 3.0E+1 Turb sidg East 2.5E+0 eft /hr UD-MH-70 West Lig 3.2E+1 Turt steg West 2.5E+0 mR/hr IICC Heat HX 1.5E+1 Radweste to ESW 3.0E+1 PA86EL P804 . Alare Redweste to Sewege' 3.6E+1 Airborne Radiation ces (caal Annulus Exh A Ces DJ[iq B h0[1. METEOROLOGICAL C01101T10lls Cntet Ate L9E. Drywel1 - HR (R/hr) L9E. Wind Speed 24.O eph As vont L9E. Wind Direction 220
- OG8 Vent Exh LDES Temperature 35 'F OG8 Vent - HR QJ[+9 Delta T -1.15 *F OG Vent Pipe Lg[t2 UI Plant Vent (i,9[+1 ui Plant Vent - Het DJL+0 1s/HS Vent {ijffl is/HS Vent - Mft 9,9[t0
$1 Packing Exh Q.
U2 Plant Vent '1. U2 Plant Vent - HR 9J M DW170C/A/10/ba
3 t t 4 h; AREA RADIATION MONITORS Time: 0845
- TAG # LOCATION READING (aR/hr)
M 1D21N030 Personnel Air Lock. Catet (600'6") 5.0E+0 . ; 1D21N040 CRD NCU West. Catet (620'6") 5.0E+0 1D21N050 RBRT Area. Catet (642') 1.0E+2
- d. 1;)21N060 Tio Drive Area. Catet (600'6") 3.0E+1 L U 1;)21N070 RWCU F/D Area. Catet (664'7") 7.0E+0
- y. 1D21N080 Upper Pool Area. Catst (689'6") 2.0E+0 ,
+: 1D21N110 Aux Blda East (574'10") 7.0E+0 1D21N120 Aux Blda West (574'10") 7.0E+0 il 1D21N130 Turb Rm East (647'6") 2.5E+0 N 1D21N140 CRD HCU East. Catet (620'6") 5.0EI0 ij 1D21N160 Turb Rs West (647'6") 2.5E+0
- . 1D21N170 Turb Blda (605'6") 2.5E+0 L! 1D21N180 Hotwell Puso Area. TB (577'6") 1.0E+1
- } 1D21N190 TB Sumo Area. TBC (548'6") 2.0E+1
- t 1D21N200 0G3 (584') 1.1E+1
'i 1D21N210 Cads F1tr Peo Area. TBC (568'6") 9.0E+0
- 1D21N220 OG After Fitr Area. 0G3 (602'6") 2.0E+1 1,321N230 HP Fdw Ntr Area. NB (600'6") 1.0E+1 yl
- i. 1.)21N240 Fde Puso Area. NB (647'6") 6.6E+0 i 11)21N400 CR. CC (654'6") 1.6E-1 j 1D21N410 00 Nold Un Area. TB (577'6") 1.0E+1 -
!; :321N250 RWB West (574'10") 2.5E+1
- i. 321N260 RWS East (574'10") 1.5E+1
., 021N270 RWB (602') 5.0E+0 '- D21N280 Process Samole Rs. RWB (623'6") 4.0E+0 s
D21N290 RW Evas. RW3 (623'6") 4.0E+0 D21N310 FPCU F/D Area. IS (599') 6.0E+0
- ,. D21N320 Fuel Preparation Pool. IS (620'6") 2.0E+3
- D21N330 Spent Fuel Storame Pool. IB (620'6") 5.8E+2
- 9> 1 . D21N420 FPCU Cire Peo Area. IB (574'10") 9.0E+0
'! 1D21N340 Unit 1 DW. Portable. Catet (655') - d D21N380 Weste Compactor Area. RWB (623'6") 6.0E+1
'; D21N370 SRW Drummina Area. RWB (623'6") 6.0E+0 ; 1D21N090 Refuelina Bridae. Catet (689'6") 3.0E+0 D21N390 Fuel Serv Hdla Platform.~IB (620'6") 2.0E+3
- U
* = Alarm OS = Offscale
c, - Time: 0900 Message No.: 26 PERRY NUCLEAR POWER PLANT [ 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE F0_Vi Messaae For: Control Room /TSC J Simulated Plant Conditions: See attached sheets b
,e Messame: ***THIS IS A DRILL ***
,j 5-e i j FOR CONTROLLER USE ONLY 3 )~. Controller Notes: The TSC and OSC should be activated by this time. 4 g Actions Expected: t' h ] f DW176/C/26/ba
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PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 0900 P601 P680 CONTAINMENT PARAMETERS SYSTEM INFORMATiul REACTOR PARAMETERS Tempe ra ture Pressure Pressure Flow P ressu re 1018 psig f*FI _10s141. Status f osial . feoel - Level 31 In. NR Catet 81 0 RWCU PMP A OP 1350 Neut ron Drywell 120 0.1 8 OP 1350 Mon 100 Range APRM HWL PMP A OP 230 Mode SW RUN Tempe ra ture Level f*F1 fFt.1 8 OP 230 FDW Flw 15.4 Mlb/hr Supr PI 88 18.2 C SS 0 ST Flw (Total) 15.4 Mlb/hr C8P A OP 275 Line A 3.8 SYSTEMS INFORMATION 8 OP 280 Line 8 3.8 . Pressure Flow Status fosiol feoel C SR 150 Line C 3.8 RNR A SR RFBP A OP 330 Line D 3.8 8 SR 8 OP 330 C SR C OP 330 LPCS SR D SR 160 RCIC SR RFP A OP 1065 15.18( HPCS SR 8 OP 1063 14.9 Y ECC A OOS MFP SR 0 0 IUftSig[-C[MERATOR 8 SR RCIRC A FAST 39254 PARAMETERS ESW A 00S 8 FAST 39254 Mwatt 1235 8 SR MVAR 350 MAJOR VALVE PARAMETERS C SR CNDR Vac 28 in. Hg Status Closed Doen .; CRD A SR Thrt Pr 950 psig MSIV NORM 0 8 8 OP 1900 44 BYP VLV SRV NORM 19 0 Posit 0 % SLC A SR 8 SR SLC STG TK LVL 4600 gal.
~
m- - - - - - - y ,-- , , 2. 3-_,_ ;- , _ . . , ,s ., . 3-..- , ,. PERRY IIUCLEAR POWER PLAali 1984 EMERGE 81CY PREPAREDIIESS EXERCISC TIME: 0900 M19 ELECTRICAL DISTRitWTIOli M CST Level 410.000 eat. Status Load (pedl Status StattM - fosiel Offsite Pwr Sources 2 AV Cent He ifVAC Supp Fan A 0F TBCC PMP A OP 75 Gen Breakers 2 CL 8 SR S OP 75 Div 1 DG 005 Cent Me HVAC Rtn Fan A OP C SS 18 Div 2 DG SR B SR SA Comp OP 128 Div 3 DG SR Cont its Eng RClitC Ten A SR IA Coop SR 120 8 SR P600 CIRW PMP A OP 46 Status f119 8 OP 45 Cntet Val Cig Fan A OP Pressure Status._ losial IICC Pump A OP 112 SJAE A OP C SS S OP 112 B SS D OP C SS 35 E OP ADDITioelAt. 181FOIIMAT10el sti Pump A OP 56 F SS Status Abbreviations: . B OP 56 Drywell Cooling Fan IA OP OP Ope ra ting C SS O 2A GP SS Secured Status D SS O 3A OP AV Avellable MTR Fire Pump SR 18 SS SR Standby Readiness DO Fire Pump SR 28 SS SHTDel Shutdown 38 SS - 5-SP Slow Speed Catet vsl Purge Supp fan A SS F-SP Fast Speed 8 SS ISOL isolated Cntet Vsl ar DW Purge Exh Fan A SS IIORM 30e rne l 8 SS 005 Out or Service Drywe I I Purge Suppl Fan A SS CL Closed , OVRD Override AECTS Fan A OOS S OP
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PERRY leUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 0900 RX WATER LEVEL M PRESS M POWER SUPR PL TEMP n JB - _1018. E119 100 % as *f 5 60- 1100- 120- 110
- 45- 950- 90- 90-30- ,
800- 40- 70-15- 650- 0 50 0 500 20 -10 0 20 -10 0 a30 10 0 20 -10 0 Time (min) Time (min) Time (sin) Time (sin) DW TEMP CONTNT TEMP CONTMT PRESS SUPR PL LEVEL 120 'I 81 'I O 111G .18.2 fl 200- 110- 20- 19-150- 90- 15- - 100- 70- 10- IS-50 50- 5- -
-30 -20 -10 0 -30 -20 -10 0 0- 17 Time (min) Time (min) -5 -30 -20 -10 0
-30 -20 -10 0 Time (min)
Time (min) m
PERRY leUCLEAR POWER PLANT 1984 EMERGEllCY PREPAREDNESS EXERCISE TIME: 0900 PANEL P604 PANELS P669. P670. P671. P672 Process Radiation Main Sic t Line RAD 6.8E+2 mR/hr Ala rm Catet Vent Exh RAD 4LDi-1 mR/hr Offgas Pre-treatment 2.5E+2 R/hr Offgas Post-treatment A 2.0E+2 cpm f_AflEL P902 8 2.0E+2 cpm Common Airborne Ces (coal Alare Eng Service Water A 3.0E+1 cpm RWB Vent Exh 2.0E+1 8 3.0E+1 cpm __ FHB Vent Exh 2.2E+1 OG Carbon Bed Vault A 6.0E+1 mR/hr CR Vent Exh 2.0E+1 8 5.5E+1 mR/hr PANEL P906 PANEL 803 Common Process and Ares gag Ala re Turb Bldg East 2,1EtQ mR/hr UD-MH-73 East Liq 3.0E+1 Turb Bldg West 2.5E+0 mR/hr UD-MH-70 West Liq 3.2E+1 NCC Heat HX 3.5E+1 PANEL P804 Radwsste to ESW 3.QE+1 Airborne Radiation Cas (comi Alarm Radweste to Sewage 3.6E+1 Annulus Exh A Cas Q QE+Q B LDEL Cntet Ata LDE. METEOROLOGICAL CONDITIONS Drywell - HR (R/hr) 1,0l:+' AB Vent 2,Qd, Wind Speed 25.0 mph OCB ve nt Exh 2,0!N Wind Direction 225 OGB Vent '- HR Q,9(19 Tempera tu re 36 *F OG Vent Pipe 2.0Lig Delta T -1.03 *F UI Plant Vent 6,0(+) Ut Plant Vent - HR Q,0[1D TB/HB Vent 6,0E_11 TB/HB Vent - HR 929[1Q ST Packing Exh 81 ,DLt_ L U2 Plant Vent LOE + ' I U2 Plant Vent - HR LOE+0 DW170C/A/11/ba o ,.
o O o AREA RADIATION MONITORS Time: 0900 t-
; TAG # LOCATION READING (mR/hr) 1D21N030 Personnel Air Lock. Cntat (600'6") 5.0E+0 i 1D21N040 CRD HCU West. Cntat (620'6")- 5.0E+0 j 1D21N050 RBRT Area. Cntat (642') 1.0E+2 j 1D21N060 Tip Drive Area Catet (600'6") 3.0E+1 2j 1D21N070 RWCU F/D Area. Cntet (664'7") 7.0E+0 j 1D21N080 Upper Pool Area. Cntet (689'6") 2.0E+0 4 ID21N110 Aux Blda East (574'10") 7.0E+0 1 1D21N120 Aux Blda West (574'10") 7.0E+0 1 1D21N130 Turb R. Es.t (647 6-) 2.5E+0 l 1D21N140 CRD HCU East. Cntet (620'6") 5.0E+0 ) 1D21N160 Turb Rm West (647'6") ...
2.5E+0 i 1D21N170 Turb Blda (605'6") 2.5E+0 1 1D21N180 Hotwell Pump Area. TB (577'6") 1.0E+1 l- 1D21N190 TB Sump Area. TBC (548'6") 2.0E+1 j 1D21N200 OGB (584') 1.1E+1 i 1D21N210 Cads F1tr Pop Area. TBC (568'6") 9.0E+0 j' 1D21N220 OG After F1tr Area. OGB (602'6") 2.0E+1 1D21N230 HP Fdw Htr Area. HB (600'6") 1.0E+1 1D21N240 Fdw Pump Area. HB (647'6") 6.6E+0 1D21N400 CR CC (654'6") 1.6E-1 1D21N410 OG Hold Up Area. TB (577'6") 1.0E+1
; D21N250 RWB West (574'10") 2.5E+1 D21N260 RWB East (574'10") 1.5E+1 ! D21N270 RWB (602') 5.0E+0 l
D21N280 Process Sample Rs. RWB (623'6") 4.0E+0 l D21N290 RW Evan, RWB (623.' 6") 4.0E+0 l D21N310 FPCU F/D Area. IB (599') 6.0E+0 D21N320 Fuel Preparation Pool. IB (620'6") 2.0E+3
- D21N330 Spent Fuel Storane Pool. IB (620'6") 5.8E+2
- D21N420 FPCU Cire Pop Area. IB (574'10") 9.0E+0 ,
) 1D21N340 Unit 1 DW, Portable. Cntet (655') - 1 D21N380 Waste Compactor Area. RWB (623'6") 6.0E+1 D21N370 SRW Drummina Area. RWB (623'6") 6.0E+0 1D21N090 Refuelina Bridae. Cntat (689'6") 3.0E+0 D21N390 Fuel Serv Mdla Platform. IB- (620'6") 2.0E+3
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* = Alarm OS = Offscale
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Time: 0915 Message No.: 27 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE P MESSAGE FORM
;. Message For: Control Room l'
Simuisted Plant Conditions: i~ Message:
***THIS IS A DRILL ***
From Perry Plant Operator on routine rounds in the Intermediate [ Building, Elevation 574':
" Simulator. I am at the Fuel Pool Coolin'g and Cleanup Backwash
, Receiving Tank, Elevation 574' . I have fallen in a pool of water out here. I gashed my head and hurt my left arm. Send some
, assistance!"
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4 i FOR CONTROLLER USE ONLY l controller Notes: There hasg,g,scp ,,leakge fromIh flangel M connection on. *%esulting in approximately ten gallons of fluid on the floor. The flange is still dripping slowly and will continue until it is tightened. Actions Expected: A First Aid Team should be dispatched. DW176/C/27/ba l l
- Time: 0915 Message No.: 28 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM
'Messaae For: Control Room /TSC i
Simulated Plant Conditions: See attached sheets Messame: ***THIS IS A DRILL *** r [. . P [. l, i-FOR CONTROLL3R USE ONLY P Controller Notes: Actions Expected g, DW176/C/28/ba 9
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1 ...;.. .s.. PERRY NUCLEAR POWER PLANT 1964 EMERGENCY PREPAREDNESS EXERCISE TIME: 0915 P601 'T6AQ _ CONTAINMENT PARAMETERS SYSTEM INFORMATION REACTOR PARAMETERS % Tempe ra ture Pressure Pressure Flow. Pressure 1018 psig ( f*F1 E slel . Status fosle) fece) . Leve l ' 31 in. NR s Cntet c 81', O RWCU PHP A OP 1350 Neutron DryweIi 120 0.1 8 OP 1350 Mon 100 l'ange Mfjg HWL PMP A OP 230 Mode SW' RUN Tempe ra ture level i'F) Ift.I 8 OP 230 FDW Flw 15.4 Mib/hr Supr PI 88 18.2 C SS O 1 ST FPw (Total). 15.4 Mib/hr '
~'
CBP A OP 275 Line A 3.8 SYSTEMS INFORMATION B OP 280 Line 8 3.8 Pressure Flow Status fosle) 100=1 C SR 150 Line C 3.8 RHR A SR RFBP t A OP 330 Line D 3.8 B SR B OP 330 C SR C OP 330 LPCS SR D SR 160 RCIC SR RFP A OP 1065 15.1 ( HPCS SR B OP 1063 14.9f ECC A OOS MFP SR 0 0 IUR811K-CEN(RATOR B SR RCIRC A FAST 39254 PARAMETERS ESW A OOS B FAST 39254 Mwatt 1235 B SR MVAR 350 MAJOR VALVE PARAMETERS C SR CNDR Vac 28 In. Hg E stus Closed _ Ooen MS1V NORM 0 8 8 OP 1900 44 BYP VLV SRV NORM 19 0 P6 sit 0 % SLC A SR B SR SLC SIC TK LVL 4600 gal. e
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_ ,. ~.. . . . . 4y-PERRY lluCLEAlt POWER PLAIIT 1984 [MERGEllCY PftEPAREDilESS EXERCISE , TIME: 0915 2019 ELECTRICAL DISTRIBUTION M CST Level 410.000 eal. Status- Load (MW) Status Status fosiel OFFsite Pwr Sources 2 AV Cont Re HVAC Supp Fan A OP s TBCC PMP A OP 75 Con Breakers 2 CL B SN B OP 75 Div 1 DG 00S Cont Re HVAC Rtn Fan .A OP C SS 18 Olv 2 DC SR B SR SA Comp OP 128 Div 3 DG SR Cont Ra Eng RCIRC Fan A SR
. 1A Comp SR 120 B SR 2000 CIRW PMP A OP 46 Status P970 8 OP 45 Cntet Val Cig Fan A OP Pressure Status fosiel C OP 46 B OP NCC Pump Af OP 112 SJAE A OP C SS B OP 112 B SS D OP C SS 35 E OP A00lil0NAL INFORMATION SW Pump A OP 56 F SS Status Abbreviations: . B OP 56 DryweiI CooiIng Fan 1A OP OP Opera t ing C SS 0 2A OP SS Secured Status D SS 0 3A OP AV Available MTR Fire Pump SR 1B SS SR Standby Readiness DD Fire Pump SR 28 SS SHTDN Shutdown 3B SS S-SP Slow Speed Cntet Vs1 Purge Supp Fan A SS F-SP Fast Speed B SS ISOL isolated Cntet Vsl as DW Purge Exh Fan A SS NORM Norea1 B SS 00S Out of Service Drywell Purge Suppl Fan A SS CL Closed OVRD Override AECTS Fan A 00S B OP
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.:h_ab PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 0915 '
PANEL P604 PANELS P669. P670. P671. P672 Process Radiation Main Steam Line RAD 6.8E+2 mR/hr' ete rs Cntet Vent Exh RAD 4.1.0E-1 mR/hr Orrgas Pre-treatment 2.5E+2 R/hr Offgas Post-treatment A 2.0E+2 cpe PANEL P902 8 2.0E+2 cpe em Airborne Gas (coal Alare Eng Service Water A 3.0E+1 cpm RW8 Vent Exh 2.0E+1 8 3.0E+1 cpe FHS Vent Exh 2.,2E+1 OG Carbon Bed Vault A 6.0E+1 mR/hr CR Vent Exh 2.0E+1 0 5.5E+1 mR/hr PANEL P906 PANEL 803 P-n Process and Area gag Alare 2 Turb Bldg East 2.5E+0 mR/hr UD-MH-73 East Liq 3.0E+1 Turb Bldg West 2.5E+0 mR/hr UD-MH-70 West Liq 3.2E+1 NCC Heat HX 3.5E+1 PANEL. P804 Radweste to ESW 3.0E+1 Airborne Radiation Gas Icoal Alers Radweste to Sewage 3.6E+1 Annulus Exh A Gas QJEtfl_ 8 M EX Cntet Ata 2J E_.+_. METEOROLOGICAL CON 0lTIONS ' Drywe l l - HR ( R/h r) 1 Oi;.+_ A8 Vent 2J'l, . Wind Speed 20.0 mph OG8 Vent Exh 2JW Wind Direction JO OG8 Vent - HR QJ 3) Temperature 38 'F OG Vent Pipe 2J ;+2 Delta T -0.82 'F UI Plant Vent 6J 11 U1 Plant Vent - HR QeQE+Q . I T8/H8 Vent 6JE1]. 18/HB Vent - HR (+f! ST Packing Exh JII U2 Plant Vent &l, . U2 Plant Vent - HR Q&;11! DW170C/A/12/ba t
AREA RADIATION MONITORS Time: 0915 TAG # LOCATION READING (mR/hr) 1D21NO30. Personnel Air Lock, Cntmt (600'6") 5.0E+0 1D21N040 CRD HCU West, Cntat (620'6") 5.0E+0 1D21N050 RBRT Area, Cntat (642') 1.0E+2 1D21N060 Tip Drive Area, Cntat (600'6") 3.0E+1 1D21N070 RWCU F/D Area, Cntet (664'7") 7.0l+0 1D21N080 Upper Pool Area, Cntmt (689'6") 2.0E+0 - 1D21N110 Aux Bldg East (574'10") 7.0E+0
+
1D21N120 Aux Blda West (574'10") 7.0E+0 l 1D21N130 Turb Rm East (647'6") 2.5E+0 i 1D21N140 CRD HCU East, Cntat (620'6") 5.0E+0 1D21N160 Turb Rm West (647'6") 2.5E+0 - 1D21N170 Turb Bldg (605'6") 2.5E+0 j 1D21N180 Hotwell Pump Area, T1 (577'6") 1.0E+1 1 1D21N190 TB Sump Area, TBC (548'6") 2.0E+1 1D21N200 OGB (584') 1.1E+1 1D21N210 Cnds F1tr Pmp Area. TBC (568'6") 9.0E+0 1D21N220 OG After F1tr Area, OGB (602'6") 2.0E+1
, 1D21N230 HP Fdu Htr Area, HB (600'6") 1.0E+1 ; 1D21N240 Fdw Pump Area, HB (647'6") 6.6E+0 i 1D21N400 CR, CC (654'6") 1.6E-1 ID21N410 OG Hold Up Arsa TB (577'6") 1.0E+1 D21N250 RWB West (574'10") 2.5E+1 D21N260 RWB East (574'10") 1.5E+1 D21N270 RWB (602') 5.0E+0 D21N280 Process Sample Rm, RWB (623'6") 4.0E+0 ;- D21N290 RW Evap, RWB (623'6") 4.0E+0 _
l D21N310 FPCU F/D Area. IB (599') 6.0E+0
; D21N320 Fuel Preparation Pool, IB (620'6") 2.0E+3
- j D21N330 Spent Fuel Storage Pool, IB (620'6") 5.8E+2
- D21N420 FPCU Cire Pmp Area, IB (574'10") 9.0E+0
,, ID21N340 Unit 1 DW, Portable, Catmt (655') - ; D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1 (623'6") D21N370 SRW Drumming Area, RWB 6.0E+0
. 1D21N090 Refueling Bridge, Cntmt (689'6") 3.0E+0 D21N390 Fuel Serv Hdig Platform, IB (620'6") 2.0E+3 *
'l
* = Alarm OS = Offscale
Time: 0920 Message No.: 29 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Messane For: Controller with injured victim Simulated Plant Conditions: Message: ***THIS IS A DRILL *** 1 f
; FOR CONTROLLER USE ONLY -l Controller Notes: 1. Section 8.2, Part A, shows the location of the Backwash Receiving Tank and contamination levels in the area.
- 2. The initial survey of the victim produces the body map
. shown in Section 8.2, Part A. The information will 3 . be provided only when appropriate surveys are taken.
j 3. The victim has a gash on his head and has broken his d upper left arm. The victim also complains of dizziness and head pain; his pupils are slightly dilated. ..,e 4 1 3 Actions Expected: 1. The victim and area should be surveyed quickly to obtain an estimate of contamination and radiation levels. Appropriate ALARA precautions should be observed. [. 2. The victim's simulated clothing (paper) should be j removed.
- 3. Request an offsite ambulance.
l- - I 1, l~ DW176/C/29/ba ( t. L
Time: 0930 Message No.: 30 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE 4 MESSAGE FORM 1 Message For: Control Room /TSC i
], Simulated Plant Conditions: See attached sheets , Message: ***THIS IS A DRILL ***
i
~
~i 1 d i r! j' FOR CONTROLLER USE ONLY .,- Controller Notes: a 4
'; Actions Expected: 1. The Shift Supervisor should direct SAS to es11 for an offsite ambulance.
[, b . 2. This request should be coordinated with Security and/or g Health Physics to designate a pickup point. l D 3. At the direction of the Shift Supervisor, SAS calls Lake County Memorial East Hospital with the following information: ki a. We are sending an injured contaminated individual. 'Li
- b. Extent of injury.
- c. Number of victims.
, d. - Estimated time of arrival at hospital.
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, Tempe ra ture Pressur$ Pressure Flow Pressure 1018 psig f*F1 _12slGI Status fosial. feos)
Level 31 in. NR Cntet 81 0 RWCU PHP A OP 1350 Neut ron Drywe l l 120 0.1 8 OP 1350 Mon 100 Rango AfBH NWL PMP A OP 230 Mode SW RUN Tempe ra tu re Level f*F1 fft.1 8 OP 230 FDW Flw 15.4 Mlb/hr Supr PI 88 18.2 C SS 0 ST Flw (Total) 15.4 Mlb/hr CBP A OP 275 Line A 3.8_ SYSTEMS INFORMATION 8 OP 280 Line B 3.8 Pressure Flow _ Status fosial fooel C SR 150 Line C 3.8 RHR A SR RFBP A OP 330 Line D 3.8 8 SR S OP 330 C SR C OP 330 LPCS SR D SR 160 RCIC SR RFP A OP 1065 15.1( HPCS SR S OP 1063 14.9af ECC A OOS ' HFP SR 0 0 IUR8IME-GEM [RATOR 8 SR RCIRC A FAST 39254 PARAMETERS ESk' A 00S 8 FAST 39254 Mwatt 1235 8 SR MVAR 350 MAJOR VALVE PARAMETERS C SR CNDR Vac 28 in. Hg _ Status Closed Goon CRD A SR Thrt Pr 950- psig MSIV NORM 0 8 8 OP 1900 '~ 44 BYP VLV SRV NORM 19 0 Posit 0 % SLC A SR S SR SLC STC TK LVL 4600 gal. e Y
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^
CST Level 410.000 est. _ Status. Load fMW) Status Status _ fosial Off aite Pwr Soutt:es 2 AV Cont Rm HVAC Supp Fan A OP , TBCC PHP A OP 75 Con Breakers 2 CL B SR B OP 75 Div 1 DG OOS Cont Rm HVAC Rtn Fan A OP C SS 18 biv 2 DG SR B SR SA Comp OP 128 Div 3 DG SR Cont Re Eng RCIRC Fan A SR IA Comp SR 120 B SR - fAQQ CIRW PMP A OP 46 Status B OP 45 Cntet Val Cig Fan A OP Pressure Status fosial C OP 46 B OP NCC Pump A OP 112 SJAE A OP C SS B OP 112 B SS D OP C SS 35 E OP ADDITIONAL INFORMATION SW Pump A OP 56 F SS Status Abbreviations: B OP 56 Drywell Cooling Fan 1 A OP OP Ope ra t ing C SS 0 2A OP SS Secured Status D SS O 3A OP AV Available MTR Fire Pump SR 18 SS SR Standby Readiness DD Fire Pump SR 28 SS SHTDN Shutdown 38 SS S-SP Slow Speed Cntet Vsl Purge Supp Fan A SS F-SP Fast Speed B SS ISOL isolated Cntet Val & DW Purge Exh Fan A SS NORM Normal B SS 00S Out of Service Drywell Purge Suppl Fan A SS CL Closed B SS OVRD Override AEGTS Fan A 00S
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1964 EMERGENCY PREPAREDNESS EXERCISE TIME: 0930 PERRY NUCLEAR POWER PLANT PANEL P6Qg PANELS P669. P670. P671. P672 Main Steam Line RAD 6.8E+2 mR/hr ' Process Radiation al!Es Cntet Vent Exh RAD 41.0E-1 mR/hr Of fgas Pre-t reatment 2.5E+2 R/hr Offgas Post-treatment A 2.0E+2 cpe , PANEL P902 2.0E+2 cpm Common Airborna Gas (coal Alarm B 3.0E+1 cpm RW8 vent Exh 2.0E+1 Eng Service Water A B 1 D111 cpm FHS Vent Exh 2.2E+1 6.0E+1 mR/hr CR Vent Exh 2.0E+1 OG Carbon Bed Vault A B 1,$[11 mR/hr PANEL P906 Common Process and Ares gag Alers PANEL 803 UD-MH-73 East Liq 3.0E+1 Turb Bldg East 2.5E+0 mR/hr UO-MH-70 West Liq 3.2E+1 Turb Bldg West 2.5E+0 mR/hr NCC Heat HX 3.5E+1 PANEL P804 Radweste to ESW 3.0E+1 Cas icom) Radweste to Sewage 3.6E+1 Ai rborne Radiation 81AIE Annulus Exh A Gas Q,0EiQ 8 1.0(1.1 METEOROLOCICAL CONDITIONS Cntet Ata 9,Q[11 Drywell - HR (R/hr) Jt9[11 Wind Speed 17.0 mph AB Vent 2,9f+1 225
- OCB Vent Exh Wind Direction Tempe ra tu re 38 'F OCB Vent - HR R20EJ+9 Q,0L1 Delta T -0.80 *F OC Vent Pipe RiQL12 U1 Plant Vent krQLil UI Plant Vent - HR Q,Q[1G TB/HB Vent 6,0Etj 18/HB Vent - HR QiD[1G ST Packing Exh M L11 U2 Plant Vent 6,Q[11 U2 Plant Vent - HR 0.0E+0 l
DW170C/A/13/ba . e'
AREA RADIATION MONITORS Time: 0930 5 TAG # LOCATION READING (mR/hr)
, 1D21NO30 Personnel Air Lock, Cntat (600'6") 5.0E+0 9, ID21N040 CRD HCU West, Cntmt (620'6") 5.0E+0
~' 1D21N050 RBRT Area, Cntet (642') 1.0E+2 'i 1D21N060 Tip Drive Area, Cntet (600'6") 3.0E+1 1D21N070 RWCU F/D Area, Cntet (664'7") 7.0E+0
' 1D21N080 Upper Pool Area, Cntet (689'6") 2.0E+0 1D21N110 Aux Blda East (574'10") 7.0E+0 .- 1D21N120 Aux Bldg West (574'10") 7.0E+0
- f 1D21N130 Turb Rm East (647'6") 2.5E+0 4 1D21N140 CRD HCU East, Cntmt (620'6") 5.0E+0 1D21N160 Turb Rm West (647'6") 2.5E+0
[ 1D21N170 Turb Bldg (605'6") 2.5E+0
- l 1D21N180 Hotwell Pump Area. TB (577'6") 1.0E+1
! 1D21N190 TB Sump Area. TBC (548'6") 2.0E+1 j
1D21N200 OGB (584') 1.1E+1
; ID21N210 Cnds Fitr Pmp Area. TBC (568'6") 9.0E+0 1D21N220 OG After Fitr Area. OGB (602'6") 2.0E+1
,f 1D21N230 HP Fdw Htr Area, HB (600'6") 1.0E+1
,l 1D21N240 Fdw Pump Area, HB (647'6") 6.6E+0
'!' 1D21N400 CR, CC (654'6") 1.6E-1 l 1D21N410 OG Hold Up Area, TB (577'6") 1.0E+1 D21N250 RWB West (574'10") 2.5E+1 D21N260 RWB East (574'10") 1.5E+1
. D21N270 RWB (602') 5.0E+0 .i D21N280 Process Sample Re, RWB (623'6") 4.0E+0 D21N290 RW Evap, RWB (623'6") 4.0E+0 D21N310 FPCU F/D Area. IB (599') 6.0E+0 D21N320 Fuel Preparatien Pool, IB (620'6") 2.0E+3 *
,; D21N330 Spent Fuel Storage Pool. IB (620'6") 5.8E+2
- D21N470 FFCU Cire Pmp Area, IB (574'10") 9.0E+0
-l 1D21N340 Unit 1 CW, Portable, Cntmt (655') - D21N380 Waste Compactor Area, RWD (623'6") 6.0E+1 D21N370 SRW Drumming Area, RWB (623'6") 6.0E+0
+
1D21N090 Refueling Bridge, Cntat. (689'6") 3.0E+0 D21N390 Fuel Serv Hdig Platform, IB (620'6") 2.0E43
- N
* = Alarm OS = Offscale
~
Time: 0935 Message No.: 31X PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Message For: Control Room h Simulated Plant Conditions: f Message: ***THIS IS 4 DRILL *** L, Call Lake County Memorial East Hospital and inform them of the impending transport of an injured contaminated victim to them. i p+ i
'i -
J
.l 't i
1
) FOR CONTROLLER USE ONLY j
2
. Controller Notes: Deliver this message only if the actions necessary to effect
- the transport of the contaminated injured victim to the hospital have not been initiated.
i. 4
'- Actions Expected: See " Action Expected," Messags No. 30. ~: .
DW176/C/31/ba
=
- - . , , - - w-- v
Time: 0940 Message No.: 32 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Messaae For: Controllers _ t Simulated Plant Conditions: Messaae: ***THIS IS A DRILL ***
'l i
- i '
I i 1 2 j FOR CONTROLLER USE ONLY Controller Notes: The ambulance arrives at the Primary Access Control (PAC) point gate approximstely at this time. c Actions Expected: 1. Security at the PAC gate should notify SAS.
- 2. PAC Security should distribute dosimetry and escort
- the ambulance to the designated area to pick up the , victim.
4 DW176/C/32/ba a i
Tima: 0945 Message No.. 33 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE' MESSAGE FORM Message For: Control Room /TSC Simulated Plant Conditions: See attached sheets i
- Messame: ***THIS IS A DRILL ***
s
.h O
9 i l FOR CONTROLLER USE ONLY q-l }. . Controller Notes: Actions Expected: 4 L DW176/C/33/ba 4
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F J .' ,* 3, '
. 1 ~ ~ ~ r. gut *
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~
- PERRY IIUCLEAR POWER Pt. ANT 1988s ENERGEllCY PREPAREDNESS EXERCISE .TiltEs 094 5 CoelTROL ROON ANNUNCIATORS P601/P877 P680 P870 4 BACK PANELS 0
1 e 4 1 l b a
- I I
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1 1 I e i 1 I DW1708/A/38/ba .. b b
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6 o o . 1 tl 0 2 d 7 8 2 i_ B 2 i_ s , v = . I e .- . : a v a . v a i R. R. W o .o 2 ' 4 - 2 2 2 i_ i_ . 2 2 5 t 5 E o o g t *1 _ @ . s- . 5 M T E - T E W 2 5-2 $ 5* $ g . - u R. - 9 9 C o
* =l .9 2 2 l* 2 i_ ,
2 i_
. I e I l 7 s il 7 s 3 R. l 2 n '
5
=
~
c- . i PERRY NUCLEAR POWER PLANT 1984 Et1ERGEleCY PREPAREDNESS EXERCISE.- TIME: 0945 211Q FLEC1RICAL DISTRIBUTION 220.g CST Level 410.000 aal. Status- Load (NW1 Status Status fosial .Of'rsite Fwr Sources 2 AV Cont Rm HVAC Supp Fan A OP TBCC PMP A OP 75 Con Breakers 2 CL ,8 SR B OP 75 Div 1 DG OOS Cont Rm HVAC Rtn Fan A OP C SS 18 Div 2 DG SR 8 SR SA Comp OP 128 Div 3 DC SR Cont Re Eng RCIRC Fan A SR IA Comp SR 120 8 SR EADQ CIRW PMP A OP 46 Status
- f210 B OP 45 Cotet Val Cig Fan A OP Pre ssu re Status fosial C OP 46 8 OP NCC Pump A ,~ OP 112 SJAE A OP C SS B OP 112 8 SS D OP
'C SS 35 E OP ADDITIONAL INFORMATION SW Pump A OP 56 F SS Status Abbreviations: 8 OP 56 prywell Cooling Fan I A OP OP Ope ra t ing C SS O 2A OP ,
SS Secured Status D SS O 3A OP AV Available MTR Fire Pump SR 1B SS SR Standby Readiness DD Fi re Pump SR 28 SS SHTDM Shutdown 38 SS S-SP Slow Speed Cntet Vsl Purge Gupp Fan A SS F-SP Fast Speed 8 SS ISOL isolated Cntat Val as DW Purge Exh Ean A SS NORM Normal 8 SS OOS Out of Service Drywe l l Pu rge Suppl Fan A SS CL Closed B SS OVRD Override AEGTS Fan A OOS 8 OP
. 1
)
l l AREA RADIATION MONITORS Time: 0945 i, l* - TAG # LOCATION READING (mR/hr)
~
1D21NO30 Personnel Air Lock, Cntet (600'6") 5.0E+0 j 1D21N040 CRD HCU West, Catet (620'6") 5.0E+0
- 4 1D21N050 RBRT Area, Cntet (642') 1.0E+2 d 1D21N060 Tip Drive Area Cntet (600'6") 3.0E+1
! 1D21N070 RWCU F/D Area, Cntet (664'7") 7.0E+0 is 1D21N080 Upper Pool Area, Cntet (689'6") 2.0E+0
.. 1D21N110 Aux Blda East (574'10") 7.0E+0
' 1D21N120 Aux Blda West (574'10") 7.0E+0 1D21N130 Turb Rm East (647'6") 2.5E+0
.; ID21N140 CRD HCU East, Cntet (620'6") 5.0E+0 I, ID21N160 Turb Rm West (647'6") 2.5E+0 3 1D21N170 Turb Blda (605'6") 2.5E+0 ii- 1D21N180 Hotwell Pump Area. TB (577'6") 1.0E+1 1 1D21N190 TB Sump Area. TBC (548'6") 2.0E+1 !l ID21N200 OGB (584') 1.1E+1 ll 1D21N210 Cnds F1tr Pep Area, TBC (568'6") 9.0E+0 1D21N220 OG After F1tr Area. OGB (602'6") 2.0E+1 1D21N230 HP Fdw Htr Area HB (600'6") 1.0E+1 l ID21N240 Fdw Pump Area HB . (647'6") 6.6E+0 1D21N400 CR, CC (654'6") 1.6E-1 ID21N410 OG Hold Up Area, TB (577'6") 1.0E+1 l}. __D21N250 RWB West (574'10") 2.5E+1 !; D21N260 RWB East (574'10") 1.5E+1 '] D21N270 RWB (602') 5.0E+0 D21N280 Proc.ess Sample Ra, RWB (623'6") 4.0E+0 D21N290 RW Evep, RWB (623'6") 4.0E+0 D21N310 FPCU F/D Area, IB (599') 6.0E+0 f; D21N320 Fuel Prepararion Pool, IB (620'6") 2.0E+3 * ' i!' D21N330 Spent Fuel Storage Pool, IB (620'6") 5.8E+2
- l D21N420 FPCU Cire Pmp Area, IB (574'10") 9.0E+0
". 1D21N340 Unit 1 DW, Portable. Cntet (655') -
fi D21N380 Waste Compactor Area RWB (623'6") 6.0E+1 '.' D21N370 SRW Drumming Area, RWB (623'6") 6.0E+0
, 1D21N090 Refueling Bridge, Catet (689'6") 3.0E+0 3
D21N390 Fuel Serv Hdla Platform. IB (620'6") 2.0E+3
- i 3
~
iI
- l li l-4
(
* = Alarm
. OS = Offscale
-n--< y,--s p-wv --gg
. . - - . a . ,. .. s. ,. . , . . % $ g- g ,.
PERRY NUCLEAR POWER PLAalT 1984 EMERCENCY PREPAREDNESS EXERCISE TIME: 0945-fgEL P604 fMELS P669. P670. P671. P672 Process Radiation i Main Steam Line RAD: 6.8E+2 mR/hr 6.l H E Cntet Vent Exh RAD e1.0E-1 mR/hr Offgas Pre-treatment 2.5E+2 R/hr-Ofrgas Post-treatment A 2.0E+2 cpm PANEL P902 8 RJ[12 cpm Common Airborne Gas fcomi AIare Eng Service Water A i d[*1* cpm RWB Vent Exh LOE+1 _ 8 3.0E+1 cpm _ _ . _ -FH8 Vent Exh 2.2E+1 OG Carbon Bed Vault A 6.OE+1 mR/hr CR Vent Exh 2.0E+1 8 5.5E+1 mR/hr PANEL P906 PANEL 803 Common Process and Area gas Alarm Turb Sidg East 2.5E+0 mR/hr UD-MH-73 East Liq 3.0E+1 Turb Bldg West ZJ[ig mR/hr UD-MH-70 West Liq 3.2E+1 NCC Heat HX 3.5E+1 PANEL P804 Radweste to ESW 3.0E+1 Airborne Radiation Cas (conj A_lara Radweste to Sewage 3.6E+1 _~ ,
~
Annulus Exh A Gas DJE10 8 3,00t1 Cotat Atm LO[t METEOROLOGICAL CONDITl0NS Drywell - HR (R/hr) ' hDEL A8 Vent 2 0[t Wind Speed 20.0 mph 0C8 Vent Exh 2JE+2 Wind Direction 225 OCS Vent - HR QJE1Q Tempe ra tu re 38 'F OG Vent Pipe LO(12 Delta T -0.75 *F ul Plant Vent 6,0Et1 U1 Plant Vent - HR OJfl0 TS/HB Vent [t,0f11 18/188 Vent - HR Q,0ff0 ST Packing Exh L_0011
- U2 Plant Vent (t,9f11 U2 Plant Vent - HR 0.UE+0 DW170C/A/14/ba ,
. - _ _. - .- . ..- .. - - - . - . - _ - . . .~ .-.
P l Time: 1000= Message No.: 34 PERRY NUCLEAR POWER PLAlfr 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Messaae For: Controllers Simulated Plant Conditions:
- Messame: ***THIS IS A DRILL *** .
9 4
- FOR CONTROLLER US2 ONLY --
e i Controller Notes: The ambulance should be leaving the site by now. Actions Expected: The PAC Security should notify SAS. i
- 4 DW176/C/34/ba 1
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- . +..-----mny, ,p , , ---.- ...yw.y, - --y-r-..9.y4.-, .7,-7 ty%,e pg - g w y
~
Time: 1000 Message No.: 35
. PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Messane For: Control Room /TSC ,
i Simulated Plant Conditions: See attached sheets Messame: ***THIS IS A DRILL ***
)
J i 1 I
'l
'~
FOR CONTRCLIIR USE ONLY
, Controller Notes: Safety Relief Valve B21-F051D inadvertently opens.
NOTE: The Major Valve Parameters on the P680 Panel - do not indicate inadvertent safety relief valve
, openings due to a mechanical failure. The annunciator coupled with other indications provide the necessary information.
Actions Expected: The operators should prepare to commence a fast reactor shutdown in accordance with Technical Specifications as I directed by ONI-B21-1, " Inadvertent Safety Relief Valve Opening. " DW176/C/35/ba d ' e s v -
..: .:...<..... ' , - . . . b ..: - l_ a , , :. :-.J . .. . a. . s u . 3 ~: r .s .
~
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i PERRY NUCLEAR POWER PLAllT 1884 EMERGENCY PREPAREDNESS EXERCISE TIME: 1000 ut01 F6a0 j CONTAINMENT PARAMETERS SYSTFM INFORMATION REACTOR PARAMETERS l Tempe ra tur- Pressure Pressure Flow Pressure 1018 psig f*F1 fosiel Status fosial ' feoal ' Level 31 in. NR Cntat 81 0
- RWCU PMP A OP 1350 Neutron Dryweii 120 0.1 B OP 1350 Mon 100 Range M HWL PMP A OP 230 Mode SW RUN Tempe ra ture Level .
I'Fl (ft.) B OP 230 FDW FIw 15.4 Mib/hr Supr PI 88 18.2 C SS 0 ST Flw (Total) 15.4 Mib/hr C8P A OP 275 Line A 3.5 SYSTEMS INFORMATION B OP 280 Line B 3.5 Pressure Flow Status. f osial _ feoel C SR 150 Line C 3.5 RHR A SR RFBP A OP 330 Line D 4.5 B SR S OP 330 C SR C OP 330 LPCS SR D SR 160 RCIC SR RFP A OP 1065 15.1 ( HPCS SR D OP 1063 14.9K ECC A 00S MFP SR 0 0 TURBillE-GENERATOR B SR RCIRC A FAST 39254 PARAMETERS ESW A 00S n FAST 39254 Hwatt 1162 B SR HVAR- 403 MAJOR VALVE PARAMETERS C SR CNDR Vac 28 in. Hg Status Closed Open CRD A SR Thrt Pr 948 psig MStV NORM O 8 8 OP 1900 44 BYP VLV SRV NORM 19 0 Posit 0 % SLC A SR B SR SLC STG TK LVL 4600 gal. _ 5 f
b 4 i S W A M
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+ C
- C = J =
43 O C W c ea O -
> O -
- E W e E
- e w J e w N
W e .J .< E e O k & e e O k l g .= N. .= g N. .= a :D ,,4, O @ O m m j 8 I ,O 8 0 0 0 0 s
- e . O O O O m O N o= m M c == e= e=
? "
. I I r_. f
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= .M W = .- C E
- C O - & O =
- .f. s= , e E bi O .E.e H t ==
. 8 8
~
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. W -
N. n 8 u N. O s- g
. W O O K X m n W E a 4 1 .,
to O O O O O e O, e o . n4
-i W N $ # N *= ==
4 g - W .I g .t y a C
& . O O l
a E
.d C W C W to O - > O -
O (A e E e= E a W I e w W e w W E W E j E A e
- H
, W O O I = e. O I 4 x += N - O N -
X E e >= 0 e t= a e m j ,
== O m
O n
. 0 8 0 0 0 0 0 9 8 9 O O O O O O O O O O e O A O e m N e e=
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& g e G w E -
0 w E K e= g N O W E m O a e= 0 E W N - N - 8= a >= 4 > ( 3 O O S e O m O O
= .O , m e 8 N
n e= 8
+=
.O E
E W v
PERRY HUCLEAR POWE3 PLAllT- . 1964 EMERGEIICY PREPAREDNESS EXERCISE . TIME: 1000 1 f1ZG ELECTRICAL DISTRIBUTIOll M CST Level 410.000 cal : Status toad fMWI Status Status fosial .OFFsite Pwr Sources 2 AV Cont Ra HVAC Supp Fan A. OF T8CC PMP A OP 75 con Breakers 2 CL 8 SR 8 OP 75 Div 1 DG OOS Cont Rm HVAC Rtn Fan A' OP C SS 18 Div 2 DG SR 8 SR SA Comp OP 128 Div 3 DG SR Cont Re Eag RCIRC Fan A SR BA Comp SR 120 8 SR fA00 CIRW PMP A OP 46 Statut, 22ZG S OP 45 Cntet Val Cig Fan A OP Pressu re Status fosial C OP 46 8 OP NCC Pump A OP 112 SJAE A OP C SS
, 8 OP 112 8 SS D OP C SS 35 E OP ADDITIOllAL lliFORMATIOld SW Pump A OP 56 F SS Status Abbreviations: 8 OP 56 DryweIi Cooling Fan IA OP OP Ope ra ting .C GS O '
2A OP Secured Status SS D SS O 3A OP AV Available MTR Fire Pump SR 18 SS SR Standby Readiness DO Fire Pump SR 28 SS SHTDN Shutdown 38 SS S-SP Slow Speed Cntet Val Purge Supp Fan A SS F-SP Fast Speed 8 SS ISOL isolated Cotat Val er DW Purge Exh Fan A SS IlORM Normal 8 SS OOS Out of Service Drywell Pu rge Suppl Fan A SS CL Closed 8 SS OVRD Override AECIS Fan A OOS , *8 OP j i l 4
I AREA RADIATION MONITORS Time: 1000 i
*; TAG # LOCATION READING (mR/hr) ; 1D21NO30 Personnel Air Lock, Cntet (600'6") 5.0E+0 f 1D21N040 CRD HCU West, Cntet (620'6") 5.0E+0 4 1D21N050 RBRT Area, Cntet (642') 1.0E+2 1 1D21N060 Tip Drive Area, Cntet (600'6") 3.0E+1
- 1. 1D21N070 RWCU F/D Area, Cntat (664'7") 7.0E+0 f 1D21N080 Upper Pool Area, Cntat (689'6") 2.0E+0
, ID21N110 Aux Blda East (574'10") 7.0E+0 1D21N120 Aux Blda West (574'10") 7.0E+0 d ID21N130 Turb Rm East (647'6") 2.5E+0 '. 1D21N140 CRD HCU East, Cntet (620'6") 5.0E+0 , ID21N160 Turb Ra West (647'6") 2.5E+0 1D21N170 Turb Blda (605'6") 2.5E+0
[ ~ 1D21N180 Hotwell Pump Area, TB (577'6") 1.0E+1 ID21N190 TB Sump Area TBC (548'6") 2.0E+1 j ID21N200 OGB (584') 1.1E+1 1D21N210 Cnds F1tr Pep Area, TBC (568'6") 9.0E+0 ] 1D21N220 OG After Fitr Area. OGB (602'6") 2.0E+1 1D21N230 HP Fdw Her Area HB (600'6") 1.0E+1 -l4 1D21N240 Fdw Pump Area HB (647'6") 6.6E+0-
! 1D21N400 CR, CC (654'6") 1.6E-1 ;. ID21N410 OG Hold Up Area TB (577'6") 1.0E+1 ', __D21N250 RWB West (574'10") 2.5E+1 D21N260 RWB East (574'10") 1.5E+1 D21N270 RWB (602') 5.0E+0 D21N280 Process Sample Ra, RWB (523'6") 4_0E+0 1 D21N290 RW Evap, RWB (623'6") 4.0E+0
.i D21N310 FPCU F/D Area. IB (599') 6.0E+0 - D21N320 Fuel Preparation Pool. IB (620'6") 2.0E+3
- lj I D21N330 Spent Fuel Storate Pool, IB (620'6") 5.8E+2
- D21N420 FPCU Cire Pop Area IB (574'10") 9.0E+0
; 1D21N340 Unit 1 DW, Portable, Cntet (655') -
1 D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1 D21N370 SRW Drummina Area, RWB (623'6") 6.0E+0 ID21N090 Refuelina Bridae, Cntet (689'6") 3.0E+0 , D21N390 Fuel Serv Hdla Platform, IB (620'6") 2.0E+3
- i -
t i i i
* = Alarm OS = Offscale
n .,, PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1000 PANEL' P60tl , c . PANELS F669. P670. P671. P672 Process Radiation -q Meln Steam I.ine RAD 16E+jfmR/hr
. .; AIa rm . e ~,
Cntet" Vent Exh RAD 41.0E-1'mR/hr y+ Orrgas Pre-treatment 2.5E+2 R/hr . r A Orrgas Post-treatment A 2.0E+2 cpm e'
? \., PANEL P902 B 2.0E+2 cpm common Airborne 'F Cas (comi Ala re Eng Service Water A 3.0E+1 cpm RW5 Vent Exh 2.0E+1 u'
8 3.0E+F cpa' FHB Vent Exh 2,2E+1 .s OG Carbon Eed Vault A 6.0E+1 mR/hr CR Vent Exh 2.0E+1
-8 . 2,5E+1 mR/hr PANEL P906 PANEL 803 Coahmon Process and Area cgtg Alarm Turb Bldg East 2.5E+0 mR/hr UD-MH-73 East Liq 3.0E+1 Turb Bldg West 2.5E+0 mR/hr UD-MH-70 West Liq L2E+1 NCC Heat HX 3.5E+1 PANEL P8Qtt Radweste to ESW LDQ1 Airborne Radiation gas icoal Alarm Radwaste to Sewage 3.6E+1 Annulus Exh A Cas Q DHQ B ldh 1 Cntat Atm 1 BE12 METEOROLOGICAL CONDITIONS Drywell - HR (R/hr) LDE.
AB Vent LDR. Wind Speed 18.0 mph 0C8 Vent Exh 220 $ Wind Di rection J 25 OGB Vent - HR Q,9!M Tempe ra ture 38 *F OG Vent Pipe 2,DE12 _ Delta T -0.80 *F U1 Plant Vent (t2DM1 U1 Plant Vent - HR Q OQQ TB/HB Vent (tJQ1 TB/ IIB Vent - HR QiDE10 ST Packing Exh i 0Ehl. U2 Plant Vent (t gel. U2 Plant Vent - HR 0.0E+U 9 DW170C/A/15/ba l I
Time: 1001 Message No.: 36 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Messane For: Control Rece/TSC Simulated Plant Conditions: See attached sheets I
- Messame
- ***THIS IS A DRILL *** .
c i. 5
- T 9
.g D
h FOR CONTROLLER USE ONLY. 1 ~ Controller Notes: i Actions Ex ected: t
,4 DW176/C/36/ba
.: .:.: ,. q :=. . :. : u. . '. . . K::. -. . .u m ~~- . .~ : - .a :. .. .~n . 2 L.2 : n u . - :n PERRY NUCLEAR POWER PLANT 1984 EMERCENCY PREPAREDNESS EXERCISE TIME: 1001 P601 P680 CONTAINMENT PARAMETERS SYSTEM INFORMATION , REACTOR PARAMETERS Tempe ra tu re Pressure Pressure Flow Pressure 1018 psig f*F1 fosial Status fosla) faom) <
Level 31 in. NR Cntet 81 0 RWCU PMP A OP 1350 Neutron D rywe l l 120 0.1 8 OP 1350 Mon 100 Range APRM HWL PMP A OP 230 Mode SW RUN Tempe ra ture Level f*F1 fft.1 8 OP 230 FDW Flw 15.4 Hib/hr Supr P1 91 18.3 C SS 0 ST Flw (Total) 15.4 Mlb/hr C8P A OP 275 Line A 3.5 SYSTEMS INFORMATION 8 OP 280 Line 8 3.5 Pressure Flow Status fosial faomi C SR 150 Line C 3.5 RHR A SR RF8P A OP 330 Line D 4.5 8 SR 8 OP 330 , C SR C OP 330 l LPCS SR D SR 160 , RCIC SR RFP A OP 1065 15.1( H PCS SR 8 OP 1063 14.9 A( ECC A 00S MFP SR 0 0 TUR8lN[-Q GERATQR 8 SR RCIRC A FAST 39254 PARAMETERS ESW A 00S 8 FAST 39254 Mwatt 1162 8 SR MVAR 403 l MAJOR VALVE PARAMETERS , C SR CNDR Vac 28 in. Hg Status Closed Doen CRD A SR Thrt Pr 948 psig MSIV NORM 0 8 8 OP 1900 44 BYP VLV SRV NORM 19 0 Posit 0 %
- SLC A SR 8 SR SLC STC TK LVL 4600 gal, a
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. . -i PERRY NUCLEAR POWER PLAitT- -1984 EMERCEIICY PREPARED 01ESS EXERCISE TIME: 1001 fRIQ ELECTRICAL DISTR 18UT1000 f2Gk -
CST Level 8s10.000 cal. Status Load IMWI Status Status fosial Offsite Pwr Sources 2 AV Cont Re HVAC Supp Fan A OP T8CC PMP A OP 75 Con Breakers 2 CL- 8 SR ' 8 OP 75 Div 1 DC 00S ' Cont Re HVAC Rtn Fan A. OP
.C SS 18 Div 2 DC SR 8 SR SA Comp OP 128 Div 3 DG SR Cont Re Eng RCIRC Fan A SR IA Comp SR 120 8 SR P800.
CIRW PMP A OP 46 Status P970 8 OP 45 Cotet Vsl Cig Fan A OP Pressure E stus_ fosial llCC Pump A- OP 112 SJAE A OP C SS 8 OP 112 8 SS D OP C SS 35 E OP ADDITl000AL INFORMATI001 SW Pump A OP 56 F SS Status Abbreviations: 8 OP 56 Drywell Cooling Fan 1A OP OP Operating C SS O - 2A OP SS Secured Status D SS O 3A OP AV Available , MTR Fire Pump SR SR Standby Readiness DD Fire Pump SR - 28 SS SHTDN Shutdown 38 . SS S-SP Slow Speed Cntet Val Purge Supp Fan .A SS . F-SP Fast Speed 8 _ SS
- ISOL isolated Cntet Vs1 at DW Purge Exh Fan A SS NORM No rea 1 8 SS 00S Out of Service Drywell Purge Suppl Fan A SS CL Closed .
8 SS OVRD override AECTS Fan A 005 8
- OP D
i AREA RADIATION MONITORS Time: 1001 r! , TAG # LOCATION _ READING (mR/hr) 4 1D21NO30 Personnel Air Lock, Cntmt (600'6") 5.0E+0 i ID21N040 CRD HCU West, Catet (62 4, ' 6") 5.0E+0 1D21N050 RBRT Area, Cntet ' (642') 1.0E+2
! 1D21N060 Tip Drive Area, Cntat (600'6") 3.0E+1 I
8 1D21N070 RWCU F/D Area, Cntmt (664'7") 7.0E+0 1D21N080 Upper Pool Area, Cntat (689'6") 2.0E+0 1D21N110 Aux Bldg East (574'10") 7.0E+0 1D21N120 Aux Bldg West (574'10") 7.0E+0 j ID21N130 Turb Rm East (647'6") 2.5E+0
) 1D21N140 CRD HCU East, Cntet (620'6") 5.0E+0 3 1D21N160 Turb Rm West (647'6") 2.5E+0 1D21N170 Turb Bldg (605'6") 2.5E+0 1D21N180 Hotwell Pump Area, TB (577'6") 1.0E+1 1D21N190 TB Sump Area, TBC (548'6") 2.0E+1 ID21N200 OGB (584') 1.1E+1 1D21N210 Cnds Fitr Pmp Area, TBC (568'6") 9.0E+0 1D21N220 OG After Fitr Area. OGB (602'6") 2.0E+1 l 1D21N230 HP Fdw Htr Area, HB (600'6") 1.0E+1 ! ID21N240 Fdw Pump Area, HB (647'6") 6.6E+0 i
1D21N400 CR, CC (654'6") 1.6E-1 1D21N410 OG Hold Up Area, TB (577'6") 1.0E+1 D21N250 RWB West (574'10") 2.5E+1 D21N260 RWB East (574'10") 1.5E+1
. D21N270 RWB (602') 5.0E+0 f D21N280 Process Sample Rm, RWB (623'6") 4.0E+0 D21N290 RW Evap, RWB (623'6") 4.0E+0 D21N310 FPCU F/D Area, IB (599') 6.0E+0 4 D21N320 Fuel Preparation Pool, IB (620'6") 2.0E+3
- i D21N330 Spent Fuel Storage Pool, IB (620'6") 5.8E+2
- D21N420 FPCU Cire Pmp Area IB (574'10") 9.0E+0 1D21N340 Unit 1 DW, Portable, Cntat (655') -
D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1 D21N370 SRW Drumming Area, RWB (623'6") 6.0E+0
, ID21N090 Refueling Bridge, Cntmt (689'6") 3.0E+0 D21N390 Fuel Serv Hdig Platform. IB (620'6") 2.0E+3
- I
* = Alarm OS = Offscale l
1
PERRY IIUCLEAR POWE2 PLANT 1984 EHERGEleCY PREPARE 000ESS EXERCISE T I8tE: 1001 PAleEL P604 PAllELS P669. P670. P671. P672 Process Radiation. Main Steam Line RAD 6.8E+2 mR/hr Alarm
. Cntet Vent Exh RAD 11.0E-1 edt/hr '
Offges Pre-treatment 2.5E+2 R/hr
~
Offgas Post-treatment A 2.0E+2 cpm PAIIEL P902 8 2.0E+2 cpm Common Airborne Gas (cool Alare Eng Service Water A 3.OE+1 cpm RWB Vent Exh 2.0E+1 8 3.0E+1 cpm FHS Vent Exh 2.2E+1 OG Carbon Bed Vault A 6.0E+1 mR/hr CR Vent Exh 2.OE+1 8 5.5E+1 mR/hr PANEL P906 PANEL 803 Common Process and Area gag Ala ris Turb 8tdg East 2.5E+0 mR/hr UO-84H-73 East Lig 3.0E+1 Turb 81dg West 2.5E+0 mR/hr UO-HH-70 West Liq 3.2[t1 10CC Heat HX 3.5E+1 PANEL P804 Radweste to ESW 3.0E+1 Airborne Radiation Gas (coal Alarm Redweste to Sewage 3.6E+1 Annulus Exh A Gas ' DdLtg 8 LQf+1 Cntet Ata L DLt2 METEOROLOGICAL. CONDITIONS i Drywell - HR (R/hr) LDL+1 AB Vent 2Jf11 Wind Speed 18.0 mph OC8 Vent Exh 2Jff2 Wind Direction 225 * , OC8 Vent - HR DJLig Tempe ra tu re 38 'F OG Vent Pipe LDES Delta T -0.80 'F U1 Plant Vent O ;+_]. U1 Plant Vent - HR ;t(! T8/HB Vent M TB/HS Vent - HR QJW! . ST Packing Exh 88 ,0 1. i u2 Plant vent al. I U2 Plant Vent - HR 0.0E+t! l DW170C/A/16/ba l . 1 l w
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4 Time: 1002 Message No.: 37 PIRRY NUCLEAR POWER PLANT 1984 EMERGENCY' PREPAREDNESS EXERCISE I MESSAGE FORM Messene For: Control Room /TSC Simulated Plant Conditions:-- See attached sheets
.. . Messame: ***THIS IS A DRILL ***
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Ii i ~ FOR CONTROLLER USE ONLY ? . Controller Notes: 1. .A scram should be initiated by placing the mode switch
,- , in " SHUTDOWN." However, there will be no inward motion of the control roda. In accordance with PEI-1, the operators should attempt to shut down the reactor using alternate rod insertion. All alternate shutdown methods fail. A manual scram is initiated, but fails. }' 2. Scram discharge Instrument Volume Level, if checked, indicates 0 gallons; level remains constant.
- 3. The reason for the failure to scram is shown on Message No.'81.
Actions Expected: 'As stated above. DW176/C/37/ba s.
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d PERRY 100 CLEAR POWER PLANT 1984 EMERGE 80CY PREPAREDetESS EXERCISE TIME: 1002 CONTROL ROOH A8100U60CIATORS P601/P877 P680 P870 4 8ACK PA8tELS Section 20A Section SA ' SUPP POOL
- MAIIUAL SCRAM LEVEL A HIGH SWITCH ARMED Section 17A RPS LOGIC MANUAL SCRAM r SUPP POOL LEVEL 8 HIGH Section 7A SAFETY / RELIEF VALVE LEAKAGE ALARM P614 i
a ll I j 4 i, i DW1708/A/47/ba __
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, , 4 PERRY llUCLEAR POWER PLA81T 1984 EMERCEllCY PREPAREDNESS EXERCISE ,
TIME: 1002 s P870 , ELECTRICAL DISTRIBUTIOle M CST Level 410.000 eat. Status Load fMW) Status Status foslo)._ OFFsite Pwr Sources 2 AV Cont Rm HVAC Su b Fan A OP , TBCC PMP A OP 75 Can Breakers _ 2 CL _ B SR 8 OP 75 Div 1 DG OOS Cont Ra HVAC Rtn Fan A OP , C SS 18 Div 2 DG SR 8 SR SA Comp OP 128 Div 3 DG SR Cont Re Eag RCIRC Fan A SR IA Comp SR 120 8 SR P800 CIRW PMP A OP 46 Status f219 8 OP 45 Catet Val CIg Fan A OP Pre ssure , Status fosial C OP 46 8 OP IICC Pump A OP 112 SJAE A OP C SS B _ OP 112 8 SS D OP C SS 35 E OP ADOITIONAL INFORMATIOle SW Pump A OP 56 F SS Status Abbreviations . 8 OP 56 Drywell Cooling Fan IA OP OP Operating C SS O 2A OP SS Secured Status D SS O 3A OP AV Available MTR Fire Pump SR 18 SS SR Standby Readiness DO Fire Pump SR 28 SS SHTDN Shutdown 38 SS S-SP Slow Speed Cntet Vsl Purge Supp Fan A SS F-SP Fast Speed 8 SS ISOL isolated Cntet Val at DW - Purge Exh Fan A SS NORM Normal 8 SS OOS Out of Service Drywell Purge Suppl Fan A SS , 8 SS OVRD Ove rride AEGTS Fan A OOS 8 OP g..
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PERRY IIUCLEAR POWER PLANT 1984 EMEltCEIICY PREPAREDIIESS EXERCISE ' TIME: 1002 2601- NtaQ CONTAllBENT PARAMETERS, SYSTEM INFORMATIOII REACTOR PARAMETERS Tempe ra ture Pressure Pressure Flow Pressure 1018 psig f*F1 fosial Status fosiel_ femel Level 31 in. IIR Cntet 81 0 RWCU PMP A OP 1350 Neutron Drywei1 120 0.1' B OP 1350 Mon 100 Range APRM HWL PMP .A OP 230 Mode SW Shutdowq Tempe ra ture Level f*F1 IFt.1 B OP 2 ? '.L_ FDW Flw 15.4 Mib/hr Sup r P B 93 18.4 C SS 0 ST Flw (Total) 15.4 MIb/hr CSP A OP 275 Line A 3.5 SYSTEMS INFORMAT1081 B OP 280 Line B 3.5 Pressure Flow A stus f osieL focal C SR 150 Line C 3.5 RHR A SR RISP A OP 330 Line D 4.5 B SR S OP 330 C SR C OP 330 LPCS SR D SR 160 RCIC SR RFP A OP 1065 15.1 IC HPCS SR S OP 1063 14.9E ECC A 00S MFP SR 0 0 IMBRIM-GEq[RATOR S SR RCIRC A FAST 39254 PARAMETERS ESW A 00S B FAST 39254 Watt 1162 B SR MVAR 403 MAJOR VALVE PARAMETERS C SR CIIDR Vac 28 in. Hg Status Closed Open CRD A SR Thrt Pr 948 psig MSIV IIORM 0 8 8 OP 1900 44 BYP VLV . SRV IIORM 19 0 Posit 0 % SLC A SR B SR SLC STC TK LVL 4600 gal.
. .. .. _ _ _ _ . . - . ~ , _ . . ._- , ~ . ~ . . . _ _ . - . , . . . . _ 1 PERRY IIUCLEAR POWER PLANT 1984 EMERCEIICY PREPAREDetESS. EXERCISE TIME: 1002 PANEL P604 fAMELS P669. P670. P671. P672 Process Radiation Main Steam Line RAD 6.8E+2 mR/hr Alsre Cntet Vent Exh RAD 41.0E-1 mR/hr Orrgas Pre-treatment 2.5E+2 R/hr Orrgas Post-treatment A 2.0E+2 cpm PANEL P902 8 2.0E+2 cpe Common Airborne Gas icool Ala re Eng Service Water A 3.0E+1 cpm RWB Vent Exh 2.0E+1 8 3.0E+1 cpe FH8 Vent Exh 2.2E+1 OC Carbon Bed Vault A 6.0E+1 mR/hr CR Vent Exh 2.0E+1 8 5.5E+1 mR/hr PANEL P906 PANEL 803 P - n Process and Area gag Alarm Turb Bldg East 2.5E+0 mR/hr UD-MH-73 East Liq 3.0E+1 Turb Bldg West 2.5E+0 mR/hr UO-MH-70 West Liq 3.2E+1 NCC Heat HX 3.5E+1 _
PANEL P804 Radweste to ESW 3.0E+1 Airborne Radiation Gas ic M Ala re Radweste to Sewage 3.6E+1 Annulus Exh A Cas Q20EfQ 8 LQ[11 Cntot Ata LS E__+ 2 METEOROLOGICAL CON 01T10NS Drywell - HR (R/hr) LQQ. A8 Vent , R Qff'. Wind speed 18.0 _ aph OC8 Vent Exh 2 QEE Wind Direction 225 OC8 Vent - HR Q Q[fD Tempe ra ture 38 *F OC Vent Pipe 2 QEE Delta T -0.80 *F ut Plant vent 6 Q0+1 U1 Plant Vent - HR Q,DE_+Q TB/HB Vent 6 QI11 18/HB Vent - HR 92D[fQ ST Packing Exh ag,QE + 1 02 Plant Vent 6 0[ 11 U2 Plant Vent - HR 0.0E+0 DW170C/A/17/ba 9
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5 AREA RADIATION MONITORS Time: 1002 TAG # _, LOCATION- READING (mR/hr) 1D21N030 Personnel Air Inck, Catet (600'6") 5.0E+0 1D21N040 CRD HCU West Catet (620'6")- 5.0E+0 1D21N050 RBRT Area. Catet (642') 1.0E+2 1D21N060 Tip Drive Area. Cntet (600'6") 3.0E+1 . 1D21N070 RWCU F/D Area Cntet (664'7") 7.0E+0 1D21N080 Upper Pool Area Cntet (689'6") 2.0E+0 1D21N110 Aux Blda East (574'10") 7.0E+0 1D21N120 Aux Blda West (574'10") 7.0E+0 1D21N130 Turb Rm East (647'6") 2.5E+0 1D21N140 CRD HCU East. Catet (620'6") 5.0E+0
'1D21N160 Turb Rm West (647'6") 2.5E+0 1D21N170 Turb Blds (605'6") 2.5E+0 1D21N180 Hotwell Pump Area. TB (577'6") 1.0E+1 1D21N190 TB Sump Area. TBC (548'6") 2.0E+1 1D21N200 OGB (584') 1.1E+1 1D21N210 Cads F1tr Pop Area. TBC (568'6") 9.0E+0 1D21N220 OG After Fitr Area. OGB (602'6") 2.0E+1 1D21N230 HP Fdw Her Area. HB (600'6") 1.0E+1 1D21N240 Fdw Pump Area. HB (647'6") 6.6E+0 1D21N400 CR. CC (654'6") 1.6E-1 1D21N410 OG Hold Up Area. TB (577'6") 1.0E+1 D21N250 RWB West (574'10") 2.5E+1 D21N260 RWB East (574'10") 1.5E+1 D21N270 RWB (602') 5.0E+0 D21N280 Process Sample Rs. RWB (623'6") 4.0E+0 D21N290 RW Evap. RWB (623'6") 4.0E+0 D21N310 FPCU F/D Area. IB (599') 6.0E+0 D21N320 Fuel Preparation Pool. IB (620'6") 2.0E+3 *
- D21N330 .ipent Fuel Storate Pool. IB (620'6") 5.8E+2
- D21N420 l'PCU Cire Pop Area. IB (574'10") 9.0E+0 1D21N340 Unit 1 DW, Portable. Cntet (655') -
D21N380 Waste Compactor Area. RWB (623'6") 6.0E+1 D21N370 SRW Drummina Area. RWB (623'6") 6.0E+0 ... 1D21N090 Refuelinz Bridae Catet (689'6") 3.0E+0 D21N390 Fuel Serv Hdla Platform. IB (620'6") 2.0E+3 *
* = Alarm OS = Offseale . =
7-Time: 1002 Message No.: 38 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Messane For: Fuel Handling Bridge Operator Simulated Plant Conditions: Messame: ***THIS IS A DRILL *** The Fuel Handling Bridge is repaired. L' t i
~
FOR CONTROLLER USE ONLY J l' F4 F Controller Notes: 1. Fuse,G has been replaced. s
.' 2. Radiation levels in the Fuel Handling Building begin to decrease at 1005.
Actions Expected: 1. Lower the fuel bundle into the pool. '. 2. Notify the Control Room. DW176/C/38/ba
Time: 1005 Message No.: 39 - PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Messaae For: Control Room /TSC 6 r Simulated Plant conditions: See attached sheets
, Messame: ***THIS IS A'DPTLL***
f FOR CONTROLLER USE ONLY a-i Controller Notes: 1. Suppression Pool. temperature is increasing.
- 2. Fuel Preparation Pool Monitor and Fuel Service Handling Platform Monitor levels begin to decrease as the fuel bundle is lowered into the pool.
f I' Actions Expected: e . DW176/C/39/ba k
6sr/g/J/91tmo 9G ZG 9% 44 0% 9E ZE 92 43 02 91 Et 90 'c1 1 9% 94 94 9% 9% 94 9% 94 94 94 9% 9% 9% 9% 50 60 94 94 94 94 9% 9% 94 9% 9% 9% 94 94 94 94 9% 94 94 94 9% 9% 9% 9% 9% 9% Et it 94 94 94 et 94 94 9% 9% 94 94 94 94 9% 9% 94 94 94 94 94 9% 9% 94 94 94 94 94 94 94 12 GZ 94 94 94 94 9% 94 9% 94 94 9% 94 94 94 94 9% . 94 94 94 94 94 9% 94 94 94 9% 9% 9% 94 94 94 62 , EE 94 9% 94 94 9% 94 94 9% 94 94 94 94 94 94 94 9% 9% 9% 94 94 94 94 94 9% 94 9% 94 9% 94 9% LE . 1% . 94 94 94 94 94 94 94 94 94 94 94 9% 9% 9% 94 94 94 9% 94 94 94 9% 94 94 94 44 G4 6% 4 9% 94 94 9% 94 94 9% 94 94 9% 94 94 94 94 94 9% 9% - 94 9% 94 EG 94 94 9% 94 9% LG M :3 Nil 3Sl3u]W] S$3NO3WJ3W A31030W3N3 4961 L ,
,__ m.. . - - . . , , , - . ~ . . . - _ . . . _ _
PEltRY leUCLEAR POWER PLAftT 1984 EMERGEIICY PREPAREDItESS EXERCISE TIME: 1005 C001 TROL ROOM AIIIIUIICIATORS P601/P877 P680 PS70 at BACM PAleELS Section 20A Section 5A-SUPP POOL MA800AL SCRAM LEVEL A telGH SWITCH Aft 00ED SUPP POOL RPS LOGIC TEMP A HIGH MA800AL SCRAM Section 17A RACS ItA81 IIll TI AT1081 SUPP POOL LEVEL 8 HlCH Section 7A
~
SUPP POOL SAFETV/ RELIEF TEMP P HICH VALVE LEAMAGE ALAftM P614 DW1708/A/50/ba
PERRY leUCLEAR POWER Plasti 1984 EMERGEleCY PREPAREDIIESS EXERCISE TiteE: 1005 fglg ELECTRICAL DISTRIBUT10st Eggg CST Level 410.000 eat. Status Load ( W) Status Status fosiel Offsite Pwr Sources 2 AV Cont me HVAC Supp Fan A np TBCC PMP A OP 75 Gen Breakers 2 CL 8 SR B OP 75 Div 1 DG OOS Cont Ra HVAC Rtn Fan A OP C SS 18 Div 2 DC SR 8 SR SA Comp OP 128 Div 3 DG SR Cont Re Esg RCIRC Fan A SR IA Comp SR 120 8 SR faQQ CIRW PHP A OP 46 _Fcatus II.10 B OP 45 Cntet Vsl Cig Faq A OP Pressu re Status fosial C OP 46 8 OP 10CC Pump A OP 112 . SJAE A OP C SS S OP 112 8 SS D OP C SS 35 ,. E OP l ADDITiostAL leeFORe%T1081 SW Pump A OP 56 F SS Status Abbreviations: B OP 56 Drywell Cooling Fan 1A OP OP Opera ting C SS O 2A OP SS Secured Status D SS O 3A OP AV Avalfable MTR Fire Pump SR 18 SS SR Standby Readiness DO l' Ire Pump SR 28 SS SHTDet Shutdown 38 SS S-SP Slow Speed Cntet Val Purge Supp Fan A SS F-SP Fast Speed B SS ISOL Isolated Cntet Val as DW Purge Exh Fan A SS DIORM leo rua I 8 SS 00S Out of Service Drywell Purge Suppl Fan A SS CL Closed B SS OVRD Override AEGIS Fan A 00S 8 OP e 0 em
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PERRY leuCLEAR POWER PLAffT 1984 EMERCEIICY PREPAREDetESS EXERCISE TIME: 1005 'l P601 Et09 C006TABIIMENT PARAMETERS SYSTEM INFORMATION REACTOR PARAMETERS Tempe ra ture Pressure Pressure Flow Pressure 953 psig f*F1 :fosial Status losleL femel Level 34 in. IIR Cntet 82 0 RWCU PMP A SS Neutron Drywe 11 120 0.1 8 $$ Mon 57 Range M HWI. PMP .A OP 230 Mode SW Shutdown Tempe ra ture Level f*F1 fft.) B OP 230 FDW Flw 8.8 Mlb/hr Supr PI 97 18.5 C SS O ST Flw (Total) 8.8 Mib/hr CSP A SS 150 Line A 2 SYSTEMS INFORMAT1008 B SS 150 Line B 2 Pressure Flow Status foslel fonal C SS 150 Line C 2 Retr A SR RFBP A OP 330 Line D 2.9 8 SR S OP 330 C SR C SS 160 LPCS SR D SS 160 RCIC SR RFP A or _ 1000 t 7.6 ( HPCS SR S SS O O ECC A 005 MFP SR 0 0 TUR8 IML-G[IfERAT0ft 8 SR RCIRC A SS O PARAMETERS ESW A OOS B SS 0 Mwatt 713 8 SR MVAR 472 MAJOR VALVE PARAMETERS Status Closed Ooen CRD A SR Thrt Pr 937 psig 8 OP 1900 44 BYP VLV SRV IIORM 19 0 Posit 0 % 8 SR , SLC STG TK LVL 4600 gal. ,
PERRY NUCLEAR POWER PtAIIT 1984 EMERGENCY PREPAREDIIESS EXEltCISE TlftE 1005 PANEL P604 PAleELS P669. P670. P671. P672 Process Radiation Mein Steam Line RAD 6.8E+2 mR/hr Alers
- Cntet Vent Exh RAD ,1.0E-1 mR/hr Offges Pre-treatment ZdLt2 R/hr Offges Post-treatment A 2.0E+2 cpe PA8til P902 B 2.OE+2 cpe Common Airborne ces fcaeI AIarm .
Eng Service Water A 3.0E+1 cpe ItW8 Vent Exh 2.0E+1 5 310E+1 cpe Fles Vent Exh 2.2E+1 OG Carbon med Vault A 6.0E+1 mR/hr CR Vent Exh 2.0E+1 5 5.5E+1 mR/hr PAf0EL P906 , PASTEL 803 cm Process and Area Eng Alarm - Turb BIdg East 2.5E+0 mR/hr U0-804-73 East Lig 3.0E+1 Turb Bldg West 2.5E+0 mR/hr UD-ItH-70 West Liq 3.2E+1 IICC Heat HX 3.5E+1 PAatEL P804 Radweste to ESW 3.0E+1 Airborne Radiation Gas Icool Alers Radweste to Sewage 3.6E+1 Annulus Exh A Gas QJL+9 B LDEL Catet Ata L DL+R METEOROLOGICAL C0010lTIOIIS Drywel 8 - HR (R/hr) LOE Aa Vent RJE. . Wind Speed is.O 225 aph oce Vent Exh 2JM Wind Direction oca Vent - HR QJLie Tempe ra ture sa *r OG Vent Pipe RJLt2 Delta T -0.80 *F U1 Plant Vent 6 0[+]. U1 Plant Vent - HR QJLt{! TB/HS Vent 6 J [1], 18/H8 Vent - HR Q OLif! ST Packing Exh ag Og ; U2 Plant Vent 6 J Lt_. U2 Plant Vent - HR 0. 0E +t ! DW170C/A/18/ba W G t Q
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AREA RADIATION MONITORS Time: 1005 TAG # LOCATION READING (mR/hr) 1D21NO30 Personnel Air Lock, Cntmt (600'6") 5.0E+0 1D21N040 CRD HCU West, Cntmt (620'6") 5.0E+0 1D21N050 RBRT Area, Cntmt (642') 1.0E+2 1D21N060 Tip Drive Area, Cntmt (600'6") 3.0E+1 1D21N070 RWCU F/D Area, Cntmt (664'1") 7.0E+0 1D21N080 Upper Pool Area, Cntmt (689'6") 2.0E+0 1D21N110 Aux Bldg East (574'10") 7.0E+0 1D21N120 Aux Bldg West (574'10") 7.0E+0 1D21N130 Turb Rm East (647'6") 2.5E+0 1D21N140 CRD HCU East, Cntmt (620'6") 5.0E+0 1D21N160 Turb Rm West (647'6") 2.5E+0 1D21N170 Turb Bldg (605'6") 2.5E+0 1D21N180 Hotwell Pump Area TB (577'6") 1.0E+1 1D21N190 TB Sump Area, TBC (548'6") 2.0E+1 1D21N200 OGB (584') 1.1E+1 1D21N210 Cnds Fitr Pmp Area. TBC (568'6") 9.0E+0 1D21N220 OG After Fitr Area, OGB (602'6") 2.0E+1 1D21N230 HP Fdw Htr Area, HB (600'6") 1.0E+1 1D21N240 Fdw Pump Area. HB (647'6") 6.6E+0 1D21N400 CR, CC (654'6") 1.6E-1 1D21N410 OG Hold Up Area. TB (577'6") 1.0E+1 D21N250 RWB West (574'10") 2.5E+1 D21N260 RWB East (574'10") 1.5E+1 D21N270 RWB (602') 5.0E+0 D21N280 Process Sample Rm, RWB (623'6") 4.0E+0 D21N290 RW Evap, RWB (623'6") 4.0E+0 D21N310 FPCU F/D Area, IB (599') 6.0E+0 D21N320 Fuel Preparation Pool, IB (620'6") 6 4.0Ftc # D21N330 Spent Fuel Storage Pool, IB (620'6") M 4'.GE*#
- D21N420 FPCU Cire Pmp Area. IB (574'10") 9.0E+0 1D21N340 Unit 1 DW, Portable, Cntmt (655') -
D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1 D21N370 SRW Drumming Area, RWB (623'6") 6.0E+0 1D21N090 Refueling Bridge, Cntmt (689'6") 3.0E+0 D21N390 Fuel Serv Hdig Platform. IB (620'6") M 9.FF+a #
* = Alarm OS = Offscale
Time: 1010 Message No.: 40 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Messaae For: Control Room /TSC Simulated Plant Conditions: See attached sheets Messame: ***THIS IS A DRILL *** I FOR COffrROLLER USE ONLY Controller Notes: Actions Expected: as b DW176/C/40/ba
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., TIME: 1010 +
P870 ELECTRICAL DISTRIBUTION P904 CST Level 410.000 cal. Status Load iMW1 Status. t _ .[ Staly'd fosial Offsite Pwr Sources 2 AV ContRmHVACSuppFAnA OP , , i TSCC PMP A OP 75 Con Breakers 2 CL B SR S OP 75 Div 1 DG 00S Cont Re MVAC Rtn Fan .A OP C SS 18 Div 2 DG SR F S SR , SA Comp 128 -'
- OP Div 3 DG. SR Cont Re Eng RCIRC Fan A SR 1A Coop SR 120 -
B SR P600 ' CIRW PMP A OP 46 _ Status , P970 B OP 45 Cntet Val Cig Fan A OP Pressure Status fostel C OP 46 B OP ' NCC Pump A OP 112 SJAE A OP C SS B OP 112 B SS D OP C SS 35 E OP ADDITIONAL INFORMAT10N SW Pump A OP 56 F SS Status Abbreviations: B OP 56 Drywell Coollag Fan 1A OP OP Op'sra t Ing C SS 0 2A OP SS Secured Status D SS O 3A ~ OP AV Available MTR Fire Pump SR - 1B SS SR Standby Readiness DD Fire Pump SR C 28 SS SHTDN Shutdown ' 3B SS S-SP Slow Speed Cntet Vsl Purge Supp Fan A SS F-SP Fast Speed
- B SS ISOL 1solated Cntet Val as DW Purge Exh Fan A SS NORM Noreai B SS DOS Out of Service Drywell Purge Suppl Fan A SS CL Closed
, B SS OVRO override AECTS Fan A 00S l B OP
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1 I PERRY NUCLEAR PCWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1010 fitQ1 f.ftBQ CONTAlllMENT PARAMETERS SYSTEM INFORMATION REACTOR PARAMETERS Tempe ra ture Pressure Pressure Flow Pressure 953 psig , , (*F1 foslo) Status fesfal facel Level. 34 In. NR Cntet 82 0 RWCU PHP A SS Neutron DryweIi 120 0.1 B SS Mon 57 Range APRM HWL PMP A OP 230 Mode SW Shutdown [ Teepa rature Level f*F1 fft.) B OP 230 FDW Flw 8.8 Mlb/hr Supr PI 104 18.7 C SS O ST Flw (Total) 8.8 Mib/hr CBP A SS 150 Line A 2 SYSTEMS INFORMATION 8 SS 150 1.Ine B 2 Pressure Flow Status losla) focal C _ SS 150 Line C 2 RHR A SR RFBP A OP 330 Line D 2.9 8 SP CLC 250 7000 8 OP 330 , C SR C SS 160 LPCS SR D SS 160 RCIC SR RFP A OP 1000 # 7.6 & HPCS SR S SS 0 0 ECC A 00S MFP SR 0 0 IVBRIME-GENERATOR B OP 114 RCIRC A SS O PARAMETERS ESW A 00S S SS 0 Mwatt 713 8 OP 95 MVAR 47P_ ] MAJOR VALVE PARAMETERS C SR CNDR Vac 28 in. Hg _ Status Closed Open , CR0 A SR Thrt Pr 937 psig MStV NORM 0 8 8 OP 1900 44 BYP VLV SRV NORM 19 0 Posit 0 % SLC A SR 8 SR SLC STC TK LVL 4600 gal. l l l
PERRY NUCLEAR POWER PLANT 1984 EMERGENCY,PREPAREDNESSEXERC{SE TIME: 1010 PANEL P604 PANELS P669. P670. P671. P672 Process Radiation Main Steam Line RAD- 6 8E+2 mR/hr Alarm Cntet Vent Exh RAD 11.0E-1 mR/hr Offgas Pre-treatment 2.5E+E R/hr Offgas Post-treatment A 2.0E+2 cpm PANEL P902 8 2.0E+r cpm Common Airborne Cas (cagl Alarm Eng Service Water A 3.0E+1 cpm RWB Vent Exh 2.0E+1 B 3.0E+1 cpm FHS Vent Exh R.2E+1 OG Carbon Bed Vault A 6.0E+1 mR/hr i CR Vent Exh 2.0E+1 8 5.5E+1 mR/hr PANEL P906 PANEL 803 Common Process and Ares gag Alarm Turb Bldg East 2.5E+0 mR/hr UD-MH-73 East Liq 3.0E+1 Turb Bldg West 2.5E+0 mR/nr UD-MH-70 West Liq 3.2E+1 NCC Heat HX M Lt1 PANEL P808 Radweste to ESW 3.0E+1 Airborne Radiation Gas from) Ala rm Radweste to sewage 3.6E+1 Annulus Exh A Gas Q,0fiQ 8 L QLt1 Cntet Ate L6Lt2 MET [0ft0 LOGICAL CONDITIONS Drywell - HR (R/hr) L DL+J ' AB Vent 2,DE_11 Wind Speed 18.0 mph OGB Vent Exh LOL+1 Wind Direction 225
- OGB Vent - HR Q OEtQ Tempe ra tu re 38 'F OG Vent Pipe RJ E_+/ Delta T -0.80 'F i . U1 Plant Vent LQE+
U1 Plant Vent - HR Q OE+ ? TB/HB Vent LQE+1 i TB/HB Vent - HR QJL1Q j ST Packing Exh 8t JL11 l U2 Plant Vent LQE+1 U2 Plant Vent - HR 0.0E+0 l l DW170C/A/19/ba I b e i
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- 4 PERRY NUCLEAR POWER PLANT 1984 EMERCENCY PREPAREDNESS EXERCISE TIME: 1010 RX WATER LEVEL RX PRESS RX POWER SUPR PL TEMP 3 34 lj 953 fjjf 57 1 104 *f 60- 1100- 120- 110
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45 ' 950- 90- ) 90-30- 800- 40- 70-1 15- 650- 0 50 0 500 -30 -20 -10 0 -30 -20 -10 0
-30 -20 -10 0 -30 -20 -10 0 Time (min) Time (min)
Time (min) Time (min) DW TEMP CONTMT TEMP CONTMT PRESS -SUPR PL LEVEL 120 *f 82 "f 0 ESE 18.7 fJ 200- 110- 20- 19-150- 90- 15- - 100- 70- 10- 18-50 50- 5- -
-30 -20 -10 0 -30 -20 -10 0 0- 17 Time (min). Time (min) -5 -30 -20 -10 0
-30 -20 -10 0 Time (min)
Time (min)
AREA RADIATION MONITORS Time: 1010 TAG # LOCATION READING (mR/hr) 1D21NO30 Personnel Air Lock, Cntmt (600'6") 5.0E+0 1D21N040 CRD HCU West, Cntmt (620'6") 5.0E+0 1D21N050 RBRT Area, Cntmt (642') 1.0E+2 1D21N060 Tip Drive Area, Cntmt (600'6") 3.0E+1 1D21N070 RWCU F/D Area, Cntmt (664'7") 7.0E+0 1D21N080 Upper Pool Area, Cntmt (689'6") 2.0E+0 1D21N110 Aux Bldg East (574'10") 7.0E+0 1D21N120 Aux Bldz West (574'10") 7.0E+0 1D21N130 Turb Rm East (647'6") 2.5E+0 1D21N140 CRD HCU East, Cntmt (620'6") 5.0E+0 1D21N160 Turb Rm West (647'6") 2.5E+0 1D21N170 Turb Bldg (605'6") 2.5E+0 1D21N180 Hotwell Pump Area. TB (577'6") 1.0E+1 1D21N190 TB Sump Area, TBC (548'6") 2.0E+1 1D21N200 OGB (584') 1.1E+1 1D21N210 Cnds F1tr Pmp Area, TBC (568'6") 9.0E+0 1D21N220 OG After F1tr Area, OGB (602'6") 2.0E+1 1D21N230 HP Fdw Htr Area, HB (600'6") 1.0E+1 1D21N240 Fdw Pump Area, HB (647'6") 6.6E+0 1D21N400 CR, CC (654'6") 1.6E-1 1D21N410 OG Hold Up Area, TB (577'6") 1.0E+1 D21N250 RWB West (574'10") 2.5E+1 D21N260 RWB East (574'10") 1.5E+1 D21N270 RWB (602') 5.0E+0 D21N280 Process Sample Rm, RWB (623'6") 4.0E+0 D21N290 RW Evap, RWB (623'6") 4.0E+0 D21N310 FPCU F/D Area, IB (599') 6.0E+0 D21N320 Fuel Preparation Pool, IB (620'6") M V.e5 +# # 4 D21N330 Spent Fuel Storage Pool, IB (620'6") m V.FE ed * " D21N420 FPCU Cire Pmp Area, IB (574'10") 9.0E+0 1D21N340 Unit 1 DW, Portable, Cntmt (655') - D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1 D21N370 SRW Drumming Area, RWB (623'6") 6.0E+0 1D21N090 Refueling Bridge, Cntmt (689'6") 3.0E+0 D21N390 Fuel Serv Hdig Platform, IB (620'6") M 3. fee # *
* = Alarm OS = Offscale
Time: 1015 Message No.: 41 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM i Messane For: Control Room
'i , Simulated Plant Conditions: See attached sheets Messame: ***THIS IS A DRILL *** .1 4
4 i' FOR CONTROLLER USE ONLY ' '.i it "
. Controller Notes: The Suppression Pool temperature reaches 110*F. Standby Liquid Control is activated. The common check valve C41-F007 does not open. SLC does not inject.
Actions Expected: The' operators should implement PEI-1, Attachment 5, and lower reactor level. Level will reach approximately
-145 inches in 30 minutes and power will be approximately . > 8%.
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, PERRY NUCLEAR POWER PLANT- 1984 EMERCENCY PREPAREDNESS EXERCISE TIME: 1015 CONTROL ROOM ANNUNCIATORS P601/P877 P680 P870 & 8ACK PANELS Section 20A Section IA CONT RM HVAC EMERC RCIRC A SUPP POOL RWCU PUMP TRIP INITIATED P904 LEVEL A HIGH SUCTION FLOW LOW CONT RM HVAC SUPP POOL EMERG AGIRC 8 TEMP A HICH Section 5A INITIATED P904 Section 17A MANUAL SCRAM SWITCH ARMED SUPP POOL LEVEL 8 HICH RPS LOCIC MANUAL SCRAM SUPP POOL TEMP B HIGH RRCS MAN
- INITIATION Section 19A Section 7A ADS B PERMISSIVE SAFETY / RELIEF RHR B/C RUN VALVE LEAKACE ALARM P614 Section 22A Section 8A CRD PUMP AUTO TRIP COMMON HVAC PANEL ALARM P904 DW1708/A/56/ba I
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, ,,.,_r .m . ...C ; & ; e .. . ...4A. . .i_ . .- .._t.. . ... n'..._.- ._T" PERRY NUCLEAR POWER Pl. ANT 1984 EMERCENCY PREPAREDNESS EXERCISE TIME: 1015 P870 ELECTRICAL DISTRIBUTION P904 CST Level 410.000 cal. Status Load fMW) Status Status A slal OFFsite Pwr Sources 2 AV Cont Rm HVAC Supp Fan A OP TBCC PHP A OP 75 . Gen Breakers 2 CL 8 OP 8 OP 75 Div 1 DG OOS Cont Rm HVAC Rtn Fan A SS C SS 18 Div 2 DG OP O B SS SA Comp OP 128 Div 3 DG SR Cont Re Eng RCIRC Fan'A OP 1A Comp SR 120 B OP P800 CIRW PHP A OP 46 Status P970 B OP 45 Cntet Vsl Cig Fan A OP Pressure Status foslo)
C OP 46 8 OP NCC Pump A SS 112 SJAE A OP C SS B SS 112 8 SS D OP
-C SS 35 E OP ADOITIONAL INFORMATION SW Pump A OP 56 F SS Status Abbreviations: 8 OP 56 Drywe l l Cool ing Fan 1 A OP OP Ope ra t ing C- SS O 2A OP SS Secured Status D SS O 3A OP AV Available MTR Fire Pump SR 18 SS SR Standby Readiness DD Fire Pump SR 28 SS SHTDN Shutdown 3B SS S-SP Slow Speed Cntet Vsl Purge Supp Fan A SS F-SP Fast Speed -
8 SS ' ISOL 1solated Cntet Vs1 4e DW Purge Exh Fan A SS NORM No raa 1 B SS OOS Out of Service Drywell Purge Suppl Fan A SS CL Closed B SS OVRD Override l AEGTS Fan A OOS 8 OP
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9 PERRY NUCLEAR POWER PLANT- 1984 EMERCENCY PREPAREDNESS' EXERCISE TIME: 1015 4
. Eft 0.1 fitAQ CONTAINMENT PARAMETERS SYSTEN INFORMATION REACTOR PARAMETERS Tempera ture Pressure Pressure Flow Pre ssure . 953 psig f*F1 losiel_ StaM!1_ fosial local Level 34 in. NR Cntet 8as 0.1 RWCU PMP .A SS Neutron ! Dryweii 120 .1 8 SS Mon 57 Range 6EB!l l HWL PMP A- OP 230 Mode SW 1[nttdown Tempe ra ture Level f*Fl frt.) 8 OP 230 FDW Flw 8.8 Mib/hr Supr P1 109 18.9 C SS O ST Flw (Total) 8.8 Mib/hr C8P A SS 150 Line A 2 SYSTEMS INFORMATION 8 SS 150 Line 8 2 Pressure Flow Status fosial foomi C SS 150 Line C 2
] RHR A PMP OVRD RF8P A OP 330 Line D 2.9 8 VLV OVRD 275 8 OP 330 C VLV DVRD 275 C SS 160 LPCS PMP OVRD D SS 160 I RCIC SR RFP A OP 1000 t 7.4 A HPCS SR 8 SS O O i ECC A 00S MFP SR 0 0 1"BRIME-C[MERATOR 8 OP 114 RCIRC A SS O PARAMETERS l ESW A 005 8 SS O Mwatt 713 8 OP 95 MVAR is72 MAJOR VALVE PARAMETERS C OP 95 ONOR Vac 28 in. Hg Status Closed Open CRD A SS Thrt Pr 937 psig MSIV NORM 0 8 8 SS ._ BYP VLV ~i SRV J ORM 19 0 Posit 0 % SLC A OP 1600 8 OP 1600 l SLC STG TK LVL. is600 gal.
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PERRY NUCLEAR POWER PLANT. 1984 EMERGENCY PREPAREDNESS EXERCISEg TIME: 1015 PANEL P604 PANELS P669.'P670. P671. P672 Process Radiation
- Main Steam Line RAD 6.8E+2 mR/hr
- Ala re Cntet Vent Exh RAD 41.0E-1 mR/hr Orrgas Pre-treatment 2.5E+1 R/hr Orrges Post-treatment A 2.0E+2 cpm PANEL P902 B 2.0E+2 cpm Common Airborne Gas icoal Ala re Eng Service Water A 3.0E+1 cpm RWB Vent Exh 2.0E+1 8 3.0E+1 cpm FHB Vent Exh 2.2E+1 OG Ca rbon Bed Vau l t A 6.0E+1 mR/hr CR Vent Exh 2.0E+1 8 5.5E+1 mR/hr PANEL P906 PANEL 803 Common Process and Area Egg Alarm Turb Bldg East 2.5E+0 mR/hr UD-MH-73 East 1.lg 3.0E+1 Turb Bldg West 2.5E+0 mR/hr UD-MH-70 West Liq 3.2E+1 NCC Heat HX 3.5E+1 ff3EL P804 Radwaste to ESW 3.0E+1 Airborne Radiation Gas icoal Alarm Redwaste to Sewage 3.6E+1 Annulus Exh A Gas QJW!
' 8 L D':+1 Cntat Ata ' LD@ METEOROLOGICAL CONDITl0NS Drywe l l - HR ( R/h r) L.0J : +_Q
- AB Vent 2JLil Wind Speed '8.0 ._ aph
' OCS Vent Exh RJL12 Wind Direction 2: 0 OGB Vent - HR gJ[ig Tempera ture :l8 'F OG Vent Pipo gJLig Delta T -0.85 *F U1 Plant Vent 0,0011 . U1 Plant Vent - HR Q OEiQ. TB/HB Vent 6J Lil TB/HB Vent - HR Q,DE_tQ ' ST Packing Exh g Olig U2 Plant Vent h0EE U2 Plant Vent - HR 0.0E+0 DWl70C/A/20/ba e e
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AREA RADIATION MONITORS Time: 1015 TAG # LOCATION READING (mR/hr) 1D21NO30 Personnel Air Lock, Cntmt (600'6") 5.0E+0 1D21N040 CRD HCU West, Cntmt (620'6") 5.0E+0 1D21N050 RBRT Area, Cntmt (642') 1.0E+2 1D21N060 Tip Drive Area, Cntmt (600'6") 3.0E+1 1D21N070 RWCU F/D Area, Cntmt (664'7") 7.0E+0 1D21N080 Upper Pool Area, Cntmt (689'6") 2.0E+0 1D21N110 Aux Bldg East (574'10") 7.0E+0 1D21N120 Aux Bldg West (574'10") 7.0E+0 1D21N130 Turb Rm East (647'6") 2.5E+0 1D21N140 CRD HCU East, Cntmt (620'6") 5.0E+0 1D21N160 Turb Rm West (647'6") 2.5E+0 1D21N170 Turb Bldg (605'6") 2.5E+0 1D21N180 Hotwell Pump Area, TB (577'6") 1.0E+1 1D21N190 TB Sump Area, TBC (548'6") 2.0E+1 1D21N200 OGB (584') 1.1E+1 1D21N210 Cnds Fitr Pmo Area, TBC (568'6") 9.0E+0 1D21N220 OG After F1tr Area, OCB (602'6") 2.0E+1 1D21N230 HP Fdw Htr Area, HB (600'6") 1.0E+1 1D21N240 Fdw Pump Area, HB (647'6") 6.6E+0 1D21N400 CR, CC (654'6") 1.6E-1 1D21N410 OG Hold Up Area, TB (577'6") 1.0E+1 D21N250 RWB West (574'10") 2.5E+1 D21N260 RWB East (574'10") 1.5E+1 D21N270 RWB (602') 5.0E+0 D21N280 Process Sample Rm, RWB (623'6") 4.0E+0 D21N290 RW Evap, RWB (623'6") 4.0E+0 D21N310 FPCU F/D Area, IB (599') 6.0E+0 D21N320 Fuel Preparation Pool, IB (620'6") ME8Ee6 8 D21N330 Spent Fuel Storage Pool, IB (620'6") m f.FE + g e D21N420 FPCU Cire Pmp Area, IB (574'10") 9.0E+0 1D21N340 Unit 1 DW, Portable, Cntmt (655') - D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1 D21N370 SRW Drumming Area, RWB (623'6") 6.0E+0 1D21N090 Refueling Bridge, Cntmt (689'6") 3.0E+0 D21N390 Fuel Serv Hdig Platform, IB (620'6") M 3.gE* 9
- 1
* = Alarm OS = Offscale
8 - . - - - - Time: 1020 Message No.: 42 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Messaae For: Control Room /TSC Simulated Plant Conditions: See attached sheets Message: ***THIS IS A DRILL *** l j FOR CONTROLLER USE ONLY it Controller Notes: Actions Expected: Emergency classification discussions should be underway. I d. DW176/C/42/ba i v.----. - , - - -- ,- -
a . . . *. r n. .w . . . - , ~.. n.a :- .. - ... . ;...;-. .....,s. . PERRY NUCLEAR POWER PLANT 1984 EMERCENCY PREPAREDNESS EXERCISE TIME:-1020
. P601 P680 CONTAINMENT PARAMETERS SYSTEM INFORMATIOff REACTOR PARAMETERS Tempe ra ture ' Pressure Pressure ' Flow Pressure 948 psig f*Fl fosial Status fosial faom) . Level 10 in. NR Cntet 87 0.2 RWCU PMP A SS Neutron-Drywe11 120 .1 8 SS Mon 40 Range effjt HWL PMP A OP 230 Mode SW Shutdown Tempe ra ture Level
(*F1 fft.) 8 OP 230 FDW Flw 6.2 Mib/hr Supr PI 115 19.1 C SS O ST Flw (Total) 6.2 Mlb/hr C8P A SS 150 Line A 1.3 SYSTEMS INFORMATION 8 SS 150 Line 8 1.3 Pressure Flow Status fosiel leon) C SS 150 Line C 1.3 RHR A PMP OVRD RF8P A OP 330 Line D 2.? 8 VLV OVRD 275 8 OP 330 C VLV OVRD 275 C SS 160 LPCS PMP OVRD SR D SS 160 RCIC SR RFP A OP 1000 6.0 ( i' HNS SR 8 SS O O
- ECC A 00S MFP SR 0 0 TUR8INE-CfMERATOR
; 8 OP 114 RCIRC A SS 0 PARAMETERS ESW A 00S S SS O Mwatt 500 8 OP 95 MVAR 100 MAJOR VALVE PARAMETERS -
, C OP 95 CNDR Vac 28 in. Hg
. Status Closed Open CRD A SS Thrt Pr 932 psig MSIV NORM O 8 8 SS BYP VLV SRV NORM 19 0 Posit O %
SLC A OP 1600 8 OP 1600 SLC STG TK LVL 4600 gal. T M
_e .. =: . . . . . --
.a - . . . .
PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1020 CONTROL ROOM ANNUNC1ATORS P601/P877 P680 P870 at BACK PANELS Section 20A Section IA
-~~~
CONT RM HVAC EMERG RClRC A SUPP POOL gRWCUPUMPTRIPl INITIATED P904 LEVEL A HIGH SUCTION FLOW LOW g CONT RM HVAC l EMERG RCIRC 8 SUPP POOL i TEMP A HIGH Section SA INITIATED P904 Section 17A MANUAL SCRAM SWITCH ARMED SUPP POOL LEVEL 8 HIGH RPS LOGIC MANUAL SCRAM SUPP POOL TEMP 8 HIGH RRCS MAN INITIATION Section 19A RPS LOW LEVEL ADS 8 L-3 PERMISSIVE RHR 8/C RUN Section 8A ADS A PERMISSIVE l COMMON HVAC l l PANEL ALARM RPV L-3 P904 ADS 8 PERMISSIVE l RPV L-3 l Section 22A CRD PUMP lAUTOTRIPl l I I ' l l 1 DW1708/A/59/ba e
._ ... .. ... - n. .. , . _ , 4_ . . . .w _ . . . . . . . . . . . . , . . . . . . - . , . _ . . , , . , . _ . . ..
PERRY NUCLEAR POWER FLANT 1984 EMERCENCY PREPAREDNESS EXERCISE TIME: 1020 RX WATER LEVEL RX PRESS RX POWER SUPR PL TEMP in jj 9he EE.Lc 40 y 115 *r 60- 1100- 120- 110 - x 45- 950- 90- 90-h 30- 800- 40- 70-15- 650- 0 50 l 0 500 -30 -20 -10 0 -30 -20 -10 0 -l l l l -30 -20 -10 0 -30 -20 -10 0 Time (min) Time (min) i l Time (min) Time (min) DW TEMP CONTMT TEMP CONTMT PRESS SUPR PL LEVEL 120 'f 87 *I 0.2 E3M 19.1 fl 200- 110- 20- 19-150- 90- y 15- - 100- 70- 10- 18-50 50- 5- - 'I
~~
-30 -20 -10 0 -30 -20 -10 0 0- 17 Time (min) i T'me (min) -5 -30 -20 -10 0
~
-30 -20 -10 0 Time (min)
~
Time (min) l . l - l 1
~ +- x,
, .u : .v.< 4_ m g,w , . . , , c,._ , .
. PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1020 Iglg ELECTRICAL DISTRIBUTION M
, CST Level 410.000 esl. Status. Lead IMW1 Status Status fosial OFFsite Pwr Sources 2 AV Cont Rm HVAC Supp Fan A OP TBCC PHP A OP 75 Gen Breakers 2 CL B OP B OP 75 Div 1 DG OOS Cont Rm HVAC Rtn Fan A SS C SS 18 Div 2 DG OP O 8 SS SA Comp OP 128 Div 3 DG SR Cont Re Eng RCIRC Fan A OP IA Comp SR 120 B OP EA90 CIRW PHP A OP 46 Status P970 8 OP 45 Cntet Vst Clg Fan A OP Pressu re Status fosie)
C OP 46 8 OP NCC Pump A SS 35 SJAE A OP C _ SS 8 SS 35 1 8 SS D OP i C OP 112 E OP ADDITIONAL INFORMATION SW Pump A OP 56 F SS Status Abbreviations: 8 OP 56
. Drywe1l Coo lIng Fan 1A OP
, OP Ope ra t ing C SS O ! ,2A OP 4 SS Secured Status D SS O , AV Available MTR Fire Pump SR 18 SS SR Standby Readiness DD Fire Pump SR 28 SS
- SHTDN Shutdown 38 SS
- S-SP Slow Speed Cntet Val Purge .
i F-SP Fast Speed B SS ISOL isolated Cntat Vsl & DW Purge Exh Fan A SS NORM No rea l B. SS OOS Out oF Service Drywell Purge . Suppl Fan A SS CL Closed OVRD Override AEGTS Fan A OOS B OP t
AREA RADIATION MONITORS Time: 1020 TAG # LOCATION READING (mR/hr) 1D21NO30 Personnel Air Lock, Cntmt (600'6") 5.0E+0 (620'6") 1D21N040 CRD HCU West, Cntmt 5.0E+0 1D21N050 RBRT Area, Cntmt (642') 1.0E+2 . 1D21N060 Tip Drive Area, Cntmt (600'6") 3.0E+1 1D21N070 RWCU F/D Area, Cntmt (664'7") 7.0E+0 1D21N080 Upper Pool Area, Cntmt (689'6") 2.0E+0 1D21N110 Aux Bldg East (574'10") 7.0E+0 1D21N120 Aux Bldg West (574'10") 7.0E+0 1D21N130 Turb Rm East (647'6") 2.5E+0 1D21N140 CRD HCU East, Cntmt (620'6") 5.0E+0 1D21N160 Turb Rm West (647'6") 2.5E+0 1D21N170 Turb Bldg (605'6") 2.5E+0 i 1D21N180 Hotwell Pump Area TB (577'6") 1.0E+1
; 1D21N190 TB Sump Area, TBC (548'6") 2.0E+1 l 1D21N200 OGB (584') 1.1E+1 ID21N210 Cnds Fitr Pmp Area, TBC (568'6") 9.0E+0 1D21N220 OG After F1tr Area, OGB (602'6") 2.0E+1
! 1D21N230 HP Fdw Htr Area, HB (600'6") 1.0E+1
~
1D21N240 Fdw Pump Area, HB (647'6") 6.6E+0
} 1D21N400 CR, CC (654'6") 1.6E-1 l'
ID21N410 OG Hold Up Area, TB (577'6") 1.0E+1 D21N250 RWB West (574'10") 2.5E+1 D21N260 RWB East (574'10") 1.5E+1
, D21N270 RWB (602') 5.0E+0 D21N280 Process Sample Rm, RWB (623'6") 4.0E+0
'} D21N290 RW Evap, RWB (623'6") 4.0E+0 ] ; D21N310 D21N320 FPCU F/D Area, IB Fuel Preparation Pool, IB (599') (620'6") 6.0E+0 6 4,#F+ 9 # D21N330 Spent Fuel Storage Pool, IB (620'6") 6 4096* D21N420 FPCU Cire Pmp Area, IB (574'10") 9.0E+0
, 1D21N340 Unit 1 DW, Portable, Cntmt (655') -
D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1 D21N370 SRW Drumming Area, RWB (623'6") 6.0E+0 1D21N090 Refueling Bridge, Cntmt (689'6") 3.0E+0 D21N390 Fuel Serv Hdig Platform, IB (620'6") 6 9.cE*7
- p i .
t
* = Alarm OS = Offscale
PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1020 , PANEL P604 PANELS P669. P670. P671. P672 Process Radiation Main Steam Line RAD 6.8E+1 mR/hr Ala r1s Orrgas Pre-treatment 2.5E+1 R/hr Offgas Post-treatment A 2.0E+2 cpm PANEL P902 8 2.0E+2 cpm Common Airborne . Gas fconi Alarm Eng Service Water A 3.0E+1 cpm RWB Vent Exh 2.0E+1 s B 3.0E+1 cpm FHB Vent Exh 2.2E+1 OG Carbon Bed Vault A 6.OE+1 mR/hr CR Vent Exh 2.0E+1 B 5.5E+1 mR/hr fANEL P906 PANEL 803 Common Process and Area Eng Alarm , Turb Bldg East 2.5E+0 mR/hr UD-MH-73 East Liq 3.0E+1 Turb Bldg West 2.5E+0 mR/hr UD-MH-70 West Liq 3.2E+1 NCC Heat HX 3.5E+1 PANEL P804 Radweste to ESW 3.0E+1 Airborne Radiation Gas (coal Alarm Radweste to Sewage 3.6E+1 Annulus Exh A Gas QJEti! B 1 DE+1 j Cntet Atm Drywel1 - HR (R/hr) RJ@ METEOROLOGICAL CONDITIONS
' IJLig AB Vent g,DE+1 Wind Speed 'R L mph
- OGB Vent Exh 2 OEM Wind Direction 2h0 OGB Vent - HR DJLig Tempe ra tu re 38 *F OG Vent Pipe atD ;+g Delta T -0.85 *F U1 Plant Vent 6J :t1 i UI Plant Vent - HR TB/HB Vent SQQ+Q gJL 1 TB/HB Vent - HR 9.0010 ST Packing Exh b6L+Q 02 Plant Vent D OE_t1
, U2 Plant Vent - HR 0.0E+0 DW170C/A/21/ba O
Time: 1025 Message No.: 43 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Messaae For: Control Room /TSC Simulated Plant Conditions: ~See attached sheets Messame: ***THIS IS A DRILL *** i
, l ~
,j FOR CORTROLLER USE ONLY ? Controller Notes: .I Actions Expected: i' - . r, '.( 6 H DW176/C/43/ba i L r 4
+ ~
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a PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1025 P601 P660 CONTAINMENT PARAMETERS SYSTEM INFORMATION REACTOR PARAMETERS Tempera ture Pressure Pressure Flow Pressure 932 psig f*F1 fosial Status foslo) feoul Level -20 in. WR Cntet 90 0.1 RWCU PMP A SS Neutron DryweIi 120 .1 8 SS Mon 30 Range M HWL PMP A OP 230 Mode SW SHTDN Tempe ra ture Level f*F1 fft.1 8 OP 230 FDW F1w 4.6 Mib/hr Supe Pt 120 19.2__ C SS O ST F1w (Total) 4.6 Mlb/hr C8P A SS 150 Line A 0.9
.2 SYSTEMS INFORMATION Pressure Flow -
Status .fosiel faomi C SS 150 Line C 0.9 RHR A PMP OVRD RF8P A OP 330 Line 0 1.8 8 VLV OVRD 275 8 OP 330 C VLV OVRD 275 C SS 160 LPCS PMP OVRD SR D SS 160 RCIC SR RFP A OP 1000 MJ K HPCS SR 8 SS 0 0 l ECC A 00S MFP SR 0 0 TUR8 ige-CEgfRATOR 8 OP 114 RCIRC A SS 0 PARAMETERS ESW A 00S S SS 0 Mwatt 375 MAJOR VALVE PARAMEfERS C OP 95 CNDR Vac 28 in. Hg , Status Close:I Open MSIV NORM O 8 8 SS SYP VLV l SRV NORM 19 0 Posit O % SLC A OP 1600 8 OP 1600 l SLC STG TK LVL 4600 gal. e
\
6
r -. ..w.- , , - PERRY NUCLEAR POWER PLANT 1984 EMERCENCY PREPAREDNESS EXERCISE TIME: 1025 CONTROL ROOM ANNUNCIATORS P601/P877 P680 P870 & BACK PANELS Section 20A 'Section SA CONT RM HVAC
'EMERC RCIRC A .
SUPP POOL MANUAL SCRAM INITIATED P904 LEVEL A HIGH SWITCH ARMED CONT RM !*VAC SUPP POOL RPS LOCIC EMERG RCIRC B TEMP A HICH MANUAL SCRAM INITIATED P904 Section 17A RRCS MAN INITIATION SUPP POOL LEVEL B HICH RPS LOW LEVEL L-3 SUPP POOL
# TEMP B HICH Section 19A ADS B PERMISSIVE RHR B/C RUN ADS A PERMISSIVE RPV L-3 ADS B PERMISSIVE RPV L-3 DW1708/A/62/es 9
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PERRY NUCLEAR POWER PLANT. 1984 EMERCENCY PREPAREDNESS EXERCISE TIME: 1025 fRIA ELECTRICAL DISTRIBUTION 22Rg CST Level 410.000 cal. _ Status- Load fMWI Status Status foslo) OFFsite Pwr Sources 2 AV Cont Rm HVAC SuptFan A OP TBCC PMP A OP 75 Can Breakers 2 CL
~
B OP B OP 75 Div 1 DG OOS Cont Rm HVAC Rtn Fan A SS C SS 18 Div 2 DG OP O B SS SA Comp OP 128 Div 3 DG OP S Cont Re Eng RCIRC Fan A OP BA Comp SR 120 8 OP fA00 - CIRW PMP A OP 46 Status f210 B OP 45 Cntet Vs1 Cig Fan A OP Pressu re , Status losial C OP 46 B OP NCC Pump A SS 35 SJAE A OP C SS B SS 35 B SS D OP C OP 112 E OP ADDITIONAL 1NFORMATION SW Pump A OP 56 F SS Status Abbreviations: B OP 56 Drywe11 Cooling Fan 1A OP OP Ope ra t ing C SS O 2A OP SS Secured Status D SS O 3A OP AV Available MTR Fire Pump _ SR 18 SS SR Standby Readiness DD Fi re Pump SR 28 SS SHTDN Shutdown
. 3B SS S-SP Slow Speed Cntet Vsl Purge Supp Fan A SS F-SP Fast Speed B SS ISOL isolated Cntet Vsl Ar DW Purge Exh Fan A SS NORM No raa 1 B SS OOS Out of Service Drywell Purge Suppl Fan A SS CL Closed B SS OVRD Override AEGTS Fan A OOS B OP i
AREA RADIATION MONITORS Time: 1025 TAG # LOCATION READING (mR/hr) 1D21NO30 Personnel Air Lock, Cntmt (600'6") 5.0E+0 1D21N040 CRD HCU West, Cntmt (620'6") 5.0E+0 1D21N050 RBRT Area, Cntmt (642') 1.0E+2 1D21N060 Tip Drive Area, Cntmt (600'6") 3.0E+1 1D21N070 RWCU F/D Area, Cntmt (664'7") 7.0E+0 1D21N080 Upper Pool Area, Cntmt (689'6") 2.0E+0 1D21N110 A'tx Bldg East (574'10") 7.0E+0 1D21N120 Aux Bldg West (574'10") 7.0E+0 1D21N130 Turb Rm East (647'6") 2.5E+0 1D21N140 CRD HCU East, Cntmt (620'6") 5.0E+0 1D21N160 Turb Rm West (647'6") 2.5E+0 1D21N170 Turb Bldg (605'6") 2.5E+0 1D21N180 Hotwell Pump Area, TB (577'6") 1.0E+1 1D21N190 TB Sump Area, TBC (548'6") 2.0E+1 1D21N200 OGB (584') 1.1E+1 i 1D21N210 Cnds Fitr Pmp Area, TBC (568'6") 9.0E+0 1D21N220 OG After F1tr Area, OGB (602'6") 2.0E+1 , ID21N230 HP Fdw Her Area, HB (600'6") 1.0E+1 j 1D21N240 Fdw Pump Area, HB (647'6") 6.6E+0 , ID21N400 CR, CC (654'6") 1.6E-1 j~ ID21N410 OG Hold Up Area, TB (577'6") 1.0E+1
- D21N250 RWB West (574'10") 2.5E+1 D21N260 RWB East (574'10") 1.5E+1 D21N270 RWB (602') 5.0E+0 D21N280 Process Sample Rm, RWB (623'6") 4.0E+0
,i D21N290 RW Evap, RWB (623'6") 4.0E+0 D21N310 FPCU F/D Area, IB (599') 6.0E+0 ! D21N320 Fuel Preparation Pool, IB (620'6") M f. GE+ 6 e D21N330 Spent Fuel Storage Pool, IB (620'6") M 00E+0 8 D21N420 FPCU Cire Pmp Area, IB (574'10") 9.0E+C 1D21N340 Unit 1 DW, Portable, Cntmt (655') - D21N380 Waste Ccsmpactor Area, RWB (623'6") 6.0E+1 D21N370 SRW Drumming Area, RWB (623'6") 6.0E+0 1D21N090 Refueling Bridge, Cntmt (689'6") 3.0E+0 D21N390 Fuel Serv Hdig Platform, IB (620'6") 6 S dE+0 9
* = Alarm OS = Offscale s
y , _ _ - _ _ y- _ _ _ _ PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPARE 0 NESS EXERCISE TIME: 1025 PANEL P604 PANELS P669. P670. P671. P672 Process Radiation Main Steam Line RA0 7.0E+1 mR/hr AlHE Orrgas Pre-treatment 2.5E+1 R/hr Orrgas Post-treatment A. 2 0E+2 cp: PANEL P902 8 R E t2 cpe Common Airborne Gas (com) Alarm Eng Service Water A 3.0E+1 cpa RWB Vent Exh 2.0E+1 8 3.0E+1 cpm FHS Vent Exh 2.2E+1 OG Ca rbon Dad Vaul t A 6.0E+1 mR/hr CR Vent Exh 2.0E+1 8 Li[11 mR/hr PANEL P906 PANEL 803 Common Process and Area' Egg Ala rm Turb Bldg East 2.5E+0 mR/hr UD-MH-73 East Liq 3.0E+1 Turb Bldg West 2.5Et0 mR/hr UD-MH-70 West Liq 3.2E+1 NCC Heat HX 3.5E+1 PANEL P804 Radweste to ESW 3.0E+1 Airborne Radiation Gas (com) Alarm Radweste to Sewage 3.6E+1 Annulus Exh A Gas Q2Dld 8 LQ 11 Cntet Atm LQ $ METEOROLOGICAL CON 01TlONS Drywell - HR (R/hr) LQ ;10 ' A8 Vent LQE.11_ Wind Speed 8.0 mph 250
- OG8 Vent Exh LQf12 Wind Direction OG8 Vent - HR Q10Lig Temporature La *F
-OG Vent Pipe L Q1 3 Delta T -0.85 'r U1 Plant Vent 620W -
U1 Plant Vent - HR 0201M TB/HB Vent LD11 TB/HB Vent - HR QJE +0 ST Packing Exh LSE+Q U2 Plant vent (tiQE11 U2 Plant Vent - HR 0.0E+0 4 DW170C/A/22/es O F
~., .
4 . . Time: 1030 Message No.: 44 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE , MESSAGE FORM i Messase For: Contro1~ Room /TSC Simulated Plant Conditions: See attached sheets Messame: ***THIS IS A DRILL *** 1 [ t' y. ( f- ,
}.
?( i
}
FOR CONTROLLER USE ONLY Controller Notes: Actions Expected: The Emergency Coordinator should declare a SITE AREA EMERG3NCY
! (EPI-A1, Section D.III.2, " Complete loss of any functions needed for plant hot shutdown").
- 1. Inplement EPI-A4, SITE AREA EMERGENCY.
b.
- 2. Make notifications.
l -3. Activate the EOF and JPIC. j.,;
- 4. Assess the situation.
l1 S. Activate Radiation Monitoring Teams in accordance wi:h EPI-B3. i, L [ DW176/C/44/ba c h I I '. b '% '* s
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i, . S fy 'p ,} f PERRY NUCLEAR POWER PLANT 1984 EMERCENCY PREPAREDNESS EXERCISE . TIME: 1030 t 1 P601 " .- P680 '
* ' ' ' - y , ,1 1
CONTAINMENT PARAMETERS' ,- SYSTEM INFORMATION ; ,, REACTOR PARAMETERS Tempe ra ture Pressu re Pressure Flow Pre ssure 930 pelg (*F1 losial Statug_ fosial local - Level '
' 50 in. WR Cntet 92 0.3 RWCH PMP A SS O Neut ron Drywell 122 . 0.1 B SS 0 Mon 23 Range APRM HWL PMP A OP 230 Mode SW SHTDN e-Tempe rature Level i*F1 iFt.I B OP 230 FDW Flw 3. 5 ' Mlb/hr ,
Supr Pl 125 19.4 C SS O ST Flw (Total) 3.5 Mlb/hr CBP A SS 150 Line A 0.7 SYSTEMS INFORMATION B SS 150 Line 8 0.7 Pressure Flow Status losial faomi C SS 150 Line C 0.7 RHR A fMP OVRD RFBP A OP 330 Line D 1.6 8 SP CLC 250 7000 B OP 330 C VLV OVRD 275 0 C SS 160 LPCS PHP OVR.g D SS 160 RCIC FLW OVRD 500 0 RFP A. OP 1000 IJ K HPCS VLV OVRD 900 ' O B SS 0 0 ECC A 00S MFP SR 0 0 TURBINE-CENERATOR 8 OP 114 RCIRC A SS 0 PARAMETERS ESW A 00S B SS 0 Mwatt 288 8 OP 95
- MVAR 20 MAJOR VALVE PARAMETERS C OP 95 CNDR Vac 28 in. Hg Ittitus Closed open
.MSIV NORM O 8 B SS BYP VLV SRV NORM 19 0 Posit 0 % -
SLC A OP 1600 S OP 1600 SLC STG TK LVL 4600 gal. O e
, ' i: . . .,; _ . .a --.
PERRY NUCLEAR POWER PLANT ~ 1984 EMERCENCY PREPAREDNESS EXERCISE TIME: 1030 CONTROL ROOM ANNUNCIATORS P601/P877 P680 P870 h BACK PANELS Section 20A Section 5A CONT RM HVAC EMERC RCIRC A SliPP POOL MANUAL SCRAM INITIATED P904 LEVEL A HICH SWITCH ARMED CON) RM HVAC SUPP POOL ' RPS LOGIC EMERG RCIRC B TEMP A HICH MANUAL SCRAM INITIATED P904 Section 17A RRCS MAN INITIATION SUPP POOL LEVEL B HICH RPS LOW LEVFL L-3 SUPP POOL TEMP B HICH RRCS RX LEVEL Section 19A LO L-2 ADS B PERMISSIVE RHR B/C RUN ADS A PERMISSIVE RPV L-3 ADS B PERMISSIVE RPV L-3 . DW1708/A/65/es 9
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PERRY NUCLEAR POWER PLANT' 1983: EMERGENCY PREPAREDNESS EXERCISE- TIME -1030 ERIQ [LECTRICAL DISTAL)UTION E2Q81 CST Level 410.000 cal. Status Load fMW1 Status Status fosial OFFsite Pwr Sources 2 AV Cont Rm HVAC Supp Fan A OP TBCC PMP A OP 75 Con Breakers 2 CL B OP B OP 75 Div 1 DG OOS Cont Rm HVAC Rtn Fan A SS C SS 18 Div 2 DG OP O 8 SS SA Comp OP 128 Div 3 DG OP O Cont Rm Eng RCIRC Fan A OP IA Comp SR 120 8 OP fAQQ CIRW PMP- A OP 46 Status 29.10 8 OP 45 Cntet Vs1 Cig Fan A OP Pressu re Status losial C OP 46 B OP NCC Pump A SS 35 SJAE A OP C SS
'B SS 35 B SS D OP C OP 112 E OP ADOIT10NAL 1NFORMATION SW Pump A OP 56 F SS Status Abbreviations: 8 OP 56 Drywe1I Coo 1Ing Fan IA OP OP Ope ra t ing C SS 0 2A OP SS Secured Status D SS 0 3A OP AV Available MTR Fire Pump SR 18 SS SR Standby Readiness DD Fire Pump SR 28 SS SHTDN Shutdown 3B SS S-SP Slow Speed Cntet Val Purge Supp Fan A SS F-SP Fast Speed 8 SS ISOL 1solated Cntet Vsl ar DW Purge Exh Fan A SS NORM Normal B SS 00S Out, of Service Drywell Purge Suppl Fan A SS
- CL Closed B SS OVRD Ove rride
- AECTS Fan A 00S-
- B OP O
e AREA RADIATION MONITORS Time: 1030 TAG # LOCATION READING (mR/hr) 1D21NO30 Personnel Air Lock, Cntmt (600'6") 5.0E+0 1D21N040 CRD HCU West, Cntmt (620'6") 5.0E+0 ., 1D21N050 RBRT Area, Cntmt (642') 1.0E+2 1D21N060 Tip Drive Area, Cntmt (600'6") 3.0E+1 1D21N070 RWCU F/D Area, Cntmt (664'7") 7.0E+0 1D21N080 Upper Pool Area, Cntmt (689'6") 2.0E+0 j 1D21N110 Aux Bldg East (574'10") 7.0E+0 j 1D21N120 Aux Bldg West (574'10") 7.0E+0 1D21N130 Turb Rm East (647'6") 2.5E+0 ID21N140 CRD HCU East, Cntmt (620'6") 5.0E+0 1D21N160 Turb Rm West (647'6") 2.5E+0 1D21N170 Turb Bldg (605'6") 2.5E+0 1D21N180 Hotwell Pump Area, TB (577'6") 1.0E+1 1D21N190 TB Sump Area, TBC (548'6") 2.0E+1 1D21N200 OGB (584') 1.1E+1 1D21N210 Cnds F1tr Pmp Area, TBC (568'6") 9.0E+0 1D21N220 OG After Fitr Area, OGB (602'6") 2.0E+1 1D21N230 HP Fdw Her Area, HB (600'6") 1.0E+1
; 1D21N240 Fdw Pump Area, HB (647'6") 6.6E+0 l 1D21N400 CR, CC (654'6") 1.6E-1 t
1D21N410 OG Hold Up Area, TB (577'6") 1.0E+1 D21N250 RWB West (574'10") 2.5E+1 D21N260 RWB East (574'10") 1.5E+1
< D21N270 RWB (602') 5.0E+0 , D21N280 Process Sample Rm, RWB (623'6") 4.0E+0 -j D21N290 RW Evap, RWB (623'6") 4.0E+0 D21N310 FPCU F/D Area, IB (599') 6.0E+0 D21N320 Fuel Preparation Pool, IB (620'6") M t/.dE 46 #
D21N330 Spent Fuel Storage Pool, IB (620'6") M 4.dE+v e D21N420 FPCU Cire Pmo Area, IB (574'10") 9.0E+0 1D21N340 Unit 1 DW, Portable, Cntmt (655') - D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1 D21N370 SRW Drumming Area, RWB (623'6") 6.0E+0 1D21N090 Refueling Bridge, Cntmt (689'6") 3.0E+0 D21N390 Fuel Serv Mdig Platform, IB (620'6") 6 3.g D e 9
* = Alarm OS = Offscale
PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS ENERCISE TIME: 1030 PANEL P604 PANELS P669. P670. P671. P672 Process Radiation Hein Steam Line RAD 7.0E+1 mR/hr-8.LUE Cntet Vent Exh RAD c1.0E-1 mR/hr Orrgas Pre-treatment 2.5E+1 R/hr , Orrgas Post-treatment A 2.0E+2 cpm PANEL P902 s B 2.0E+2 cpm Common Airborne Gas Icom) AIare Eng Service Water A 3.0E+1 cpm RW8 Vent Exh 2.0E+1 8 3.0E+1 cpm FHS Vent Exh 2.2E+1 OG Ca rbon Bed Vaul t A 6.0E+1 mR/hr CR Vent Exh 2.0E+1 B 5.5E+1 mR/hr PANEL P906 PANEL 803 Common Process and Area gas. Ala re Turb Bldg East 2.5E+0 mR/hr UD-MH-73 East Lig 3.0E+1 Turb Bldg West 2.5E+0 mR/hr UD-MH-70 West Liq- 3.2E+1 NCC Heat HX 3.5E+1 PANEL P804 Radweste to ESW 3.0E+1 Airborne Radiation Gas (coal Alarm Radweste to Sewage 3.6E+1 Annulus Exh A Cas QJEM B L QE;ti Cntet Atm EJ E_+2 METEOROLOGICAL CONOITIONS Dryvell - HR (R/hr) IJf+Q _ AB Vent R Of_t1 Wind Speed 17.5 mph 230
- OC8 Vent Exh 2.,QE+2 Wind Direction OC8 Vent - HR QJf.ig Tempe ra tu re 40 *F OG Vent Pipe gJIM Delta T -1.02 *F U1 Plant Vent 6JI;+1 U1 Plant Vent - HR Q.,0 M TB/HB Vent L D{ti 18/HB Vent - HR QJf.iQ ST Packing Exh 3dE1Q U2 Plant Vent LQf_11 U2 Plant Vent - HR 0.0E+0 DW170C/A/23/es l
r . 5 Time: 1035 Message No.: 45-PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM
~
- Messaae For: Control Room /TSC Simulated Plant Conditions: See attached sheets i
Messame: ***THIS IS A DRILL *** , s 5 i FOR CONTROLLER USE ONLY
?. . Controller Notes:
l Actions Expected: i.- DW176/C/45/ba 1 t r I^ F i
c.. a . .i.. eu .. nd.a :.. .. : - :.
.>.~ -. . .2... .
< r si , - - n.. .. C . . . .
PERRY NUCLEAR POWER PLANT' 1984 EMERCENCY PREPAREDNESS EXERCISE TIME: 1035 fnR1 P680 CONTAINMENT PARAMETERS SYSTEM INFORMATION REACTOR PARAMETERS Tempe ra ture Pressu re Pressure Flow Pressure 927 psig I'Fl fosiel_ Status foslo) feoel Level -80 in. WR Cntet 95 0.4 RWCU PMP A SS 0 Neut ron Drywell 134 0.4 8 SS O Mon 18 Range efftj HWL PMP A OP 230 Mode SW SHTDN Tempera ture Level f*F1 fft.1 8 OP 230 FDW Flw 2.8 Mib/hr Sup r P t 130 19.6 C SS O $7 F1w (Totel) 2.8 Mlb/hr. C8P A SS 150 Line A O.5 SYSTEMS INFORMATION 8 SS '150 Line 8 0.5 Pressure Flow Status losiel feos). C SS 150 Line C 0.5 RHR A PMP OVRD RFBP A OP 330 Line D 1.5 8 SP CLC 250 7000 8 OP 330 , C VLV OVRD 275 0 C SS 160 LPCS PHP OVRD D SS 160 RCIC FLW OVRD 500 0 RFP A OP 1000 ELV 4 HPCS VLV OVRD 900 0 8 SS O O ECC A 00S MFP SR 0 0 IM!!Ellf[-Q[MERATOR 8 OP 114 RCIRC A SS O PARAMETERS ESW A 00S 8 SS 0 Mwatt 225 8 OP 95 MVAR 10 MAJOR VALVE PARAMETERS C OP 95 CNDR Vac 28 in. Hg Status Closed Open CRD A SS Thrt Pr 925 psig MSIV NORM 0 8 8 SS .. 8YP VLV SRV NORM 19 0 Posit 0 1 SLC A OP 1600 - B OP 1600 SLC STG TK LVL 4600 gal. 9 e e
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- 7 PERRY NUCLEAR POWER PLANT. 198s EMERGENCY PREPAREDNESS EXERCISE TIME: 1035 CONTROL ROOM ANNUNCIATORS ,
P601/P877 P680 P870 4 BACK PANELS Section 20A Section 5A' CONT RM HVAC EMERG RCIRC A SUPP POOL MANUAL SCRAM INITIATED P904 LEVEL A HIGH SWITCH ARMED CONT RM HVAC SUPP POOL RPS LOGIC EMERG RCIRC B TEMP A HIGH MANUAL SCRAM INITIATED P904 Section 17A RRCS MAN INITIATIDN SUPP POOL LEVEL B HICH RPS LOW LEVEL L-3 SUPP POOL TEMP B HICH RRCS RX LEVEL Section 19A , LO L-2 ADS B PERMISSIVE RHR B/C RUN ADS A PERMISSIVE RPV L-3 ADS B PERMISSIVE RPV L-3 DW1708/A/68/es
- e
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- - - ~ - .u. ...,-2. --
PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1035 RX WATER LEVEL RX PRESS RX POWER SUPR PL TEMP
' -80 jj WR 927 PSIG 18 7 130 'f 60- 1100- 120- 110 -
45- 950- 90- 90-30- 800- 40- 70-15- 650- 0 50 0 500 -30 -20 -10 0 -30 -20 -10 0
, -30 -20 -10 0 -30 -20 -10 0 Time (min) Time (min)
Time (min) Time (min) DW TEMP CONTMT TEMP CONTMT PRESS SUPR PL LEVEL 134 'f 95 'f 0.4 f_fLC 19.6 FT 200- 110- 20- 19-l 150- 90- 15- -
/
100- 70- 10- 18- - 50 50- 5- -
-30 -20 -10 0 -30 -20 -10 0 0- 17 i
.9e (min) Time (min) -5 -30 -20 -10 0
-30 -20 -10 0 Time (min)
Time (min) d e o e
,,,g-....
- . . :. t ?., . w.. ,. 7 .. ..- .
...y- ., . ,, .;..---..
PERRY NUCLEAR POWER PLANT -1984 EMERCENCY PREPAREDNESS EXERCISE TIME: 1035 P870 ELECTRICAL DISTRIBUTION P904s CST Level 410.000 aal. Status Load fMWI Status Status fosiG) Offsite Pwr Sources 2 AV Cont Rm HVAC Supp Fan A OP TBCC PMP A OP 75 Con Breakers 2 CL 8 OP 8 OP 75 Div 1 DC OOS Cont Rm HVAC Rtn Fan A~ SS C SS 18 . Div 2 DC OP O 8 SS SA Comp OP 128 Div 3 DG OP O Cont Rm Eng RCIRC Fan A OP IA Comp SR 120 8 OP P800 CIRW PMP A OP 46 Status P970 8 OP 45 Cntet Vsl Cig Fan A OP Pressure Status (psiel C OP 46 8 OP NCC Pump A SS 35 ! SJAE A OP C SS 8 SS 35 , 8 SS D OP C OP 112 a E OP ADDITIONAL INFORMATION SW Pump A OP 56 F SS Status Abbreviations: 8 OP 56 Drywell Cooling Fan 1A OP OP Ope ra t ing C SS 0 2A OP SS Secured Status D SS 0 3A OP AV Available MTR Fire Pump SR 18 SS SR Standby Readiness DD Fire Puep SR 28 SS SHTDN Shutdown 38 SS S-SP Slow Speed Cntet Vs1 Purge Supp fan A SS F-SP Fast Speed 8 SS ISOL isolated Cntet Val & DW Purge Exh Fan A SS 8 SS 00S Out of Service Drywe l l Purge .l Suppl Fan A SS CL Closed , 8 SS ! OVRD Ove rride AEGTS Fan A OOS i 8 OP 0
1 l AREA RADIATION MONITORS Time: 1035 TAG # LOCATION READING (mR/hr)
, ID21NO30 Personnel Air Lock, Cntmt (600'6") 5.0E+0 1D21N040 CRD HCU West, Cntmt (620'6") 5.0E+0 1D21N050 RBRT Area, Cntmt (642') 1.0E+2 1D21N060 Tip Drive Area, Cntmt (600'6") 3.0E+1 1D21N070 - RFCU F/D Area, Cntmt (664'7") 7.0E+0 1D21N080 Upper Pool Area, Cntmt (689'6") 2.0E+0 1D21N110 Aux Bldg East (574'10") 7.0E+0 1D21N120 Aux Bldg West (574'10") 7.0E+0 1D21N130 Turb Rm East (647'6") 2.5E+0 1D21N140 CRD HCU East, Cntmt (620'6") 5.0E+0 l ID21N160 Turb Rm West (647'6") 2.5E+0 1D21N170 Turb Bldg (605'6") 2.5E+0 l ID21N180 Hotwell Pump Area, TB (577'6") 1.0E+1 l 1D21N190 TB Sump Area, TBC (548'6") 2.0E+1 !
1D21N200 OGB (584') 1.1E+1 l 1D21N210 Cnds F1tr Pmp Area, TBC (568'6") 9.0E+0 1D21N220 OG After Fitr Area, OGB (602'6") 2.0E+1 l 4 1D21N230 HP Fdw Htr Area, HB (600'6") 1.0E+1 1 1D21N240 Fdw Pump Area, HB (647'6") 6.6E+0 1 1D21N400 CR, CC (654'6") 1.6E-1 1D21N410 OG Hold Up Area, TB (577'6") 1.0E+1 D21N250 RWB West (574'10") 2.5E+1 D21N260 RWB East (574'10") 1.5E+1 D21N270 RWB (602') 5.0E+0 D21N280 Process Sample Rm, RWB (623'6") 4.0E+0 D21N290 RW Evap, RWB (623'6") 4.0E+0 i D21N310 FPCU F/D Area, IB (599') 6.0E+0 D21N320 Fuel Preparation Pool, IB (620'6") M K FE+0 # D21N330 Spent Fuel Storage Pool, IB (620'6") M Sct+6 # D21N420 FPCU Cire Pmp Area, IB (574'10") 9.0E+0 1D21N340 Unit 1 DW , Portable, Cntmt (655') - D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1 D21N370 SRW Drumming Area, RWB (623'6") 6.0E+0 1D21N090 Refueling Bridge, Cntmt (689'6") 3.0E+0 D21N390 Fuel Serv Hdig Platform, IB (620'6")- 6 3. peed 8 l l .e l l
* = Alarm OS = Offscale
. , _ . m m._,m ., o ;,_ . . , , _ ,, . , , , , ,
PERRY HUCLEAR POWER PLANT 1984 EMERGEllCY PREPAREDilESS EXERCISE T'IME: '1035 PAllEL P604 28HELS P669. P670. P671. P672 Process Radiation Main Steam Line RAD 7.0E+1 mR/hr Ala re Cntet Vent Exh RAD 41.0E-1 mR/hr Offges Pre-treatment ,2.5E+1 R/hr j . Offges Post-treatment A 2.0E+2 cpm PAllEL P902 8 2.0E+2 cpm Common Airborne Gas (coal Alarm Eng Service Water .A 3.0E+1 cpm RWB Vent Exh 2.OE+1 8 3.0E+1 cpm FHS Vent Exh 1 2E+1 OG Carbon Bed Vault A 6.0E+1 mR/hr CR Vent Exh 2 OE+1 8 5.5E+1 mR/hr PANEL P906 PANEL 803 Common Process and Area Egg Alare
' ~
Turb Bldg East 2.5E+0 mR/hr UD-MH-73 East Lig 3.0E+1 i Turb Bldg West 2.5E+0 mR/hr UD-MH-70 West Liq 3.2E+1
- NCC Heat HX 3.5E+1 PANEL P804 Radweste to ESW 3.0E+1 Airborne Radiation Gas (" coni Alare Radweste to Sewage 3.6E+1 l Annulus Exh A Gas LDE+Q l- B bDL+1 i Cntet Ata LJE12 METEOROLOGICAL CONDITIONS
. Drywell - HR (R/hr) 1 DEig AB Vent LQE11 Wind Speed 17.5 yh OC8 Vent Exh 2JE12 Wind Direction 230 OG8 Vent - HR QJW Tempe ra ture 40 *F
- OG Vent Pipe 2JW Delta T -1.02 *F U1 Plant Vent (gJ!;1],
U1 Plant Vent - HR OJ!M! TB/HB Vent (t 0[1]. l TS/HB Vent - HR g O L+1! , ST Packing Exh LBEM l U2 Plant Vent 6JL11 _ i i U2 Plant Vent - HR 'O.0E+0 i I . f DW170C/A/24/es i l j
Time: 1040 Message No.: 46 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE
- MESSAGE FORM Messane For: Control Room /TSC Simulated Plant Conditions: See attached sheets Massame: ***THIS IS A DRILL ***
3-t
'ge i'
+ ;.
- j. .
[ FOR CONTROLLER USE ONLY Controller Notes: Actions Expected: J f g,
- DW176/C/46/ba r 6 e
a
.++.e , - - -o -e- -, - ---%v- *.my-,- --w.cgg,-- -,n-,97,+ . .ry-m-,,-,y w ,,y,.yyy, g pp,--t, ., --y,- -w,.4- q ,m,r-g w wy-.
. . . . :.;.....w- ..:Lv..-:.. .~ .- ,...:.w. ~ ..- -... . s ... . .L; '. . . ,,
PERRY NOCLEAR POWER PLANT 1984 EMERCENCY PREPAREDNESS EXERCISE TIME: 1040 Et01 NtAQ CONTAINMENT PARAMETERS SYSTEM INFORMATION . REACTOR PARAMETERS Tempe ra ture Pressure Pressure Flow Pressure 925 psig. f*F1 foslel Status fosial feoul Level '-100 in. WR Cntet 98 0.5 RWCU PMP A SS O Meutron Drywell 139 0.9 8 SS 0 Mon 14 Range APRM HWL PMP A OP 230 Mode SW SHTDN Tempe ra ture Level f*F1 fft.1 B OP 230 FDW Flw 2.2 Mib/hr Sup r P t 132 19.8 C SS O ST Flw (Total) 2.2 Mib/hr
, C8P A SS 150 Line A .3 SYSTEMS INFORMATION 8 SS 150 Line 8 .3 Pre s su re Flow Status fosial. feoel C SS 150 Line C .3 RHR A PMP OVRD RFBP A OP 330 Line D 1.2 8 SP CLC 250 7000 8 OP 330 C VtV OVRD 275 0 C SS 160 LPCS PMP OVBD D SS 160 RCIC FLW OVRD 500 0 RFP A OP 1000 PK HPCS VLV bVRD 900 O 8 SS O O ECC A DOS MFP SR 0 0 IUBBIME-C[MERATOR B OP 114 RCIRC A SS 0 PARAMETERS ESW A 00S 8 SS 0 Mwatt 225 B OP 95 MVAR 10 MAJOR VALVE PARAMETERS C OP 95 CNDR Vac 28 in. Hg Status Closed Open CRD A SS ' Thrt Pr 924 psig MSIV NORM 0 8 8 SS BYP VLV SRV NORM 19 0 Posit 0 %
SLC A OP 1600 8 OP 1600 SLC SIG TK LYL 4600 gal.
.: ;1' . _ . ~O. A a. , _ . " . J *, wa: L2 ._ . - -J.- r_ ; - w.. e m . - , - -
q W PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDIIESS EXERCISE TIME: 1040 CONTROL ROOM AIIIIUIICf ATOL P601/P877 P680 P870 as BACK PANELS SectIon 20A SectIon 5A C000T RM MVAC EMERG RCIRC A SUPP POOL MAleUAL SCRAM INITIATED P904 -
; LEVEL A HIGH SWITCH AHMED SUPP POOL ; RPS LOGIC CollT RM HVAC TEMP A HIGH MA100AL SCRAM EMERG RCIRC 8
. INITIATED P904
! CONTAlleMENT RRCS MAN PRESS A HIGH INITIAT1000 DRYWELL RPS LOW LEVEL PRESS A HIGH L-3 Section 17A RRCS RX LEVEL SUPP POOL LO L-2 LEVEL 8 HIGH l SUPP POOL TEMP & HIGH CONTA180 MENT
- PRESS S HIGH ._
~
~.
l DRYWELL PRESS B HIGH Section 19A ADS B PERMISSIVE . RHR B/C RUN ! ADS A PERMISSIVE 3 RPV L-3 , ADS B 1 PERMISSIVE l RPV L-3 i l DW1708/A/71/es i I
'..~'_s,a_..'.._.. n2' ...1, ^.. L a.J w a ,. -.. a ..- 4/. a _1. _-- .c._:..V.. ;.- . . a ~ ,c.t.2 , .
PERRY NUCLEAR POWER PUUIT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1040 RX WATER LEVEL RX PRESS RX POWER SUPR PL TEMP
-100 D WR 925 filf 14 j' 132 'T 60- 1100- 123- 110 i
45- 950- 90- 90-30- 800- 40- 70-15- 650- G 50
, 0 500 -30 -20 -10 0 -30 -20 -10 0
-30 10 0 -30 -20 -10 0 Time (min) Time (min) e Time (min) Time (min)
DW TEMP CONTMT TEMP CONTMT PRESS SUPR PL LEVEL 139 *f 98 'f 0.5 PSIG 19.8 IJ 200- 110- 20 . 19-150- 90- 15- -
/
100- 70- 10- 18-50 50- 5- -
-30 -20 -10 0 -30 -20 -10 0 0- IT Time (min) Time (min) -5 -30 -20 -10 0
-30 -20 -10 0 Time (min)
Time (min) 9
=
h.
PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDelESS EXERCISE TIME: 1040 f1ZQ EtECTRICAL DISTRIBUT10N P904 CST Level 410.000 cal. _ Status load fMWl' Status Status fosial 0FFsite Pwr Sources 2 AV Cont Rm HVAC Supp Fan A OP TBCC PMP A OP 75 Con Breakers 2 CL 8 OP B OP 75 Div 1 DG OOS Cont Rm HVAC Rtn Fan A SS C SS 18 Div 2 DG OP O 8 SS SA Comp OP 128 Div 3 DG OP O Cont Re Eng RCIRC Fan A OP IA Comp SR 120 < 8 OP CIRW PMP A OP 46 Status P970 8 OP 45 Cntet Val Cig Fan A OP . Pressure Status iosion C OP 46 8 OP NCC' Pump A SS 35 SJAE A OP C SS - 8 SS 35 8 SS D OP C OP 11L E OP ADDITIOttAL INFORMATION SW Pump 56 A OP F SS Status Abbreviations: 8 OP 56 Dr>veiI Coo lIng Fan 1A OP OP Ope ra t ing C SS O 2A OP SS Secured Status D SS O 3A OP Av Available MTR Fire Pump SR 18 SS SR Standby Readiness DD Fire Pump SR 28 SS SHTDN Shutdown 38 SS S-SP Slow Speed Cntet Vs1 Purge Supp Fan A SS F-SP Fast Speed 8 SS ISOL isolated Cntet Vs1 & DW Purge Exh Fan A SS NORM Normal 8 SS 00S Out or Service Drywell Purge Suppl Fan A SS CL Closed 8 SS OVRD Override AECTS Fan A 00S 8 OP
AREA RADIATION MONITORS Time: 1040 TAG # LOCATION READING (mR/hr) 1D21NO30 Personnel Air Lock, Cntmt (600'6") 5.0E+0 1D21N040 CRD HCU West, Cntmt (620'6") 5.0E+0 1D21N050 RBRT Area, Cntmt (642') 1.0E+2
, ID21N060 Tip Drive Area, Cntmt (600'6") 3.0E+1 1D21N070 RWCU F/D Area, Cntmt (664'7") 7.0E+0 1D21N080 Upper Pool Area, Cntmt (689'6") 2.0E+0 1D21N110 Aux Bldg East (574'10") 7.0E+0 1D21N120 Aux Bldg West (574'10") 7.0E+0
. ID21N130 Turb Rm East (647'6") 2.5E+0 1D21N140 CRD HCU East, Cntmt (620'6") 5.0E+0 1D21N160 Turb Rm West (647'6") 2.5E+0' 1D21N170 Turb Bldg _ (605'6") 2.5E+0 1D21N180 Hotwell Pump Area, TB (577'6") 1.0E+1 1D21N190 TB Sump Area, TBC (548'6") 2.0E+1 1D21N200 OGB (584') 1.1E+1 1D21N210 Cnds F1tr Pmp Area, TBC (568'6") 9.0E+0 1D21N220 OG After Fltr Area, OGB (602'6") 2.0E+1 1D21N230 HP Fdw Htr Area, HB (600'6") 1.0E+1 1D21N240 Fdw Pump Area, HB (647'6") 6.6E+0
. 1D21N400 CR, CC (654'6") 1.6E-1 ; 1D21N410 OG Hold Up Area, TB (577'6") 1.0E+1 D21N250 RWB West (574'10") 2.5E+1 D21N260 RWB East (574'10") 1.5E+1 D21N270 RWB (602') 5.0E+0 D21N280 Process Sample Rm, RWB (623'6") 4.0E+0 i D21N290 RW Evap, RWB (623'6") 4.0E+0 l D21N310 FPCU F/D Area, IB (599') 6.0E+0 D21N320 Fuel Preparation Pool, IB (620'6") M Mdftf
- i D21N330 Spent Fuel Storage Pool, IB (620'6") M ycf+0
- D21N420 FPCU Cire Pmp Area IB (574'10") 9.0E+0 1 1D21N340 Unit 1 DW, Portable, Cntmt (655') -
D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1 D21N370 SRW Drumming Area, RWB (623'6") 6.0E+0 1D21N090 Refueling Bridge, Cntmt (689'6") 3.0E+0 D21N390 Fuel Serv Hdig Platform, IB (620'6") 6 3.v E+ 0 8 4
* = Alarm OS = Offscale
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. 9 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1040 PANEL P604 PANELS P669. P670. P671. P672 Process Radiation Main Steam Line RAD 7.0E+1 mR/hr Alarm Cntet Vent Exh RAD 41.0E-1 mR/hr Offgas Pre-treatment 2.5E+1 R/hr 2 '
Offgas Post-treatment A 2.0E+2 cpm PANEL P902 8 2.0E+2 cpm Common Airborne Gas (com) Ala re Eng Service Water A 3.0E+1 cpm RWB Vent Exh 2.0E+1 8 3.0E+1 cpm FHS Vent Exh 2.2E+1 OG Carbon Bed Vault A 6.0E+1 mR/hr CR Vent Exh 2.0E+1 8 5.5E+1 mR/hr PANEL P906 PANEL 803 Common Process and Area Egg Ala rm Turb Bldg East 2.5E+0 mR/hr UD-MH-73 East Liq 3.0E+1 Turb Bldg West 2.5E+0 mR/hr UO-MH-70 West Liq 3.2E+1 NCC Heat HX 3.5E+1 PANEL P804 Radweste to ESW 3.0E+1 Airborne Radiation Gas (coal Alare Radwaste to Sewage 3.6E+1 Annulus Exh A Gas Q,0!;1Q 8 3,9!;11 . Cntat Ata 2J ;12 METEOROLOGICAL CONDITIONS Drywell - HR (R/hr) 1 D!;ig 4 AB Vent 2,GE11 Wind Speed 17.5 mph 0C8 Vent Exh 2,9Eig Wind Di rection __g}0
- 0C8 Vent - HR Q1D!;10 Tempe ra ture 40 *F OG Vent Pipe 2,0 ;12 Delta T -1.0.g_ *F q U1 Plant Vent 610l[11 U1 Plant Vent - HR Q,0 ;fD l 18/HB Vent 6,DE11 -
1 18/HB Vent - HR Q,DLiD i
, ST Packing Exh 11BL1Q l U2 Plant Vent 6,0[11 U2 Plant Vent - HR 0.0E+0
- DW17DC/A/25/es
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k Time: 1045 Message No.: 47 PERRY NUCLEAR POWER PLAffr 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Messane For: Control Room /TSC-
. Simulated Plant Conditions: See attached sheets , Messame: ***THIS IS A DRILL ***
L 4
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k FOR CONTROLLER USE ONLY i. 4 Controller Notes: '.3 . Actions Expected: l-L (- L J
- DW176/C/47/ba i
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PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1045 , fn21 f1AQ - CONTAIMMENT PARAMETERS SYSTEM INFORMATION REACTOR PARAMETERS Tempe ra ture Pressure P re s sure Flow Pre ssu re 924 psig f*F1 fosiel_ Status fosial faomi Level -130 in. WR Cntet 102 0.6 RWCU PMP A SS O Neutron Drywe l l 145 1.5 B SS O Mon 11 Range APRM HWL PMP A OP 230 Mode SW SHTDN Tempe ra tu re Level (*Fl (ft.) B OP 230 FDW Flw 1.7 Mlb/hr Supr PI 134 20 C SS O ST FIw (Total) 1.7 Mlb/hr CBP A SS 150 Line A .3 SYSTEMS INFORMATION B SS 150 Line B .3 Pressu re Flow Status fosial feoul C SS 150 Line C .3 RHR A PMP OVRD RFBP A OP 330 Line D .8 8 SP CLC 250 7000 B OP 330 C VLV OVRD 275 0 C SS 160 LPCS PHP OVRD D SS 160 RCIC FLW OVRD 500 0 RFP A OP 1000 /.J R HPCS VLV OVRD 900 0 B SS 0 0 ECC A DOS MFP SR 0 0 TURBINE-cIgERATOR B OP 114 RCIRC A SS O PARAMETERS ESW A DOS B SS 0 Mwatt 225 B OP 95 MVAR 10 MAJOR VALVE PARAMETERS C OP 95 CNDR Vac 28 in. Hg Status Closed Open CR0 A SS Thrt Pr 923 psig MSIV NORM 0 8 B SS BYP VLV SRV NORM 19 0 Posit O % SLC A OP 1600 8 OP '1600 SLC STG TK LVL 4600 gal. 9
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PERRY lluCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1045 CONTROL ROOM AINIUIICI ATORS P601/P877 P680 P870 & BACK PANELS Section 2GA Section 5A COIIT 3M HVAC EMERC RCIRC A SUPP POOL MAleUAL SCRAM INITIATED P904 LEVEL A HIGH SWITCH ARMED Colli RM HVAC SUPP POOL RPS LOGIC EMERG RCIRC 8 TEMP A HIGH MA000AL SCRAM INITIATED P904 CONTAIIIMENT RRCS MAN PRESS A HIGH INITIATION DRWELL RPS LOW LEVEL PRESS A !!GH L-3 Section 17A RRCS RX LEVEL SUPP POOL LO L-2 LEVEL 8 HIGH SUPP POOL TEMP B HIGH CONTAINMENT PRESS B HIGH DRWELL PRESS B HIGH Section 19A ADS 8 PERMISSIVE RHR B/C RUN ADS A ' PERMISSIVE RPV L-3 ADS B PERMISSIVE RPV L-3 DWl708/A/74/es W
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PflIItY NUCLEAR POWER PLAIIT 1984 EMEstGEIICY PREPAREDesESS EXERCISE TlpeE: 1045 P870 ELECTRICAL DISTRIBUTicle Pg04 CST Level 410.000 eat. Status Load flein Status Status fasiel Orrsite Pwr Sources 2 AV Cent fhe HVAC Supp Fan A- 0F TBCC P90P A OP 75 Gen Sreakers 2 CL B OP B OP 75 Div 1 DC 00S Cont its HVAC Rtn Fan A. SS C SS 18 Div 2 DG OP O B SS SA Comp OP 128 Div 3 DG OP O Cont its Eng RCIRC Fan A OP 1A Comp SR 120 8 OP 2000 CIRW PMP A OP 46 Status P970 8 OP 45 Cntet Vsl Cig Fan A OP Pressure Status 'fosial C OP 46 B OP i IICC Pump A SS 35 SJAE A OP C SS B SS 35 8 SS D OP C OP 112 E OP ADDIT 1000AL INF0ftMAT1016 SW Pump A OP 56 F SS Status Abbreviations: B OP 56 Drywell Cooling Fan IA OP OP Ope ra ting C SS O 2A OP SS Secured Status D SS 0 3A OP AV Avellable MTR Fire Pump SR
~ 18 SS SR Standby Readiness DD Fire Pump SR 28 SS SHTDN Shutdown 38 SS 5-SP Slow Speed Cntet Val Purge Supp Fan A SS F-SP Fast Speed B SS ISOL lsolated Catet Val & DW Purge Exh Fan A SS ItoftM storma l B SS DOS Out of Service Drywell Purge Suppl Fan A SS CL Closed 8 SS OVRO Ove rride AEGTS Fan A 00S 8 OP -
9
AREA RADIATION MONITORS Time: 1045 TAG # LOCATION READING (mK/hr) 1D21NO30 Personnel Air Lock, Cntmt (600'6") 5.0E+0 i 1D21N040 CRD HCU West, Cntmt (620'6") 5.0E+0 1D21N050 RBRT Area, Cntmt (642') 1.0E+2
, 1D21N060 Tip Drive Area, Cntmt (600'6") 3.0E+1 1D21N070 RWCU F/D Area, Cntmt (664'7") 7.0E+0 1D21N080 Upper Pool Area, Cntmt (689'6") 2.0E+0 1D21N110 Aux Bldg East (574'10")
- 7.tE+0 1D21N120 Aux Bldg West (574'10") 7.0E+0 1D21N130 Turb Rm East (647'6") 2.3E+0 1D21N140 CRD HCU East, Cntmt (620'6") 5.0E+0 i 1D21N160 Turb Rm West (647'6") 2.3E+0 1D21N170 Turb Bldg (605'6") 2.5E+0 1D21N180 Hotwell Pump Area, TB (577'6") 1.0E+1 1D21N190 TB Sump Area. TBC (548'6") 2.0E+1 1D21N200 OGB (584') 1.1E+1 1D21N210 Cnds F1tr Pmp Area, TBC (568'6") 9.0E+0 1D21N220 OG After Fitr Area OGB (602'6") 2.0E+1 1D21N230 HP Fdw Her Area, HB (600'6") 1.0E+1 I
1D21N240 Fdw Pump Area. HB (647'6") 6.6E+0 1D21N400 CR, CC (654'6") 1.6E-1 1D21N410 OG Hold Up Area, TB (577'6") 9.5E+0 D21N250 RWB West (574'10") 2.5E+1 D21N260 RWB East (574'10") 1.5E+1 D21N270 RWB (602') 5.0E+0 D21N280 Process Sample Rm, RWB (623'6") 4.0E+0 D21N290 RW Evap, RWB (623'6") 4.0E+0 1 D21N310 FPCU F/D Area. IB (599') 6.0E+0 I D21N320 Fuel Preparation Pool, IB (620'6") M 4'.0E+g e D21N330 Spent Fuel Storage Pool, IB (620'6") m f.vr+6 8 D21N420 FPCU Cire Pmp Area, IB (574'10") 9.0E+0 1D21N340 Unit 1 DW, Portable, Cntmt (655') - D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1 D21N370 SRW Drumming Area, RWB (623'6") 6.0E+0 1D21N090 Refueling Bridga, Cntmt (689'6") 3.0E+0 D21N390 Fuel Serv Hdig Platform, IB (620'6") - 6 3.dE*G #
* = Alarm OS = Offscale
3., ., . . - . ,.m. , , _ __ _ , _ __;___,_, _ PERRY 800 CLEAR POWER PLAllT 1984 EMERGENCY PREPAREDieCSS EXERCISE TIME: 1045 l fAKEL P604 PANELS P669. P670. P671. P672 Process Radiation Main Steam Line RAD 7.OE+1 mR/hr Alarm Cntet Vent Exh RAD 41.0E-1 mR/hr - Offgas Pre-treatment 2.5E+1 R/hr . Offges Post-treatment A 2.0E+2 cpm i PANEL P902 8 2.0E+2 cpm Common Airborne Gas (coal Ala re Eng Service Water A 3.0E+1 cpm RWB Vent Exh 2.0E+1 8 3.0E+1 cpm FHS Vent Exh 2.2E+1 OG Carbon Bed Vault A 6.OE+1 mR/hr CR Vent Exh 2.0E+1 8 5.5E+1 mR/hr j PANEL P906 PANEL 803 P-n Process and Area gem Alarm Turb Bldg East 2.5E+0 mR/hr UD-MH-73 East Liq 3.OE+1 Turb Bldg West 2.5E+0 mR/hr UC-MH-70 West Liq 3.2E+1 1 NCC Heat HX 3.5E+1 PANEL P804 Radwaste to ESW 3.0E+1 1 Airborne Radiation Cas (comi Alarm Radweste to Sewage 3.6E+1 Annulus Exh A Cas QJ[tg B bgE_11 Cntet Ata g,.3[tg METEOROLOGICAL CONDITIONS Drywell - HR (R/hr) 1 0[19 A8 Vent 2 OLil Wind Speed 17.0 mph OC8 Vent Exh 2JLig Wind Direction 235 i OC8 Vent - HR Q OE_tg Tempe ra ture 40 *F . OC Vent Pipe 2002 Delta T -1.00 *F i U1 Plant Vent 6J[11 U1 Plant Vent - HR Q OEtQ TB/H8 Vent 6J[+1 i 18/HB Vent - HR Q 0[tg ST Packing Exh LSE_10 U2 Plant Vent 6JE11 U2 Plant Vent - HR 0.0E+0 ~ DW170C/A/26/es
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Time: 1045 Message No.: 48X PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Massane For: Emergency Coordinator Simulated Plant Conditions: See attached sheets Messame: ***THIS IS A DRILL *** Declare a SITE AREA EMERGENCY (EPI-A1, Section D.III.2, "Courplete loss of any functions needed for plant hot shutdown"). 4
+
I i- , 'I ) FOR CONTROLLER USE ONLY ? Controller Notes: Deliver this message if a SITE AREA EMERGENCY has not been declared. Do not deliver this message if Emergency Classification discussions are underway. Actions Expected: .See " Actions Expected," Message No. 44.
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x-PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1155 f.nQ.1 f.662 CONTAINMENT PARAMETERS SYSTEM INFORMATION REACTOR PARAMETERS Teepe ra ture Pressu re Pressure Flow . Pressure _ 323 _ psig
- f*Fl fosiel Status fosiel feuel Level -145 in. WR Cntet 135 1.5 _ RWCU PMP A SS 0 i Meutron Drywell 201 3.9 8 SS 0 Mon 8 Range A,lBM HWL PMP A OP 230 Mode SW SHTDN Toepe ra ture Level f*F1 fft.) B OP 230 FDW Flw. 1.2 Mib/hr Supr Pt 140 20.9 C SS 0 ST Flw (Total) 12 Mlb/hr CSP A SS 150 Line A .3 SYSTEMS INFORMATION B SS __ 150 Line B .3 Pressure Flow
_ Status fosial faomi C SS 150 Line C .3 RHR A PMP OVRD RFBP A OP 330 Line D .3 B SP CLG 250 J QQQ._ B OP 330 C VLV DVRD 275 0 C SS ?60 LPCS PHP OVRQ D SS 160 RCIC FLW OVRD 500 0 RFP A OP 1000 f. 2 r HPCS VLV OVRD 900 0 8 $$ _ O O ECC A 005 MFP SR 0 0 ILLRB1ME-GENERATOR B OP 114 RCIRC A SS 0 PARAMETERS ESW A OOS S SS O Mwatt 0 8 OP 95 MVAR 0 MAJOR VALVE PARAMETERS C OP 95 CNOR Vac 28 in. Hg - Status Closed Open CRD A SS Thrt Pr 922 psig MSly NORM 0 8 8 SS BYP VLV SRV NORM 19 0 Posit 2/ ~ g SLC A OP 1600 B OP 1600 SLC STG TK LVL 4609 gal. au.e
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PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS Ex[RCISE TfM 1155 CONTROL ROOM AleNUllCI ATORS P601/P877 .P680 PB70 as BACK PANELS Section 20A Section 19A Section 5A CONT IWI HVAC EMERG RCIRC A SUPP POOL ADS B MANUAL SCRAM INITIATED P904 LEVEL A HIGH PERMISSIVE SWITCH ARMED RHR B/C RUN Coeli ItM HVAC SUPP POOL RPS LOGIC EMERG RCIRC B TEMP A HIGH ADS A MANUAL SCRAM INITIATED P904 PERMISSIVE CONTAINMENT RPV L-3 RRCS MAN PRESS A HIGH INITIAT1001 ADS B DRWELL PERMISSIVE RPS LOW LEVEL PRESS A HIGH RPV L-3 L-3 logic FOR LPCS/ ADS A RRCS LPCI A FRM RHR A PERMISSIVE RX LEVEL DW PRESS HIGH DW PRESS HIGH LO L-2 CONTAINMENT ADS B RPS TEMP A HIGH PERMISSIVE DRWELL DW PRESS HIGH PRESS HIGH DRWELL TEMP A Section 7A HIGH -
' SAFETY / RELIEF 5 Section 17A, Section 17A lVALVELEAKAGQ SUPP POOL CONTAlNMENT lALARMP614---l LEVEL B TEMP S HIGH ,
HIGH DRWELL SUPP POOL TEMP S TEMP B HIGH HIGH CONTAINMENT PRESS S HIGH - DRWELL - PRESS B HIGH LOCIC FOR LPCI B/C FM RHR DW PRESS HIGH DW1708/A/95/kay
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m PERRY NUCLEAR POWER PLANT- . 1984 EMERGEBICY PREPAREDNESS EXERCISE TIME: 1155 fAID ELECTRICAL DISTRIBUTION 2293 CST Level 410.000 est. Status Load IMW1 Status Jtatus _ fosial Offsite Pwr Sources - 2 AV Cont Rm HVAC Supp Fan A OP TBCC PHP- A OP 75 Con Breakers 2 CL 8 OP B OP 75 Div 1 DG OOS Cont Rm HVAC Rtn Fan A SS C SS 18 Div 2 DG OP O B- SS SA Comp OP 128 Div 3 DG OP O Cont Re Eng RCIRC Fan A OP 1A Comp SR 120 8 OP ZR00 CIRW PMP A OP 46 Status fil9
- B OP 45 Cntet Val Cig Fan A OP . Pressure
,. Status f osial _
C OP 46 8 OP IICC Pump A SS 35 i SJAE A OP C SS B SS D OP C OP 112 E OP ADDITIONAL INFORMATION SW Pump A OP 56 F SS Status Abbreviations: a B OP 56 Drywell Coollag Fan IA OP OP Ope ra ting C SS _ 0 SS Secured Status D SS O 3A OP AV Available MTR Fire Pump SR 18 SS SR Standby Readiness DO Fire Pump. SR 2B SS SHTDN Shutdown 38 SS - S-SP Slow Speed Cntet Vsl Purge Supp Fan A SS F-SP Fast Speed B SS ISOL isolated Cntet Vsl er DW Purge Exh Fan A SS NORM No raa 1 B SS 00S Out of Service Drywell Pu rge Suppl Fan A SS CL Closed , 8 SS OVRD . 0ve rride AEGTS Fan A 00S B OP O 4
, AREA RADIATION MONITORS Time: 1155 TAG # LOCATION READING (mR/hr) 1D21NO30 Personnel Air Lock, Cntmt (600'6") 5.0E+0 1D21N040 CRD HCU. West, Cntmt (620'6") 5.0E+0 i
1D21N050 RBRT Area, Cntmt (642') 1.0E+2 1D21N060 Tip Drive Area, Cntmt (600'6") 3.0E+1 1D21N070 RWCU F/D Area, Cntmt (664'7") 7.0E+0 ID21N080 Upper Pool Area, Cntmt (689'6") 2.0EM 1D21N110 Aux Bldg East (574'10") 7.0E+0 1D21N120 Aux Bldg West (574'10") 7.0E+0 1D21N130 Turb Rm East (647'6") 2.0E+0 1D21N140 CRD HCU East, Cntmt (620'6") 5.0E+0 Turb Rm West (647'6") 1D21N160 2.0E+0 1D21N170 Turb Blda (605'6") 2.2E+0 1D21N180 Hotwell Pump Area. TB (577'6") 1.0E+1 1D21N190 TB Sump Area, TBC (548'6") 2.0E+1 1D21N200 OGB (584') 1.1E+1 1D21N210 'Cnds F1tr Pmp Area, TBC (568'6") 9.0E+0 1D21N220 OG After Fitr Area, OGB (602'6") 2.0E+1 1D21N230 HP Fdw Htr Area, HB (600'6") 1.0E+1
! 1D21N240 Fdw Pump Area, HB (647'6") 6.4E+0 l
1D21N400 CR, CC (654'6") 1.6E-1
, ID21N410 OG Hold Up Area TB (577'6") 8.7E+0 j D21N250 RWB West (574'10") 2.5E+1 i D21N260 RWB East (574'10") 1.5E+1 D21N270 RWB (602') 5.0E+0 D21N280 Process Sample Rm, RWB (623'6") 4.0E+0 D21N290 RW Evap, RWB (623'6") 4.0E+0 , D21N310 VPCU F/D Area, IB (599') 6.0E+0 i D21N320 Fuel Preparation Pool IB (620'6") M //. 0 E* G
, D21N330 Spent Fuel Storage Pool, IB (620'6") M V. dE+# D21N420 FPCU Cire Pmp Area, IB (574'10") 9.0E+0 1D21N340 Unit 1 DW, Portable, Cntmt (655') - D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1 D21N370 SRW Drumming Area, RWB (623'6") 6.0E+0 1D21N090 Refueling Bridge, Cntmt (689'6") 3.0E+0
- .D21N390 Fuel Serv Hdig Platform, IB (620'6") m 3.#E+F t
* = Alarm OS = Offscale
. ~ . , . . . . .x ....,n. . - , - . - .. -
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PERRY NUCLEAR POWER PLANT 198N EMERGENCY PREPAREDNESS EXERCISE TIME: 1155 PANEL P60as PANELS P669. P670. P671. P672 Process Radiation Main Steam Line RAD 7.0E+1 mR/hr ' Alare Cntet Vent Exh RAD 41.0E-1 mR/hr Orrgas Pre-treatment 2.5E+1 R/hr . Offgas Post-treatment A 2.0E+2 cpm PANEL P902 a B 2 0E+2 cpm Co.amon Airborne Gas fcomi Alare Eng Service Water A 3.0E+1 com RWB Vent Exh 2.0E+1 8 3.0E+1 cpm FHS Vent Exh 2.2E+1 i 00 Ca rbon Bed Vaul t A 6.0E+1 mR/hr CR Vent Exh 2.0E+1 8 5.5E+1 mR/hr PANEL P906 ML 803 Common Process and Area. Een Alare
,. Turb Bldg East- 2.5E+0 mR/hr UD-MH-73 East Liq 3.0E+1 Turb sidg West 2.5E+0 mR/hr UD-MH-70 West Liq 1 2E+1 NCC Heat HX 3.5E+1 PANEL F80se Radwaste to ESW 3.0E+1 Airborne Radiation Gas (com) Ala re Radwas;te to Sewage 3.6E+1 Annulus Exh A Gas 0,QE1D 8 Antti Cntet Ate L7[t2 NE7E0!10 LOGICAL CONDITIONS Drywe1i - HR (R/hr) LQEtg AB Vent 2,0E+1 Wind Speed 10.0__ aph 000 Vent Exh LDL12 Wind Direction 28eo OGB Vent - HR gigtig Tempe ra ture as - *F OG Vent Pipe giDE12 Delta T -' .51 "F U1 Plant Vent 619[11 U1 Plant Vent - HR Q OEtQ TB/HB Vent LQ[11 TB/HB Vent - HR Di o M ST Packing Exh LA ;11! '
U2 Plant Vent fi,0 M U2 Plant Vent - HR Rgil! DW170C/A/33/es 4 m
Time: 1200 Message No.: 58 PERKY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM r Messaae For: Control Room Simulated Plant Conditions: See attached sheets Messame: ***THIS IS A DRILL *** I-. i-
\ \ $- FOR CONTROLLFR USE ONLY l.
2-Controller dotes: 1. The running turbine driven reactor feed pump and feedwater
. booster pump trip due to Surge Tank Low Level Switch N21-N335 malfunction; the entire feedwater system-is rendered unavellable.
- 2. Reactor water level begins to decrease; when it decreases below -148 inches, it will initiate MSIV isolation.
. Actions Expecr.ed:
L I DW176/C/58/ba
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Time: 1050 Message No.: 49 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Messate For: Control Room /TSC Simulated Plant Conditions: See attached sheets Messame: ***THIS IS A DRILL *** 3 1 'i . 4
- I l-. FOR CONTROLLER USE ONLY l
y Controller Notes: Reactor water level is being maintained at -145 inches; reactor power remains at 8%. Actions Expected: S 4
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DW176/C/49/ba 9
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PERRY NUCLEAR POWER PLANT 1984 EMERCENCY PREPAREDNESS EXERCISE' TIME: 10',0 fit 01 fltAQ CONTAINMENT PARAMETERS SYSTEM INFORMATION REACTOR PARAMETERS Tempe ra tu re Pressure Pressure Flow Pressure 923- psig f*F1 fosial Status fosial faomt Level -145 in. WR Cntet 106 0.7 RWCU PMP A SS O Neutron Drywell 152 1.8 8 SS O Mon 8 Range AffM HWL PMP A OP 230 Mode SW SHTDN _ Tempe ra ture Level f*F1 fft.) B OP 230 FDW Flw 1.2 Mib/hr Supr P1 135 20.1 C SS 0 ST Flw (Total) 1.2 Mib/hr , C8P A SS 150 Line A .2 i SYSTEMS INFORMATION 8 SS 150 Line B .2 Pressure Flow Status fosial faomi C SS 150 Line C .2 l l RHR A PHP OVRD RFBP A OP 330 Line D .6 l B SP CLC 250 7000 8 OP 330 C VLV OVRD 275 0 C SS 160 LPCS PHP OVRD D SS 160 RCIC FLW OVRD 500 0 RFP A OP 1000 /2C HPCS VLV OVRD 900 0 8 SS 0 0 ECC A 00S MFP SR 0 0 IURSINC-C[H[RATOR B OP 114 RCIRC A SS 0 PARAMETERS ESW A 00S B SS 0 Mwatt 0 B OP 95 HVAR O MAJOR VALVE PARAMETERS C OP 95 CNDR Vac 28 in. Hg _ Status Closed _ Open CRD A SS Thrt Pr 922 psig MSlV NORM 0 8 8 SS BYP VLV l SRV NORM 19 0 Posit 16 % B OP 1600 SLC STG TK LVL 4600 gal,
=
a . . -- _ _ _ - . . _ _ . . - . . .-- _ . . . PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1050 CONTROL ROOM ANNUNCIATORS P601/P877 P680 P870 & BACK PANELS
~~
Section 20A Section 5A CONT RM HVAC EMERC RCIRC A - SUPP POOL MANUAL SCRAN INITIATED P904 LEVEL A HICH SWITCH ARMED CONT RM HVAC SUPP POOL RPS L0cic .EMERG RCIRC B TEMP A HICH MANUAL SCRAM . INITIATED P904 CONTAINMENT RRCS MAN PRESS A HICH INITIATION DRWELL RPS LOW LEVEL PRESS A HICH L-3 , Section 17A RRCS RX LEVEL SUPP POOL LO L-2 LEVEL B HICH Section 7A SUPP POOL TEMP B HICH SAFETY / RELIEF VALVE LEAKAGE CONTAINMENT ALARM P614 PRESS B HICH Section 9A DRWELL
, PRESS B HICH CENERATOR LOCKOUT RELA)
Section 19A TRIP ADS B AUTO VOLTAGE PERMISSIVE REGULATOR RHR B/C RUN TRIP ADS A
- PERMISSIVE RPV L-3 ADS B PERMISSIVE RPV L-3 DW1708/A/77/es 9
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w M x w .. . : _. w . r . .u . e u , u - . PERRY NUCLEAR POWER PLANT 1984.EMERCENCY PREPAREDNESS EXERCISE . TIME: 1050 fAZQ ELECTRICAL DISTRIBUTION P904 CST Level 410.000 cal. Status Load fMW) Jta tus Status _fosial Offsite Pwr Sources 2 AV Cont Rm HVAC Supp Fan A OP TBCC PHP A OP 75 Gen Breakers 2 CL B OP B OP 75 Div 1 DG OOS Cont Rm HVAC Rtn Fan A SS l C SS 18 Div 2 DG OP O B SS SA Comp OP 128 Div 3 DG OP O Cont Re Eng RCIRC Fan A OP 1A Comp SR 120 B OP P800 CIRW PMP A OP 46 Status P970 B OP 45 Cntet Vsl Cig Fan A OP P ressu re
. Status fosial C OP 46 B OP NCC Pump A. SS 35 SJAE A OP C SS B SS 35 B SS D . OP C OP 112 E OP ADDITIONAL 1NFORMAT10N SW Pump A OP 56 F SS Status Abbreviations: B OP 56 Drywe 1 l Cooling Fan 1A OP OP Ope ra t ing C SS 0 2A OP SS Secured S'tatus D SS 0 3A OP
- AV Available MTR Fire Pump SR l IB SS j SR Standby Readiness DD Fire Pump SR 2B SS SHTDN Shutdown
! 3B SS 4 S-SP Slow Speed Cntet Vsl Purge Supp Fan A _ SS i F-SP Fast Speed B SS ISOL 1solated Cntet Val ar DW Purge Exh Fan A SS NORM Noras1 B SS 00S Out of Service Drywell Purge Suppl Fan A SS CL Closed B SS OVRD Ove rride , AECTS Fan A 00S B OP 4 i
I AREA RADIATION MONITORS Time: 1050 TAG # LOCATION READING (mR/hr) 1D21NO30 Personnel Air Lock, Cntmt (600'6") 5.0E+0 1D21N040 CRD HCU West, Cntmt (620'6") 5.0E+0 i 1D21N050 RBRT Area, Catmt (642') 1.0E+2
, ID21N060 Tip Drive Area, Cntmt (600'6") 3.0E+1 1D21N070 RWCU F/D Area, Cntmt (664'7") 7.0E+0 1D21N080 Upper Pool Area, Cntmt (689'6") 2.0E+0 1D21N110 Aux Bldg East (574'10") 7.0E+0 , ID21N120 Aux Blda West (574'10") 7.0E+0 1D21N130 Turb Rm East (647'6") 2.3E+0 1D21N140 CRD HCU East, Cntmt (620'6") 5.0E+0 1D21N160 Turb Rm West (647'6") 2.3E+0 1D21N170 Turb Bldg (605'6") 2.5E+0 1D21N180 Hotwell Pump Area, TB (577'6") 1.0E+1 . 1D21N190 TB Sump Area, TBC (548'6") 2.0E+1 1D21N200 OGB (584') 1.1E+1 1D21N210 Cnds F1tr Pmp Area, TBC (568'6") 9.0E+0
- 1D21N220 OG After Fltr Area, OGB (602'6") 2.0E+1 1D21N230 HP Fdw Htr Area, HB (600'6") 1.0E+1 1D21N240 Fdw Pump Area, HB (647'6") 6.~6E+0 1D21N400 CR, CC (654'6") 1.6E-1
! 1D21N410 OG Hold Up Area, TB (577'6") 9.5E+0 j D21N250 RWB West (574'10") 2.5E+1 D21N260 RWB East (574'10") 1.5E+1 D21N270 _
RWB (602') 5.0E+0
^
D21N280 , Process Sample Rm, RWB (623'6") 4.0E+0 D21N290 RW Evap, RWB (623'6") 4.0E+0 .k D21N310 FPCU F/D Area, IB (599') 6.0E+0 f D21N320 Fuel Preparation Pool, IB (620'6") 6 EdEtF 4
. D21N330 Spent Fuel Storage Pool, IB (620'6") 6 Edfte
- D21N420 FPCU Cire Pmp Area, IB (574'10") 9.0E+0
. 1D21N340 Unit 1 DW, Portable, Cntmt (655') -
i D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1 D21N370 SRW Drumming Area, RWB (623'6") 6.0E+0 1D21N090 Refueling Bridge, Cntrrt (689'6") 3.0E+0 D21N390 Fuel Serv Hdig Platform, IB (620'6") 6 7.0f* 0 *
* = Alarm OS = Offscale
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PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE ' TIME: 1050 PANEL P6036 PANELS P669. P670. P671. P672 Process Radiation Main Steam Line RAD 7.0E+1 mR/hr Ala re Cntet Vent Exh RAD 41.0E-1 mR/hr Offgas Pre-treatment 2.5E+1 R/hr Orrgas Post-treatment A 2.0E+2 cpm PANEL P902 8 2.OE+2 cpm Common Airborne Ces Icomi AIa re Eng Service Water A 3.0E+1 cpm RW8 Vent Exh 2.0E+1
~8 3.0E+1 cpm FHS Vent Exh 2.2E+1 00 Carbon Bed Vault A 6.0E+1 mR/hr CR Vent Exh 2.0E+1 8 5.5E+1 mR/hr PANEL P906 M EL 803 Common Process and Area- Eng Alarm Turb Bldg East 2.5E+0 mR/hr UD-MH-73 East Laq 3.0E+1 Turb Bldg West 2.5E+0 mR/hr UD-MH-70 West Liq 3.2E+1 NCC Heat HX 3.5E+1 PANEL P804 Radwaste'to ESW 3.0E+1 Airborne Radiation Cas (com] ,
Ala re Redweste to Sewage 3.6E+1 Annulus Exh A Cas QJEiG B M (11 Cntet Atm 2JE_12 METEOROLOGICAL CONDITIONS Drywell - HR (R/hr) IJLt_0 A8 Vent LDE_11 Wind Speed 17.0 ph OGB Vent Exh 2J E_12 Wind Direction 235 0C8 Vent - HR 0JE10 Tempe ra ture a0 s *F OC Vent Pipe 2 0012 Delta T -1.00 'F U1 Plant Vent 6 0[11 UI Plant Vent - HR OJEtQ T8/HB Vent f 0[11 TB/HB Vent - HR QJEtQ ST Packing Exh MW! U2 Plant Vent 6JW U2 Plant Vent - HR QJfd! DW170C/A/27/es
Time: 1055 Message No.: 50
' PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Messaae For: Control Room /TSC Simulated Plant Conditions: See attached sheets
, Messame: ***THIS IS A DRILL ***
F 1 i { FOR CONTROLLER USE ONLY s 3 - Controller Notes: Actions Expected: l-l^ 1 .
^
DW176/C/50/ba i-t m- m mww
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PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1055 fit 01 fitRQ CONTAINMENT PARAMETERS SYSTEM INFORMATION REACTOR PARAMETERS . Tempe ra ture Pressure Pressu re Flow Pressure 923 psig (*F1 fosial . Status fosial faomi Level -145 in. WR Cntet 110 0.8 RWCU PHP A 'SS O Neu t ron 1 Drywe I i 160 2.2 8 SS O Mon 8 Range efjM
~ .- IfWL PMP A OP 230 Mode SW SHTDN ! Tempe ra ture Level f*F1 fFt.) B OP 230 FDW Flw 1.2 Mlb/hr Supr Pt 136 20.2 . C SS 0 ST FIw (Total) 1.2 Mlb/hr CSP A SS 150 Line A .2 SYSTEMS INFORMATION ,
B SS 150 Line B .2 Pressure Flow Status losial faom) C SS 150 , Line C .2 RHR A PMP OVRD RFBP A OP 330 Lir.e D .6 B SP CLG 250 7000 B OP 330 C. VLV OVRD 275 0 C SS 160 LPCS PHP OVRD D SS 160 RCIC FLW OVRQ 500 0 RFP A OP 1000 #* I/C - HPCS VLV OVRD 900 0 B SS O O ECC A 00S MFP SR 0 0 TURBigE-CE_RERATOR B OP 114 RCIRC A SS O PARAMETERS ESW A 00S B SS 0 Mwatt 0 B OP 95 MVAR 0 MAJOR VALVE PARAMETERS C OP 95 CNDR Vac 28 in. Hg Status Closed Open CRD A SS Thrt Pr 922 psig MSlV NORM 0 8 B SS BYP VLV SRV NORM 19 0 Posit 16 % SLC A OP 1600 B OP 1600 SLC STG TK LVL 4600 gal. 4 4
, PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE- TIME: 1055
^, CONTROL ROOM ANNUNCIATORS
! ,c P601/P877 P680 P870 & BACK PANELS Section 20A Section 19A Section 5A CONT RM HVAC EMERG RCIRC A SUPP POOL ADS B MANUAL SCRAM INITIATED P904 LEVEL A HIGH PERMISSIVE SWITCH ARMED RHR B/C RUlls CONT RM HVAC SUPP POOL T RPS LOGIC EMERG RCIRC B TEMP A HIGH ADS A' MANUAL SCRAM INITIATED P904 PERMISSIVE CONTAINMENT RPV L-3 RRCS MAN PRESS A HIGH INITIATION ADS B.
, DRWELL PERMISSIVE RPS LOW LEVEL 4 PRESS A HIGH RPV L-3 L-3
, LOGIC FOR LPCS/ ADS A RRCS
, i LPCI A FRM RHR A PERMISSIVE RX LEVEL DW PRESS HIGH DW PRESS HIGH LO L-2 CONTAINMENT ADS B RPS TEMP A HIGH PERMISSIVE DRYWELL DW PRESS HIGH PRESS HIGH SUPP POOL Section 7A MAKEUP TRAIN A TIMER ACTUATED SAFETY / RELIEF VALVE LEAKAGE' ALARM P614 Section 17A Section 17A ORVWELL ---- Section 9A TEMP A CONTAINMENT HIGH TEMP B HIGH GENERATOR l l LOCKOUT RELAY SUPP POOL DRWELL s TRIP l LEVEL B TEMP B B HIGH HIGH l AUTO VOLTAGE l I REGULATOR I SUPP POOL TEMP B HIGH SUPP POOL MAKEUP TRAIN B TIMER ACTUATED
!- TRIP!
CONTAINMENT PRESS B HIGH DRWELL PRESS B HIGH LOGIC FOR LPCI B/C FM RHR , DW PRESS HIGH DW1708/A/80/es O
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PERRY NUCLEAR POWER PLANT 1984 EMERCENCY PREPAREDNESS EXERCISE TIME: 1055 - fglg ELECTRICAL DISTRIBUTION ffQ41 CST Level 410.000 cal. Status- Load fMW) Status
! Status fosle) Off site Pwr Sources 2 AV Cont Rm HVAC Supp Fan A OP TBCC PHP A OP 75 Gen Breakers 2 CL B OP S OP 75 Div 1 DG OOS Cont Rm HVAC Rtn Fan A SS C SS 18 Div 2 DG OP O B SS SA Comp OP 128 Div 3 DC OP O Cont Re Eng RCIRC Fan A OP lA Comp SR 120 B OP P800 CIRW PMP A OP 46 Status P970 8 OP 45 Cntet Vsl Clg Fan A. OP Pressure i
Status fosial C OP 46 B OP NCC Pump A SS 35 t A OP C SS SJAE S SS 35 B SS D OP C OP 112 E OP ADDITIONAL INFORMATION SW Pump A OP 56 F SS-Status Abbreviations: B- OP 56 Drywe1I Coo lIng Fan IA OP OP Ope ra t ing C SS O 2A OP SS Secured Status D SS O 3A OP AV Available MTR Fire Pump SR 18 SS SR Standby Readiness DD Fire Pump SR 28 SS SHTDN Shutdown 3B SS S-SP Slow Speed Cntet Vsl Purge Supp Fan A SS F-SP Fast Speed 8 SS ISOL isolated Cntet Val as DW Purge Exh Fan A SS ! NORM No rea i B SS 00S Out of Service Drywell Purge , Suppl Fan A SS , CL Closed 8 SS OVRD Override AEGTS Fan A 00S B. OP J t
AREA RADIATION MONITORS Time: 1055 TAG # LOCATION READING (mR/hr) 1D21NO30 Personnel Air Lock, Cntmt (600'6") 5.0E+0 1D21N040 CRD HCU West, Cntmt (620'6") 5.0E+0 1D21N050 RBRT Area, Cntmt (642') 1.0E+2 1D21N060 Tip Drive Area, Cntmt (600'6") 3.0E+1 1D21N070 RWCU F/D Area, Cntmt (664'7") 7.0E+0 1D21N080 Upper Pool Area, Cntmt (689'6") 2.0E+0 1D21N110 Aux Bldg East (574'10") 7.0E+0 1D21N120 Aux Bldg West (574'10") 7.0E+0 1D21N130 Turb Rm East (647'6") 2.3E+0
+
1D21N140 CRD HCU East, Cntmt (620'6") 5.0E+0
. 1D21N160 Turb Rm West (647'6") 2.3E+0 1D21N170 Turb Blda (605'6") 2.5E+0 1D21N180 Hotwell Pump Area, TB (577'6") 1.0E+1 1D21N190 TB Sump Area, TBC (548'6") 2.0E+1 ; 1D21N200 OGB (584') 1.1E+1 1D21N210 Cnds F1tr Pmp Area, TBC (568'6") 9.0E+0 1D21N220 OG After Fitr Area, OGB (602'6") 2.0E+1
.l 1D21N230 HP Fdw Htr Area, HB (600'6") 1.0E+1 1 1D21N240 Fdw Pump Area, HB (647'6") 6.6E+0 ID21N400 CR, CC (654'6") 1.6E-1
-l ID21N410 OG Hold Up Area, TB (577'6") 9.5E+0 (574'10") ~
D21N250 RWB West 2.5E+1 D21N260 RWB East (574'10") 1.5E+1 (602') D21N270 RWB 5.0E+0 D21N280 Process Sample Rm, RWB (623'6") 4.0E+0 (623'6") i D21N290 RW Evap, RWB 4.0E+0 i D21N310 FPCU F/D Area, IB (599') 6.0E+0
] D21N320 Fuel Preparation Pool, IB (620'6") m EpE+d
- D21N330 Spent Fuel Storage Pool, IB (620'6") m gcE+, e D21N420 FPCU Cire Pmp Area, IB (574'10") 9.0E+0 1D21N340 Unit 1 DW, Portable, Cntmt (655') -
. D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1 -
D21N370 SRW Drumming Area, RWB (623'6") 6.0E+0 1D21N090 Refueling Bridge, Cntmt (689'6") 3.0E+0 . D21N390 Fuel Serv Hdig Platform, IB (620'6") m 3.0Ee#
- a i
* = Alarm OS = Offscale
~
, , . w. ......:..n. .. a , w. r. ., w PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1055 PANEL P604 PANELS P669. P670. P671. P672 i
Process Radiation Main Steam Line RAD 7.0E+1 mR/hr Alarm Orrgas Pre-treatment 2.5E+1 R/hr Orrgas Post-treatment A 2.0E+2 cpm PANEL P902 8 2.0E+2 cpm Common Airborne Gas Icoal A[an Eng Service Water A 3.0E+1 cpm RWB Vent Exh 2.0E+1 8 3.0E+1 cpm FHB Vent Exh 2.2E+1 OG Carbon Bed Vault A 6.0E+1 mR/hr CR Vent Exh 2.0E+1 8 5.5E+1 mR/hr PANEL P906
, PANEL 803 Common Process and Area Egg Ala re Turb Bldg East 2.5E+0 mR/hr UD-MH-73 East Liq 3.0E+1 Turb Bldg West 2.5E+0 mR/hr UD-MH-70 West Liq. 3.2E+1 NCC Heat HX Li[+1 PANEL P80f( Radweste to ESW 3.0E+1 , Airborne Radiation Cas (coal Ala rm Radweste to Sewage 3.6E+1 Annulus Exh A Gas QJEiQ B LDL11 Cntat Ata 216[tg HETEOROLOGICAL COND1TIONS DryweiI - HR (R/hr) IJ[19 AB Vent gJEE Wind Speed 17.0 mph 0C8 Vent Exh a 0[fg Wind Direction 235
- OCB Vent - HR Q 0[tg Tempera ture eo s *F OG Vent Pipe giD[fg Delta T -1.00 *F U1 Plant Vent 6 0[11 U1 Plant Vent - HR _Oi g[1Q 18/HB Vent 6 OL+1 TB/HB Vent - HR QiD[fQ ST Packing Exh hgtfq U2 Plant Vent 6,Q[11 U2 Plant Vent - HR 0.00+0 DW170C/A/28/es .
o O
Time: 1100 Message No.: 51 PERRY NUCLEAR POWER PLA.T V 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Messare For: Control Room /TSC/ EOF j Simulated Plant Conditions: See attached sheets Messame: ***THIS IS A DRILL *** E i II i 5I J FOR CONTROLLER USE ONLY 't Controller Notes: EOF and JPIC activation should be underway. 1 4 Actions Expected: l e
-}
e A e e ^ DW176/C/51/ba 4
=
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~~
o ..._..;. , . .-a ,.L. . - . s ._.%.-, .. -. . . . . . . - .
. PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1100
- P601 P680 CONTAINMENT PARAMETER $' SYSTEM INFORMATION REACTOR PARAMETERS
' Tempe ra ture Pre ssure Prest"re Flow Pressure 923 psig f*F1 fosial . StatuL fosion local *
- 1. eve l -145 in. WR Cntet 110 0.8 RWCU PHP A SS O Neutron Drywell 160 2.2 B SS 0 Mon 8 Range MBH HWL PMP A OP 230 Mode SW SHTDN Tempe ra ture Level f*F1 frt.) B OP 230 FDW F1w 1.2 Mlb/hr Supr Pl 136 20.2 C SS 0 ST Flw (Total) 1.2 Mib/hr CBP A SS 150 Line A .2 SYSTEMS INFORMATION B SS 150 Line B .2 Pressure Flow Status fosla) faomi C SS 150 Line C .2 RHR A PHP OVRD RFBP A OP 330 L!ne D .6 B SP CLG 250 7000 8 OP 330 C VLV OVRD 275- 0 C SS 160 LPCS PMP OVRD D SS 160 -
RCIC FLW OVRD 500 0 RFP A OP 1000 /. ? R HPCS VLV OVRD 900 0 B SS 0 0 ECC A OOS MFP SR 0 0 TURBl K-GENERATOR S OP 114 RCIRC A SS O PARAMETERS ESW A 005 B SS 0 Mwatt 0 8 OP 95 MVAR 0 MAJOR VALVE PARAMETERS C OP 95 CNDR Vac 28 In. Hg Status Closed Open CRD A SS Thrt Pr 922 psig MSly NORM O 8 - B SS BYP VLV SRV NORM 19 0 Posit __1L %
- SLC A OP 1600 B OP 1600 SLC STC TK LVL 4600 gal. ,
i m i
- ,.- u. .~ a . - . m. , .. - -
PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1100 CONTROL ROOM ANNUNCIATORE P601/P877 P680 P870 ar BACK PANELS Section 20A Section 19A Section SA CONT RM HVAC ' EMERG RCIRC A-SUPP POOL ' ADS B MANUAL SCRAM
^
INITIATED P904 LEVEL A HIGH PERMISSIVE
- SWITCH ARMED RHR B/C RUN CONT RM HVAC SUPP POOL RPS LOGIC EMERG RCIRC B TEMP A HIGH ADS A MANUAL SCRAM INITIATED P904 PERMISSIVE
' CONTAINMENT RPV L-3 RRCS MAN PRESS A HIGH INITIATION-ADS B .
DRWELL PERMISSIVE RPS LOW LEVEL PRESS A HIGH RPV L-3 L-3 - LOGIC FOR LPCS/ ADS A RRCS LPCI A FRM RHR A PERMISSIVE RX LEVEL l DW PRESS HIGH DW PRESS HlCH - LO L-2 CONTAINMENT ADS B RPS , TEMP A HIGH' PERMISSIVE- DRWELL
- DW PRESS HIGH PRESS HIGH SUPP POOL MAKEUP TRAIN A Section TA TIMER ACTUATED SAFETY / RELIEF DRYWELL VALVE LEAKAGE TEMP A Al. ARM P614 .
HIGH Section 17A Section 17A SUPP POOL CONTAINMENT LEVEL 8 TEMP B HIGH HIGH DRWELL SUPP POOL TEMP B TEMP B HIGH HIGH CONTAINMENT SUPP POOL PRESS B HIGH MAKEUP TRAIN B TIMER ACTUATED DRWELL PRESS B HIGH LOGIC FOR LPCI B/C FM RHR DW PRESS HIGH DW1708/A/83/kay
~
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t
. PERRY h0 CLEAR POWER PLANT 1984 EMERCENCY PREPAREDNESS EXERCISE TIME: 1100 RX WATER LEVEL RX PRESS RX POWER SUPR PL TEMP
-145 y WR ' '
923 f_US 8 7 136 'f 60- - 1100- 120- 110 45- 950- 90- 90-N 30- 800- 40- 70-15- 650- 0 50 0 500 -30 -20 -10 0 -30 -20 -10 3 l
-30 -20 -10 0 -30 -20 -10 0 Time (min) Time (min)
Time (min) Time (min) DW TEMP CONTMT TEMP CONTMT PRE.11 SUPR PL LEVEL 160 'f 110 'f 0.8 f1LG 20.2 fJ 200- 110- 20- 19-4 150- 90- 15- - 100- 70- 10- 18-50 50- 5- -
-30 -20 -10 0 -30 -20 -10 0 0 -~~"~~~~ 17 Time (min) Time (miti) -5 -30 -20 -10 0
-30 -20 -10 0 Time (min)
Time (min) e
a > ,w e c .- n . +-- ;,, _ ,. m. . .. , ,
.n. . . . . .. .. ., . . . , . . _ , . . _ _,
PERRY NUCLEAR POWER PLMIT 1984 EMERCENCY PREPAREDNESS EXERCISE . TIME: 1100 fAZA ELECTRICAL DISTRIBUTION 3 CST Level 410.000 aal. Status Load (MW) Status Status. losial OFFsite Pwr Sources 2 AV Cont Rm HVAC Supp Fan A OP TBCC PMP A OP 75 Gen Breakers 2 CL 8 OP B OP 75 Div 1 DG OOS Cont Rm HVAC Rtn Fan A SS C SS 18 Div 2 DG OP O 8 SS SA Comp OP 128 Div 3 DG. OP O Cont Rm Eng RCIRC Fan A' OP IA Comp SR 120 8 OP P800 . CIRW PMP A OP 46 , Status i P970 B CP 45 Cntet Val Cig Fan A OP Pres sure
- _ Status Iosial NCC Pump A SS 35 SJAE A OP C SS 8 SS 35 8 SS D OP C OP 112 E OP 4 ADDITIONAL INFORMATION SW Pump A OP 56
. F SS Status Abbreviations: B OP 56 Drywe l l Coo l ing Fan I A OP OP Ope ra t ing C SS O 2A OP SS Secured Status D SS O 3A OP AV Available MTR Fire Pump' SR
. 1B SS SR Standby Readiness DD Fire Pump SR 28 SS SHTDN Shutdown 3B SS S-SP Slow Speed Cntet Vsl Purge Supp Fan A SS F-SP Fast Speed 8 SS ISOL isolated Crtat Val & DW Purge Exh Fan A SS NORM Normal 8 SS OOS Out of Service Drywell Purge Suppl Fan A SS CL Closed OVRD Override AEGTS Fan A OOS 8 OP e
t w
AREA RADIATION MONITORS Time: 1100 TAG # LOCATION READING (mR/hr) 1D21NO30 Personnel Air Lock, Cntmt ( 600 ' 6"-) 5.0E+0 ., ID21N040 CRD HCU West, Catmt (620'6") 5.0E+0 1D21N050 RBRT Area, Cntmt (642') 1.0E+2 i 1D21N060 Tip Drive Area, Cntmt (600'6") 3.0E+1 8 1D21N070 RWCU F/D Area, Cntmt (664'7") 7.0E+0 i 1D21N080 Upper Pool Area, Cntmt (689'6") 2.0E+0 1D21N110 Aux Bldg East (574'10") 7.0E+0
- 1D21N120 Aux Bldg West (574'10") 7.0E+0 1D21N130 Turb Rm East (647'6") 2.2E+0 1D21N140 CRD HCU East, Cntmt (620'6") 5.0E+0 1D21N160 Turb Rm West (647'6") 2.2E+0 1D21N170 Turb Bldg (605'6") 2.5E+0 1D21N180 Hotwell Pump Area, TB (577'6") 1.0E+1 1D21N190 TB Sump Area, TBC (548'6") 2.0E+1 1D21N200 OGB (584') 1.1E+1 1D21N210 Cnds F1tr Pmp Area, TBC (568'6") 9.0E+0 1D21N220 OG After Fitr Area, OGB (602'6") 2.0E+1 1D21N230 HP Fdw Htr Area, HB (600'6") 1.0E+1 1D21N240 Fdw Pump Area, HB (647'6") 6.6E+0 l 1D21N400 CR, CC (654'6") 1.6E-1 l 1D21N410 OG Hold Up Area, TB (577'6") 9.3E+0 D21N250 RWB West (574'10") 2.5E+1 D21N260 RWB East (574'10") 1.5E+1 D21N270 RWB (602') 5.0E+0 ~
D21N280 Process Sample Rm, RWB (623'6") 4.0E+0
; D21N290 RW Evap, RWB (623'6") 4.0E+0 l D21N310 FPCU F/D Area, IB (599') 6.0E+0 D21N320 Fuel Preparation Pool, IB (620'6") M Edf* O # ; D21N330 Spent Fuel Storage Pool, IB (620'6") M K CE*d #
D21N420 FPCU Cire Pmp Area, IB (574'10") 9.CE+0 t 1D21N340 Unit 1 DW, Portable, Cntmt (655') - D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1 D21N370 SRW Drumming Area, RWB (623'6") 6.0E+0 1D21N090 Refueling Bridge, Cntmt (689'6") 3.0E+0 D21N390 Fuel Serv Hdig Platform. IB (620'6") 6 3.OE*0 *
* = Alarm OS = Offseale l
1
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- . . a. ,.
-s PERRY NUCLEAR POWER PLANT 1984 EMERCENCY PREPAREDNESS EXERCISE TIME: 1100 C
PANEL P604 PANELS P669. P670. P671. P672 Process Radiation Main Steam Line RAD 7.0E+1 mR/hr Alarm Cntet Vent Exh RAD 41.0E-1 mR/hr Ofrgas Pre-treatment 2.5E+1 R/hr Offgas Post-treatment A 2.0E+2 cpm PANEL P902 8 2.0E+2 cpm Common Airborne cas fcom) Ala rm Eng Service Water A 3.0E+1 cpm RWB Vent Exh 2.0E+1 8 3.0E+1 cpm FHB Vent Exh 2.2E+1 OC Carbon Bed Vault A 6.0E+1 mR/hr CR Vent Exh 2.0E+1 B 5.5E+1 mR/hr PANEL P906
, PANEL 801 Common Process and Area EEE Ala rm Turb Bldg East 2.5E+0 mR/hr UD-MH-73 East Liq 3.0E+1 Turb Bldg West 2.5Et0 mR/hr UD-MH-70 West Liq 3.2E+1 NCC Heat HX 1 5E+1 PANEL P804 Radwaste to ESW 3.0E+1 ,
Airborne Radiation Cas (coal Ala rm Radwaste to Sewage 1,6[11 j Annulus Exh A ces Q,D Eff! 4 B LDL11 Cnt9t Atm Rt][ig METEOROLOGICAL CONDITIONS D rywe l l - HR ( R/hr) - LDE10
- AB Vent R&DLil Wind Speed 16.5 mph OCB Vont Exh R DE12 Wind Direction 235
- 0C8 Vent - HR QtDLig Tempe ra ture 41 *F OC Vent Pipe g D[12 Delta T -0.95 'F t U1 Plant Vent 6 DL11 U1 Plant Vent - HR DmDL1D TB/ IIB Vent (t 0E+].
IB/ IIB Vent - HR Q2DEJ! ST Packing Exh itBEiQ U2 Plant Vent 6 0011 U2 Plant Vent - HR 0.0E+0 1 DW170C/A/29/es ,,
Time: 1115 Message No.: 53 PERRY NUCLEAR POWER PIANT 1984 EMERGENCY PREPAREDNESS EXERCISE
, MESSAGE FORM Message For: Control Room /TSC/ EOF i Simulated Plant Conditions: See atta ed sheets Message: ***THIS IS A DRILL *** .
--j.. j J. i h-i. g- . t I, FOR CONTROLLER USE ONLY , k. Controller Notes: Suppression Pool temperature reaches a peak of 143*F and holds steady. l. Actions Expected: - l'i 3
)
DW176/C/53/ba
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4 PERRY NUCLEAR POWER PLANT 1984 EMERCENCY PREPAREDNESS EXERCISE TIME: 1115 fit 9.1 fItRQ CONTAINMENT PARAAETERS EYSTEM INFORMATION REACTOR PARAMETERS Tempe ra ture Pressure Pressure Flow Pressure 923 psig f*F1 fosial Status _fosial local Level -145 in. WR Cntet 124 1.2 RWCU PMP A SS O Neutron Drywell 177 2.9 B SS O Mon _ 8 Range Aff.M HWL PMP A OP 230 Mode SW'. SMTDN Tempe ra ture Level f*F) fft.) B OP 230 FDW Flw 1.2 Mlb/hr Supr P1 143 20.5 C SS 0 ST Flw (Total) 1.2 Mlb/hr CBP A SS 150 Line A .2 SYSTEMS INFORMATION . B SS 150 Line B .2 . Pre ssu re Flow Status ,1gsig) faomi C SS 150 Line C .2 RHR A PHP OVRD RFBP A OP 330 , Line D .6 B SP CLC 250 7000 8 OP 330 C VLV OVRD 275 0 C SS 160 LPCS PHP OVRD D SS _ 16_0__._ RCIC FLW OVRD 500 0 RFP A OP 1000 le 2 K HPCS VLV OVRD 900 0 B SS 0 0 ECC A OOS MFP SR 0 0 J.MBigf-Q[N[RATOR 8 OP 114 RCIRC A SS 0 PARAMETERS ESW A 00s B SS O Mwatt 0 B OP 95 MVAR 0 MAJOR VALVE PARAMETERS C OP 95 CNDR Vac 28 in. Hg Status Closed Open , CRD A SS . Thrt Pr 922 psig MSIV NORM 0 8 8 SS BYP VLV . SRV NORM 19 0 Posit 16 % SLC A OP 1600 B OP 1600 SLC STC TK LVL 4600 gal.
. , , . .~ ~ w47. ; .: ..> ...- i. . . _
PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1115 CONTROL ROOM ANNUNCIATORS P601/P877- P680 P870 & BACK PANELS Section 20A section 19A Section SA CONT RM HVAC ThERG RCIRC A SUPP POOL ADS B MANUAL SCRAM INITIATED P904 LEVEL A HIGH PERMISSIVE SWITCH ARMED RHR B/C RUN CONT RM HVAC SUPP POOL RPS LOGIC EMERG RCIRC B TEMP A HIGH ADS A MANUAL SCRAM INIYlATED P904 PERMISSIVE CONTAINMENT RPV L-3 RRCS MAN PRESS A HIGH INITIATION ADS B DRWELL PERMISSIVE RPS LOW LEVEL PRESS A HIGH RPV L-3 L-3 k LOGIC FOR LPCS/ ADS A RRCS LPCI A FRM RHR A PERMISSIVE RX LEVEL
- DW PRESS HIGH .DW PHESS HIGH LO L-2 -
CONTAINMENT ADS B RPS TEMP A HIGH PERMISSIVE DRWELL DW PRESS HIGH PRESS HIGH SUPP POOL' MAKEUP TRAIN A Section 7A TIMER ACTUATED SAFETY / RELIEF DRWELL VALVE LEAKAGE TEMP A ALARM P614 HIGH Section 17A Section 17A. , SUPP POOL CONTAINMENT LEVEL B TEMP B HIGH HIGH DRWELL SUPP POOL TEMP B TEMP B HIGH HIGH CONTAINMENT SUPP POOL PRESS B HIGH MAKEUP TRAIN 8
- TIMER ACTUATED DRWELL PRESS B HICH LOGIC FOR LPCI B/C FM RHR DW PRESS HIGH DW1708/A/86/kay
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yg - ? ;. PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1115-
'2119 - ELECTRICAL DISTRIBUTlON 22931
, CST Level 410.000 cal. _ Status Load fMW) Status Status f osial _ 0FFsite Pwr Sources 2 AV Cont Rm HVAC Supp Fan A OP TBCC PHP A OP 75 Con Breakers 2 CL B OP 8 OP 75 Div 1 DG OOS Cont Rm HVAC Rtn Fan A SS C SS 18 Div 2 DG OP O 8 SS SA Comp OP 128 Div 3 DG OP O Cont Re Eng RCIRC Fan A OP 1A Comp SR 120 8 OP CIRW PMP A OP 46 Status f110 L OP 45 Cntet Val Cig fan A OP Pressu re Status fosial a C OP 46 8 OP NCC Pump A SS 35 SJAE A OP C SS
, 8 SS 35 B SS D OP C OP 112 E OP ADOIT10NAL INFORMATION SW Pump A OP 56 F SS Status Abbreviations: B OP 56 Drywe l l Coo l ing Fan 1 A OP OP Ope ra t ing C SS 0 2A OP SS Secured Status D SS O 3A OP AV Available MTR Fire Pump SR 18 SS SR Standby Readiness DD Fi re Pump SR 28 SS SHTDN Shutdown 38 SS S-SP Slow Speed Cntet Vsl Pu rge Supp Fan A SS F-SP Fast Speed 8 SS ISOL isolated Cntet Val as DW "
Purge Exh Fan A SS NORM No rea 1 8 SS OOS Out of Service Drywell Pu rge Suppl Fan A SS CL Closed B SS OVRD Override AEGTS Fan A OOS B OP
't
AREA RADIATION MONITORS Time: 1115 TAG # LOCATION READING (mR/hr) 1D21NO30 Personnel Air Lock, Cntmt (600'6") 5.0E+0 1D21N040 CRD HCU West, Cntmt (620'6") 5.0E+0 1D21N050 RBRT Area, Cntmt (642') 1.0E+2 1D21N060 Tip Drive Area, Cntmt (600'6") 3.0E+1 i>' 1D21N070 RWCU F/D Area, Cntmt (664'7") 7.0E+0 l' ID21N080 Upper Pool Area, Cntmt (689'6") 2.0E+0
, ID21N110 Aux Bldg East (574'10") 7.0E+0 1D21N120 Aux Bldg West (574'10") 7.0E+0 1D21N130 Turb Rm East (647'6") 2.2E+0 1D21N140 CRD HCU East, Cntmt (620'6") 5.0E+0 1D21N160 Turb Rm West (647'6") 2.2E+0 1D21N170 Turb Blda (605'6") 2.4E+0 ~
1D21N180 _Hotwell Pump Area, TB (577'6") 1.0E+1
, 1D21N190 TB Sump Area, TBC (548'6") 2.0E+1 1D21N200 OGB (584') 1.1E+1 1D21N210 Cnds Fitr Pmp Area, TBC (568'6") 9.0E+0 1D21N220 OG After F1tr Area, OGB (602'6") 2.0E+1 1D21N230 HP Fdw Htr Area, HB (600'6") 1.0E+1 j 1D21N240 Fdw Pump Area, HB (647'6") 6.6E+0 -l 1D21N400 CR, CC (654'6") 1.6E-1 'j 1D21N410 OG Hold Up Area, TB (577'6") 9.0E+0 '; D21N250 RWB West (574'10") 2.5E+1 (574'10") 1.5E+1 D21N260 RWB East D21N270 RWB (602') 5.0E+0 D21N280 Process Sample Rm, RWB (623'6") 4.0E+0 D21N290 RW Evap, RWB (623'6") 4.0E+0 ,
(599') 6.0E+0
; D21N310 FPCU F/D Area, IB ;
{ D21N320 Fuel Preparation Pool, IB (620'6") 6 9.(Eed
- l D21N330 Spent Fuel Storage Pool, IB (620'6") m gef + 0 e
! D21N420 FPCU Cire Pmp Area, IB (574'10") 9.0E+0 - 1D21N340 Unit 1 DW, Portable, Cntmt (655') -
D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1 D21N370 SRW Drumming Area, RWB (623'6") 6.0E+0 l 1D21N090 Refueling Bridge, Cntmt (689'6") 3.0E+0 D21N390 Fuel Serv Hdig Platform. IB (620'6") m F. Meg s t e
* = Alarm OS = Offscale s
, , - v m o. , , -
.-.m..m. _ .s -_ - . ,. _
. PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1115 PANEL P604 PANELS P669. P670. P671. P672 Process Radiation Main Steam Line RAD 7.0T+1 mR/hr '
Alarm
. Cntet Vent Exh RAD s.1.0E-1 mR/hr Orrgas Pre-treatment 2.5E+1 R/hr Orrgas Post-treatment ' A 2.0E+2 cpm PANEL P902 8 2.0E+2 cpm Common Airborne Gas fcomi AIare Eng Service Water A 3.0E+1 cpm RW8 Vent E>.h 2.0E+1 8 3.0E+1 cpm FHC Vent l'xh 2,2[+1 OG Carbon Bed Vault A 6.0E+1 mR/hr CR Vent Exh 2.0E+1 8 5.5E+1 mR/hr PANEL P906 FANEL 803 Common Process and Area Egg Alarm Turb Bldg East 2.5E+0 mR/hr UD-MH-73 East Liq 3.OE+1 Turb Bldg West 2.5E+0 mR/hr UD-MH-70 West Liq 3.2E+1 NCC Heat HX 3.5E*1
*AMEL P804 Radwaste to ESW 3.0E+1 Airborne RedIation Gas fcomi AIa re Radwasto to Sewage 3.6E41 Annulus Exh A Gas Q,0Eig 8 3,9011 Cntat Ata UE.12 METEOROLOGICAL CONDITIONS DryweII - HR (R/hr) JJEtQ_
AB v nt 2,p(11 Wind Speed 15.0 mph 235
- OCB Vent Exh 2,0012 Wind Direction OCS Vent - HR Q,gE_ig Tempe ra ture 41 'F OG Vent Pipe 2 QLt2 Delta T -0.95 'F U1 Plant Vent 6J Lt1 U1 Plant Vent - HR Q,901Q TB/HB Vent 6,DEE 18/HB Vent - HR Q,0 M ST Packing Exh M M U2 Plant Vent (t,D ;.11 U2 Plant Vent - HR QJ3 DWl70C/A/30/es
. Tima: 1120 Message No.: 54 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Messaae For: Controllers Simelated Plant' Conditions:
.. - Message: ***THIS IS A DRILL *w*
5 I .
- TOR CONTROLLER USE ONLY
; Controller Notes: All upper pool dump valves fail to open automatically. Both trains fail due to a hydraulic lock that exists between the dump valves because of a failure of check valves G43-F508A i and G43-F508B. Any effort to manually open these valves fails.
~
- Actions Expected:
O t . l DW176/C/54/ba l l i i 4
.s-.. --
Tims: 1130 Message No.: 55 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM
,- Messaae For: Control Room /TSC/ EOF i
Simulated Plant Conditions: See attached sheets t Messame: ***THIS IS A DRILL *** i I FOR CONTROLLFR 'JSE ONIX i Controller Notes: Reactor power remains steady at 8% power. All efforts to y insert the control rods continue to fail. i Actions Expected: 7 i. (' DW176/C/55f ba
c w . &w,::1 + ..~:- . ; , =. x ..,..a. .....a, . ,r PERRY NUCLEAR POWER PLANT ~ 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1130 CONTROL ROOM ANNUNC1ATORS P601/P877 P680 P870 at BACK PANELS Section 20A Section 19A Section 5A *
. CONT RM HVAC EMERG RCIRC A SUPP POOL ADS B MANUAL SCRAM INITIATED P904 LEVEL A HIGH PERMISSIVE SWITCH ARMED-RHR B/C RUN CONT RM HVAC-SUPP POOL RPS LOGIC EMERG RCIRC B TEMP A HIGH ADS A MANUAL SCRAM INITIATED P904 PERMISSIVE CONTAINMENT RPV L-3 RRCS MAN PRESS A HIGH INITIATION ADS B DRWELL' PERMISSIVE APS LOW LEVEL PRESS A HIGH RPV L-3 L-3 LOGIC FOR LPCS/ ADS A RRCS LPCI A FRM RHR A PERMISSIVE RX LEVEL DW PRESS HIGH DW PRESS HICH LO L-2 CONTA'INMENT ADS B RPS TEMP A HIGH PERMISSIVE DRWELL DW PRESS HIGH PRESS HIGH DRWELL TEMP A Section 7A HIGH
. SAFETY / RELIEF Section 17A Section 17A VALVE LEAKAGE ALARM P614 SUPP POOL CONTAINMENT -
I LEVEL 8 TEMP B HIGH HIGH
' DRWELL SUPP POOL TEMP B TEMP B HIGH HIGH r
CONTAINMENT PRESS B HIGH DRWELL PRESS B HIGH LOGIC FOR LPCI B/C iM RHR DW PRESS filGH DW1708/A/89/kay e
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PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1130 fitQ.1 fitRQ CONTAINMENT PARAMETERS SYSTEM INFORMATION REACTOR PARAMETERS Tempe ra tu re Pressure Pressure Flow Pressure 923 psig t'Fl fosial Status fosial feDeI Level -145 in. WR Cntet 130 1.3 RWCU PHP A SS 0 Neut ron Drywell 189 3.3 S SS 0 Mon 8 Range efBJ IfWL PMP A OP 230 Mode SW SHTDN Tempe ra tu re Level f*F1 IFt.) B OP 230 FDW Flw 1.2 Mlb/hr Supr P1 142 20.8 C SS 0 ST Flw (Total) 1.2 Mib/hr CBP A SS 150 Line A .2 SYSTEMS INFORMATION 8 SS 150 Line B .2
' Pressure Flow Status fosial fenol C SS 150 Line C .2 RHR A PMP DVRD RFBP A OP 330 Line D .6 8 SP CLC 250 7000 8 OP 330 , C VLV OVRD 275 0 C SS 160
- LPCS PMP OVRO D SS 160 RCIC FLW OVRD 500 0 RFP A OP 1000 A 4 4I
! HPCS VLV DVRD 900 0 B SS O O ! ECC A 00S MFP SR 0 0 R TURB1ME-GENE.ATOR S OP 114 RCIRC A SS 0 PARAMETERS , ESW A DOS B SS O Mwatt 0 B OP 95 MVAR 0 MAJOR VALVE PARAMETERS C OP 95 CNDR Vac 28 in. Hg _ Status closed open CRD A SS Thrt Pr 922 psig MSIV NORM 0 8 B SS BYP VLV SRV NORM 19 0 Posit 16 % SLC A OP 1600 B OP 1600 SLC STG TK LVL 4600 gal. I e o 1 - i t
te . . . - .u- n r. x .,..c. m . z w. .m .. , .. x . 7 . , e i n ,. e PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXEACISE TIME: 1130 1110 ELECTRICAL DISTRIBUTION E2Qh e CST Level 410.000 cat. J tatus Load fMW) Status Status Iosial Offsite Pwr Sources 2 AV Cont he HVAC Supp Fan A OP TBCC PMP A OP 75 Con Breakers 2 CL 8 OP B OP 75 Div 1 DG 00S Cont Rm HVAC Rtn Fan A SS C SS 18 Div 2 DG OP O 8 SS SA Comp OP 128 Div 3 DG OP G Cont Ra Eng RCIRC Fan A OP - IA Comp SR 120 8 OP 2000 CIRW PMP A OP 46 Status f2ZQ 8 OP 45 Cntet Val Cig Fan A OP Pressure Ah fosiel C OP 46 8 OP NCC Pump A SS 35 SJAE A OP C SS 8 SS 35 8 SS D OP C OP ~? E OP ADolTIONAL INFORMATION SW Pump A OP 56 F SS Status Abbreviations: 8 OP 56 Drywell Cooling Fan IA OP OP Ope ra t ing C SS O 2A OP SS Secured Status D SS O 3A OP AV Available MTR Fire Pump SR 18 SS SR Standby Readiness DO Fire Pump SR 28 SS SHTDM Shutdown 38 SS S-SP Slow Speed Cntet Vsl Purge Supp Fan A SS F-SP Fast Speed 8 SS ISOL isolated Cntet Vsl ar DW-Purge Exh Fan A SS NORM No raa 8 8 SS 005 Out of Service Dryweli Purge Suppl Fan A SS CL Closed 8 SS OVRD Override AEGTS Fan A OOS 8 OP F
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PERRY NUCLEAR POWER PLANT 19881 EMERGENCY PREPAREDIIESS EXERCISE TIME: 1130 PANEL P604 PANELS P669. P670. P671. P672 Process Radiation Main Steam Line RAD 7.0E+1 mR/hr Alarm
. Cntet Vent Exh RAD 41.0E-1 mR/hr Orrgas Pre-treatment 2.5E+1 R/hr Orrgas Post-treatment A '2.0E+2 cpm PANEL P902 8 '2.0E+2 cpm Common Airborne Gas fenol Alarm Eng Service Water A 3.0E+1 cpm RWS Vent Exh 2.0E+1 4
8 3.0E+1 cpm FH8 Vent Exh 2.2E+1 OG Carbon Bed Vault A 6E+1 mR/hr CR Vent Exh 2.0E+1 8 5.5E+1 mR/hr PANEL P906 PANEL 803 Common Process and Area gag Alarm Turb Bldg East 2.5E+0 mR/hr UO-MH-73 East Liq 3.OE+1 Turb Bldg West 2.5E+0 mR/hr UD-MH-70 West Liq 3.2E+1 NCC Heat HX 3.5E+1 PANEL P804 Radweste to ESW 3.0E+1
, Airborne Radiation cas Icom) Alarm Radwaste to .ewage 3.6E+1 Annulus Exh A Ces Q,DE1D 8 3 D[11 Catet Atm 2d[12 METEOROLOGICAL CONDITIONS Drywell - HR (R/hr) LD[19 AB Vent OG8 Vent Exh 2JE_.11 2.DE+2 Wind Speed Wind Direction 12.0 240 ph 0C8 Vent - HR Q,DE_iQ Tempe ra ture 41 *F OG Vent Pipe 2,DL12 Delta T -0.85 *F U1 Plant Vent LOL11 U1 Plant Vent - HR 0.9E1Q IB/HB Vent . [t.D[t1 IB/HB Vent - HR Q,QE1Q ST Packlog Exh 3.8[1D U2 Plant Vent (tJE11 U2 Plant Vent - HR 0.0E+0 t
l DW170C/A/31/es i i
,+
l
o AREA RADIATION MONITORS Time: 1130 0 TAG # LOCATION READING (mR/hr) 1D21NO30 Personnel Air Lock, Cntmt (600'6") 5.0E+0 1D21N040 CRD HCU West, Cntmt (620'6") 5.0E+0 1D21N050 RBRT Area, Cntmt (642') 1.0E+2 1D21N060 Tip Drive Area, Cntmt (600'6") 3.0E+1 ID21N070 RWCU F/D Area, Cntmt (664'7") 7.0E+0 1D21N080 Upper Pool Area, Cntmt (689'6") 2.0E+0 1D21N110 Aux Bldg East (574'10") 7.0E+0 1D21N120 Aux Bldg West (574'10") 7.0E+0 1D21N130 Turb Rm East (647'6") 2.1E+0 1D21N140 CRD HCU East, Cntmt (620'6") 5.0E+0 ID21N160 Turb Rm West (647'6") 2.1E+0 i 1D21N170 Turb Blda (605'6") 2.3E+0 1D21N180 Hotwell Pump Area, TB (577'6") 1.0E+1 1D21N190 TB Sump Area, TBC (548'6") 2.0E+1 1D21N200 OGB (584') 1.1E+1 1D21N210 Cnds F1tr Pmp Area, TBC (568'6") 9.0E+0 1D21N220 OG After Fitr Area, OGB .(602'6") 2.0E+1 ID21N230 HP Fdu Htr Area, HB (600'6") 1.0E+1 1D21N240 Fdw Pump Area, HB (647'6") 6.6E+0 1D21N400 CR, CC (654'6") 1.6E-1 1D21N410 OG Hold Up Area, TB (577'6") 9.0E+0 D21N250 RWB West (574'10") 2.5E+1 D21N260 RWB East (574'10") 1.5E+1 D21N270 RWB (602') 5.0E+0 D21N280 Process Sample Rm, RWB (623'6") 4.0E+0 ,, D21N290 RW Evap, RWB (623'6") 4.0E+0 1 D21N310 FPCU F/D Area, IB (599') 6.0E+0
- D21N320 Fuel Preparation Pool, IB (620'6") M 4/.gf t9 i D21N330 Spent Fuel Storage Pool, IB (620'6") M V.66+ &
D21N420 FPCU Cire Pmp Area IB (574'10") 9.0E+0 1D21N340 Unit 1 DW, Portable, Cntmt (655') - D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1 D21N370 SRW Drumming Area, RWB (623'6") 6.0E+0 1D21N090 Refueling Bridge, Cntmt (689'6") 3.0E+0 D21N390 Fuel Serv Hdig Platform, IB (620'6") m 3.0E+g i I l a
* = Alarm OS = Offscale
4 Tims: 1145 Message No.: 56 PERRY ~NUCIIAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE
. MESSAGE FORM
~ Messane For: Control Room /TSC/ EOF Simulated Plant Conditions: See attached sheets i
. Messame: ***THIS IS A DRILL ***
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i} FOR' CONTROLLER USE ONLY q. '] !J Controller Notes: i4 - . Actions Expected: ^h. . {. 9
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, DW176/C/56/ba 4
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PERRY llUCLEAR POWER PLANT 1984 EMERGEleCY PREPAREDNESS EXERCISE TIME: 1145' CONTROL ROOM AllNullCI ATORS P601/P877 P680 P870 & BACK PANELS Section 20A Section 19A Section 5A CONT RM HVAC EMERG RCIRC A. SUPP POOL ADS B MANUAL SCRAM INITIATED P904 LEVEL A HIGH PERMISSIVE SWITCH ARMED RHR B/C RUN CONT RM HVAC SUPP POOL RPS LOGIC EMERG RCIRC B TEMP A HIGH ADS A MANUAL SCRAM INITIATED P904 PERMISSIVE CONTAlteMENT RPV L-3 RRCS MAN PRESS A HIGH INITIATION .
. ADS 8 DRWELL PERMISSIVE RPS LOW LEVEL PRESS A HIGH RPV L-3 L-3 LOGIC FOR LPCS/ ADS A RRCS LPCI A FRM RHR A PERMISSIVE RX LEVEL DW PRESS HIGH DW PRESS HIGH LO L-2 CONTAINMENT ADS 8 RPS TEMP A HIGH PERMISSIVE DRWELL DW PRESS HIGH PRESS HIGH DRWELL TEMP A Section 7A HIGH ,
SAFETY / RELIEF Section 17A Section 17A VALVE LEAKAGE ALARM P614 SUPP POOL CONTAINMENT, LEVEL B TEMP S HIGH HIGH DRWELL SUPP POOL TEMP B TEMP B HIGH HIGH CONTAINMENT PRESS 8 HIGH DRWELL PRESS 8 HIGH LOG 1C FOR LPCI 8/C FM RHR DW PRESS HIGH DW1708/A/92/kay e e
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PERRY NUCLEAR POWER PLANT -1984 EMERCENCY PREPAREDNESS EXERCISE TIME: 1145 ^; fit 0.1 fitAQ CONTAINMENT PARAMETERS SYSTEM INFORMATION REACTOR PARAMETERS Tempe ra ture Pressure Pressure Flow Pressure 923 psig . f*F1 fosial Status fosial feost Level -145 in. WR Cntet 133 1.4 RWCU PMP A SS 'O Neut ron Dryvell 197 3.7 8 SS O Mon 8 Range APRM HWL PMP A OP 230 Mode SW SHTDN Tempe ra tu re Level f*F1 IFt.) B OP _ .. 2 3 Q_. , FDW Flw. 1.2 Mlb/hr Sup r P t 140 20.9 C SS O ST Flw (Total) 1.2 Mib/hr C8P A SS 150 Line A .2-1Y'oTEMS IhFORMATION 8 SS 150 Line B .2 Pressure Flow Statu=, fosial faomi C SS 150 Line C .2 RHR A PMP OVRD RF8P A OP 330 Line D. .6 8 SP CLG 250 7000 8 OP 330 C VLV DVRD 275 0 C SS 160 - LPCS PMP OVRD D SS 160 RCIC Fth nygg 500 a RFP A OP 1000 4 2 df HPCS VLV OVRD _ 900 A B SS 0 0 ECC A 00S MFP SR O O JURBlME-CEMERAToft 8 OP 114 RCIRC A SS O PARAMETERS ESW A DOS 8 SS 0 Mwatt 0 8 OP 95 MVAR 0 MAJOR VALVE PARAMETERS C OP 95 CNDR Vac 28 in. Hg Status Closed Open CRD A SS Thrt Pr 922 psig MSIV NORM 0 8 B SS BYP VLV SRV NORM 19 0 Posit 16 % SLC A OP 1600 8 OP 1600 SLC STG TK LVL 4600 gal.
~
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PERRY NUCLEAR POWER PLANT 19"*4 EMERCENCY PREPAREDNESS EXERCISE TIME: 1145 P870 ELECTRICAL DISTRIBUTION P904 CST Level 410.000 ea_.L Status . Load IMW) Status Status losial Offsita Pwr Sources 2 AV Cont Rm H' o Fan A OP TBCC PMP A OP 75 Con Breakers 2 CL B OP ' B OP 75 Div 1 DG OOS- Cont Rm HVAC Rtn Fan A SS C SS 18 Div 2 DG OP O B SS SA Comp OP 128 Div 3 DG OP O . Cont Re Eng RCIRC Fan A OP 1A Comp SR 120 8 OP P800 CIRW PHP A OP 46 Status - P970 B OP 45 Cntet Vsl Clg Fan A OP Pressure Status fusiel C OP 46 B OP - MCC Pump A SS 35 SJAE A OP C SS B SS 35 B SS D OP C OP 112 E OP ADOIT10NAL INFORMATION SW Pump A OP 56 _ Status Abbreviations: 8 GP 56 Drywell Cooling Fan 1A OP OP Ope ra t ing C SS O 2A OP SS Secured Status D SS O 3A OP AV Available MTR Fire Pump SR 18 SS SR Standby Readiness DD Fire Pump SR 28 SS SHTDN Shutdown 3B SS S-SP Slow Speed Cntet Vsl Purge Supp Fan A SS F-SP Fast Speed B SS ~ ISOL isolated Cntet Vsl & DW Purge Exh Fan A SS NORM No rua i B SS 00S Out of Service Drywell Purge Suppl Fan A SS CL Closed 6 SS OVRD Override AECTS Fan A 00S B OP e i
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J PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1145 ; RX WATER LEVEL RX PRESS RX POWER SUPR PL TEMP
-145 D WR -
923 PSIC 8 1 140 *E , 60- 1100- 120- - 110 l l 45- 950- 90- 90-30- 800- 40- 70-i ' 15- 650- 0 50 0 500 -30 -20 -10 0 -30 -20 -10 0 20 -10 0 -30 -20 -10 0 Time (min) Time (min) l l' Time (min) Time (min) l l DW TEMP CONTMT TEMP CONTMT PRESS SUPR PL LEVEL 197 'f 133 'f 1.4 PSIC 20.9 LT 200- ~ 110- 20- 19- - 150- 90- 15- - 100- 70- 10- 18-50 50- 5- -
-30. -20 -10 0 -30 -20 -10 0 0- 17 Time (min) Time (min) -5 -30 -20 -10 0
-30 -20 -10 0 Time (min)
Time (min) 9
. r- , . . . . s. , ~:,. w , - . n.;. . .,. ~ s. .. -. - -
PERRY IIUCLEAR POWER PLANT 1984 EMERCEIICY PREPAREDIIESS EXERCISE Til4E: 1145 PAllEL P604 PANELS P669. P670. P671. P672 Process Radiation femin Steam Line RAD . 7.0E+1 mR/hr Alare Cntet vent Exh RAD 41.0E-1 mR/hr Offgas Pre-treatment 2.5E+1 R/hr Offgas Post-treatment A 2.0E+2 cpm PANEL P902 8 2.0E+2 cpm Common Airborne Gas (coal Alare e Eng Service Water A 3.0E+1 cpe' RW8 Vent Exh 2.0E+1 8 3.0E+1 cpe FHS Vent Exh 2.2E+1 OG Carbon Bed Vault A L.0L+1 mR/hr CR Vent Exh 2.0E+1 8 5.5E+1 mR/hr PANEL P906 PANEL 803 Common Process and Area gag Ala re Turb Bldg East LXtg mR/hr UD-MH-73 East Liq 3.0E+1 Turb Bldg West R.5E+0 mR/hr UD-MH-70 West Liq 3.2E+1 NCC Heat HX 3.5E+1 PANEL P804 Radweste to ESW 3.0E+1 Airborne Radiation cas fcoal Alarm Radweste to Sewage Lg+1 , Annulus Exh A Cas 69[+Q 8 ;J[11 Cntet Ata U E12 METEOROLOGICAL CONDIT10N3 Drywell - HR (R/hr) LDE+0 Wind Speed 10.0 mph A8 Vent gJLil
- OC8 Vent Exh 2 0[i2 Wind Direction 240 OC8 Vent - HR 9 QL19 Tempe rature ,
4 'F OC Vent Pipe g 0012 Delta T -' .51 'F U1 Plant Vent 6JEE un Plant Vent - HR QJL10 T8/HS Vent 6 OQ1 T8/HS Vent - HR Q,9QQ ST Packing Exh L8 3 U2 Plant. Vent L9 ;.11 U2 Plant Vent - HR QJJ L+9 DW170C/A/32/es
AREA RADIATION MONITORS Time: 1145 . TAG # LOCATION READING (mR/hr) 1D21NO30 Personnel Air Lock, Cntmt (600'6") 5.0E+0 1D21N040 CRD HCU West, Cntmt (620'6") 5.0E+0 1D21N050 RBRT Area, Cntmt (642') 1.0E+2 1D21N060 Tip Drive Area, Cntmt (600'6") 3.0E+1
', ID21N070 RWCU F/D Area, Cntmt (664'7") 7.0E+0 1D21N080 Upper Pool Area, Cntmt (689'6") 2.0E+0 1D21N110 Aux Bldg East (574'10") 7.0E+0 1D21N120 Aux Bldg West (574'10") 7.0E+0 1D21N130 Turb Rm East (647'6") 2.0E+0 1D21N140 CRD HCU East, Cntmt (620'6") 5.0E+0
- ID21N160 Turb Rm West (647'6") 2.0E+0 1D21N170 Turb Bldg (605'6") 2.2E+0 1D21N180 Hotwell Pump Area, TB (577'6") 1.0E+1 j 1D21N190 TB Sump Area, TBC (548'6") 2.0E+1 1D21N200 OGB (584') 1.1E+1
, 1D21N210 Cnds F1tr Pmp Area, TBC (568'6") 9.0E+0 1D21N220 OG After F1tr Area, OGB (602'6") 2.0E+1 1D21N230 HP Fdw Her Area, HB (600'6") 1.0E+1 1D21N240 Fdw Pump Area, HB (647'6") 6.6E+0 -f 1D21N400 CR, CC (654'6") 1.6E-1 l 1D21N410 OG Hold Up Area. TB (577'6") 8.8E+0 i D21N250 RWB West (574'10") 2.5E+1 ! D21N260 RWB East (574'10") 1.5E+1
(, D21N270 RWB (602') 5.0E+0 l D21N280 Process Sample Rm, RWB (623'6") 4.0E+0 D21N290 RW Evap, RWB (623'6") 4.0E+0
- D21N310 FPCU F/D Area, IB (599') 6.0E+0 l D21N320 Fuel Preparation Pool IB (620'6") 6 K5f+$
! D21N330 Spent Fuel Storage Pool, IB (620'6") m F.CE+ 0 1 D21N420 FPCU Cire Pmp Area, IB (574'10") 9.0E+0 ! 1D21N340 Unit 1 DW, Portable, Cntmt (655') -
1, D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1 D21N370 SRW Drumming Area, RWB (623'6") 6.0E+0 1D21N090 Refueling Bridge, Cntmt (689'6") 3.0E+0 ! D21N390 Fuel Serv Hdig Platform, IB (620'6") M 3.GE*W l 9
* = Alarm OS = Offscale
Tima: 1155 Message No.: 57 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Messane For: Control Room /TSC/ EOF Simulated Plant Conditions: See attached sheets Messame: ***THIS IS A DRILL *** 1 t ,a i. P FOR CONTROLLER USE ONLY ]-i " Controller Notes: Safety Relief Valve B21-F051D has closed, and Suppression Pool temperature begins to decrease. Actions Expected: , I DW176/C/57/ba
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.a TIME: 1200 1988: EMERGENCY PREPAREDNESS EXERCISE PERRY IIUC8 EAR POWER PLANT
- CONTROL ROOM AleNUllCI ATORS P680 P870 as BACK PANELS P601/P877 Section 3A CONT RM HVAC Section 5A js Section 20A Section 19A EMERG RCIRC A P904 MA10UAL SCRAM FDW BOOSTER INITIATED
] ADS B SUPP POOL SWITCH ARMED PUMP A l LEVEL A HIGH PERMISSIVE TRIP CONT RM HVAC' l RHR B/C RUll RPS LOGIC EMERG RCIRC B SUPP POOL FDW BOOSTER INITIATED. P904 l ADS A MANUAL SCRAM ' TEMP A HIGH PUMP B PERMISSIVE RRCS MAN TRIP 4 CONTAIMMENT RPV L-3 INITIATION PRESS A HIGH FDW BOOSTER ADS B RPS LOW LEVEL PUMP C DRYWELL PERMISSIVE L-3 Fall TO START PRESS A HIGH RPV L-3 RRCS FDW BOOSTER LOGIC FOR LPCS/ ADS A RX LEVEL PUMP D LPCI A FRM RHR A PERMISSIVE LO L-2 Fall TO START , DW PRESS HIGH DW PRESS HIGH RPS REACTOR FDW C00lTAIIIMENT ADS B DRWELL PUMP A TRIP l
! TEMP A HIGH PERMISSIVE PRESS HICH DW PRESS HIGH MOTOR FDW PUMP DRWELL Section 7A FAIL TO START i TEMP A HIGH SAFETY / RELIEF VALVE LEAKAGE Section 17A Section 17A ALARM P614 i
SUPP POOL CONTAINMENT TEMP B HIGH l LEVEL B HIGH DRWELL SUPP POOL TEMP B 1 TEMP B HIGH HIGH i CONTAlleMENT
- _[ ! PRESS B HIGH DRWELL t PRESS B HICH
- LOGIC FOR LPCI B/C - FM RHR DW PRESS HIGH i
\
i DW170B/A/98/kay b i
li._ ..,: Mr ,/- e. . _ - - s _. ;,; .- %. ; / ._.w _ _ c ..;. . ~ . . . _ . .,_. PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1200 J P601 P680 CONTAINMENT PARAMETERS SYSTEM INFORMATion REACTOR PARAMETERS Tempe ra ture Pressure Pressure Flow Pressure 923 psig f*FI fosiel Status fosion feoel i. Level -146 In. WR Cntet 136 1.5 RWCU PMP A SS Neutron Drywell 203 4.0 B SS Mon 8 Range ef33 HWt_ PHP A OP 230 Mode SW SHTDN Tempe ra ture Level (*F1 fft.) B OP 230 FDW Flw 0 Mib/hr Supr Pt 136 21.0 C SS 0 ST F1w (Total) 1.2 Mlb/hr C8P A SS 150 Line A .3 SYSTEMS INFORMATION 8 SS 150 Line 8 .3 Pressure Flow Status. fosten fopel C SS 150 _ Line C .3 RHR A PMP OVRD 0 RFBP A SS 160 Line D .3 8 SP Ctc 250 7000 B SS 160 C VLV OVBD 275 0 C SS 160 LPCS PMP OVRD 0 D SS 160
, RCIC OP 1000 700 RFP A SS O O HPCS y1V OVRD 1000 0 8 SS O O ECC A 00S MFP 'SS 0 0
.TUBSI NE-GMERATOR B OP 114 RCIRC A SS O PARAMETERS
. ESW A OOS 8 SS O Natt 0 r 8 OP 95 M 14R 0 MAJOR VALVE PARAMETERS C OP 95 CNF Vac 28 in. Hg Status Close<1 Open CRD A SS Thrt Pr 922 psig MSIV NORM 0 8 8 SS BYP VLV SRV NORM 19 0 Posit 2/ %
SLC A OP 1600 8 OP 16C0 SLC STC TK LVL 4600 gal.
=
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TIME: 1200 1984 EMERCEDICY PREPAREDNESS EXERCISE PERRY NUCLEAR POWER PLANT ELECTRICAL DISTRIBUTION 2298 P870 StatuL. 413.000 cal. E stus_ Load 10011 CST Level Cont Re HVAC Supp Fan A OP
-Offsite Pwr Sources 2 AV Status losiel_
8 OP con Breakers 2 CL TBCC PMP A 0F _ 75 SS 00S Cont Re HVAC Rtn Fan A B OP 75 Div 1 DG B SS OP O C SS 18 Div 2 DG Cont Rm Eng RCIRC Fan A OP OP O SA Coop OP 128 Div 3 DG B OP IA Coop SR 120 _ pg 46 _ Status _ CIRW PMP A OP ure P Cntet Vsl Cig Fan A 0F B OP 45 B OP SS 35 C OP 46 IICC Pump A C SS SJAE A OP D OP p B SS E 09 A OP 56 SW Pump ADOITIONAL INFORMATION 3 OP 56 8 Status Abbreviations: Drywell Coollag Fan IA OP C SS 0 OP Opera ting 2A OP O D SS SS Secured Status p SR MTR Fire Pump AV Available DO Fire Pump SR SR Standby Readiness SHTDN Shutdown . Slow Speed Cntet Val Purge S-SP Supp fan A SS F-SP Fast Speed ISOL isolated Cntet Val er DW SS Purge Exh Fan A 910RM Normal 3 Out of Service Drywell Purge 00S Suppl Fan A SS CL Closed OVRD Override A 00S AECTS Fan B OP
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3 ~- PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1200
~ + PANEL P604 PANELS P669. P670'. P671. P672 Process Radiation Main Steam Line RAD' 1.0E+1 mR/hr MtEn Cntet Vent Exh RAD 41.0E-1 mR/hr Orrgas Pre-treatment 2.5E+1 R/hr Offgas Post-treatment A 2.0E+2 cpm EA,NEL P902 8 2.0E+2 cpm Common Airborne Gas (coal Alarm l
Eng Service Water A- 3.0E+1 cpm RWB Vent Exh 2.0E+1 B 3.0E+1 cpm FHB Vont Exh 2.2E+1 OG Carbon Bed Vault A 6.0Et1 mR/hr CR Vent Exh 2.0E+1 B 5.5E+1 mR/hr PANEL P906 PANEL 803 Common Process and Area EEg Alarm Turb Bldg East 2.5E+0 mR/hr UD-Mil-73 East Liq 3.0E+1 Turb Bldg West 2.5E+0 mR/hr UD-MH-70 West Liq 3.2E+1 NCC Heat HX 3.5E+1 PANEL P804 Radweste to ESW 3.0E+1 Airborne Radiation Gas (comi Alarm Radweste to Sewage 3.6E+1 Annulus Exh A Gas QJ EiQ B 3 0(11 METEOROLOGICAL CONDITIONS Cntet Ata 2.7E+2 Drywell - HR (R/hr) L QE_+2 AB Vent 2JEE Wind Speed 7.0 mph 250
- OGB Vent Exh 2J 12 Wind Direction Tempe ra tu re 4 *F OGB Vent - HR Q0 d -' .42 "F OG Vent Pipe 20 12 Delta T U1 Plant Vent 6J 11
, U1 Plant Vent - HR Q101Q TB/ IIB Vent LDEM l 18/118 Vent - HR O_ 0[1Q . ST Packing Exh 3JE_tQ U2 Plant Vent 6 OL+1 U2 Plant Vent - HR 0.0E+0 l DW170C/A f 34/es e
d
~
AREA RADIATION MONITORS Time: 1200 , TAG # LOCATION READING (mR/hr) 1D21NO30 Personnel Air Lock, Cntmt (600'6") OS) 1.0E+4
- 1D21N040 CRD HCU West, Cntmt (620'6") OS> 1.0E+4
- ID21N050 RBRT Area, Cntmt (642') OS > 1. 0E+4 *
! 1D21N060 Tip Drive Area, Cntmt (600'6") OS> 1.0E+4 *
- , ID21N070 RWCU F/D Area, Cntmt (664'7") OS> 1.0E+4
- i 1D21N080 Upper Pool Area, Cntat (689'6") OS > 1.0E+4
- 1D21N110 Aux Bldg East . (574'10") 3.4E+2 *
~! 1D21N120 Aux Bldg West (574'10") 3.4E+2
- _; 1D21N130 Turb Rm East (647'6") 2.0E+0
-j 1D21N140 CRD HCU East, Cntmt (620'6") OS > 1.0E+4 *
- 1 1D21N160 Turb Rm West (647'6") 2.0E+0 j 1D21N170 Turb Bldg (605'6") 2.2E+0 1D21N180 Hotwell Pump Area, TB (577'6") 1.0E+1
.j 1D21N190 TB Sump Area, TBC (548'6") 2.0E+1
- j 1D21N200 OGB (584') 1.1E+1
! ID21N210 Cnds F1tr Pmp Area, TBC (568'6") 9.0E+0 1 1D21N220 OG After Fitr Area, OGB (602'6") 2.0E+1 i 1D21N230 HP Fdw Htr Area, HB (600'6") 1.0E+1 1D21N240 Fdu Pump Area, HB (647'6") 6.0E+0 ID21N400 CR, CC (654'6") 1.6E-1
- 4 1D21N410 OG Hold Up Area TB (577'6") 8.7E+0 4
i D21N250 RWB West (574'10") 2.5E+1 j D21N260 RWB East (574'10") 1.5E+1 i D21N270 RWB (602') 5.0E+0 D21N280 Process Sample Rm, RWB (623'6") 4.0E+0
.; D21N290 RW Evap, RWB (623'6") 4.0E+0 D21N310 FPCU F/D Area, IB (599') 3.5E+2
- 4 D21N320 Fuel Preparation Pool, IB (620'6") 3.2E+2 *
.]
; D21N330 Spent Fuel Storage Pool, IB (620'6") 3.3E+2
- D21N420 FPCU Cire Pmp Area, IB (574'10") 3.0E+2
- Unit 1 DW, Portable Cntmt (655')
~
1D21N340 - D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1 D21N370 SRW Drumming Area, RWB (623'6") 6.0E+0 1D21N090 Refueling Bridge, Cntmt (689'6") 05 > 1. 0E+4 * (620'6") 3.4E+2 *
- l. D21N390 Fuel Serv Hdig Platform, IB i'
l ra t .
* = Alarm OS = Offscale
Time: 1201 Message No.: 59 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM
- Message For: Control Room /TSC/ EOF ! Simulated Plant Conditions: See attached sheets Messaae: ***THIS IS A DRILL ***
'l. _
~*
t i 4 . 3 FOR CONTROLLER USE ONLY 4-fj l{ Controller Notes: 1. RCIC is placed in service, but reactor water level . continues to decrease to seven inches above the top of active fuel.
- 2. Reactor water level is -153" (7" above TAF) and MSIVs isolate.
ii
- 3. Main Steam Isolation Valves status shows both open and y closed, indicating that the valves are closing.
3-Actions Expected: 4 4 DW176/C/59/ba
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PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1201 CONTROL ROOM ANNUNCIATORS I P601/P877 P680 P870 & BACK PANELS Section 20A Section 19A Section 19A Section SA Sectica 3A CONT RM HVAC EMERC RCIRC A SUPP POOL ADS B ADS A MANUAL SCRAM 1FDWBOOSTER INITIATED P904 LEVEL A HICH PERMISSIVE INSTANTAN:0US SWITCH ARMED PDMP A RHR B/C RUN LOGIC INITIATED ~ - - TRIP CONT RM HVAC SUPP POOL RPS LOGIC EMERC RCIRC B TEMP A HICH ADS A ADS B MANUAL SCRAM FDW B00SlER INITIATED P904 PERMISSIVE INSTANTANEOUS PUMP B CONTAINMENT- RPV L-3 LOGIC INITIATED RRCS MAN TRIP e i PRESS A HICH INITIATION a l ADS B ADS A l FDW BOOSTER DRYWELL PERMISSIVE TIME DELAY RPS LOW LEVEL PUMP C . PRESS A HIGH RPV L-3 LOGIC INITIATED L-3 lFAllTOSTART I FDW BOOSTER I LOGIC FOR LPCS/ ADS A ADS B RRCS LPCI A FRM RHR A PERMISSIVE TIME DELAY RX LEVEL PUMP D DW PRESS HICH DW PRESS HICil LOGIC INITIATED LO L-2 lFAllTOSTARTl CONTAINMENT ADS B RPS REACTOR FDW TEMP A HIGH PERMISSIVE ! DRYWELL DW PRESS HICH PRESS HICH __, P.MHf (_JR1P,l g SUPP POOL MOTOR FDW PUMP 3 MAKEUP TRAIN A TIMER ACTUATED RPS MSIV CLOSURE l---Fall --- TO STARH DRYWELL Section 7A TEMP A SAFETY / RELIEF HICH VALVE LEAKAGE , *LAPM P614 5 Section ITA Section 17A SUPP POOL CONTAINMENT LEVEL B TEMP B HICH HIGH AREA RAD DRYWELL MON PANEL SUPP POOL TEMP B ALARM P803 TEMP B 181Cl1 H IGil Section 8A CONTAINMENT SUPP POOL PRESS B HIGH MAKEUP TRAIN B COM AREA /PRCS TIMER ACTUATED RAD MON PANEL DRYWELL ALARM P906 PRESS B lilGil LOGIC FOR LPCI B/C IM RHR , DW PRESS tilCH t DW170B/A/101/Jsg
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O PERRY NUCLEAR POWER PLAlli 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1201 P870 ELECTRICAL DISTRIBUTION P904 , CST Level 410.000 cal. Attus._ Load fMW1 Status Status josial . Offsite Pwr Sources 2 AV Cont Rm HVAC Supp Fan A OP , TBCC PM? A OP 75 Can Breakers 2 CL B OP B OP 75 Div 1 DG 00S Cont Rm HVAC Rtn Fan A SS C SS 18 Div 2 DG OP O 8 SS SA Comp OP 128 Div 3 DG OP O Cont Rm Eng RCIRC Fan A OP IA Comp SR 120 B OP E600
.CIRW PMP A OP 46 __ Status P970 B OP 45 Cntet Vsl Cig Fan A OP Pressu re Status fosial C OP 46 B OP NCC Pump A SS 35 SJAE A OP C SS B SS 35 B SS D OP C OP- 112 E OP ADOITIONAL INFORMATION SW Pump A OP 56 F SS Status Abbreviations: B OP 56 Drywe 1 i Coo I ing Fan 1 A OP OP Ope ra ting , C SS O 2A OP ,
SS Secured Status D SS O 3A OP Av Available MTR F i re Pump SR 1B SS SR Standby Readiness DD Fire Pump SR 2B SS
- SHTDN Shutdown 38 SS S-SP Slow Speed Cntet Vs1 Purge Supp Fan A SS F-SP Fast Speed B SS ISOL 1solated Cntet Val & DW Purge Exh Fan A SS NORM No rua i B SS 00S Out of Service Drywe l l Purge Suppl Fan A SS CL Closed B SS OVRD Override AEGTS Fan A OOS B OP
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PERRY NUCLEAR POWER PLANT 1984 EMERCENCY PREPAREDNESS EXERCISE. TIME: 1201 RX WATER LEVEL RX PP QE RX POWER SUPR PL TEMP
+7 la FZ 957 Efg 8 y 136
- f.
60- 1100- 120- 110 45- 950- 90-' 90- . 30- 800- 40- 70-15- 650- 0 50 0 500 -30 -20 -10 0 -30 -20 -10 0 r
-30 -20 -10 0 -30 -20 -10 0 Time (min) Time (min)
Time (min) Time (min) t i DW TEMP CONTMT TEMP CONTMT PRESS SUPR PL LEVEL 203 *f 136 *f 1.5 ESE. 21.0 fl 110- 19-200- -. 20-150- 90- 15- - 100- 70- 10- 18-l 50 50- 5- - 4
-30 -20 -10 0 -30 -20 -10 0 0- 17 Time (min) Time (min) -5 -30 -20 -10 0 l -30 -20 -10 0 Time (min) i Time (min)
I I i :
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PERRY lluCLEAR POWER PLANT 1984 EMERCENCY PREPAREDNESS EXERCISE TIME: 1201-PANEL P604 PANELS P669. P670. P671. P672 Process Radiation Main Steam Line RAD 0.0E+0 mR/hr Alarg Cntet Vent Exh RAD 41.0E-1 mR/hr Offgas Pre-treatment 2.5E+1 R/hr Offgas Post-treatment A 2.0E+2 cpm PANEL P902 8 2.0E+2 cpm Common Airborne Cas Icomi Ala re Eng Service Water A 3.0E+1 cpm RW8 Vent Exh 2.0E+1 8 3.0E+1 cpm FHS Vent Exh 2.2E+1 OG Carbon Bed Vault A 6.0E+1 mR/hr CR Vent Exh 2.0E+1 8 5.5E+1 mR/hr PANEL P906 PANEL 803 Common Process and Area ggtg Alarm . Turb Bldg East 2.5E+0 mR/hr UD-MH-73 East Liq 3.0E+1 Turb Bldg West 2.5E+0 mR/hr UD-MH-70 West Liq 3.2E+1 NCC Heat HX 3.5E+1 M[L_,.[M Radweste to ESW 3.0E+1 Airborne Radiation G!LICoal Alare Radwasto to Sewage L61+1 Annulus Exh A Cas 0,9&O 8 LQEg Catet Ate al,DE_ tit H METEOROLOGICAL CONDITIONS DryweII - HR (R/hr) }JE12_ Wind Speed 7.0 mph A8 Vent LDE_t1 250
- OC8 Vent Exh g,9[.12 Wind Direction OG8 Vent - HR O u GE_+9 Tempe rature 4'- *F OG Vent Pipe 2 0012 Delta T -' .42 *F
- U1 Plant Vent 6,9Q1 .
Us Psant Vent - HR Q,QE_tQ TB/HB Vent 6,p E_+ 1 18/118 Vent 'tR 0 0010 ST Packing Exh 2,QE_tQ U2 Plant Vent 6,0E_11 U2 Plant Vent - HR QJMQ DW170C/A/35/es
AREA RADIATION MONITORS Time: 1201 ,
'}
r TAG # LOCATION READING (mR/hr) 1D21NO30 Personnel Air Lock. Cntet (600'6") OS >1.0E+4
- i 1D21N040 CRD HCU West. Cntet RBRT Area Catet (620'6") OS 11.0E+4
- 4 1D21N050 (642') OS > 1.0E+4
- 1 1D21N060 Tip Drive Area. Catet (600'6") OS > 1.0E+4 *
] 1D21N070 RWCU F/D Area. Cntet (664'7") OS > 1.0E+4
- j 1D21N080 Upper' Pool Area. Cntet (689'6") OS > 1. 0E+4
- 1 1D21N110 Aux Blda East (574'10") 3.4E+2
- 1 1D21N120 Aux Blda West (574'10") 3.4E+2 *
] - 1D21N130 Turb Rm East (647'6") 2.0E+0 a 1D21N140 CRD HCU East. Cntet (620'6") OS > 1.0E+4
- 1D21N160 Turb Rm West (647'6"). 2.0E+0
, ID21N170 Turb Blda (605'6") 2.2E+0 i 1D21N180 Hotwell Pump Area. TB (577'6") 1.0E+1
] 1D21N190 TB Sump Area. TBC (548'6") 2.0E+1 1D21N200 OGB (584') 1.1E+1 l 1D21N210 Cnds F1tr Pmp Area. TBC (568'6") 9.0E+0 i 1D21N220 OG After Fitr Area. OGB (602'6") 2.0E+1
't 1D21N230 HP Fdw Htr Area. HB (600'6") 1.0E+1 1D21N240 Fdw Pump Area. HB (647'6") 5.8E+0 1D21N400 CR CC (654'6") 1.6E-1
. 1D21N410 OG Hold Up Area. TB (577'6") 8.7E+0
'l D21N250 RWB West (574'10") 2.5E+1 i D21N260 RWB East (574'10") 1.5E+1 4 D21N270 RWB (602') 5.0E+0 D21N280 Process Sample Rs. RWB (623'6") 4.0E+0 D21N290 RW Evan. RWB (623'6") 4.0E+0 D21N310 FPCU F/D Area. IB (599') 3.5E+2
- D21N320 Fuel Preparation Pool. IB (620'6") 3.2E+2
- ej. D21N330 Spent Fuel Storane Pool. IB (620'6") 3.3E+2 *
'n D21N420 FPCU Cire Pmp Area. IB (574'10") 3.0E+2
- 1D21N340 Unit 1 DW, Portable. Cntet (655') -
u _ D21N380 Waste Compactor Area. RWB (623'6") 6.0E+1 d D21N370 SRW Drummina Area. RWB (623'6") 6.0E+0 j 1D21N090 Refuelina Bridae. Cntet (689'6") OS > 1. 0E+4 *
; D21N390 Fuel Serv Hdla Platform. IB (620'6") 3.4E+2 * .4
, s. ' i
'r'
'l 4
* = Alarm OS = Offscale
~ . .. - . ~_ - .. .--. _
Time: 1202 Message No.: 60 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM d. ( Messane For: Control Room /TSC/ EOF
.. Simulated Plant Conditions: See attached sheets Messame: ***THIS IS A DRILL *** ,3 e # j.
3 O -
;[- .
4
- i. .' .
i FOR CONTROLLER USE ONLY 41 [ Controller Notes: . Containment Building Area Radiation Monitors alarm. The
;; Reactor Core is uncovered.
r s' The reactor should be depressurized to the Suppression Pool s Actions Expected: by the operators via the safety relief valves (SRVs) in -
' accordance with PEI-1, Attachment 5.
i k 4
- DW176/C/60/ba ,
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PERRY IIUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDI6ESS EXERCISE TIME: 1202 ColliROL ROOM AlinullCI ATORS P601/P877 P680 , P870 t 8ACK PANELS Section19A Section 5A SectionhA CONT RM HVAC Section 20A Section 19A i EMERC RCIRC A ADS 8 ADS A MANUAL SCRAM REACTOR FDW INITIATED P904 SUPP POOL PUMP A TRIP LEVEL A HIC:t PERMISSIVE INSTANTANEOUS SWITCH ARMED LOGIC INITIATED i CONT RM HVAC RHR 8/C RUN EMERC RCIRC 8 SUPP POOL RPS LOGIC ADS A ADS 8 MANUAL SCRAM INITIATED P904 TEMP A HICH + PERMISSIVE INSTANTANEOUS CONTAINMENT RPV L-3 LOGIC INITIATED RRCS MAN PRESS A HICH INITIATION ADS 8 ADS A DRWELL PERMISSIVE TIME DELAY RPS LOW LEVEL PRESS A HIGH RPV L-3 LOGIC INITIATED L-3 LOGIC FOR LPCS/ ADS A ADS 8 RRCS LPCI A FRM RHR A PERMISSIVE TIME DELAY RX LEVEL DW PRESS HIGH DW PRESS HIGH LOGIC INITIATED LO L-2 C00lTAINMENT ADS B RPS TEMP A HICH PERMISSIVE DRWEL L DW PRESS HICH PRESS HIGH DRWELL RPS TEMP A MSIV CLOSURE HICH l Section 7A Section 17A Section ITA SUPP POOL C006TAlleMENT SAFETY / RELIEF LEVEL 8 TEMP 8 HICH VALVE LEAKAGE HICH ALARM P614 DRWELL SUPP POOL TEMP B AREA RAD TEMP B HICH HIGH MON PANEL ALARM P803 CONTAlleMENT PRESS 8 HICH Section 8A DRWELL COM AREA /PRCS PRESS 8 HICH RAD MON PANEL
. ALARM P906 f LOGIC FOR LPCI B/C f M RilR DW PRESS HICH e
DW1708/A/104/Jsg
- - w.mm . .,2 . -..~_;, .. _ __. 4 s . 2 -- ~ m.n a - , m . . , ,
1 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPARE 0 NESS EXERCISE TIME: 1202 2601 f489 C04TAl4NENT PARAMETERS SYSTEM INFORMATION REACTOR PARAMETERS Tempe ra ture Pressure Pressu re Flow Pressure 303 psig ' f*F1 fosial Status fosle) feoel
, tevel -8 In. FZ Catet 136 1.5 RWCU PMP A SS Neutron Drywel l 203 4.0 8 SS Mon 7 Range APftM HWL PMP A OP 230 Mode SW SHTDN Tempera ture Level f*F1 (Ft.) B OP 230 FDW Few 0 Mlb/hr Supr Pl 138 21.0 C SS 0 ST FIw (Total) O MIb/hr C8P A SS 150 Line A 0 SYSTEMS INFORMATION 8 SS 150 Line 8 0 Pressure Flow Jtatus f osien . -
femel C SS 150 Line C 0 RHR A PMP OVRD RFBP A SS 160 Line D 0 B VLV OVRO 275 0 8 SS 160 C VLV OVRD 275 0 C SS 160 LPCS PMP OVRO D SS 160 j RCIC FLOW OVRO 200 0 RFP A SS L 0 HPCS VLV OVRO 1000 0 B SS 0 0 ECC A 005 MFP SS O O Tuft 81NE-GENERATOR S OP 114 RCIRC A SS O PARAMETERS ESW A 00S S SS , O Na tt 0 8 OP 95 MVAR 0 MMOR VALVE PARAMETERS C OP 95 CNOR Vac 26 in. Hg CRO A SS Thrt Pr 0 psig MSIV ' ISOL 8 0 S SS BYP VLV SRV AOS 11 8 Posit O % SLC A OP 1600 8 OP 1600 SLC STC TK LVL 4600 gal. e
.---. ,, -- . ,. n n. - . . . ~ . - - -
FUWtY IguCLEAR P0hfER PLAsIT 1984 EfeEftCEtICY PREPAftEDIIESS EXERCISE TiteE: 1202 2329 ELECiltlCAL DISTRIBUT10el 29th , CST Level 410.000 eat. Status Load trail Status i Statess fesiel -Offsite Pwr Sources 2 AV Cont its HVAC Supp Fan A OP -TOCC Fler A OP 75 Gen Brechers 2 CL B OP a OP 75 - Div 1 DC 005 Coat Rm HVAC Rtn Fan A SS C SS 18 Div 2 DC OP O B SS SA Ceep OP 128 Div 3 DC OP O Cont Its Eag IICIRC Fan A OP IA Ceep Sfl 12e B 0F CIftli 790P A OP 46 Status P970 g OP 45 Catet Vsl Cig Fan A OP 9 Pressure Status insiel C OP 46 8 OP l IICC Pump A SS 35 SJAE A OP C SS B SS 35 3 SS D OF C OP 112 E OF ADDITICIIAL INF0futATl001 SW Pump A OP 56 F $$ Status Abbreviations:
' B OP 56 Dryuell Coeling Fan IA 0F OP Ope rating C SS O 2A OP SS Secured Status D SS O 3A OP AV Available DITR Fire Pump SR IS SS SR Standby Readiness DO Fire Pump SR 28 SS SetTDII $8eutdoun
- 38 SS S-SP Slow Speed Cntat Vsl Purge Supp fan A 'SS F-SP Fast Speed B SS I $04. IsoIated Catat vsI ar DW Purge Exte Fan A SS Isoftet Itsrue I B ' SS 00S Out of Service Dryuell Purge
- Suppl Fan A SS CL Closed B SS OVRO Override AECTS Fan A 00s B OP
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i 1984 EleERGEIICY PREPAftEDII(SS EMACISE
. TifeE: 1202 PEmitY IIUCLEAR POWES PUMIT PASEL P604 PAeEI_5 P669. M70. P671. M72
. IIsin Steen Line RAD 0.0E+0 est/hr .
Preessa medletlen Afare
- Catet Vent Exh IRAD 41.0E-1 aft /hr Offges Pre-trootment 2.M+1 R/hr PAIIEL PgG2 Offges Post-treeteent A 2.0E+2 cpe 2.0E+2 cpe Ceeman Atrtorne Gas iceal Alare S
A Lghi cpe Hida Vent ' Exh 2.0E+1 Eng Service Water S LgQ1 cpe Fles Vent Exh 2.2E+1 Cat Vent Exh 2.0E+1 OG Carten Red vault A 6.0E+1 aft /hr 3 5. M+1 oA/hr PAIIEL P906 Ceeman Process and Aree gag - Alare PAIIEL 803 400 -886- 1 3 East Lig 3.0E+1 Turt Side East 2. M +0 aft /hr US-Sef-T0 West Lig 3.2E+1 Turt SIdg West 2. M +0 est/hr IICC Heat NK 3.5E+1 PAfgEL P904 Radweste to ESW 3.0E+1 Gas Icool Alare Itadweste to Sowege 3.6E+1 Airterne mediation Annulus Ext A Cas g E ig 8 LOT M IIETEOROLOGICAL COISITIcess Catet Ate >LDC+h Drywel t - IIR (R/hr) 3,9di 7.o eph As vent 2.9W Wind Speed
- g,prft Wind oirection. 2%
oGS vent Exn Temperature t' 'I OGS vent - sem g,p[ig -
.42 *F Oc vent Pipe 2.9[12' Belta T vi esent vent 6.ohl
'J1 Plant vent - IIR g,9[+9 18/188 vent 6.9Lt1 18/918 vent - IIR g,9{+9 ST Packing Enti gpEM u2 riant vent m phi u2 Psant vent - east 0.0E+0 sW170C/A/3E/es .
O e
i . j. l; 4 1 AREA RADIATION MONITORS Time: l'202
!i
- i TAG # LOCATION READING (mR/hr)
- 1D21NO30 Personnel Air Lock. Cntat (600'6") OS > 1.0EM
- A 1D21N040 CRD HCU West. Catst (620'6") 05 > 1.0EM
- d 1D21N050 RBRT Area. Catet (642') 08 > 1.0E+4 *
}t 1D21N060 Tio Drive! Area. Catet (600'6") 05 > 1.0EM * .! 1D21N070 RWCU F/D Area. Catet (664'7") OS > 1.0EM *
- 1D21N080 Upoor Pool Area. Catet (689'6") 08 > 1.0EM
- 1' 1D21N110 Aux Blda East .
(574'10") 3.4E+2 *
!! 1D21N110 Aux Blda West (574'10") 3.4E+2
- II 1D21N130 Turb Re East (647'6") 2.0E+0 ij 1D21N140 CRD HCU East. Catst (620'6") OS > 1.0EM
- 1D21N160 Turb Rs West (647'6") 2.0E+0 1D21N170 Turb Blda (605'6") 2.2E+0
.: 1D21N180 Hotwell Pump Area. T3 (577'6") 1.0E+1 jl 1D21N190 T3 Suen Area. TBC (548'6") 2.0E+1 it 1D21N200 OG3 (584') 1.1E+1 '! 1D21N210 Cads Fitr Pan Area. TSC (568'6") 9.0 ;+0 ;l 1D21N220 OG After Fitr Area. 0GB (602'6") 2. 0: ;+1
!l 1D21N230 HP Fdu Mtr Area. MB (600'6") 1. 0' ;+1 - 1 1)21N240 Fdw Pues Area. MB (647'6") 5.4 ;+0 ' ! 1:321N400 CR. CC (654'6") 1. 6' ;-1 :
.c 1D21N410 OG Hold Us Area. T3 (577'6") 8.7 ;+0 -
D21N250 RW3 West (574'10") 2. 5: ;+1 D21N260 RW3 East (574'10") 1. 5: ;+1 l l. D21N270 RWB (602') 5.0 ;+0 > t D21N280 Process Saanle Rs. RWB (623'6") 4.0E+0 , U ~ 021N290 RW Evas.8RWB (623'6") 4.0E+0 l FPCU F/D' Area. IS (599') * ' D21N310 3.5E+2 D21N320 Fuel Preparation Pool. IS (620'6") 3.2E+2 * !I D21N330 Spent Fuel Storane Pool. 13 (620'6") 3.3E+2 * : jl D21N420 FPCU Cire Pao Area. II (574'10") 3.0E+2 * ;
. 1021N340 Unit 1 DW, Portable. Catet (655') -
j!
; D21N380 Waste Cospactor Area. RWB (623'6") 6.0E+1 3' D21N370 SRW Drummina Area. RWB (623'6") 6.0E+0 L' 1 )21N090 Refuelina Bridae Cntet (689'6") 05 > 1.0E+4 *
- i. )21N390 Fuel Serv Ndla Platfore. IB (620'6") 3.4E+2 *
.i
!} u . l} ! <4 I l t i
, * = Alare I j 08 = Offscale l
y -. ,.%,,--.--_m . c.., - --- , - - , . . ,.~.. ...-.. - - - ~ -+ - - . w ----wrw.-
Time: 1204 Message No.: 61 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM t Messaae For: Control Room /TSC/ EOF Simulated Plant Conditions: See attached sheets .' *I { Messame: ***THIS IS A DRILL *** 1 ( f . b
\
l tL 4 FOR CONTROLLER USE ONLY l l -1
; controller Notes: Reactor water decreases to 43 inches below the top of the 4 , active fuel. ;t Actions Expected:
I. S
, DW176/C/61/ba
, ,. ._u,, .g- _ __.
i PERRY IIUCLEAR POWER PLAdli 1964 EMERCEIICY PREPAREDISESS EXERCISE TIME: 1204 COIITROL ROOM A8IIIUpICI ATORS P601/P877' P680 P870 & BACK PA81ELS Section 20A Section 19A Section 19A Section SA Section 3A . Cotti RM HVAC EMERC RCIRC A SUPP POOL ADS S ADS A MAseUAL SCRAM REACTOR FDW INITIATED P904 LEVEL A HICH PEllMISSIVE IIISTAIITA8eEOUS SWITCH ARMED PUMP A TRIP RHR S/C Ruel LOGIC INITIATED CONT RH IIVAC SUPP POOL RPS LOGIC Section 2A [ HERG RCIRC 8 TEMP A HIGH ADS A ADS S MA800Al SCRAM INITIATED P90as PERMISSIVE INSTANTAstEOUS LP C0000EllSER CoelTAllpeENT RPV L-3 LOGIC INITIATED RitCS Mall VACUUM LOW PftESS A HICH INITIAT1000 ADS S ADS A IP C008 DENSER CRWELL PElsetSSIVE TapeE DELAY RPS LOW LEVEL VACUUM LOW PftESS A HICH RPV L-3 LOCIC INSTIATED L-3 tiP C0eIDENSER LOCIC FOR LPCS/ ADS A ADS S RRCS VACUUM LOW LPCI A FItM RHet A PEllMISSIVE TIME DELAY RX LEVEL DW PRESS HICH DW PRESS HBCH LOCIC INITIATED LO L-2 CaseTA B NetEItT ADS S RPS TEMP A HIGH PERMISSIVE DetWELL DW PRESS HICH PRESS HICH DRWELL 1 TEMP A RPS i HICH MSIV CLOSultE Sectices ITA Section ITA Section 7A , SUPP POOL CoseTAINMENT SAFETY / RELIEF LEVEL 8 TEtte S HIGH VALVE LEAKACE HICH ALARM P611s DRWELL - SUPP POOL TEMP S l t TEMP S HBCH HICH l AREA RAD M001 PANEL C0elTAI199ENT PftESS S HIGH Section SA DRWELL COMAREA/PRCd PetESS S HICH RADH0elPANEtj , AtARM r906 LOCIC FOR -I LPCI */C fM RHR DW PRESS HICH DW1708/A/107/jsg O
~ ~
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. _ _ . , _ _ _.- _ .. . .._ q FLaRY RUCLEAR POWER PLAsIT 1984 EMERGENCY PREPARED 00ESS EXERCISE TIME: 1204 f6El f600 COGITAIIIMElli PAllAMETERS SYSTEM IIsFORMAT1001 NEACTOR PARAMETERS Toepera ture Pressure Pressure Flow Pressure 294 psig f*F1 J o s iel._ Atu_L fosiel_ femel Level -43 in. FZR Catet 138 1.6 ftWCU PMP A SS Neutron DryweiI 204 4.1 8 SS Mon 3 Range e_PBtl MM.,PMP A OP 230 Mode SW SHTD18 Tempera ture Level f*F1 IFt.1 B OP 230 FDW Flw 0 Mib/hr Supr PI 140 21.0 C SS 0 e ST Flw (Total) O Mib/hr CSP A SS 150 Line A 0 SYSTEMS Imf0AMAT1011 8 SS 150 Line 8 0 Pressure Flow Status fasiel femel C SS 150 Line C 0 AHR A PMP OVRD RFBP A' SS 160 Line D 0 S VLV Ovmo 275 'o a SS 160 C VLY OVRO 275 0 C SS 160 LPCS Peer OVRO O SS 160 BCIC FLOW OVRO 120 0 AFP A SS O O MPCS VtV OVRO 1000 0 3 SS 0 0 ECC A 005 MFP SS 0 0 IMERlltf-GfMEftATOR S OP 114 RCIRC A SS O PARAMETERS ESW A 005 B SS 0 Watt 0 B OP 95 MVAR 0 MAJost VALVE PARAMETERS C OP 95 CleDR Vac 25 in. Hg Status Closed Open Cao A SS Thrt Pr 0 psig MSly ISOL 8 0 3 SS SYP VLV SRV ADS 11 8 Posit 0 %
SEC A OP 1600 8 0F 1600 SLC STG TK LVL 4600 gal. e
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1964 EMERCEIICY PREPAREDIIESS EXERCISE TIME: 1204 PERRY IIUCLEAR POWER PLAIIT Pg70 ELECTRICAL DISTRIBUTIOII M 410.000 eat. It1HEL. toad IIed) _ Status CST Level 2 AV Cont Re HVAC Supp Fan A 0F Status fosiel OFFsite Pwr Sources 2 CL 8 OP TDCC Pete A OP 75 Con Breakers 00S Cont Rm HVAC Rtn Fan A SS R OP 75 Div 1 DC OP O 5 SS C SS 18 Div 2 DG Div 3 DC OP O Cont Am Eng RCIRC Fan A or SA Camp OP 128
- B OP IA Camp Sft 120 "
~
P900 46 Status CIIIW Pter A OP P970 A OP Pressure 45 Catet Vs1 Cig Fan 3 OP Status J osial c SS O a OP 35 IICC Pump A SS C SS SJAE A SS B SS 35 . D OP a SS C OP 11L E OP SW Pump A OP 56 ADDITIOEAL IIsf 0RetAT t ost F SS
.B OP 56 Status Abbreviations: DryweII Cooling Fan 1A OP C SS O OP Operating 2A OP D SS 0 SS Secured Status 3A OP MTR Fire Pump SR AV Available SS 18 DO Fire Pump SR SA Standby Readiness 28 SS SHID01 Shutdown SS 38 S-SP Slow Speed Cntet Vst Purge Supp Fan A SS F-SP Fast Speed B SS BSOL 1solated Catet Vs1 at DW Purge Exh Fan A SS ,
IsoftM mormal SS B 005 Out of Service Drywell Purge Suppl Fan A SS CL Closed SS B OVRD Ove rride AECTS Fan A 00S 8 OP
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PERRY muCLEAR POWER PLAftT 1964 EMERCEIICY PftEPAREDIIESS EXERCISE TIME: 1204 l PAfgEL P604 PA00ELS P663. P670. P671. P672 Process Radiation Main Stese Line RAD 0.0E+0 mR/hr Alare Catet Vent Exh RAD 41.0E-1 aft /hr Offges Pre-treatment 2.5E+1 R/hr Offges Post-treatment A 2.OE+2 cpe PANEL P902 5 2.0E+2 cpm em Airborne Gas icool Ala re Eng Service Water A 3.0E+1 cpe ItWB vent Exh LOE+1 B 3.0E+1 cpe FHS Vent Exh 2.2E+1 OG Carbon Bed Vault A 6.0E+1 aft /hr CR Vent Exh 2.0E+1 3 5.5E+1 aft /hr PAftEL P906 PAIIEL 803 cm Process and Area see Alare Turt Bldg East 2.5E+0 ' oft /hr US-peH-73 East Lig 3.0E+1 Turt sids West 2.5E+0 aft /hr UO-9tH-70 West Lig 3.2E+1 IICC Heat HX 3.5E+1 PAfsEL P904 Redweste to ESW 3.0E+1 Alrtorne Radiation Gas (csel Alare Radwaste to Sewage 3.6E+1 Annulus Exh A Ces 9 O(+9 5 LQEE Cntet Ato >1 QE+6 H METEOROLOGIGAL CoseppTioses Drywell - leR (R/hr) 6J[1} As Vent LgE_t.1 Wind Speed 7.0 mph OCS Vent Exh L O(+2 Wind Direction 250 OCS Vent - teR QJ[+9 Tempe ra ture 4'
'I OG Vent Pipe LQ[12 Delta T .42 'F U1 Plant vent 6,9[i.1 ul Piant Vent - east 9.o[+9 18/HS Vent 6,9EJ 18/HS Vent - MR g,9(+0 Si Packing Exh hgE_+9 l U2 Plant Vent 6. PEE l U2 Plant Vent - teR 0.OE+0 l
l DW170C/A/37/es 1P e
1 AREA RADIATION MONITORS Time: 1204 , TAG # LOCATION READING (mR/hr) 1D21NO30 Personnel Air Lock, Cntmt (600'6") OS > 1. 0E+4
- 1D21N040 CRD HCU West, Cntmt (620'6") OS ) 1.0E+4
- 1D21N050 RBRT Area, Cntmt (642') OS > 1.0E+4
- 1D21N060 Tip Drive Area, Cntmt (600'6") OS > 1. 0E+4
- 1D21N070 RWCU F/D Area, Cntmt (664'7") OS >1.0E+4
- ID21N080 Upper Pool Area, Cntmt (689'6") OS >1.0E+4
- 1D21N110 Aux Bldg East (574'10") 3.4E+2
- 1D21N120 Aux Blda West (574'10") 3.4E+2
- 1D21N130 Turb Rm East (647'6") 2.0E+0 1D21N140 CRD HCU East, Cntmt (620'6") OS > 1. 0E+4
- 1D21N160 Turb Rm West (647'6") 2.0E+0 1D21N170 Turb Bldg (605'6") 2.1E+0 1D21N180 Hotwell Pump Area. TB (577'6") 1.0E+1 1D21N190 TB Sump Area TBC (548'6") 2.0E+1 -
ID21N200 OGB (584') 1.1E+1 1D21N210 Cnds F1tr Pmp Area, TBC (568'6") 9.0E+0 1D21N220 OG After Fitr Area, OGB (602'6") 2.0E+1 1D21N230 HP Fdw Her Area. HB (600'o") 1.0E+1 1D21N240 Fdw Pump Area, HB (647'6") 1.0E+0 1D21N400 CR, CC (654'6") 1.6E-1 1D21N410 OG Hold Up Area. TB (577'6") 8.7E+0 D21N250 RWB West (574'10") 2.5E+1 D21N260 RWB East (574'10") 1.5E+1 D21N270 RWB (602') 5.0E+0 D21N280 Process Sample Rm, RWB (623'6") 4.0E+0 D21N290 RW Evap, RWB (623'6") 4.0E+0 D21N310 FPCU F/D Area. IB (599') 3.5E+2
- D21N320 Fuel Preparation Pool, IB (620'6") 3.2E+2
- D21N330 Spent Fuel Storage Pool, IB (620'6") 3.3E+2
- D21N420 FPCU Cire Pmp Area. IB (574'10") 3.0E+2
- ID21N340 Unit 1 DW, Portable Cntmt (655') -
D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1 D21N370 SRW Drumming Area, RWB (623'6") 6.0E+0 1D21N090 Refueling Bridge, Cntmt (689'6") OS> 1.0E+4
- D21N390 Fuel Serv Hdig Platform. IB (620'6") 3.4E+2 *
* = Alarm OS = Offscale
V" Time: 1206
, Message No.: 62 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Messane For: I&C Technician at Panel H13-P618 Simuisted Plant Conditions:
4 Messame: ***THIS IS A DRILL *** You have slipped and fallen, damaging some equipment in the panel. You fall to the floor, dazed and unable to speak for a few minutes. When someone arrives, you are somewhat dazed for a short time, but otherwise you are fine. i .? -
- T
,o . FOR CONTROLLER USE ONLY l ' t 1 Controller Notes: 1. In accordance with PEI-1, Attachment 5, Step 7, the i operators direct jumpers to be installed in Panel i
. H13-P618 in order to use RHR B to regain reactor water ' level.
- 2. The I&C Technician inadvertently shorts out the Division 2 RHR LOCA logic which realigns RHR B and C in the LPCI mode. When the sparks arc, he slips and l damages the LPCI B Injection Valve Manual Override Relay E12 K248 in the de-energized mode.
4 .
" Actione Expected i
l l DW176/C/62/ba l l i _ _ - - - _ _ _ . _ - _ - _ - - _ _ _ _ _ . _ _ _ _ _____m_ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ . . _
{. - l 1 I Tico: 1206 Message No.: 63 PERRY NUCLEAR POWER PIJNr i
- h. 1984 EMERGENCY PREPAREDNESS EXERCISE F
, MESSAGE FORM i
Hessaae For: Control Room /TSC/ EOF 1 Simulated Plant Conditions: See attached sheets Messame ***THIS IS A DRILL *** ta l4 a lj - b .
- j r
l .} FOR CONTROLLER USE ONLY controller Notes: The Reactor Vessel begins to floo.d rapidly. RER (LPCI)
- +,
Pumps B and C are injecting cold water into the vessel at the combined flow rate of 14,000 gym. Reactor Vessel level reaches +5 inches Wide Range. Reactor power peaks at 35% and decreases to 40%. t J. Actions Expected go ,'ii , k 'k
'I 4
DW176/C/63/ba L.
. w . = .-- . ; : a. : .o . M. m a - L - > w .. - ~ - . ~ . - .. .,
PEINty amrt rast POWER PLAllT 1984 EMEftGENCY PREPAREDNESS EXERCISE TiteE: 1206 COIITROL ft00lg AIIIIUIICI ATORS P601/PS77 - P680 P870 A BACK'PAIIELS Section 20A Section 198L Section 19A Section 5A Section 3A COIIT RM HVAC EMEftG RCIRC A SUPP POOL ADS S ADS A I4480UAL SCRAM REACTOR FDW INITIATED P90al LEVEL A HIGH PEmpts SSIVE INSTANTAleEOUS SWITCH ARNED PUMP A TRIP RIeR t/c Ruel LOGIC INITIATED COIIT RM HVAC SUPP POOL RPS LOGIC Section 2A EMERG RCIRC 8 TDer A HIGal ADS A ADS B MAIIUAL SCRAM INITIATED P9048 PEmptlSSIVE INSTAleTAalEOUS LP COIIDENSER CoelTAINBeENT RPV L-3 LOGIC INITIATED RRCS Mall VACUUM LOW PRESS A HIGOS INITIAT1000 AOS B ADS A SP COIIDENSER DetWELL PEnstISSIVE TIIEE DELAY RPS LOW LEVEL VACUUM LOW PRESS A HIGbl RPV L-3 LOGIC IIIITIATED L-3 HP COIIDENSER LOGIC FOR LPCS/ AOS A ADS 5 RetCS VACUUM LOW LPCI A FRM RNR A PERetISSIVE TII9E DELAY RX LEVEL DW PRESS HIGli DW PRESS HIGH LOGIC INITIATED LO L-2 CostTAINpeENT ADS S RPS TEMP A HIGal PERetISSIVE DetWELL DW PRESS HIGet PRESS HIGH DRWELL TEMP A RPS HIGH MSIV CLOSultE Section 17A Section 17A Section 7A SUPP POOL CostTAIIIMENT SAFETY / RELIEF LEVEL S TEMP S HIGH VALVE LEAKAGE
^
HIGH ALARM P614 DetWELL SUPP POOL IDer 5 TiMP S HICH HIGH COIII AIMMENT PRESS S HiGH l OstWELL PRESS S mCH LOGIC E0ft LPCI 8/C IM RHft DW PRESS HIGH DW1700/A/110/Js9
5 PERRY IIUCLEAR POWER PLAf8T 1984 EMERCEIICY PREPARED 80ESS EXERCISE TIME: 1206 fnR1 2680 CossTAlWEENT PAfuweETERS SYSTEM INFOfWIATl001 - REACTOR PARAMETERS Temperature Pressure Pressure flow Pressure 200 psig f*FI fasiel Status insiel femel Level -40 in. FZR Catet 138 1.6 RWCU P9er A SS Iseutron Dryuell 204 4.1 8 SS Mon 55 Range afgg HWL P90P A OP 230 Mode SW JJgeL Tampa rature tevel f*F1 fFt.) B OP 230 FDW Flw 0 Mlb/hr Supr PI 140 21.0 C SS O ST Flw (Total) O Mib/hr CSP A SS 150 Line A 0 SYSTDes iRF00 stat 1018 8 SS 150 Line 8 0 Pressure Flow Status fasiel femel C SS 150 Line C 0 RBER A PetP OVRO RFSP A SS 160 Line D 0 S LPCI 278 4000 8 SS 160 C tPCI 275 4010 C SS 160 LPCS Peep OVRO D SS 160 BCIC FLOW oveo 100 0 AFP A SS O O 8tPCS YLV OVRO 1000 0 8 SS O O [CC A 005 MFP SS 0 0 S OP 114 J.MRRIE -C MERATOR RC8RC A SS O PARAMEiERS ESW A OOS S SS 0 Watt 0 S OP MVAR 0
- MAJOR VALVE PARAME1ERS C OP C800R Vac 20 in. Hg Status Closed Osen CRO A SS Thrt Pr 0 psig MSIV ISOL 8 0 8 SS SYP VLV SRV ADS II 8 Posit 0 %
SLC A OP 1600 B OP 1600 SLC Sic TK LYL 4600 gal. N
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i - Pgasy esacasAS pegs PLAST 19386 ENEASEIICY PREreAEButts ENERClK TisIE: 1206 F819 ELECTSICAL StSTSIBIsfles M-l mia.-- ens. Statens Land 10 Sin . Status CST Es Saatans faniet eFFsite Pwr Soestees 2 AW Cent Am IIWC SesPp Fan A OP D ulC pe r A er M Goa Breakers 2 CL , S er S er M Siw 1 SS e85
- Cent As IIWAC Rtm Fan A SS Siw 2 SG er S 8 SS C SS 18 SA Camp er 128 Div 3 SG er e Cent An Eag RCIAC Fan A OP 12e B OP 84 Camp SB CSNdper A er 45 . S$stess M
S er 45 *Catet Val Cig Fan A er Pressure Status fasial C SS e B er NCC Pesep A SS 35 A SS C SS 1AAE S SS 35 S SS S OF C er 112 E OF SW Pesep A OP 56 ASSITIGSAL IN GNehiles SS F 3 OP 56 6 Statass Abbrewletlems: er arywetI CesIlag Fan 1A. C SS 0 er aparettag 2A er 9 SS 0 SS Secesred Statass 3A er MTR Fire Pump' SA Av Avellable IS SS
**medhe SS Fire Pump Sit SS t Goodiness 28 SS SISTSN Saastdown 38 SS S-SP Stew Speed catet vsi Pestge ,
Seapp Fan A SS F-SP Fast Speed 3 SS ISOL Iselsted Catet Vsf & Md Pierge Emte Fan A SS SONO merenI B SS
. 006 West of Sorwice Drywe8i Pierge seappl Fan A SS CL C8osed B SS SWSS everries AEGIS Fan A 006 3 OP 4
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1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1206 PERRY NUCLEAR POWER PLANT PANEL P604 PANELS P669. P670. P671. P672 Main Steam Line RAD 0.0E+0 mR/hr Process Radiation Alarm CntmL Vent Exh RAD 41.0E-1 mR/hr Offgas Pre-treatment 1.25E+2 R/hr 2.0E+2 cpm PANEL P902 Offges Post-treatment A Common Airborne Gas (com) Alarm B 2.0E+2 cpm 3.0E+1 cpm RW8 Vent Exh 2.0E+1 Eng Service Water A 8 3.0E+1 cpm __ FHB Vent Exh 2.2E+1 A 6.0E+1 mR/hr CR Vent Exh 2.0E+1 , OC Carbon Bed Vault 8 5.5E+1 mR/hr PANEL P906 fAliEt, 801 Common Process and Area ggg Afare Turb Bldg East 2.5E+0 mR/hr UD-MH-73 East Liq 3.0E+1 Turb Bldg West 2.5E+0 mR/hr UD-MH-70 West Liq 1 2E+1 . NCC Heat HX 3.5E+1 PANEL P804 Radweste to ESW 3.0E+1 Alarm Radwaste to Sewage 3.6E+1 Airborne Radiation Cas fcoal Annulus Exh A Cas 0,0 +D B LO :+ METEOROLOGICAL CONDITIONS Cntat Atm SLDF+ t H Drywell - HR (R/hr) 6JI:X Wind Speed 7.0 mph AB Vent LQE.1, Wind Direction 250
- OG8 Vent Exh L 915 Tempe ra tu re 4' 'T OCB Vent - HR Q 01:+D
-' .42_ *F OG Vent Pipe LO M Delta T U1 Plant Vent 6 AEil UI Plant Vent - HR Q,0[tD T8/HB Vent 6,0E+1 IB/HB Vent - HR Q,0EiG
- ST Packing Exh h0[-1 U2 Plant Vent 6J[11 U2 Plant Vent - HR 0.0E+0 DW170C/A/38/es b
1 1
- AREA RADIATION MONITORS Time: 1206 ,
3 i TAG # LOCATION READING (mR/hr) ID21NO30 Personnel Air Lock, Cntet (600'6") OS > 1.0E+4
- l j 1D21N040 CRD HCU West, Cntet (620'6") OS> 1.0E+4
- 1 ID21N050 RBRT Area, Cntet (642') OS > 1.0E+4
- h 1D21N060 Tip Drive Area, Cntet (600'6") OS N 1.0E+4
- j 1D21N070 RWCU F/D Area, Cntet (664'7") OS > 1.0E+4 *
- j
, 1D21N080 Upper Pool Area, Cntet (683'6") OS > 1.0E+4 * ,;; 1D21N110 Aux Blda East (574'10") 3.4E+2 *
- 1D21N120 Aux Blda West (574'10") 3.4E+2
- 3 1D21N130 Turb Rm East (647'6") 2.0E+0 y 1D21N140 CRD HCU East, Cntet (620'6") OS > 1.0E+4 *
-j 1D21N160 Turb Rm West (647'6") 2.0E+0 1D21N170 Turb Blda (605'6") 2.1E+0 j 1D21N180 Hotwell Prap Area, TB - (577'6") 1.0E+1
. 1D21N190 TB Sump Area, TBC (548'6") 2.0E+1 1D21N200 OGB (584') 1.1E+1
- 1D21N210 Cnds F1tr Pmp Area TBC (568'6") 9.0E+0 i 1D21N220 OG After Fitr Area, OGB (602'6") 2.0E+1 3 1D21N230 HP Fdw Her Area, HB (600 6") 1.0E+1 1D21N240 Fdw Pump Area, HB (647'6") 9.5E+1 1 1D21N400 CR, CC (654'6") 1.6E-1 1D21N410 OG Hold Up Area, TB (577'6") 8.7E+0 D21N250 RWB West (574'10") 2.5E+1 D21N260 RWB East (574'10") 1.5E+1 j' D21N270 RWB (602') 5.0E+0 i D21N280 Process Sample Rm, RWB (623'6") 4.0E+0 gj.
D21N290 RW Evap, RWB (623'6") 4.0E+0 1 ~' D21N310 FPCU F/D Area, IB (599') 3.5E+2
- j D21N320 Fuel Preparation Pool, IB (620'6") 3.2E+2
- j D21N330 Spent Fuel Storane Pool IB (620'6") 3.3E+2 *
.,' D21N420 FPCU Cire Pmp Area, IB (574'10") 3.0E+2
- j 1D21N340 Unit 1 DW, Portable, Cntat (655') -
- D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1 D21N370 SRW Drummina Area, RWB (623'6") 6.0E+0 J 1D21N090 Refuelina Bridge, Cntet (689'6") OS > 1.0E+4 *
- D21N390 Fuel Serv Hdla Platform, IB (620'6") 3.4E+2
- ii 4
-3 il
* = Alarm OS = Offseale 1
g .
Time: 1208 Message No.: 64 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Messane For: Control Room /TSC/ EOF Simulated Plant Conditions: .See attached sheets
!- Me'ssame: ***THIS IS A DRILL ***
T
- i i- _.
I y .. 3 (i
! 'FOR CONTROLLER USE ONLY "i
4 Controller Notes: 1. The operators should close LPCI-C injection valve, but
- 'i efforts to close the LPCI-B injection valve fail.
.i l-: 2. When the LPCI-B pump control switch is placed in the l -
"Stop" position, the Breaker Trip Control Power Fuse J blows, thus allowing the pump to run. The pump cannot ,7 be tripped from the Control Room. .
- 3. Reactor power decreases to 20%.
Actions Expected: Dispatch a PPO to open the RHR Pump B Breaker (Elevation 620' in the Control Complex). DW176/C/64/ba y or -p e +
,. 7 _ , , , , , , .
PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1208 CONTROL ROOM ANNUNCIATORS P601/P877 P680 P870 & BACK PANELS Section 20A Section 19A Sect'lon 19A Section 5A Section 3A CONT RM HVAC EMERG RCIRC A ' SUPP POOL ADS B ADS A MANUAL SCRAM REACTOR FDW INITIATED. P904 LEVEL A HIGH PERMISSIVE INSTANTANEOUS SWITCH ARMED PUMP A TRIP RHR B/C RUN LOGIC INITIATED CONT RM HVAC SUPP POOL RPS LOGIC Section 2A EMERG RCIRC B TEMP A HIGH ADS A ADS B MANUAL SCRAM INITIATED P904 PERMISSIVE INSTANTANEOUS LP CONDENSEN CONTAINMENT RPV L-3 LOGIC INITIATED RRCS MAN VACUUM LOW PRESS A lilGH INITIATION ADS B ADS A IP CONDENSER . DRYWELL PERMISSIVE TIME DELAY RPS LOW LEVEL VACUUM LDW PRESS A HIGH RPV L-3 LOGIC INITIATED L-3 HP CONDENSER LOGIC FOR LPCS/ ADS A ADS B RRCS VACUUM LOW 4 LPCI A FRM RHR A PERMISSIVE
- TIME DELAY RX LEVEL DW PRESS HIGH DW PRESS HIGH LOGIC INITIATED LO L-2 CONTAINMENT ADS B RPS 4 TEMP A HIGH PERMISSIVE DRYWELL DW PRESS HIGH PRESS HIGH DRYWELL ,
i TEMP A RPS HIGH MSly CLOSURE , Section 17A Section 17A Section 7A SUPP POOL CONTAINMENT SAFETY / RELIEF LEVEL B TEMP B HIGH VALVE LEAKAGE HIGH ALARM P614 SUPP POOL DRYWELL ! TEMP B HIGH TEMP B HIGH CONTAINMENT PRESS B lilGH DRYWELL PRESS B lilGH LOGIC FOR i LPCI B/C FM RHR DW PRESS HIGH 4. DW170B/A/113/rmk f i 1
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- 1 PERRY NUCLEAR POWER PLA81T 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1208 P601 P680 CONTAINMENT PARAMETERS SYSTEM INFORMATION REACTOR PARAMETERS Tempe ra tu re Pressu re Pressure Flow Pressure 230 psig '
(*Fl fosial Status losial feos) < Level -38 In, WR 4 Cntet 155 2.2 RWCU PMP A SS Neutron Drywell 206 4.1 B SS Mon 40 Range APRM HWL PMP A OP 230 Mode SW SHTDN Tempe ra tu re Level f*F1 frt.1 B OP 230 FDW Flw 0 Mlb/hr Supr Pt 140 P1.0 C SS 0 ST Flw (Total) O MIb/hr CBP A SS 150 Line A 0 SYSTEMS INFORMATION B SS 150 Line B 0 Pressure Flow Status fosial faomi C SS 150 Line C 0 , RHR A PHP OVRD RFBP A SS 160 Line D 0 B LPCI 265 5000 B SS 160 C VLV OVRD 250 4750 . C SS 160 LPCS PMP OVRO D SS 160 - RCIC FLOW OVRO 100 0 RFP A SS 0 0 , HPCS YLV OVRD 1000 0 B SS O O ECC A 00S MFP SS O O IURSlHL-CELRATOR S OP 114 RCIRC A SS 0 PARAMETERS ESW A OOS B SS 0 Mwatt 0 B OP MVAR 0 MAJOR VALVE PARAMETERS C OP CNDR Vac 20 in. Hg Status Closed Open CRD A SS Thrt Pr _ .0 psig MSIV ISOL 8 0 B SS SYP VLV SRV ADS 11 8 Posit 0 % SLC A OP 1600 B OP 1600 SLC STG TK LVL 4600 gal.
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I PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1208 gj2g ELECTRICAL DISTRIBU ION g2.Qh CST Level 410.000 cal. Status -Load fMW) Status Status fosial OFFsite Pwr Sources 2 AV Cont Rm HVAC Supp Fan A OP TBCC PHP A OP 75 Con Breakers 2 CL B OP B OP 75 Div 1 DG OOS Cont Rm HVAC Rtn Fan A SS C SS 18 Div 2 DG OP O B SS SA Comp OP 128 Div 3 DG OP O Cont Re Eng RCIRC Fan A OP IA Comp SR 120 8 OP EADQ CIRW PMP A OP 46 Status f910 B OP 45 Cntet Vsl Cig Fan A OP Pressu re Status foslo) C SS O B OP NCC Pump A SS 35 SJAE A SS C SS B SS 35 B SS D OP C OP 112 E OP ADDIT 1ONAL INFORMATION SW Pump A OP 56 F SS Status Abbreviations: B OP 56 Drywell Cooling Fan IA OP OP Ope ra t ing C SS O 2A OP SS Secured Status D SS O 3A OP AV Available MTR Fire Pump SR 1B SS SR Standby Readiness , DO Fire Pump SR SHTDN Shutdown , 3B SS S-SP Slow Speed Cntet Vsl Purge Supp Fan A SS F-SP Fast Speed 8 SS ISOL , isolated Cntet Vsl as DW Purge Exh Fan A SS NORM Normal - B SS OOS Out of Service Drywall Purge Suppl Fan A SS CL Closed B SS OVRD Ove rride
,,,c AEGTS Fan A OOS B OP
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PERRY NUCLEAR POWER PLANT 1984 EMERCENCY PREPAREDNESS EXERCISE TIME: 1208 RX WATER LEVEL RX PRESS RX POWER SUPR PL TEMP
-38 it WR 230 EllC 40 f- 140 'f 60- 1100- 120- 110 45- 950- 90- 90-
, 30- 800- 40- 70-15- 650- 0 50 0 500 -30 -20 -10 0 -30 -20 -10 0
-30 -20 -10 0 -30 -20 -10 0 Time (min) Time (min)
Time (min) Time (min) DW TEMP CONTMT TEMP CONTMT PRESS SUPR PL LEVEL 206 *F 155 *F 2.2 E11C 21.0 EJ 200 - 110- 20- 19-150- 90- 15- - 100- 70- 10- 18- - 50 50- 5- -
-30 -20 -10 0 -30 -20 -10 0 0- 17 Time (min) Time (min) -5 -30 -20 -10 0
-30 -20 -10 0 Time (min)
Time (min) O
.: ~, .:~ ' c.s s -
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TIME: 1208 1984 EMERGEleCY PREPAREDNESS EXERCISE PERRY IIUCLEAR POWER PLANT PA88EL P604
-PANELS P669. P670. P671. P672 Main Steam Line RAD 0.0E+0 mR/hr Process Radiation Alarm Cntet Vent Exh RAD st.0E-1 mR/hr-Offges Pre-treatment 1,9Q1 R/hr PANEL P902 Offgas Post-treatment A 2.0E+2 cpm Common Airborne- Gas fcoal Alarm B Z,9Lig cpm RWB Vent Exh 2.0E+1 Eng Service Water A 3.0E+1 cpm FH8 Vent Exh Z,2f+1 8 3.OE+1 cpm CR Vent Exh 2.0E+1 OG Carbon Ded Vault A 6.0E+1 mR/hr 8 5.5E+1 mR/hr i PANEL P906 Common Process and Area ERE Ala rm PANEL 803 o UD-MH-73 East Liq . 3.0E+1 Turb Bldg East 2.5E+0 mR/hr UD-MH-70 West Liq 3.2E+1 Turb Bldg West 2.5E+0 e6/hr 8tCC Heat HX 3.5Et1 Radweste to ESW 3.00+1
_ PANEL P804 Radweste to Sewage 3.6E+1 Airborne Radiatlan cas (comi Alarm 1 Annulus Exh A Cas Q,9Lif! B 1,DE+ , METEOROLOGICAL CONDIT10NS
>l 0[ fit N Catet Ata Drywell - HR (R/hr) 6,JLtl Wind Speed 7.0 mph g,0Q1
- AB Vent gigtig Wind Direction _ 250 OGB Vent Exh Tempera ture 4' 'F OGB Vent - HR Q,9Eig -' .42 'F .
OC Vent Pipe g Of_ig Delta T U1 Plant Vent 6,DL+1 UI Plant Vent - HR Q,9019 TB/HB Vent 6J L+ ]. TB/HB Vent - HR O_ OE_1f! ST Packing Exh $JEi U2 Plant Vent 6,DL1_. U2 Plant Vent - HR 0.0Liu DW170C/A/39/es
AREA RADIATION MONITORS Time: 1208 , TAG # LOCATION READING (mR/hr) (600'6") ID21NO30 Personnel Air Lock, Cntet OS) 1.0E+4
- 1D21N040 CRD HCU West, Cntat (620'6") OS > 1. 0E+4
- ID21N050 RBRT Area Cntat (642') OS > 1. 0E+4 *
} ID21N060 Tip Drive Area, Cntet (600'6") i' OS> 1.0E+4
- 1D21N070 RWCU F/D Area, Cntat (664'7") i' OS) 1.0E+4
- 1D21N080 Upper Pool Area, Cntat (689'6") OS) 1.0E+4
- 1D21N110 Aux Blda East (574'10") 3.4E+2
- j ID21N120 Aux Blda West (574'10") 3.4E+2 *
! 1D21N130 Turb Rm East (647'6") 1.9E+0 i 1D21N140 CRD HCU East, Cntet (620'6") OS >1.0E+4 * ! 1D21N160 Turb Rm West (647'6") 1.9E+0 ) 1D21N170 Turb Blda (605'6") 2.1E+0 1D21N180 Hotwell Pump Area, TB (577'6") 1.0E+1 1 1D21N190 TB Sump Area TBC (548'6") 2.0E+1
. 1D21N200 OGB (584') 1.1E+1 ID21N210 Cnds Fitr Pmp Area. TBC (568'6") 9.0E+0
,' . 1D21N220 OG After Fitr Area, OGB (602'6") 2.0E+1 s 1D21N230 HP Fdw Her Area. HB (600'6") 1.0E+1 j 1D21N240 Fdw Pump Area, KB (647'6") 9.3E+1 i I 1D21N400 CR, CC (654'6") 1.6E-1 1D21N410 OG Hold Up Area TB (577'6") 8.7E+0 j D21N250 RWB West (574'10") 2.5E+1 D21N260 RWB East (574'10") 1.5E+1 D21N270 RWB (602') 5.0E+0 D21N280 Process Sample Ra, RWB (623'6") 4.0E+0
~
D21N290 RW Evap, RWB (623'6") . 4.0E+0 D21N310 FPCU F/D Area. IB (599') 3.5E+2 * [ D21N320 Fuel Preparation Pool. IB (620'6") 3.2E+2
- D21N330 Spent Fuel Storage Pool, IB (620'6") 3.3E+2
- f D21N420 FPCU Cire Pmp Area. IB (574'10") 3.0E+2
- 1D21N340 Unit 1 DW, Portable, Cntat (655') -
[ D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1 ', D21N370 SRW Drummina Area, RWB (623'6") 6.0E+0 1D21N090 Refuelina Bridge, Cntet (689'6")
- OS) 1.0E+4
, D21N390 Fuel Serv Hdla Platform, IB (620'6") 3*.4E+2
- I l
l i t i
* = Alarm OS = Offscale
Time: 1210 Message No.: 65 PERRY NUCLEAR POWER PIANT 1984 EMERGENCY PREPAREDNESS EXERCISE
~
MESSAGE FORM Messaae For: Control Room /TSC/ EOF Simulated Plant Conditions: See attached sheets s Messame: ***THIS IS A DRILL *** . f i _
- g. .
t i ' i i FOR CORI' ROLLER USE ONLY Controller Notes:- Suppression Pool temperature increases, approaching 212*F. Containment radiatica levels increase. W Actions Expected: b DW176/C/65/ba-
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l TIME: 1210-PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREP.AREDNESS EXERCISE CONTROL ROOM AIINUteCIATORS P680 P870 & BACK PANELS P601/P877 section SA Section 3A CONT RM HVAC Section 20A Section 19A Section 19A EMERC RCIRC A MANUAL SCRAM REACTOR FDW INITIATED P904 SUPP POOL ADS 8 ADS A INSTANTANEOUS SWITCH ARMED PUMP A TRIP LEVEL A HIGH PERMISSIVE CONT RM HVAC RHR B/C RUN LOGIC INITIATED Section 2A EMERG RCIRC B R *S LOGIC P904 SUPP POOL MANUAL SCRAM INITIATED TEMP A HIGH ADS A ADS B INSTANTANEOUS LP CONDENSER PERMISSIVE RRCS MAN VACUUM LOW CONTAINMENT RPV L-3 LOGIC INITIATED INITIATION PRESS A HIGH IP CONDENSER ADS B ADS A TIME DELAY RPS LOW LEVEL- VACUUM LOW DRYWELL PERMISSIVE L-3 PRESS A HIGH RPV L-3 LOGlc INITIATED HP CONDENSER ADS B RRCS VACUUM LOW LOGIC FOR LPCS/ ADS A PERMISSIVE TIME DELAY RX LEVEL LPCI A FRM RHR A LO L-2 DW PRESS HIGH DW PRESS HIGH LOGIC INITIATED RPS CONTAINMENT ADS 8 DRYWELL TEMP A HIGH PERMISSIVE DW PRESS HIGH PRESS HICH . DRYWELL l RPS . I TEMP A MSiv CLOSURE HIGH i Section 17A Section 17A Section 7A
~
CONTAINMENT SAFETY / RELIEF SUPP POOL VALVE LEAKAGE LEVEL 8 TEMP 8 HIGH ALARM P614 HIGH DRYWELL SUPP POOL TEMP 8 TEMP 8 HICH HIGH CONTAINMENT l PRESS 8 HIGH DRYWELL PRESS B HIGH LOGIC FOR Lsci B/C FM RHR DW PRESS HIGH i DW1708/A/116/jsg
._,. _ . .;4 4-
. . L. a :. . _. ,a A . . - . . . . . . ,, .- a . - . ..~.:. . .L . - . - . ._a PERRY NUCLEAR POWER PLANT 1984 EMERGEllCY PREPAREDNESS EXERCISE TIME: 1210 j%Q1 P680 CONTAINMENT PARAMETERS SYSTEM INFORMATIOli REACTOR PARAMETERS Tempe ra ture Pressure Pressure Flow Pressure 210 psig f*F1 losial Status fosiel leon)
Level -95 in. WR Cntet 160 2.2 RWCU PMP A SS Neutron Drywell 207 4.2 8 SS Mon 20 Range APRM HWL PMP A OP 230 Mode SW SHTON Tempe ra ture Level
- f*F1 fft.) 8 OP 230 FDW Flw 0 Mlb/hr Supe PI 179 21.3 C SS O ST Flw (Total) O Mlb/hr
. CSP A SS 150 Line A 0 SYSTEMS INFORMATion 8 SS 150 Line 8 0 Pressure Flow Status fosle) fecal C SS 150 Line C 0 RHR A PMP OVRD RFSP A SS 160 Line D 0 8 L PCI 260 6000 8 SS 160 C VLV OVRD 0 0 C SS 160 LPCS PMP OVRD D SS 160 RCIC FLOW OVRD 100 0 RFP A SS 0 0 HPCS VLV OVRD 900 0 8 SS 0 0 ECC A 00S MFP SS 0 0 TUR8INE-cENERATOR S OP 114 RCIRC A SS 0 PARAMETERS ESW A 00S S SS 0 Mwatt 0 8 OP 95
- MVAR 0 MAJOR VALVE PARAMETERS C OP 95 CNDR Vac 16 in. Hg Status Closed Open CRD A SS Thrt Pr 0 psig MSIV l SOL 8 0 8 SS SYP VLV SRV ADS 11 8 Posit 0 %
SLC A OP 1600
- 8 OP 1600 SLC STC TK LVL 4600 gal.
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PERRY 900 CLEAR POWER PLANT . 1984 EMERGEleCY PREPAREDNESS EXERCISE TIME: 1210 P870 ELECTRICAL DISTRIBUTION 299h CST Level 410.000 cal. Status Load fMWI Status' OP I Status fosial Offsite Pwr Sources 2 AV Cont Rm HVAC Supp Fan A s OP I TBCC PMP A OP 75 Gen Breakers 2 CL B OP 75 Div 1 DG OOS Cont Rm HVAC Rtn Fan A SS SS 18 Div 2 DG OP O B SS C SA Comp OP 128 Div 3 DG OP O Cont Re Eng RCIRC Fan A OP IA Comp SR 120 B OP CIRW PMP A OP 46 Status. 8 SS 0 Cntet Vsl Cig Fan .A OP Pressure Status Iosial C SS 0 8 OP NCC Pump A SS 35 SJAE A SS C SS 8 SS D OP C OP 112 E OP AD0lil0NAL INFORMAT1001 SW Pump A OP 56 f SS Status Abbreviations: B OP 56 Drywell Cooling f an IA OP OP Ope ra ting C SS O 2A OP SS Secured Status D SS 0 3A OP Av Available MTR Fire Pump SR 18 SS SR Standby Readiness DO Fire Pump SR 28 SS SHIDN Shutdown 3B SS S-SP Slow Speed Cntet Vsl Purge Supp Fan A SS ; F-SP Fast Speed . B SS i ISOL Isolated Cntet Val at DW
- Purge Exh Fan A SS NORM 800 rea I 8 SS 00S Out of Service Drywell Purge Suppl Fan A SS CL Closed 8 SS OVRO Ove rride AEGTS Fan A OOS 8 OP 1
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1964 EMERGEIICY PREPAREDIRESS EMERCISE TIME: 1200 PERRY IIUCLEAR POWER PLAIIT J PAf0EL P604 PAsIELS PM9. P670. N71. M72 - Process Radiation IInin Steam Line RAD 0.0E*0 alt /hr Alare Catet Vent Exh RAD al .0E-1 eft /hr - Offges Pre-treatment 5.0E+1 R/hr 2.0E+2 cpe PAIIEL P902 Offges Post-treatment A B LDLt2 cpe e m Airborne Gas (cool Alare Eng Service Water A 3.0E+1 com ItWB Vent Exh L9[11 .. B 3.0E+1 cpe IMS Vent Exh 2.2E+1 A CR Vent Exh 2.0C+1 OG Carben Dod Vault 6 0E+1 met /hr 5.5E+1 aft /hr ^ S PAIIEL P906 LANEL 803 Ceemon Process and Area gag Alare 2.5E+0 aft /hr 90-fee-73 East Lig LRE11 Turb Side East 2.5E+0 aft /hr UD-MI6-70 West Lig 3.2E+1 I Turb Bide West 81CC Heat HM 3.5E+1 i Radweste to ESW 3.0E+1 PAIIEL P904 cas f emel Alare Redweste to Sewage 3.6E+1
, Airborne Radiation Annulus Exh A Gas
- QJ[in i
a L9Er It HETEOROLOGICAL CONDITICIIS Cntet Ata zhD[tji i DryweIi - HR (R/hr) 6J[1.3 Wind Speed 7.0 mph
- A8 Vent 2J[+ 1 Wind Direction 250 *
!, OG8 Vent Exh 2,9[12 DJLig Temperature 4' 'F i OG8 Vent - HR Detta T -
.42 'r OG Vent Pipe 2J012 l U1 Plant Vent 6,9[+_1
; v1 Plant Vent - Hft DJ[tg 18/HS Vent 6 Dt_ll 18/HS Vent - Mft DJ[tg ST Packing Exh hel_1 v2 Plant Vent 6 OE.+1 U2 Plant Vent - hit 0.0E+0 1
DW170C/A/39/es i i
, r,. ,m-.- , _ , , , - _ _ _ - _
AREA RADIATION MONITORS Time: 1208 TAG # LOCATION READING (mR/hr) 1D21NO30 Personnel Air Lock, Cntmt (600'6") OS ) 1.0E+4 *
, ID21N040 CRD HCU West, Cntmt (620'6") OS > 1. 0E+4
- 1D21N050 RBRT Area, Cntmt (642') OS > 1.0E+4
- l 1D21N060 Tip Drive Area, Cntmt (600'6") OS > 1.0E+4 *
-2 1D21N070 RWCU F/D Area, Cntmt (664'7") OS > 1. 0E+4 * .; 1D21N080 Upper Pool Area, Cntmt (689'6") OS ) 1.0E+4
- 1D21N110 Aux Bldg East (574'10") 3.4E+2
- ID21N120 Aux Bldg West (574'10") 3.4E+2
- ID21N130 Turb Rm East (647'6") 1.9E+0 ID21N140 CRD HCU East, Cntmt (620'6") OS) 1.0E+4 *
} 1D21N160 Turb Rm West (647'6") 1.9E+0 1D21N170 Turb Bldz (605'6") 2.1E+0 1D21N180 Hotwell Pump Area, TB (577'6") 1.0E+1 1D21N190 TB Sump Area TBC (548'6") 2.0E+1 1D21N200 OGB (584') 1.1E+1 1D21N210 Cnds F1tr Pmp Area TBC (568'6") 9.0E+0 1D21N220 OG After F1tr Area, OGB (602'6") 2.0E+1 1D21N230 HP Fdw Her Area, HB (600'6") 1.0E+1 1D21N240 Fdw Pump Area. HB (647'6") 9.3E+1 1D21N400 CR, CC (654'6") 1.6E-1 1D21N410 OG Hold Up Area TB (577'6") 8.7E+0 D21N250 RWB West (574'10") 2.5E+1 l D21N260 RWB East (574'10") 1.5E+1 D21N270 RWB (602') 5.0E+0 D21N280 Process Sample Rm, RWB (623'6") 4.0E+0 g
D21N290 RW Evap, RWB (623'6") 4.0E+0
, D21N310 FPCU F/D Area. IB (599') 3.5E+2
- D21N320 Fuel Preparation Pool, IB (620'6") 3.2E+2 *
.! D21N330 Spent Fuel Storage Pool, IB (620'6") 3.3E+2 *
; D21N420 FPCU Cire Pmp Area, IB (574'10") 3.0E+2 *
(655') ID21N340 Unit 1 DW, Portable. Cntmt - D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1
. D21N370 SRW Drumming Area RWB (623'6") 6.0E+0 1D21N090 Refueling Bridge, Cntmt (689'6") OS) 1.0E+4
- D21N390 Fuel Serv Hdig Platform, IB (620'6") 3.4E+2 *
* = Alarm OS = Offscale
Time: -1210 Message No.: 65 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE
'- MESSAGE FORM 1
Messane For: Control Room /TSC/ EOF Simulated Plant Conditions: See attached sheets 1 Messame: ***THIS IS A DRILL *** E r
?, _ .r
- Y r
b FOR CONTROLLER USE ONLY i h [' Controller Notes: Suppression Pool temperature increases, approaching 212*F. Containment radiation levels increase. I Actions Expected: S DW176/C/65/ba
- e. p.
- g
PERRV IIUCLEAR POWER PLAIT 1980s EMERGEIICY PetEPAREDIIESS EXERCISC TIME: 1210 COIITROL ROING AIIIANICIAT0fts P601/Ps77 P680 P870 & BACK PAIIELS - Section 20A Section 19A Section 19A section SA section 3A COIIT HM HVAC EMEltC RCIRC A SUPP POOL ADS B ADS A MANUAL SCRAM REACTOR FDW IIllTIATED P9005 LEVEL A HIGIS PERMISSIVE INSTAllTAIIEOUS SWiiCH AltMED PUMP A TRIP ltHR S/C Rust LOGIC IIIITI ATED Colli RM HVAC SUPP POOL RPS LOGIC Section 2A EMEltC RCIRC B TEMP A HIGH ADS A ADS S MAIOUAL SCRAM INITIATED P904 PERMISSIVE I18STAIITAIIEOUS LP COIIDENSER COIITAIIIMENT RPV L-3 LOGIC INITIATED RRCS MAN VACUUM LOW PRESS A HIGet IIII T I AT ICII ADS S ADS A IP COIIDENSER DetMLL PElIMISSIVE TIIIE DELAY RPS LOW LEVEL VACUUM LOW PetESS A HIGH RPV L-3 LOGIC INiilATED L-3 HP COIIOENSER LOGIC FOR LPCS/ ADS A ADS 8 RACS VActMI LOW LPCB A iflet RIIR A PEllMISSIVE TIIIE DELAY RX LEVEL DW PRESS HIGH DW PRESS HIGH LOGIC INITIATED LO L-2 COIITASIWIENT ADS B RPS
, TEIIP A HIGH PERMISSIVE DRYWFLL DW PetESS HIGH PRESS HIGH DR M LL T DIP A RPS HIGH MSIV CLOSURE Section 17A Section 17A Section'7A '
SUPP POOL COIII A1IIMEIIT SAFETY / RELIEF LEVEL 8 TEMP 8 HIGH VALVE LEAKAGE HIGH ALARM P614 DetMLL SUPP POOL TEMP 8 TEMP S HIGH HIGH COIITAIIIMENT PetESS S HIGH DR M LL PetESS B HIGH LOGIC IOR LPCI 8/C IM RHR DW PRESS HIGH DW1708/A/116/Jsg
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PERRY IIUCLEAR POWER PLANT 1964 EMERCEIICY PREPARED 10ESS EXERCISE TIME: 1210 M P680 PATAIIpeElsi PAftAMETERS SYSTEM IIIFORMAT1000 REACTOR PARAMETERS Tempe ra ture Pressure Pressure Flow Pressure 210 psig f*F) 3 11g L Status _[gligL tepel Level -95 in. WR Cntet 160 2.2 RWCU PMP A SS Neutron Drywell 207 4.2 8 SS Mon 20 Range APRM , HWL PMP A OP 230 Mode SW SHTDet Tempe ra ture tevel f*F1 IFt.1 8 OP 230 FDW Flw 0 Mlb/hr Supr PI 179 21.3 C SS 0 ST Flw (Total) O MIb/hr CSP A SS 150 Line A 0 SYSTEMS IIIFORMATloss B SS 150 Line 8 0 Pressure Flow Status _(ps le L lesel C SS 150 Line C 0 . Rhet A PMP OvetD RFBP A SS 160 Line D 0 B LPCI 260 6000 B SS 160 C VLV oVstO O O C SS 160 LPCS PMP OVRD D SS 160 RCIC FLOW Ovsto 100 0 RFP A SS 0 0 HPCS VLV OVRO 900 0 S SS 0 0 ECC A 00S MFP SS 0 0 Igetglig[-C[esERATOR S OP 114 RCIRC A SS O PARAMETERS ESW A 005 B SS O pha tt 0 5 OP 95 MVAR 0 MAJOft VALVE PARAMETERS C OP 95 C800R Vac 16 in. Hg _ Status Closed Open CRD A SS Thrt Pr o psig MSIV ISOL 8 0 s SS sYP vLv SNV ADS 11 8 Posit 0 % SLC A OP 1600 8 OP 1600 StC STG TK LYL 4600 gal.
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=,
5 PERetY leUCLEAR POWER PLANT 1984 EMERGEsICY retEPAstEDetESS EXERCISE TIME: 1210 ft19 ELECTitICAL DISTRIOUTI0ld M-CST Level 410.000 est. . Status Load (MW) Status Status fasiel Offsite Pwr Sources 2 AV Cont Its MVAC Supp Fan A 0F TOCC Peep A OP 75 Con Brealiers 2 CL a OP S OP 75 Div 1 DG 005 Cont fte HVAC Rtn Fan A- SS C SS 18 Div 2 DG OP O 8 SS SA Ceep OP 128 Div 3 DG OP O ' Cont lie Eng ftCIRC Fan A' OP IA Camp SR 120 8 OP Pe00 CIRef PetP A OP_ 46 Status P970 3 SS O Cntet Vsl Cig Fan A OP ' Pressure Status fosle) C SS 0 s OF IOCC Pump A SS 35 SJAE A SS C SS B SS 35 S SS D OP
. C OP 112 E OP
. ADDITICIIAL INF0fumV10N Sti Pump A OP 56 F SS Status Abbreviations: B OP 56 Drywell Cooling Fan IA OP OP Ope ra t Ing C SS 0 2A OP
$$ Secured Status D SS 0 3A 0F AV Available MTR Fire Pump SR 18 SS SA Standby Readiness DO Fire Pump SR 28 SS ,
SMTDet Shutdown 38 SS l S-SP Slow Speed Catet Val Purge j Supp Fan A SS t F-SP Fast Speed S SS l ISOL isolated Cntet Vsl & DW , ! Purge Exh Fan A SS seOftM Isormal ~ B SS l OOS Out or Service Drywell Purge Suppl Fan A SS CL Closed B SS OVRD Ove rride AECTS Fan A GOS 8 OP
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e . . . _ - . . . . . - . - - - - . , _ - _ _ PERRY IIUCLEAR POWER PLAleT 19eas EMERGEIICY PREPAREDIIESS EXERCISE TIIIE: 1210 PAfEL P604 PAIBElS M69. M70. M71. M72 Process Radiation IInin stese Line RAD 0.0E+0 aft /hr Alers Catet Vent Exh RAD 41.0E-1 idt/hr Offges Pre-treatment L.91+1 R/hr Offges Post-treatment A 2.0E+2 cpe PAIIEL P902 5 2.0E+2 cpe Common Airhorne Gas Icool AIare Eng Service Water A 3.0E+1 cpe RWS Vent Exh 2.0E+1 8 3.0E+1 cpe FNs Vent Exh 2.2E+1 OG Carhon Bed Vault A 6.0E+1 mR/hr CR Vent Exh 7 0E+1 8 5.5E+1 aft /hr PA10EL P906 Pastel. 303 Common Process and Area Eag - Alare l i Turb Steg East 2.5E+0 aft /hr 90-stH-73 East Lig 3.0E+1 Turh Bldg West 2.5E+0 met /hr 90-Mee-70 West Lig 3.2E+1 80CC Heat NK 3.5E+1 PA81EL P904 Radweste to ESW 3.0E+1 i Airhorne Radiation Gas tcool Alare Radweste to sewage 3.6E+1 1 1 Annulus Exn A Gas 9,9E_+9 a },9E+1 i i Cntot Ato 31,9 @ H 90ETEOROLOGICAL COIIDIT10003 Orywes t - tea (R/hr) 6 JL+3 Wiad Speed 7.O aph . ) AB Vent 2,9(11
- 1 Oca vent Exh 2,90+2 Wlad Direction 250 Oca Vent - Mft 9 # 19 Temperature 4' 'F OG Vent Pipe 2,9[+ g Delta T -' .h2 *F 4
ui Plant Vent 6.90+1 s ut Plant Vent - Het 0,9L+9 IS/HS Vent 6,9(11 is/HS Vent - 80R 9,9ff9
- h 00_1
) 51 Packing Exh U2 Plant Vent 6.00+1 U2 Plant Vent - hit 0.0E+0 - i DW170C/A/40/es J
AREA RADIATION MONITORS Time: 1210 ,
, TAG # LOCATION READING (mR/hr) 1D21NO30 Personnel Air Lock, Cntmt (600'6") OS > 1. 0E+4
- ID21N040 CRD HCU West, Cntmt (620'6") OS > 1. 0E+4 *
. ID21N050 RBRT Area, Cntmt (642') OS >1.0E+4
- 1D21N060- Tip Drive Area, Cntmt (600'6") OS ) 1.0E+4 *
' ID21N070 RWCU F/D Area, Cntmt (664'7") OS ) 1.0E+4
- 1D21N080 Upper Pool Area, Cntmt (689'6") OS>1.0E+4
- ID21N110 Aux Bldg East (574'10") 3.4E+2
- ID21N120 Aux Bldg West (574'10") 3.4E+2
- 1D21N130 Turb Rm East (647'6") 1.9E+0
+
1D21N140 CRD HCU East, Cntmt (620'6") OS ) 1. 0E+4
- 1D21N160 Turb Rm West (647'6") 1.9E+0 1D21N170 Turb Blda (605'6") 2.1E+0 1D21N180 Hotwell Pump Area. TB (577'6") 1.0E+1 1D21N190 TB Sump Area. TBC (548'6") 2.0E+1 1D21N200 OGB (584') 1.1E+1 1D21N210 Cnds Fitr Pmp Area. TBC (568'6") 9.0E+0 1D21N220 OG After Fitr Area, OGB (602'6") 2.0E+1 1D21N230 HP Fdu Her Area, HB (600'6") 1.0E+1 .
{ 1D21N240 Fdw Pump Area, HB (647'6") 9.0E-1 i 1D21N400 CR, CC (654'6") 1.6E-1 1D21N410 OG Hold Up Area. TB (577'6") 8.7E+0 i D21N250 RWB West (574'10") 2.5E+1 D21N260 RWB East (574'10") 1.5E+1 D21N270 RWB (602') 5.0E+0 D21N280 Process Sample Rm, RWB (623'6") 4.0E+0 D21N290 RW Evap, RWB (623'6") 4.0E+0 j D21N310 FPCU F/D Area. IB (599') 3.5E+2
- D21N320 Fuel Preparation Pool, IB (620'6") 3.2E+2
- D21N330 Spent Fuel Storage Pool. IB (620'6") 3.3E+2
- D21N420 FPCU Cire Pmp Area. IB (574'10") 3.0E+2
- 1D21N340 Unit 1 DW, Portable Cntmt (655') -
(623'6") 6.0E+1 D21N380 Waste Compactor Area, RWB D21N379 SRW Drumming Area RWB (623'6") 6.0E+0 (689'6")
- 1D21N090 Refueling Bridge, Cntmt OS )1.0E+4 D21N390 Fuel Serv Hdig Platform, IB (620'6") 3.4E+2 *
* = Alarm OS = Offscale
' Tina: 1215 (approx.) Message No.: 66 PERRY NUCLEAR POWER PIINT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Message For: Operator at RHR Pump B Breaker e Simulated Plant Conditions: Message: ***THIS IS A DRILL *** . You become aware of the scent of charred paint and metal. Upon investigation, you discover the Motor Control Cabinet for Bypass Valve E12-F048B is charred and inoperable. 9 4 FOR CONTROLLER USE ONLY Controller Notes: 1. The operator successfully opens RHR Pump B breaker locally (Elevation 620' Control Complex). As he completes the task, give him this message, j
+ 2. RHR Heat Exchanger B Bypass Valve E12-F048B is stuck f open.
Actions Expected: 1. Notify the Control Room.
- 2. Control Room should dispatch request that an Emergency Maintenance Team expedite repairs to Emergency Service Water Pump P45-C001A. l NOTE: P45-C001A will not be returned to service until 1340. Controllers to verify that an Emergency Maintenance Team is dispatched at an appropriate time to fix P45-C001A by 1340.
l DW176/C/66/ba 1 l 1
Time: >1215
^
Message No.: 67 PERRY NUCLEAR POWER PIANT r 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Messame Fort Control Room /TSC/ EOF Simulated Plant Conditions: See attached sheets Messame ***THIS IS A DRILL *** 1 !j FOR CONTROLLER USE ONLY l Controller Notes: i. ? Actions Expected: l 0 DW176/C/67/ba
.- l
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PEIulY IIIICLEAR PONER PLAIIT 1984 E8EEftGEIICY PREPAAESSESS EXEACISE - TleeE: 1215
- . i CONTROL R0WI A M IATORS .
P601/PS77 P680 PS70 at BACE PAIIELS , Section 20A Sectlen 19A Section 19A section SA Section 3A C00li HN HVAC EstEftG stCiltC A SIfPP POOL ADS S ADS A IIAIIIIAL SCRAft REACTOR FDtf. IIIlil ATED P9045 LEVEL A NIGIS PEIWOISSIVE IIISTAIITAIIEctf5 StfliCII ANIED PtNIP A TRIP HIIR S/C must LOGIC IstTIATED COIII fift HVAC
$#PP POOL RPS LOGIC Section 2A E9EERG ftCiftC B TEf0P A telGII ADS A ADS S ORAIIIIAL SCRAfl INITIATED P9015 PEngeISSIVE INSTAIITAIIEOUS LP COIIDEIISER CONTAIISEmi StPV L-3 LOGIC INITIATED RACS StAN VAcutNe LCtf PRESS A NIGes 8N8ilATION ADS S ADS A . IP COISEIISER DItWELL PEmpesSSIVE TigeE DELAY RPS Lott LEVEL VACIseles Leni PRESS A MIGII ItPV L-3 LOGIC 14tilATES L-3 MP COISEIBSER LOGIC F00t LPCS/ ADS A ADS S IIRCS VACUUM Lott LPCI A FIWO ABIR A PERIst SSIVE T18eE DELAY Rd LEVEL Stf PRESS NICII Stf PRESS NICII LOGIC INITIATES LO L-2 ComTAIIpeENT ADS S RPS 1EftP A NIGIS PEfWet SSIVE DRWELL Stf PRESS allG00 PRESS NIGel DItWELL TEf0P A RPS MIGII MStV CLOSIME Section 17A section 17A Section 7A SUPP POOL COIliAllWEEmi SAFETY / RELIEF LEVEL B IEfer B IIIGel VALVE LEAEAGE MIGet AUtABI P614 DetWELL ,
SUPP POOL TEfer S IEftP S MIGIS MIGII CONTAlWEENT PRESS S tIIGet DetWELL PRESS S NICII LOGIC F00t LPCI S/C
- f se Reen hi PRESS NICII -
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. _ . . . . _ _ _ . . . . . . . _ _ . - - . . - . _ ~ _ , _ _ . . . .~..,__...._.a..~... . - . .
PERitY IIUCLEAR POWER PLAdIT 1964 EMERCEIICY PflEPAREDIIESS EXEIICISE TIME: 1215 P601 fitA0 MTAIIBGEGIT PARAMETERS . SYSTEM IIIFORMATI0ld itEACTOR PAstAMETERS Tempe ra ture Pressure Pressure Flow Pressure 110 psig , (*ft tosial Status fosiel femel Level -95 in. wit Cntet 160 2.3 ftWCU PHP A SS IIeut ron Drywell 210 4.3 8 SS Mon 20 Range APRM HWl_ PMP A OF 230 Mode SW SHTDII Toepera ture tevel f*F1 fFt.1 8 OP 230 FDW Flw 0 MIb/hr Supr Pt 208 21.4 C SS O ST Few (Total) O MIb/hr CSP "A SS 150 Lire A 0 SYSTEMS IIIFORMAT tott , 8 SS 150 Line 8 0 Pressure Flow Status _ f osiel _ fese) C SS 150 Line C 0 RHR A PM* OVRO RFBP A SS 160 Line D 0 8 PMP OVRO O 'O 8 SS 160 , C yty OyRg O O C SS 160 .' LPCS PMP OVRO D SS 160 RCIC Flow OVRO 100 0 RFP A SS O O HPCS VLV OVRO 900 0 8 SS O O ECC A 005 MFP SS O O ll!BRIIl[-C[It(!tATOR 8 OP 114 RCIRC A SS O PARAMETERS ESW A OOS S SS O Na tt 0 l 8 OP 95 MVAR 0 MAJOR VALVE PARAMETERS . C OP 95 CIIOR Vac 0 in. Hg Status Closed Open CRD A SS 1hrt Pr O psig MSIV ISOL 8 0 j 8 SS BYP VLV SRV ADS 11 8 Posit 0 % l SLC A OP 1600 8 OP 1600 \ . SLC SIG IK LYL 4600 ga8.
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PERRY NUCLEAR POWER PLANT 19884 EMERCENCY PREPAREDNESS EXERCISE T il1E: 1215-P870 . ELECTRICAL DISTRIBUTION P9088
, CST Level 1s10.000 en h' Status _ Load IMW) _ Status Status (psiqL ,
OFFsite Pwr Sources 2 AV Cont Rm HVAC Supp Fan A OP TBCC PMP A OP 75 Cen Breakers 2 CL B OP B OP 75 Div 1 DG OOS Cont Rm HVAC Rtn Fan A SS C SS -18 Div 2 DC OP O B SS SA Comp OP 128 Div 3 DG OP O Cont Rm Eng RCIRC Fan A: OP lA Comp SR 120 . B OP P800 ' ClRW PMP A OP 16 4 Status P970 8 SS O Cntet Vsl Cig Fan A OP Pressure Status (psial C SS O B OP NCC Pump A SS 35 SJAE A SS . C SS B SS 35 B SS D OP C OP 112 E OP ADDITIONAL INFORMATION SW Pump A OP 56 F SS Status Abbreviations: B OP 56 Drywe i I Cool ing Fan 1 A OP OP - Ope ra t i ng C SS O 2A OP SS Secured Status D SS O 3A OP AV Available MTR Fire Pump SR
% 18 SS SR Standby Readiness DD Fire Pump SR 28 SS SHTDN Shutdown -
S-SP Slow Speed Cntet Val Purge Supp Fan A SS F-SP Fast Speed B SS ISOL 1solated . Cntet Val a: DW Purge Exh Fan A SS NORM Normal B SS OOS Out of Service Drywell Pu rge
- Suppl Fan A SS CL Closed B SS OVRD Ove rride -
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ha. . r r . % '.* ,1s% . - . . . PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1215 PANEL P604 PANELS P669. P670. P671. P672 Process Radiation Main Steam Line RAD 0.0E+0 mR/hr Alarm Cntet Vent Exh RAD 41.0E-1 mR/hr
,0f fges Pre-treatment 2.5E+1 R/hr Offgas Post-treatment A 2.0E+2 cpm PANEL P902
- B 2.0E+2 cpm Common Airborne cas (cool Ala rm Eng Service Water A M E+_1 cpm RWB Vent Exh 2.0Et1 8 3.0E+1 cpm EHB vent Exh 2.2E+1
~
OG Carbon Bed Vault A (t Q[.+1 mR/hr CR Vent Exh 2.0E+1 B LSE+1 mR/hr PANEL P906 fA NEl. 603 Common Process and Area m c Alarm Turb Bldg East ret.Q mR/hr UD-MH-73 East Liq 3.0E+1 Turb Bldg West 2.5E+0 mR/hr UD-MH-70 West Liq 3.2E+1
.NCC Heat HX 3.5E+1 PANEL P804 Radwaste to ESW 3.0Et1 Airborne Rediation Cas Icoal AIare Radwasto to Sewage 1,.ft[+.1 Annulus Exh A Cas Q 0[tg B h0E+1 METEOROLOGICAL CONDITIONS Cntet Atm 31M"if t . H Drywell - HR (R/hr) 6,JEM R,0EM Wind Speed 5.0 _ mph AB Vent
- OGB Vent Exh 210Eig Wind Direction 280 OGB vent - HR QJ)LtQ Tempe ra tu re 40 *F OG Vent Pipe RJ!Eig Delta T -1.45 *F U1 Plant Vent 6, ply U1 Plant Vent - HR Q.,0E+Q TB/HB Vent h0011 TB/HB Vent - HR Dm0E+Q ST Packing Exh 3,0 E '
U2 Plant Vent JJ E_i_ U2 Plant Vent - HR 0.00+U DW170C/A/41/es
AREA RADIATION MONITORS Time: 1215 TAG # LOCATION READING (mR/hr) 1D21NO30 Personnel Air Lock, Cntmt (600'6") OS > 1.0E+4
- 1D21N040 CRD HCU West, Cntmt (620'6") OS > 1.0E+4
- ID21N050 RBRT Area, Cntmt (642') OS > 1.0E+4
- 1 1D21N060 Tip Drive Area, Cntmt (600'6") OS > 1.0E+4
- I' 1D21N070 RWCU F/D Area, Cntet (664'7") OS> 1.0E+4
- 4 1D21N080 Upper Pool Area, Cntet (689'6") OS > 1.0E+4
- 1D21N110 Aux Bldg East (574'10") 3.4E+2
- ID21N120 Aux Bldg West (574'10") 3.4E+2
- 1D21N130 Turb Rm East (647'6") 1.9E+0
! 1D21N140 CRD HCU East, Cntmt (620'6") OS> 1.0E+4 * ! 1D21N160 Turb Rm West (647'6") 1.9E+0 -
1D21N170 Turb Bldg (605'6") 2.1E+0 1D21N180 Hotwell Pump Area, TB (577'6") 1.0E+1
; ID21N190 TB Sump Area, TBC (548'6") 2.0E+1 j 1D21N200 OGB (584') 1.1E+1 1D21N210 Cnds F1tr Pmp Area, TBC (568'6") 9.0E+0
] ID21N220 OG After Fitr Area, OGB (602'6") 2.0E+1 1D21N230 HP Fdw Htr Area HB (600'6") 1.0E+1
, 1D21N240 Fdw Pump Area HB (647'6") 8.8E-1 1r21N400 CR, CC (654'6") 1.6E-1 ID;'N410 OG Hold Up Area TB (577'6") 8.7E+0
~7:'IN250 RWB West (574'10") 2.5E+1 1 D21N266 RWB East (574'10") 1.5E+1
'I D21N270 RWB (602') 5.0E+0 D21N2G) Process Sample Rm, RWB (623'6") 4.0E+0
, D21N290 RW Evap, RWB (623'6") 4.0E+0 D21N310 FPCU F/D Area, IB (599') 3.5E+2
- D21N320 Fuel Preparation Pool IB (620'6") 3.2E+2 *
, D21N330 Spent Fuel Storage Pool, IB (620'6") 3.3E+2 *
(574'10")
- i D21N420 FPCU Cire Pmp Area, IB 3.0E+2 i' 1D21N340 Unit 1 DW, Portable, Catmt (655') -
D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1
' 6.0E+0 D21N370 SRW Drumming Area, RWB (623'6")
ID21N090 Refueling Bridge, Cntmt (689'6") OS ) 1.0E+4
- D21N390 Fuel Serv Hdig Platform, IB (620'6") 3.4E+2 *
.i ~.
* = Alarm OS = Offscale
F
- Time: 1220 Message No.: 68' PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Messane For: Control Room /TSC/ EOF
- Simulated Plant Con'itions:
d See attached sheets
. Message: ***THIS IS A DRILL ***
4 FOR CONTROLLER USE ONLY
-. Controller Notes: The Emergency Coordinator should be considering upgrading to a GENERAL EMERGENCY (EPI-A1, Section D.IV.1, " Loss of two fission-product barriers with a potential loss of a third" or Attachment 3, Condition 2, " Transient plus failure of requisite core shutdown systems. Could lead to core melt in several hours with containment failure likely. More severe consequences if reactor Recirculation Pump Trip does not function").
( Actions Expected: 1. Implement EPI-5 (GENERAL EMERGENCY). -
- 2. Make notifications.
- 3. Make an immediate Protective Action Recommendation.
- a. . Shelter 2 miles radius.
- b. Shelter 5 miles downwind.
- 4. Consider other Protective Action Recommendations based upon dose projections.
NOTE: Do not let Emergency Coordinator upgrade these Protective Action Recommendations until 1315,.if possible. DW176/C/68/ba l l-
.... .; .- .- 4 d
's PERRY NUCLEAR POWER PLA'lli 1984 EMERCEllCY PREPAREDNESS EXERCISE TIME: 1220 i E fit 00 CONTAI81MDfT PARAMETERS . SYSTEM INFORMATIOff REACTOR PARAMETERS Tempe ra ture Pressure Pressure Flow Pressure 155 psig (*F1 fosial Status . f osig n . foom) Level -145 in. WR Cntet 193 _ 2.6 RWCU PMP A SS Neutron Drywell 212 4.4 8 SS Mon 8 Range M s HWL PMP A OP 230 Mode SW SHTDet Tempera ture Level f*F1 fft.1 8 OP 230 FDW Flw 0 Mlb/hr Sup r P t 213 21.5 C SS O ST Flw (Total) O Mib/hr CSP A SS 150 Line A 0 SYSTEMS INF0ftMAT10N B SS 150 Line B 0 Pressure Flow Status fosial feon) C SS 150 Line C 0 RHR A PHP OVRD RFBP A SS 160 Line D *'C , B VLV OVRD 275 0 B SS 160 C VLV OVRQ 275 0 C SS 160 LPCS PHP OVRD D SS 160 RCIC FLOW OVRO 100 0 RFP A SS O O HPCS OP 1095 2500 5 SS O O ECC A 00S MFP SS O O llLRglMt-CEMfRATOR S OP 114 RCIRC A SS O PARAMETERS ESW A 00S S SS O Mwatt B OP 95 MVAR MAJOR VALVE PARAMETERS C OP 95' CNOR Vac 0 in. Hg Status Closed Open CRD A SS Thrt Pr psig MSIV ISOL 8 0 B SS BYP VLV SRV ADS 11 8 Posit 0 % SLC A OP 1600 . B OP 1600 SLC STC TK LVL 4600 gal.
. -:x-. . .a . .a _ . ..; . - x--a - . . - . . . . . . - . . ;u-PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1220 CONTROL ROOM ANNUNCIATORS P601/P877 P680 P870 & BACK PANELS Section 20A Section 19A Section 19A Section 5A Section 3A CONT RM HVAC f
EMERC RCIRC A SUPP POOL ADS B ADS A MANUAL SCRAM REACTOR FDW' INITIATED P904 LEVEL A HIGH PERMISSIVE INSTANTANEOUS SWITCH ARMED PUMP A TRIP - RHR B/C RUN LOGIC INITIATED CONT RM HVAC SUPP POOL RPS LOCic Section 2A EMERC RCIRC B TEMP A HICH ADS A ADS B MANUAL SCRAM INITIATED P904 . PERMISSIVE INSTANTANEOUS LP CONDENSER CONTAINMENT RPV L-3 LOGIC INITIATED RRCS MAN VACUUM LOW PRESS A HIGH INITIATl0N ADS B ADS A IP CONDENSER ORYWELL PERMISSIVE TIME DELAY RPS LOW LEVEL VACUUM LOW PRESS A HIGH RPV L-3 LOGIC INITIATED L-3 HP CONDENSER LOGIC FOR LPCS/ ADS A ADS B RRCS VACUUM LOW LPCI A FRM RHH A PERMISSIVE TIME DELAY RX LEVEL DW PRESS HIGH DW PRESS HIGH LOGIC INITIATED LO L-2 CONTAINMENT ADS B RPS TEMP A HICH PERMISSIVE DRYWELL DW PRESS HICH PRESS HIGH DRYWELL TEMP A RPS HIGH MSIV CLOSURE Section 17A Section 17A Section 7A SUPP POOL CONTAINMENT SAFETY / RELIEF LEVEL B TEMP BlilCH VALVE LEAKAGE lilCH ALARM P614 DRYWELL SUPP POOL TEMP B TEMP B HIGH llIGH - CONTAINMENT PRESS B lilGH DRYWELL PRESS B HIGH
- LOCic FOR LPCI B/C IM RHR DW PRESS HICH DW1708/A/122/rmk
r- .- < .:...,_.. - a__ _c . _ . . . u- . - - . . . . . . . _ . PERRY leuCLEAR POWER PLAllT 1934 [MERCE91CY PREPARED 00ESS EXERCISE TIME: 1220 P870 ELECTRICAL DISTRIBUTION M
~
CST Level 410.000 cal. Status Load fMWI Status Status J p_15el_ OFFsite Pwr Sources 2 AV Cont Ra IfVAC Supp Fan A OP TBCC PMP A OP 75 Cen Breakers 2 CL 8 OP 8 OP 75 Div 1 DC OOS Cont Rm HVAC Rtn Fan A SS C SS 18 Div 2 DG OP O 8 SS SA Comp OP 128 Div 3 DC OP O Cont Re Eng RClRC Fan A OP IA Comp SR 120 8 OP P800 CIRW PMP A OP 46 Status P970 8 SS O Cntet vsl CIg Fan A OP Pressure
. Status.. Iosial C SS O 8 OP IICC Pump A SS 35 SJAE A SS C SS S SS 35 8 SS D OP C OP 112 E OP ADDITIO8tAL INFORMATIOst SW Pump A OP 56 F SS Status Abbreviations: 8 OP 56 Drywe l l Cool ing Fan I A OP OP Ope ra t ing C SS O 2A OP SS Secured Status D SS O 3A OP AV Available MTR Fire Pump SR 18 SS SR Standby Readiness DD Fire Pump SR 28 SS 1 SHTDN Shutdown 38 SS S-SP Slow Speed Cntet Vsl Purge Supp Fan A SS <
F-SP Fast Speed 8 SS ISOL 1solated Cntet Vsl ac DW Purge Exh Fan A SS NORM 900 raa I 8 SS OOS Out of Service Drywo I I Purge Suppi Fan A SS CL Closed 8 SS OVRD Override AECTS Fan A OOS 8 OP
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3 PERftY IIUCLEAR POWER Pt.AIIT 1964 DeOlGUICY PftEPAftEOstESS EMERCISE . TIME: 1220 PAllEL P604 PAsIELS P669. P670. P671. P672 s Process Radiation feeln Steam Line RAD 0.0C+0 aft /hr Alare Catet Vent Exh RAD 41.0E-1 aft /hr offges Pre-treatment 2.5E+1 R/hr offgas Post-treatment A 2.0E+2 cpe PAIIEL P902 8 2.0E+2 cpe Common Airborne Gas (coal Alare Eng Service Water A 3.0E+1 cpe RWB Vent Exh 2.0E+1 8 3.0E+1 cpe Fles vent Exh 2.2E+1 ! OG Carbon Bed Vault A 6.0E+1 aft /hr CR Vent Exh 2.0E+1 B 5.5Ett aft /hr PA10EL P906 PA8tEL 803 Commen Process and Area ggg Algre l ! Turb Bldg East 2.5E+0 aft /hr UD-9EM-73 East Lig L9[21 i Turb Bldg West 2.5E+0 aft /hr 90-900-70 West Lig 1.2E+1 1 IICC Heat HX 3.5E+1 PAI0EL P904 Radweste to ESW 3.0C+1 Airhorne Radiation Ges (coal Atern Redueste to sewage 3.6E+1 1 Annulus Exh A Ces 0.0C+0 9 9AEX . 90ETEOROLOGICAL C0010lTIOpl$ Cntet Ato >L9ff6 H Drywell - HR (R/hr) 6.]{ +;i A8 Vent Zafi Wind speed 5.0 mph 280
- OG8 Vent Exh 2,9ffg Wind Direction
, OG8 Vent - HR Q,Q[19 Tempe rature 40 *F OG Vent Pipe 2,9E+2 Delta T -1.45 *F i UI Plant Vent 6,0E+1 i U1 Plant Vent - Hft D J[tg 18/HB Vent 6,0(+1 j- 18/H8 Vent - Hft 9,9E3 ST Packing Exh h 9t-1 U2 Plant Vent Id(+1 , U2 Plant vent - HR 0.0E+0 DW170C/A/42/es
AREA RADIATION MONITORS Time: 1220 , TAG # LOCATION READING (mR/hr) , ID21NO30 Personnel Air Lock, Cntmt (600'6") OS :1.0E+4 *
. 1D21N040 CRD HCU West, Cntmt (620'6") OS ) 1.0E+4
- 1D21N050 RBRT Area, Cntmt (642') OS >1.0E+4
- 1D21N060 Tip Drive Area Cntmt (600'6") OS > 1. 0E+4
- ID21N070 RWCU F/D Area, Cntmt (664'7") OS > 1. 0E+4
- 1D21N080 Upper Pool Area, Cntmt ,
(689'6") OS ) 1.0E+4
- ID21N110 Aux Bldg East (574'10") 3.4E+2
- 1D21N120 Aux Bldg West (574'10") 3.4E+2
- 1D21N130 Turb Rm East (647'6") 1.9E+0 1D21N140 CRD HCU East, Cntmt (620'6") OS ) 1. 0E+4
- ID21N160 Turb Rm West (647'6") 1.9E+0 1D21N170 Turb Blda (605'6") 2.1E+0 1D21N180 Hotwell Pump Area TB (577'6") 1.0E+1
- 1D21N190 TB Sump Area. TBC (548'6") 2.0E+1 i 1D21N200 OGB (584') 1.1E+1 ID21N210 Cnds Fitr Pmp Area, TBC (568'6") 9.0E+0 ' ' 1D21N220 OG After Fitr Area, OGB (602'6") 2.0E+1 1D21N230 HP Fdw Her Area, HB (600'6") 1.0E+1 1D21N240 Fdw Pump Area. HB (647'6") 8.5E-1 1D21N400 CR, CC (654'6") 1.6E-1 1D21N410 OG Hold Up Area. TB (577'6") 8.7E+0 l D21N250 RWB West (574'10") 2.5E+1 l D21N260 RWB East (574'10") 1.5E+1 ' - D21N270 RWB (602') 5.0E+0 D21N280 Process Sample Rm, RWB (623'6") 4.0E+0 D21N290 RW Evap, RWB (623'6") 4.0E+0 D21N310 FPCU F/D Area. IB (599') 3.5E+2
- i D21N320 Fuel Preparation Pool, IB (620'6") 3.2E+2
- D21N330 Spent Fuel Storage Pool, IB (620'6") 3.3E+2
- 1 D21N420 FPCU Cire Pmp Area, IB (574'10") 3.0E+2
- 1D21N340 Unit 1 DW, Portable, Cntmt (655') -
D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1 D21N370 SRW Drumming Area RWB (623'6") 6.0E+0 1D21N090 Refueling Bridge, Cntmt (689'6") OSS 1.0E+4
- D21N390 Fuel Serv Hdig Platform, IB (620'6") 3.4E+2
- i t
* = Alarm OS = Offscale
$2.3W Tica: m -
Message No.: 81 PERRY NUCLEAR POWER PLANT
. 1984 EMERGENCY PREPAREDNESS EXERCISE c
MESSAGE FORM Messame For: Plant Technical Engineer
. SimulatedPEantConditions:
4
.I Messame: ***THIS IS A DRILL *** .
The attached notice was found.in your office "IN" Basket.
)
a f k i J-p ..
- i. . .
s . FOR CONTROLLER USE ONLY I ') Controller Notes:
'. Actions Expected:
4
-p .
. DW176/C/81/dlh
# 4
5 C7 . ~. Cf ./S e /Q ' :~~ > OE 1171 DOUO'NMAN (PPSL) 16-OCT-04 00:00 PT S ula.Je c t. : POTENTIAL FOR FAIT.URE OF CONTROL ROD DRIVE SCRAM PILOT VALVE F UNIT - SUSOUEHANNA UNIT 1 gg (VENT DATE - OCTODER 12e 1984 NSSS/AE - DE/DECHTEL OCT Ul @ I RATINO - 3293 MUT na gg'"* b , POTENTIAL l'OR FAILURE OF CONTROL ROD DRIVE SCRAM PILOT VALVES. 5 EVENT DESCRIPTION: ON OCTODliR 6e l'7 G 4 e ROUTINE SCRAM TIME TIESTINO WAS DEINO PERf*0RMf*D ON A SELECTED NUMDER OF SUSOUCHANNA UNIT 1 CONTROL. RODS.
. IT WAS NOTED THAT SOME RODS HAD LONOER THAN NORMAL SCRAM TIMES AND SOME WOULD NOT SCRAM.
INVESTIGATION FOUND THAT THE DUAL ASCO SOLENOID VALVES USED AS SCRAM PII;OT val.VES ON THE RESPECTIVE CONTROL ROD HYDRAULIC ACCUMul.ATORS WERE NOT OPERATINO PROPERLY. THE DEFECTIVE VALVES WERE REPLACED AND THE CONTROL RODS RETESTED SATISFACTORILY. A D D I T I O N Al.l. Y
~ ]
ALL 105 CONTROL RODS ON UNIT 1 WERE SCRAM TIME TESTED SATISFACTORILY SEVERAL OF THE DEFECTIVE SOLENOID VALVES WERE SENT GUT I? O R TESTINO TO DlITICitMINED THE CAUSE OF THE FAILURE. ANALYSIS DIi1 ERh ! N f*.D THAT THE FAILURE WAS DUE TO A DREAK DOWN OF THE POLYURETHANE VALVE SEATe CAUSING IT TO STICK TO THE INTERIOR OF THE VALVE DODY. THE CAUSE OF THE DREAK DOWN OF THE POLYURETHANE IS DEINO INVESTIDATED,
, DUT APPf!ARS TO DE DlJE TO HIOH TEMPERATURE. ' THE'RESULTS OF THE ANALYSIS WrIRC REPORTED TO PPSL ON FRIDAY, OCTODER 12, 1904. DOTH UNITS 1 AND 2 AT SUSOUEHANNA WERE GilUrllOWN AS A PRECAUTIONARY MEASUREe DECAUSE THE ANALYSIS INDICATED A P O Tf! N T I A I. FAILURE MECHANISM FOR A l. L SCRAM PILOT SOLEHOI D Vol.VES .
r/ O LI.O W I NO SHUTDOWN, Al.L POLYURETHANE SEATS IN THE HCU DUAL ASCO I SCRAM l II.OT V A I. Vf! S WERE REF'LACIID WITH SEATS MADE OF VITON. J A L Tl4 0 llO H THE CAUSE OI? THE DREAK DOWN'OF THE POLYURETHANE VALVE o SEATS IIAS NOT YET DEEN DETERMINED, IT APPL!ARS TO DE CAUSED DY Hlf A T . lill? tililJRCl! Off Tile lifiAT MAY DE THE Dil Al. ti Ot.li N U I D S ON TliEGE VA. Vlis e 111A r ARE NORM Al.LY f* N E R G I '/. h* D . I n f ri c tie n t i n n C n re t. te ra t OARY W. DOllili tM AN *!15-770-7902 8
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Time: 1230 Message No.: 69 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM [ Messaae Fort Control Room /TSC/ EOF Simulated Plant Conditions: See attached sheets e ggg,m s ***TNIS IS A DRILL *** k i U 1' FOR CONTROLLER USE ONLY 1 i. Controller Notes: 1. Suppression Pool temperature reaches 224*F; containment pressure is 5 psig and increasing.
- 2. RHR 3 is being used for containment spray, but RHR Heat Exchanger Bypass Valve E12-F0488 is open, rendering the spray ineffective due to lack of cooling.
- 3. HPCS is maintaining water level.
- 4. Annulus Exhaust Gas Treatment System (AEGTS) and the Unit 2 vent monitor detect small but increasins levels of radiation, a.
Actions Expected: DW176/C/69/ba 4 .. ..
PEftRY IIUCLEAR POWER PLANT 1964 DIEstGEIICY PREPAREDeESS EXElICISE T IIIE: 1230 COIITROL IIOOM AIIIIUNCI AT0fts P601/P877 P680 P870 ar BACR PAIIELS Section 20A Section 19A
- Section 19A Section 'JA Sect!cn 3A COtti RII HVAC EIIERG RCillC A SUPP POOL ADS 8 ADS A MAaIUAL SCRAM REACT 0ft FDW IIllTI ATED P90al LEVEL A HIGH PEIIMISSIVE INSTANTANEOUS SWITCH ARIIED PUMP A TRSP ftIIR 8/C RUII LOGIC INITIATED COIII stM HVAC SUPP POOL RPS LOG 1C Section 2A DIERC RCIRC 8 TEMP A HIGH ADS A ADS 8 IIAaIUAL SCRAM INiilATED P904 ~
PERDIISSIVE INSTAsIT AstEOUS LP COIIDENSER COIITAIISIENT RPV L-3 LOGIC IIllTIATED RRCS 80488 VACUUM LOW PRESS A HIGIt 18II TI AT ICII ADS 8 ADS A IP COIIDEIBSER DetWELL PEftMISSIVE TillE DELAY IIPS LOW LEVEL VACUUM LOW PRESS A HIGH RPV L-3 LOGIC INITIATED L-3 NP COIIDEIISER LOGIC IOR LPCS/ ADS A ADS 8 RftCS VACUUM LOW LPCI A FRM RHR A PERIIISSIVE TlHE DELAY RX LEVEL DW PRESS HICH DW PftESS HIGH LOCic INITIATED LO L-2 COIITAllIMElli ADS 8 Section 20A RPS TEMP A HIGN PERMISSIVE DRYWELL DW PRESS HIGH CNTM SPftAY 8 PItESS HIGIt - DRWELL INITIATED TEMP A APS HIGH CNTM SPRAY 8 MSiv CLOSultE MAII 1811TI ATE Section 17A Section 17A. SWITCH AftMED Section 7A SUPP POOL COIITA BIIMENT SAFETY / RELIEF LEVEL 8 TEMP S HIGH VALVE LEAKAGE HIGH ALANI P614 DRYWELL SUPP POOL TEMP 8 TEMP S HIGH HIGH COIITAIIIMENT PRESS 8 HIGH DRYWELL l PitESS S HIGH LOGIC FOR LPCI 8/C IM RHR , DW PitESS HIGH J DW1708/A/125/rmk
PEmmV IeUCLEAR POWER PLAlti 1984 EM[ItGENCY PREPAREDNESS EXERCISE TIME: 1230 .I P601 P600 COIITAllWEEIIT PARAfETERS , SYSTEM INFORMATION REACiell PARAMETERS . Temperature Pressure - Pressure Flow Pressure 155 psig , 7 f*Fl fosiel
- Status tesien femal I LoveI -142 in ' A
, Catet 220 5.5 MWCW PMP A SS ] Neutron Orywell 216 4.6 S SS Mon a Range M 80WL P9er A OP 230 Stode SW SMTON l Tempe ra ture Level j f*F1 iFt.) B OP 230 FDW Ftw 0 Mab/hr i Supr Pt 224 21.6 C SS 0 ST FIw (Tetal). O Mib/hr
! CSP A SS 150 Line A 0 l -
SYSTEMS IIIFORMATICII 1 3 SS 150 Line a O Pressure Flow Status insiel femel C SS 150 Line C 0 1 i mesR A Peer OWItp RFBP A $$ 160 Line D 0 I B CNT SPftAY 250 7000 B SS 160 C Vty Oyst0 275 0 C SS 160 LPCS PMP OVItD D SS 160 1 Itcic FLOW OVRD 100 0 RFP A SS 0 0 i HPCS OP 1000 3400 B SS e 0 ECC- A 00$ MFP SS 0 0 I TURSIIIC-G[NCRATOR S OP 114 IICIltC a SS o PAftAfGEiER$ ESW A 005 B SS _ 0 Mwatt 0 5 OP 95 MVAR 0 i Mfucet VALVE PARAMETERS l C OP 95 CaoR vac 0 in, ng 4 Status Closed Omen i CRO A SS 1hrt Pr 0 psig 1 MSiv IsOL a 0
< B SS BYP VLV say AOS 11 a Posit 0 g .
SLC A OP 1600 8 OP 1600 q Sic Sic in Lvt y . ,as. i 1
Pfasty guesCLEAR POWER PLAIIT 1984 E90ERGEleCY PettrastESeetSS EXERCISE TieEE: 1230 2R29 ELECTRICAL 9951R8810I101I M CST Level 410.000 eat. Statess Lead leeft Status Status losial 0FFsite Pwr Sources 2 AV Cent he IfWAC Supp Fan A OP ., TOCC P9tP A 0F 75 Con Broshers 2 CL' S OF S OP 75 Div 1 BC 00$ Cent Am IIWAC Rtn Fan A SS C SS 18 Div 2 BC OP O S $$ SA Camp OP 128 Div 3 BC OP O Cent Am Eag IICIAC Fan A OP
^
IA Comy SR 120 S OP f300 CIfti P90P A OP 46 Status
~
P970 S SS 0 . Catet Vsl CIg Fan A 0F Pressure Status losial C SS 0 -B OP SJAE A SS C SS S SS n B SS D OF 0 OP 112 E OP ADDITICIIAL lutonemTICII Sed Pump A OP 56 F SS Status Abbreviations: B OP 56 DryweII Coeling Fan 1A OP OP Opera ting C SS 0 2A OP SS Secured Status O SS 0 3A 0F AV Available 90TR Fire Pump SR IS SS SR Standby iteadiness- DD Fire Pump SR 28 SS SMTOet Shutdoun 38 SS . S-SP Slow Speed Catet Vsl Purge Supp fan A SS F-SP Fast Speed 8 SS i 5 00. Isolated Catet VsI er DW
. Purge Exh Fan A SS 8008Ut IIeres i B SS DOS Out of Service Dryuell Purge
- Seappt Fan A SS CL Closed 8 $$
DVIto Override AECTS Fan A 005 3 0F
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PEmitY IpICLEAll POWE'l PLAIIT 1994 EDIElbCEIICY PREPAREDIIESS ENEACISE Y tee: CSS i !) PAAEL P604 P m is Psae. P67e_ P67t_ M72 - IIsla Stees Line RAS 0.0E+9 mR/hr Process mediation Alers Catet Want Exh RAS 41.ef-1 mit/hr j
- Offges Pre-treatment 2.5E+1 R/hr Offges Post-treeteent A Z,9[+2 cpe FAAEL P902 5 2.0E+2 cpe Common Airterne Gas Icmel Alarm A 3.0E+1 cpe AIS Vent Emit 2.K+1 ,
Eag Service Water B 3.0E+1 *:pe. FIIS Vent Emh 2.2E+1 LGE 1 mR/hr CR Vent Exh 2.K+1 OG Cerben Bed Vault A, 3 5.M +1 alt /hr PAML Pgen PAIIEL 803 Common Process and Ares m Alere IID-le6-73 East Lig 3.K+1 Turt SIds East 2.5E+0 alt /hr s Turt Bldg West 2.5E+0 mR/hr IID-lel-70 West Lig 3.2E+1 NCC IIsot IIK. 3.5E+1 PAIIEL P904 Redweste to EShi 3.K+1 Gas (coal Redweste to Sewage - 3.6E+1 Airborne Radiation Alere Annulus Exh A ces 0,0L+9 Catet Ate > JE a IIETEOROLOGICAL COISIT1935 orywes t - IIR (R/hr) 01(11 Wind speed 43 aph As vent unil Wind Berection. 300
- OCs vent Exh 2,9L12 vamperature to *r Oca vent - IIn e.gue -1.30 *F OG vent Pipe 2,9L+2 Bolta T v1 Plant Vent Let_f_1 U1 Plant Vent - M gm0[+g IS/les vent 6 JI* 1.
18/105 Went - IM 0,9(*9 ST Paciting Exh $,9fd 412 Plant Vent 2,0f+2 482 Plant Vent - IIR 0.0E+0 Dbfl70C/A/43/es
AREA RADIATION MONITORS Time: 1230
~
TAG # LOCATION READING (mR/hr) 1D21NO30 Personnel Air Lock, Cntmt (600'6") OS 51.0E+4
- 1D21N040 CRD HCU West, Cntmt (620'6") OS > 1. 0E+4
- 1D21N050 RBRT Area Cntmt (642') OS 11.0E+4 *
- 1D21N060 Tip Drive Area, Cntmt (600'6") OS s 1.0E+4
- 1D21N070 RWCU F/D Area, Cntmt (664'7") OS 71.0E+4
- ID21N080 Upper Pool Area, Cntmt (689'6") OS41.0E+4
- ID21N110 Aux Bldg East (574'10") 3.4E+2
- ID21N120 Aux Blda West (574'10") 3.4E+2
- 1D21N130 Turb Rm East (647'6") 1.8E+0 1D21N140 CRD HCU East, Cntmt (620'6") OS ) 1.0E+4
- ID21N160 Turb Rm West (647'6") 1.8E+0 1D21N170 Turb Blda (605'6") 2.0E+0 1D21N180 Hotwell Pump Area. TB (577'6") 1.0E+1 1D21N190 TB Sump Area. TBC (548'6") 2.0E+1 1D21N200 OGB (584') 1.1E+1 1D21N210 Cnds F1tr Pmp Area. TBC (568'6") 9.0E+0 1D21N220 OG After F1tr Area. OGB (602'6") 2.0E+1 1D21N230 HP Fdw Her Area. HB (600'6") 1.0E+1 1D21N240 Fdw Pump Area. HB (647'6") 8.3E-1 1D21N400 CR, CC (654'6") 1.6E-1 ID21N410 OG Hold Up Area. TB (577'6") 8.6E+0 D21N250 RWB West (574'10") 2.5E+1 D21N260 RWB East (574'10") 1.5E+1 D21N270 RWB (602') 5.0E+0 D21N280 Process Sample Rm, RWB (623'6") 4.0E+0 D21N290 RW Evap, RWB (623'6") 4.0E+0 D21N310 FPCU F/D Area. IB (599') 3.5E+2
- D21N320 Fuel Preparat*.on Pool IB (620'6") 3.2E+2
- D21N330 Spent Fuel Storage Pool, IB (A20'6") 3.3E+2
- D21N420 FPCU Cire Pmp Area. IB (574'10") 3.0E+2
- 1D21N340 Unit 1 DW, Portable, Cntmt (655') -
D21N380 Wasta Compactor Area, RWB (623'6") 6.0E+1 D21h370 SRW Drumming Area RWB (623'6") 6.0E+0 1D21N090 Refueling Bridge, Cntmt (689'6") OSi 1.0E+4
- D21N390 Fuel Serv Hdig Platform. IB (620'6") 3.4E+2 *
* = Alarm OS = Offscale
Time: 1235 Message No.: 70X' PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Messane For: Emergency Coordinator Simulated Plant Conditions: Message: ***THIS IS A DRILL *** . . Declare a GENERAL EMERGENCY (EPI-A1, Section D.IV.1, " Loss of two fission product barriers with a potential loss of a third" or Attachment 3. Condition 2. " Transient plus failure of requisite core shutdown systems. Could lead to core melt in several hours with containment failure likely. More severe consequences if reactor Recirculation Pump Trip does not function"). 1 e 0 FOR CONTROLLER USE ONLY ? Controller Notes: Deliver this message if a GENERAL EMERGENCY has not been declared. Do not deliver this message if Emergency Classification discussions are underway. e Actions Expected: See " Actions Expected," Message No. 68. DW176/C/70/ba
T'
- 1 l .
Timer 1245 i Message No.: 71 ! i; g PERRY NUCLEAR POWER PLANT . ! 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORN Messame For: Control Room /TSC/ EOF- j Simulated Plant Conditions: see attached sheets i 3333333: ***TNIS IS A DRILL *** , l 1 I I l
! \
FOR C0tf!1t0LLER USE ONLY I l Controller Notes: Containment pressure and temperature continue to increase. l- Suppression Pool temperature is 238'F containment pressure
; is 10 pois and increasing. [
' I
,1 Actions Expected 1
?
g i i e DW176/C/71/ba
?
r h
PEIIRY IIUCLEAR POWER PLAdli 196at EMEItGEIICY PREPAREDmESS OtERCISE TieIE: 12e55 COIITIt0L 2004 AMIIIIICIATORS Mel/PSIT P640 PS70 at SACK PalgELS Section 204 Section 19A Section 19A Section SA Section 3A COIII Ist leVAC E8EERC RCIRC A SesPP POOL ADS S - AOS A m SCRAft REMTOR FDid Ile Bi8 ATED P90es LEVEL A MICet PEliseISSIVE IIBSTANTA8IEOUS SWITCII ARNES PtIBOP A TRIP RNR S/C steel LOGIC INITIATED COIIT IIIS 9fv4C SUPP POOL RPS LectC Section 2A EleERC ftC8IIC S TEper A NIGet ADS A ADS S femenIAL SCRAGE IeiiIATED P90dB PEltretSSIVE INSTAalTAIIEOUS LP COIIDEIISER , COIIIA BIstE NT RPV L-3 LOGIC INIllATED RACS 94485 VN LOld PRESS A HIG86- INITI Ail 0lt A05 B ADS A IP COISEleSER DRWELL PEmpet SS BvE Titel DELAY RPS Lott LEVEL VAcunst LOW PRESS A HICM RPV L-3 LOGIC INITIATED L-3 MP rnmartsSER EOGIC IOR LPCS/ AOS A AOS S RACS VACIItst LOW LPCI A f fWt RHft A PERftISSIVE ilfeE DEEAY RX LEVEL ' DW PRESS MIC88 DW PRESS HICat LOGIC IIIIII ATED LO L-2 ColliAIIpeEN T ADS S Section 20A RPS TEfte A MIGN PEItsetSSIVE DR M LL 044 PRESS HICH CNTM SPRAY S PRESS 30lGB0 , DetWELL 8NITIATED 1EMP A RPS HBCH CIIIM SPIIAY S 9054V CLMM
- ptAll IIIITI AIE Section ITA Section liA SWiiCM Afift[D Section TA SUPP PSOL SAsETY/ RELIEF LEVEL S VALVE LEAILACE HIGN ALANG P6145 SUPP P00t_ COIITAIIpeE mi TEMP S HICbe 1[ftP S HICBS CoatTAIIsetIli DetWEtL PRESS S HIGN TEler S HICH DRWEE L PIRESS S MICM toGIC telt LPCI R/C g iM RHft DW PRESS MICet Old1 TOS/A/128/rmk
PERRY IRACLEAA POWER PLAtli 1304 EMERCERCY PftEPAftERRESS EMERCISE TieEE: 1 24:5 Mel Psao COIlTAI M 4i PASAfETER$ , SYSTEM IIBF0R804iIOR REACTSR PAMpETERS Temperature Pressure Pressure Flow Pressere 160 psig f*F1 fasiel Status- fasiel femel Level -140 in. W Catet 235 9.8 3RdCaf PEOP A SS aboutron oryw: e 230 4.9 s $$ seen a Renee Aggs ledL Pter A OP 230 feede SW SelTOR Temperature tevet (*F1 fft.1 S OP 230 FSW Flw 0- selb/hr Supr Pt 238 21.6 C SS O ST FIw (Total) O Mit/hr CSP A SS 150 Line A 0 - SYSTEBOS lef0 Ret 4Ttces B SS 150 Line B O Pressure Flow Status fosiel femel- C SS 150 Line C 0 ' anR A Cast traay 2sa 7080 RESP A SS 160 Line 8 0 - S CIIT SPRAY 250 7000 5 $$ 160 C VLV OVRO 275 0 C SS 160 LPCS Pter OVRO O SS 160 . RCIC FLOW OWRB 100 0 RTP A SS 0 0 tePCS OF 1000 3400 S SS O O [CC A 005 10FP $$ 0 0 f tpRSIg(-C_E_Isf RA TOR 8 OP 114e RC8AC A SS O PASAfEILRJ t ESW A OOS S SS O su tt 0 l B OP 95 85 WAR 0 SOfL90R VALVE PARASEffR$ 1 C OP 95 CROR vac 0 in seg l Status Closed A CitO A SS Thrt Pr o psig 8858V ISOL e O S SS SYP VLV SRV ADS 11 a Posit 0 1 SLC A OP 1600 B OP 1600 SLC STC TK LVL E gal. 4
.6
PERRY IRICLEAR P0ldER PLAeT 1984 EMERGENCY PIREPAAESIIESS EMERCISE TieIE: IMS PS79 ELEC11tlCAL DISTAL 0 Nil 0ll 2399 CST Level 410.000 eal. .Statui Leed INI Status _3tates . f esiel - 0FFsite Pwr Sources 2 AV Cent As IfwAC Supp Fan A 0F TBCC Peer A OP 75 Con Breakers 2 Ct S OF S OP 75 Div 1 DG 00$ Cent Am 9Mic Rtn Fan A SS C SS 18 Div 2 BC OP O S. SS SA Cony OP 128 Div 3 DG OP O Cent An Eag RCIRC Fan A OP IA Comp SR 120 S OP P900 Ctant FnP A OP M Status Pg79 - S $$ 0 Catet Yst CIg Fan A OP Pressure Status tesiel C $$ 0 B OP NCC Pump A $$ 35 l UAE A 55 C $$ l 8 $$ s5 B SS o OP C OP 112 E OP A00YTIOstAL laBFolemiIOg SW Pimp A OP % Status Abbreviations: B 0F M l DrytseIB CoeIing Fan IA OP OP Opera ting C SS O 2A OP
$$ Secured Status D SS 0 3A OP -
l AV Available IITR Fire Peep SR i 18 $$ SR Standby Readiness SS Fire Peep SR 28 SS SteTDss Shutdoun 38 SS S-SP Slow Speed Catet Vst Purge Supp Fan A $$ F-SP Fast Speed B SS B Sot _ Ssolated Catet vst at End Purge Esta Fan A SS 180000 merans S SS 005 Out of Service Drywll Purge Suppi fan A SS CL Closed
. S SS OVRO Override AEGIS Fan A 00S B 0F
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PERRY NtfCLEAR POWER PLAer 19e4 EleEDGEIICY PetEPAAEBRESS EXERCISE T esE: 12ts5 i PAIREt P604 Paetts P669. P679. P671. P672
]
Process Radiation etsin Steen Line SAS 9.3E+G mA/hr ! Alors . a f.ef-1 mA/hr
~
l Catet went Emh RAD l l
. Otrges Pre-treatment 2.5E+1 R/hr i
errges Post-treatment A 2.0E+2 cpe _ PAGEL P982 B LO Q Z cpe Common Airterne ces (caal Alare , Eng Service unter A 3.Of*1 cpe SWB Went Emh . 2.9E+1 a L _0 Q 1 cpe FMS Vent Enh 2.2E+1 OG Carbon Bed Vault A 6.0E+1 mR/hr CR went Exh 2.9ft1 l 8 L}{ti aft /hr l PAM L P906 i l ELueR_30] Cemeen Process and Aree gag . AIare Turt steg East ?.St+0 aft /tr us-eas-73 East Lig 3.0E+1 Turt side West 2.5E+0 aft /hr up-tes-78 West Lig 3.2E+1 IICC 8enet ME 3.5E+1 PaseEL P90s Radweste to E5ht Lg(+1 l Airterne Radiation Ces fcael M Eg Redweste to sewege L&[+1 Annulus Enh A Ces O JE_+9 a 3.4t?2 21.0L+6 Cates Ata # IEETEOROLOGICAL COIIDITIONS Drywe I - MR (R/hr) 6.Ril Aa vent zJw11 - Wind speed 4.o mph oca vent Enh 2d4_*2 Wind Direction J to oCa vent - sen 0 ot_+o vesperature to *r oc vent ripe 2.o(12 Setta T -1.no *r un riant vent 6.pf+1 ut Psant vent - sem o.sw ?q . Is/ ass vent 6.ot+1 is/nse vent - asm o,s4_to si racking Exh },ts-J v2 riant vent q Jw .2 u2 riant Vent - teR Q _O W l DWITOC/A/44/es
AREA RADIATION MONITORS Time: 1245 , TAG # LOCATION READING (mR/hr) ID21NO30 Personnel Air Lock, Cntmt (600'6") OS >1.0E+4
- 1D21N040 CRD HCU West. Cntmt (620'6") OS > 1.0E+4 *
, 1D21N050 RBRT Area, Cntet (642') OS > 1.0E+4
- I 1D21N060 Tip Drive Area, Cntmt (600'6") 0S *1.0E+4
- j ID21N070 RWCU F/D Area, Cntmt (664'7") OS> 1.0E+4 *
- 1D21N080 Upper Pool Area, Cntme (689'6") OS 31.0E+4
- 1D21N110 Aux Bldg East (574'10") 3.4E+2
- 1D21N120 Aux Bldg West (574'10") 3.4E+2 *
! 1D21N130 Turb Rm East (647'6") 1.8E+0 1D21N140 CRD HCU East, Cntmt (620'6") OS >1.0E+4 *
!l ID21N160 Turb Rm West (647'6") 1.8E+0 l _ID21N170 Turb Blda (605'6") 1.9E+0 1D21N180 Hotwell Pump Area. TB (577'6") 1.0E+1 ID21N190 TB Sump Area. TBC (548'6") 2.0E+1 6 1021N200 OGB (584') 1.1E+1
- ' 1D21N210 Cnds Fitr Pmp Area. TBC (568'6") 9.0E+0 l} 1D21N220 OG After Fitr Area. OGB (602'6") 2.0E+1 1D21N230 HP Fdw Her Area HB (600'6") 1.0E+1 1D21N240 Fdw Pump Area. HB (647'6") 8.0E-1 1D21N400 CR, CC (654'6") 1.6E-1 1D21N410 OG Hold Up Area, TB (577'6") 8.6E+0
- g D21N250 RWB West (574'10") 2.5E+1
-
- D21N260 RWB East (574'10") 1.5E+1 3
'D21N270 RWB (602') 5.0E+0 D21N280 Process Sample Rm, RWB (623'6") 4.0E+0
'I D21N290 RW Evap, RWB (623'6") 4.0E+0 _D21N310 FPCU F/D Area, 1B (599') 3.5E+2 D21N320 Fuel Preparation Pool, IB (620'6") 3.2E+2 D21N330 Spent Fuel Storage Pool, IB (620'6") 3.3E+2 * (574'10") iD21N420 FPCU Cire Pmp Area, 1B 3.0E+2
- 1021N340 Unit 1 DW, Portable. Cntmt (655') -
D21N380 Waste Compactor Area RWB (623'6") 6.0E+1 ll D21N370 SRW Drumming Area RWB (623'6") 6.0E+0 il 1D21N090 Refueling Bridge, Cntmt (689'6") OS > 1. 0E+4
- _D21N390 Fuel Serv Hdig Platform, IB (620'6") 3.4E+2
- i i
1 l i' i
* = Alarm OS = Offscale
<.. Tims: 1300 s
Message No.: 72 J PERRY NUCLEAR POWER PLANT s. 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Messaae For: Control Room /TSC/ EOF Simulated Plant Conditions: See attached sheets - Message: ***THIS IS A DRILL *** 1 mt' f-4 L J. i. I
?-
FOR CONTROLLER USE ONLY
~
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y . - Controller Notes:
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I e
, Actions Expected:
^
i l 4 4 (- 6 r i DW176/C/72/ba.'- 4
) * *
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PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1300 CONTROL ROOM ANNUNCI ATORS - P601/P877 P680 P870 & BACK PANELS - Section 20A Section 19A Section 19A S3ction 5A Section 3A CONT RM HVAC EMERC RCIRC A SUPP POOL ADS B ADS A MANUAL SCRAM REACTOR FDW INITIATED P904 LEVEL A filGH PERMISSIVE INSTANTANEOUS SWITCH ARMED PUMP A TRIP RHR B/C RUN LOGIC INITIATED CONT RM llVAC SUPP POOL RPS LOGIC Section 2A [MERG RCIRC B TEMP A HIGH ADS A ADS B MANUAL SCRAM INITIATED P904 PERMISSIVE INSTANTANEOUS LP CONDENSER CONTAINMENT RPV L-3 LOGIC INITIATED RRCS MAN VACUUM LOW PRESS A HIGH INITIATION ADS B ADS A IP CONDENSER DRYWELL PERMISSIVE TIME DELAY RPS LOW LEVEL VACUUM LOW PRESS A tilGH RPV L-3 LOGIC INITIATED L-3 HP CONDENSER LOGIC FOR LPCS/ ADS A. ADS B RRCS VACUUM LOW LPCI A TRM RilR A PERMISSIVE TIME DELAY RX LEVEL DW PRESS tilGH DW PRESS HIGH LOGIC INITIATED LO L-2 CONTAINMENT ADS B Section 20A RPS TEMP A IIIGH PERMISSIVE DRYWELL DW PRESS HICal CNTM SPCAY B PRESS HICH DRYWELL INITIATED TEMP A RPS 111 061 CNTH SPRAY B MSIV CLOSURE MAN INITIATE Section 17A Section ITA SWITCll ARMED ,Section 7A SUPP POOL CONTAINMENT SAFETY / RELIEF LEVEL B TEMP B 111 Cal VALVE LEAKAGE HIGH ALARM P614 DRYWELL SUPP POOI. TEMP B TEMP BlilGH lilGH CONTAINMENT PRESS B HIGli , DRYWELL PRESS B li1CH LOGIC IOR
- LPCI 8/C FM RilR DW PRESS HICH DW1708/A/131/rmk .
J
. _. . , , , . _ . E t- . . ..rsh hn _# h ',- i L :'. ..GmEJaw + Aa-- u. . sh c_L . : G.. ;. . 9 ~ v .t.:.... r . . .- . ;- PERRY NUCLEAR POWER PLANT 1984 EMERCENCY PREPAREDNESS EXERCISE TIME: 1300 , E6Q1 P680 - CONTAINMENT PARAMETERS SYSTEM INFORMATION REACTOR PARAMETERS Tempe ra tu re Pressure Pressu re flow Pressure 160 psig '. f*F) _{psig1_ Status fosial fqpel Level -130 in. WR Cntet 250 16.7 RWCU PMP A SS Neutron Drywe1I 245 12.0 B SS Mon 8 Range APRPJ IfWL PMP A OP 230 Mode SW SHIDN Tempe ra ture Level f*F1 IFt.) B OP 230 FDW Flw 0 Mlb/hr Supr Pt 252 21.9 C SS 0 ST Flw (Total) O Mib/hr CBP A SS 150 Line A 0 SYSTEMS INFORMATION B SS 150 Line B 0 Pressure Flow
. Status fosial (com] C SS 150 Line C 0 RHR A C Nf . $ PRAY 250 7000 RFBP A SS 16Q__ Line D 0 B CNT SPRAY 250 7000 B ____SS 160 C VLV OVRO 275 0 C SS 160 LPCS PHP OVRO .D SS 160 RCIC FLOW OVRO 100 0 RFP A SS 0 0 , HPCS OP 1000 3400 B SS 0 0 ECC A 00S MFP SS 0 0 T URB l q[-C[NE R ATOR B OP 114 RCIRC A SS O EARAMETERS .
ESW A 00S B SS O__ Mwatt 0 , B OP 95 MVAR 0 MAJOR VALVE PARAMETERS C _ OP 95 CNDR Vac 0 in. Hg Status Closed Open CR0 A SS Thrt Pr 0 psig MSIV ISOL 8 0 B SS BYP VLV SRV ADS 11 8 Posit 0 % SLC A OP 1600 8 OP 1600 SLC STC TK LVL 4600 gal. i
PERRY NUCLEAR POWER PLANT 19884 EMERCENCY PREPAREDNESS EXERCISE TIME: 1300-MZQ LIECTRICAL DISTRIBUTION HQh CST Level 410.000 cal _Staties Ioad fMW1 .Stattes Status .losial OFFsite Pwr Sources 2 AV Cont Rm HVAC Supp Fan A OP TBCC PHP A OP 75 Cen Breakers- 2 Cl. B .. OP B OP 75 Div 1 DC OOS Cont Rm HVAC Rtn Far. A SS C SS 18 Div 2 DG OP O B SS SA Comp OP 128 Div 3 DC OP O Cont Re Eng RCIRC Fan A OP 1A Comp SR 120 B OP MQQ CIRW PHP A OP 46 . Status fil9 8 SS 0 Cntet Vs1 Cig Fan A OP Pre ssu re Status losie) C SS O B OP NCC Pump A SS 35 SJAE A SS C SS 8 SS 35 B SS D OP C OP 112 E OP ADDITIONAL INFORMATION SW Pump A OP 56 F SS Status Abbreviations: B OP 56 Drywe l l Cool ing fan I A OP OP Ope ra t ing C SS 0 2A OP SS Secured Status D SS O 3A OP AV Available MTR Fi re Pump SR IB SS SR Standby Readiness DD Fire Pump SR 2B SS SHTDN Shutdown 3B SS S-SP Slow Speed a Cntet Vs1 Pu rge Supp Fan A SS F-SP Fast Speed B SS ISOL isolated Cntet Val as DW Purge Exh Fan A SS NORM Normal B SS DOS Out OF Service Drywe l l Pu rge Suppl Fan A SS CL Closed B SS OVRD Override AECTS Fan A 005 B OP k 0
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= .J N = N N -
M L I W E s >= 2 A p . E 3 A D O m M c m M $ 0 s
. I 8 0 0 0 t C C O O m C N
, a m P= c - - -
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s PERRY NUCLEAR POWER PLA'NT ,. 1984 EMERGENCY PREPAREDNESS EXERCISE ! TIME: 1300 PANEL P604 PANELS P669. P670. P671. P672 Process Radiation Main Steam Line RAD. 0.0E+0 mR/hr Ala re . Cntet Vent Exh RAD- 41.0E-1.mR/hr Offgas Pre-treatment 2,3[11 R/hr Offgas Post-treatment A R,9{12 cpm PANEL P902 B C.0E+2 cpm Common Airborne Gas (coal Algag Eng Service Water A 3.0E+1 cpa- RWB Vent Exh 2.0E+1 8 3.0E+1 cpm FHB. Vent Exh 2.2E+1 OC Ca rbon Bed Vaul t A 6.0E+1 mR/hr CR Vent Exh 2.0E+1 B 1,5[t1 mR/hr PANEL P906 PANEL. 803 Common Process and Area gem Alarm Turb Bldg East 2.5E+0 mR/hr UD-MH-73 East Liq- 3.0E+1 Turb Bldg West 2.5E+0 mR/hr UD-MH-70 West Liq 3.2E+1 NCC Heal HX M [+1 PANEL P804 Radweste to ESW 3.0E+1 Airborne Radiation cas (com) Alarm Radweste to Sewage 1,4[+1 Annulus Exh A Cas DJ[+0 8 JJld+ METEOROLOGICAL CONDITIONS CntmL Ata >JJUD H Drywe l l - HR (R/hr) 6.7f13 AB Vent R,0 L+ 1 Wind Speed 3.8 mph 0C0 Vent Exh RJD2 Wind Direction 305 OGB Vent - IIR DJtM Tempe ra ture 40 *F OC Vent Pipe RJffR Delta T -1.35 *F U1 Plant Vent 6Jf +1 U1 Plant Vent - HR D a nE+0 TB/llB Vent 6,0E+1 18/Hu Vent - HR QJQQ ST Packing Exh 5 JL-1 U2 Plant Vent 6.0012 U2 Plant Vent - HR Q,0E+0 __ DWl70C/A/45/es
a AREA RADIATION MONITORS Time: 1300 t i TAG # LOCATION READING (mR/hr) v 1D21NO30 Personnel Air Lock, Cntmt (600'6") OS> 1.0E+4
- 1D21N040 CRD HCU West, Cntmt (620'6") OS :1.0E+4
- 1D21N050 RBRT Area, Cntmt (642') OS > 1.0E+4 *
'] 1D21N060 Tip Drive Area, Cntmt (600'6") OS > 1. 0E+4 *
!! ID21N070 RWCU F/D Area, Cntmt (664'7") OS ) 1.0E+4 * ; 1D21N080 Upper Pool Area, Cntmt (689'6") OS > 1. 0E+4 * -j 1D21N110 Aux Bldg East (574'10") 3.4E+2
- 1D21N120 Aux Bldg West .
(574'10") 3.4E+2
- _j 1D21N130 Turb Rm East (647'6") 1.7E+0 1D21N140 CRD HCU East, Cntmt (620'6") OS > 1. 0E+4 *
.l 1D21N160 Turb Rm West (647'6") 1.7E+0 I ID21N170 Turb Bldg (605'6") 1.9E+0 I 1D21N180 Hotwell Pump Area, TB (577'6") 1.0E+1
! 1D21N190 TB Sump Area, TBC (548'6") 2.0E+1 1D21N200 OGB (584') 1.1E+1 . 1D21N210 Cnds F1tr Pmp Area, TBC (568'6") 9.0E+0 ! 1D21N220 OG After F1tr Area, OGB (602'6") 2.0E+1 i 1D21N230 HP Fdw Htr Area, HB (600'6") 1.0E+1 1D21N240 Fdw Pump Area, HB (647'6") 7.8E-1 1D21N400 CR, CC (654'6") 1.6E-1 1D21N410 OG Hold Up Area, TB (577'6") 8.6E+0 D21N250 RWB West (574'10") 2.5E+1 D21N260 RWB East (574'10") 1.5E+1 ; D21N270 RWB (602') 5.0E+0
_[ _ D21N280 Process Sample Rm, RWB (623'6") 4.0E+0 l D21N290 RW Evap, RWB (623'6") 4.0E+0 D21N310 FPCU F/D! Area, IB (599') 3.5E+2 l D21N320 Fuel Predaration Pool, IP (620'6") 3.2E+2 D21N330 Spent Fuel Storage Pool, IB (620'6") 3.3E+2
- D21N420 FPCU Cire Pmp Area, IB (574'10") 3.0E+2 *
, ID21N340 Unit 1 DW , Portable, Cntmt (655') -
l D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1
- D21N370 SRW Drumming Area, RWB (623'6") 6.0E+0 l 1D21N090 Refueling Bridge, Cntmt (689'6") OS > 1.0E+4
- 4 D21N390 Fuel Serv Hdig Platform, IB (620'6") 3.4E+2
- t k
3 .{ - l 4
* = Alarm OS = Offscale O
Time: 1300 Message No.: 73X PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Message For: Radiation Protection Coordinator l'
. Simulated Plant Conditions.
Message: ***THIS IS A DRILL *** Order a Post-Accident Sample. FOR CONTROLLER USE ONLY j i Controller Notes: 1. Deliver this message only if a Post-Accident Sample has
-not been ordered.
- 2. The performance of a Post-Accident Sample is an exercise objective. Thus, if a Post-Accident Sample has not been ordered by now, this message is necessary.
Actions Expected: Initiate a Post-Accident Sample. 9 a DW176/C/73/ba r l l-
.. z-,-
n Time: 1315 Message No.: 74 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Message For: Control Room Simulated Plant Conditions: See attached sheets Messame: ***THIS IS A DRILL *** FOR CONTROLLER USE ONLY Controller Notes: 1. Containment pressure reaches 27 psig. AEGTS and the Unit 2 vent monitor indicate substantially increased levels of radiation. Offsite radiological monitoring teams detect increases in radiation readings.
- 2. A release path f' rom the containment to the annulus is available through a crack in the containment dome-to-wall circumferential weld. From the annulus, the radioactive gas is released through the AEGTS to the environment.
Figure 8.la shows a diagram of the release path. . Note that AEGTS Train A was out-of-service as an Initial Condition.
- 3. The operators should not turn off the AEGTS fan; if they do, the extreme annulus-to-atmosphere pressure could leak out through the Shield Building unmonitored and unfiltered. In any event, the extreme annulus-to-etmosphere pressure would force the release by the fan.
- 4. The fire dampers do not shut due to defective fusible
. links.
- 5. Radiological release information is available in Section 8.
- 6. Standby Liquid Control System starts to inject into the Reacror Vessel as Common Check Valve C41-F007 opens at this time.
Actions Expected: DW176/C/74/ba
1984 EMERGENCY PREPAREDNESS EXER'CISE TIME: 1315 PERRY NUCLEAR POWER PLA'NT CONTROL ROOM ANNUNCIATORS P680 P870 & BACK PANELS P601/P877
= .__
Section SA Section 3A. ANNULUS Section 20A Section 19A Section 19A A DIFF-PRESS ADS A MANUAL SCRAM REACTOR FDW HIGH SUPP POOL ADS B PERMISSIVE INSTANTANEOUS SWITCil ARMED PUMP A TRIP LEVEL A lilGH ANNULUS RilR B/C RUN l.0Cic INITIATED B DIFF PRESS SUPP POOL RPS LOGIC Section 2A ADS B MANUAL SCRAM- HIGH TEMP A ti1GH ADS A PERMISSIVE INSTANTANEOUS LP CONDENSER LOGIC INITIATED RRCS MAN VACUUM LOW CONT RM HVAC . CONTAINMENT RPV L-3 EMERG RCIRC A PRESS A HIGH INITIATION ADS B ADS A IP CONDENSER __; INITIATED TIME DELAY -- RPS LOW LEVEL VACUUM LOW '~- DRYWELL PERMISSIVE CONT RM HVAC PRESS A lilGH RPV L-3 LOGIC INITIATED L-3 _ HP CONDENSER EMERG RCIRC B ADS A ADS B RRCS VACUUM LOW INITIATED LOGIC FOR LPCS/ RX LEVEL LPCI A FRM RilR A PERMlbslVE TIME DELAY DW PRESS lilGH DW PRESS lilGil LOGIC INITIATED LO L-2 ADS B Section 20A RPS CONTAINMENT TEMP A tilGH PERMISSIVE - DRYWELL DW PRESS HIGil CNTM SPRAY B PRESS HIGH DRYWELL INITIATED 1[MP A Si c RPS STORAGE TANK CNTH SPRAY B MSly CLOSURE lilGH LEVEL lilGil/ LOW MAN INITIATE
- SWITCH ARMED Section 7A Section 17A Section 17A Section 21A SAFETY / RELIEF SUPP POOL CONTAINMENT VALVE LEAKAGE LEVEL B TEMP B HIGH RCIC & RHR ST LN ALARM P614 tilGH ISOL-RCIC RM DRYWELL TEMP HIGil SUPP POOL TEMP B TEMP B HIGH H IGil RCIC AREAS LD AMB TEMP HVAC PANEL CONTAINMENT REC ALARM P632 ALARM P800 PRESS B lilGH DRYWELL PRESS B HIGH IOCIC FOR LPCI B/C IM RilR DW PRESS tilGH DW1708/A/134/rmk .
b l
.- sI . '.
. . e.u.
. ..d. ~L . :.. . - , . . ~ . .r . . . - _ . .
PERRY NUCLEAR POWER PLANT .1984 EMERCENCY PREPAREDNESS EXERCISE TIME: 1315 fitQ.1 fit 19 CONTAINMENT PARAMETERS SYSTEM INFORMATION- REACTOR PARAMETERS Tempe ra tu re Pressu re Pre ssu re Flow Bressure. 155 psig i f*Fl (psigl_ _1tatus (GDm) (DsiQ) _ Level -128 in. WR Cntet 265 26.7 RWCU PMP A SS
, Neut ron Drywe l l, 260 22.0 B SS Mon 10 Range APRM HWL PMP A OP 230 Mode SW SH T D4_ '
Tempe ra ture Level f*F1 (Ft.) B OP 230 FDW Flw 0 Mlb/hr Supr P1 268 22.0 C SS O ST Flw (Total) O Mib/hr CBP A SS 150 Line A 0 4 SYSTEMS INFORMATION ' B SS 150 Line B 0 Pressure Flow
. Status (psial __13pm1_ C SS 150 Line C 0 RHR A CNT SPRAY. 250 7000 RFBP A SS 160 Line 0 0 I
B CNT SPRAY 250 7000 B SS 160 I [ C VLV OVRD 275 C SS 160 i i LPCS PMP OVRD D SS 160 I RCIC SS 0 0 RFP A SS 0 0 llPCS OP 1000 3400 B SS 0 0 ECC A 00S MFP SS 0 O IURBlNC-CLNERATOR B OP 114 RCIRC A SS O PARAMETERS ESW A DOS B SS 0 Mwatt 0 8 OP 95 MVAR 0
. MAJOR VALVE PARAMETERS C OP 95 CNDR Vac 0 in. Hg Status Closed _ Open MSIV ISOL 8 0 B SS .
BYP VLV SRV CONTROL 6 13 Posit O % SLC A OP 550 ' B OP 5} L SLC STG TK LVL 4420 gal. l e D
PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1315
'PglQ EtECTRICAL DISTRIBUTION E2Qh CST Level 410.000 cal. _1tatus Lead fMWI Status Status _(pslal Offsite Pwr Sources 2 AV Cont Rm HVAC Supp Fan A OP
-TBCC PMP A 'OP 75 Gen Breakers 2 CL B OP B OP 75 Div 1 DC OOS Cont Rm HVAC Rtn Fan A SS C SS 18 Div 2 DC OP O B SS SA Comp OP 128 Div 3 DC OP O Cont Rm Eng RCIRC Fan A OP IA Comp SR 120 B OP 2000 CIRW PHP A OP I6 4 Status B SS 0 f210 Cntet Vsl Clg fan A OP P re s su re
_ Status _fpsial C SS 0 B OP NCC Pump A SS 35 SJAE A SS C SS B SS 35 B SS D OP C OP 112 E OP ADDITIONAL INFORMATION SW Pump A OP 56 F SS Status Abbreviations: 8 OP 56 D rywe l l Coo l ing Fan I A OP OP Ope ra t i ng C SS O 2A OP SS Secured Status D SS 0 3A OP AV Available MTR F i re Pump SR IB SS SR Standby Readiness DD Fire Pump SR 2B SS SiliDN Shutdown 3B SS S-SP Slow Speed Cntet Vsl Pu rge Supp Fan A SS F-SP Fast Speed 8 SS ISOL isolated Cntet Vsl & DW Purge Exh Fan A SS NORM Normal B SS DOS Out of Service Drywell Purge Suppl Fan A SS CL Closed 8 SS OVRD Override AEGIS Fan A OOS B OP I E
- u. . . . .-..---.s..._.~_....-..,.....+..- . - . . . . . ... .,
PERRY NUCLEAR POWER PLANT '1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1315
, IRX WATER LEVEL RX PRESS RX POWER SUPR PL TEMP
-128 1H WR 155 PSIG 10 5 268 'f 60- 1100- 120- 110 45- 950- 90- 90-30- 800- 40- 70-15- 650- 0 50 0 500 -30 -20 -10 0 -30 -20 -10 0
-30 -20 -10 0 -30 -20 -10 0 Time (min) Time (min)
Time (min) Time (min) DW TEMP CONTMT TEMP CONTMT PRESS SUPR PL LEVEL 260 *f 265 *f 26.7 PSIG 22.0 [J 200- 110- 20- 19-150- 90- 15- - 100- 70- 10- 18-50 . 50- 5- -
-30 -20 -10 0 -30 -20 -10 0 0- 17 Time (min) Time (min) -5 -30 -20 -10 0
-30 -20 -10 0 Time (min) 0 Time (min) 4
PERRY NUCLEAR POWER PLA'NT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1315 faMEL P604 PANELS P669. P670. P671.-P672 Process Radiation Main Steam Line RAD 0.0E+0 mR/hr Ala rm Cntet Vent Exh RAD 41.0E-1 mR/hr Orrgas Pre-treatment 2.5E+1 R/hr Orrgas Post-treatment A 2.0E+2 cpm PANEL P902 B 2.0E+2 cpm Common Airborne Cas (comi Alors Eng Service Water A 3.0E+1 cpm RWB Vent Exh 2.0E+1 B 12D[11 cpm rHB Vent Exh 2.2E+1 OG Ca rbon Bed Vaul t A 6.0E+1 mR/hr CR Vent Exh 2.OE+1 8 5.5E+1 mR/hr PANEL P906 PANEL 803 Common Process and Area gem Ala rm Turb Bldg East gi2[ig mR/hr UD-MH-73 East Liq 3.0E+1 Turb Bldg West 2.5E+0 mR/hr UD-MH-70 West Liq 3.2E+1 NCC Heat HX 3.5Et1 PANEL P804 Radwaste to ESW 3.0E+1 Ai rborne Radiation Cas (coal Alarm Radweste to Sewage 3.6E+1 Annulus Exh A Gas OtD[iG B >110 L+ H Cntet Atm >1,0[+ H METEOROLOGICAL CONDITIONS Drywell - HR (R/hr) 6,7[1] AB Vent 2,0(11 Wind Speed 4.0 mph 310
- OGB Vent Exh 2.0L12 Wind Di rection OCB Vent IIR Oi !![+Q Tempera tu re 40 'F OG Vent Pipe 210[12 Delta T -1.40 'F U1 Plant Vent 6,DE tj UI Plant Vent - HR 0,0t+0 IB/HB Vent 6,001]
TB/HB Vent - HR 0,0[10 Si Packing Exh >20 L- 1 U2 Plant Vent b liOLf 6 H U2 Flant Vent - HR 1,0E+4 DW170C/A/46/es O
Time: AREA RADIATION MONITORS 1315 1 r TAG # LOCATION READING (mR/hr) 1D21NO30 Personnel Air Lock, Cntet (600'6") OS> 1.0E+4
- 1D21N040 CRD HCU West, Cntat (620'6") OS > 1. 0E+4 *
'i 1D21N050 RBRT Area, Cntet (642') OS>1.0E+4
- 1D21N060 Tip Drive Area, Cntat (600'6") OS > 1. 0E+4
- ID21N070 RWCU F/D Area, Cntet (664'7") OS) 1.0E+4
- I 1D21N080 Upper Pool Area, Cntat (689'6") OS > 1. 0E+4
- 1D21N110 Aux Bldg East (574'10") -
3.4E+2' *
, 1D21N120 Aux Blda West (574'10") 3.4E+2 * .; 1D21N130 Turb Rm East (647'6") 1.7E+0 i 1D21N140 CRD HCU East, Cntet (620'6") OS> 1.0E+4
- ID21N160 Turb Rm West (647'6") 1.7E+0 1D21N170 Turb Blda (605'6") 1.8E+0 a 1D21N180 Hotwell Pump Area TB (577'6") 1.0E+1 i 1D21N190 TB Sump Area. TBC (548'6") 2.0E+1 1D21N200 OGB (584') 1.1E+1 1 1D21N210 Cnds F1tr Pmp Area, TBC (568'6") 9.0E+0 1D21N220 OG After F1tr Area, OGB (602'6") 2.0E+1 i 1D21N230 HP Fdw Htr Area. HB (600'6") 1.0E+1 j 1D21N240 Fdw Pump Area, HB (647'6") 7.8E-1
; 1D21N400 CR, CC (654'6") 1.5E+1
- l 1D21N410 OG Hold Up Area, TB (577'6") 8.6E+0 j D21N250 RWB West (574'10") 2.5E+1
'I D21N260 RWB East (574'10") 1.5E+1
} ._ D21N270 RWB (602') 5.0E+0 D21N280 Process Sample Rm, RWB (623'6") 4.0E+0 ! D21N290 RW Evap, RWB (623'6") 4.0E+0 I (599') 3.5E+2
- D21N310 FPCU F/D Area. IB D21N320 Fuel Preparation Pool, IB (620'6") 3.2E+2
- D21N330 Spent Fuel Storage Pool, IB (620'6") 3.0E+2 *
- ) -
D21N420 FPCU Cire Pmp Area, IB (574'10") 2.9E+2
- i 1D21N340 Unit 1 DW, Portable, Cntmt (655') -
D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1 D21N370 SRW Drumming Area, RWB (623'6") 6.0E+0 1D21N090 Refueling Bridge, Cntmt (689'6") OS) 1. 0E+4
- D21N390 Fuel Serv Mdig Platform, IB (620'6")
3.3E+2 * ,f. .i 4 4 4
. * = Alarm OS = Offscale
Time: 1330 Message No.: 75 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE
, MESSAGE FORM - Message For: Control Room /TSC/ EOF Simulated Plant Conditions: See attached sheets Message; ***THIS IS A DRILL ***
4
+ - . .
I 1 I, k i FOR CONTROLLER USE ONLY l' Controller Notes: 1. Containment pressure peaks at 28 psig at 1325.
. 2. RHR Bypass Valve E12-F048B is. closed; Containment Spray Loop B is in full operation.
Actions Expected: >t t DW176/C/75/ba y
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PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1330 CONTROL ROOM ANNUNCIATORS P601/P877 P680 P870 & BACK PANELS Section 20A Section 19A Section 19A section SA Section 3A ANNULUS A DIFF PRESS SUPP POOL ADS B ADS A MANUAL SCRAM REACTOR FDW- HIGH LEVEL A tilGH PERMISSIVE INSTANTANEOUS SWITCH ARMED PUMP A TRIP RHR B/C RUN LOGIC INITIATED ANNULUS SUPP POOL RPS LOGIC Section 2A B DIFF PRESS TEMP A HIGH ADS A ADS B MANUAL SCRAM . HICH PERMISSIVE' INSTANTANEOUS LP CONDENSER CONTAINMENT RPV L-3 LOGIC INiilATED RRCS MAN VACCUM LOW . CONT RM llVAC PRESS A HIGH INITIATION EMERG RCIRC A ADS B ADS A IP CONDENSER INITIATED P904 DRYWELL PERMISSIVE TIME DELAY RPS LOW LEVEL VACUUM LOW PRESS A HIGH RPV L-3 LOGIC INITIATED L-3 CONT RM HVAC HP CONDENSER EMERG RCIRC B LOGIC FOR LPCS/ ADS A ADS B RRCS VACUUM LOW INITIATED P904 LPCI A FRM RilR A PERMISSIVE TIME DELAY RX LEVEL DW PRESS HIGH DW PRESS lilGH LOGIC INITIATED LO L-2 CONTAINMENT ADS B Section 20A RPS TEMP A HIGH PERMISSIVE DRYWELL DW PRESS HIGil CNTH SPRAY B PRESS HIGH DRYWELL INITIALED TEMP A SLC RPS 111 011 STORAGE TANK CNTH SPRAY B MSIV CLOSURE LEVEL HIGil/ LOW MAN INITIATE SWITCil ARMED Section 7A Section 17A Section 17A Section 21A SAFETY / RELIEF SUPP POOL CONTAINMENT VALVE LEAKAGE LEVEL B TEMP B lilGil RCIC & RilR ST LN ALARM P614 HIGH ISOL-RCIC RM DRYWELL TEMP lilGH Section 6A SUPP POOL TEMP B TEMP BlilGH HIGH RCIC AREAS APRM LD AMit TEMP DOWNSCALE CONTAINHENT REC ALARM P632 PRESS B HIGli DRYWELL PRESS B lilGil LOGIC FOR LPCI H/C FM RHR DW PHESS lilGH DW170B/A/137/rmk 9
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. q PERRY NUCLEAR POWER PLANT 1984'EMERCENCY PREPAREDNESS EXERCISE TIME: 1330
~P601 P660 CONTAINMENT PARAMETERS . SYSTEM INFORMATION REACTOR PARAMETEgg Tempe ra ture Pressure Pressure Flow Pre ssu re 90 psig
(*F1 fpsiq1_ Status (psig) (comi Level -122 in. WR Cntet 269 27.5 RWCU PMP A SS i Neutron Drywell 265 23.6 B SS Mon 2 Range APRM HWL PMP A OP 230 . Mode SW SHTDN_ Tempe ra tu re Level
, f*F1 fFt.) B OP 230 FDW Flw 0 Mlb/hr Supr PI 269 21.9 C SS O ST Flw (Total) O Mib/hr -j CBP A SS 150 Line A 0 SYSTEMS INFORMATION B SS 150 Line B 0
- Pressure Flow 3
_ Status _ (psial __1gpo l . C SS 150 Line C 0 RHR A CJ T SPRAV 250 7000 RFBP A SS 160 Line D 0 B CNT SPRAY 250 7000 B SS 160 C YLV OVRD 275 0 C SS 160 LPCS PHP OVRD D SS 160 RCIC SS 0 0 RFP A SS O O HPCS OP 1050 700 B SS 0 0 ECC A 00S MFP SS 0 0 IMRBjNE-GENERATOS B OP 114 RCIRC A SS O EARAMETERS ESW A 00S B SS 0 Mwatt 0 B OP 95 MVAR 0 - MAJOR VALVE PARAMETERS C OP__ 95 CNDR Vac 0 in. Hg Status Closed Open CR0 A SS Thrt Pr 0 psig MSIV ISOL 8 0 B SS BYP VLV [ SRV _ CONTROL 6 13 Posit 0 % l SLC A OP 420 l . B OP 422 SLC SIC TK LVL 3200 gal. 1. l l 4
u i. ' . . w , c w.m- ; . . ~ .~ ~ .s .. . - , . . . . , - . - . - -_ PERRY NUCLEAR POWER PLANI 1984 EMERCENCY PREPAREDNESS EXERCISE TIME: 1330 P870 ELECTRICAL DISTRIBUTION P904 CST Level 410.000 cal. Status Load fMW) Status
. Sta11tL, _{g1Lql_ 0FFsite Pwr Sources 2 AV Cont Rm HVAC Supp Fan A _ OP TBCC PMP A OP 75 Cen Breakers 2 CL B OP B OP 75 Div 1 DC OOS Cont Rm HVAC Rtn Fan A SS C SS 18 Div 2 DC OP O B SS SA Comp OP 128 Div 3 DC OP O Cont Rm Eng RCIRC Fan A OP 1A Comp SR 120 8 OP P800 CIRW PMP A OP 46 . Status P970 B SS 0 Cntet Vsl Cig Fan A OP Pressure Status (psial C SS 0 B OP NCC Pump A SS 35 SJAE A SS C SS B SS 35 8 'SS D OP.
C OP 112 E OP ADDITIONAL INFORMATION. SW Pump A OP 56 F SS Status Abbreviations: B OP 56 D rywe l l Cool ing Fan .1 A OP OP Ope ra t i ng C SS O 2A- OP SS Secured Status D SS O
, 3A OP AV Available MTR Fi re Pump SR 18 SS SR Standby Readiness DD Fire Pump SR 28 SS SHTDN Shutdown 3B SS S-SP Slow Speed Cntet Val Purge Supp Fan A SS F-SP Fast Speed B SS ISOL 1solated Catet '*?I & OW Purge Fxh Fan A SS NORM Norma 1 , B SS 005 Out of Service Drywell Purge Suppi Fan A SS CL Closed B SS OVRD Override ALGIS Fan A 00S B OP O
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PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1330 RX WATER LEVEL RX PRESS RX POWER SUPR PL TEMP
-122 11! M 90 PSIG 2 1 269 *[
60- 1100- 120- 110 45- 950- 90- 90-30- 800- 40- 70-15- 650- 0 50 O $00 -30 -20 -10 0 -30 -20 -10 0
-30 -20 -10 0 -30 10 0 Time (min) Time (min) 5 Time (min) Time (min)
DW TEMP CONTMT TEMP CON 1MT PRESS SUPR PL LEVEL 265 *f 269 'f 27.5 PSIG 21.9 LI 200- 110- 20- 19-150- 90- 15- - 100- 70- 10- 18-50 50- 5- -
-30 -20 -10 0 -30 -20 -10 0 0- 17 Time (min)}}