ML17309A531
| ML17309A531 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 11/17/1993 |
| From: | Beldue R, Polfleit P, Watts R ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| References | |
| NUDOCS 9312020559 | |
| Download: ML17309A531 (548) | |
Text
THE ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION EMERGENCY PREPAREDNESS EXERCISE h/IANUAL 1993 PLUME EXPOSURE EMERGENCY PREPAREDNESS EXERCISE November 171993 Prepared By:
e,.P f t Wesl H. Backus Reviewed By:
Richard J. Watts Approved By:
Ric d . Beldue (Emergency Planning Milestone Committee)
CONTROLLED COPY NO.
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ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION 1993 PLUME EXPOSURE EMERGENCY PREPAREDNESS EXERCISE FOREWORD This Exercise package has been developed to provide the basis for the conduct of a simulated radiological accident at the Ginna Station located in Ontario, New York.
Through this Exercise, the capabilities and effectiveness of the Emergency Response Plans for the Rochester Gas and Electric Corporation, the State of New York, and Monroe and Wayne Counties will be evaluated. This package is to be utilized by the Exercise Controllers and observers to initiate, control and evaluate the activities of the participants in the Exercise.
The Rochester Gas and Electric Corporation approves this document as the standard for'conduct in performance of the November, 1993 Emergency Preparedness Exercise.
THE ROCHESTER GAS AND ELECTRIC CORPORATION, GINNA STATION 1993 PLUME EXPOSURE EMERGENCY PREPAREDNESS EXERCISE INTRODUCTION The Nuclear Emergency Response Plan (NERP) describes the emergency response capabilities for a nuclear emergency at the Ginna Station, including support from Federal, State, and local government agencies and private organizations. The Nuclear Emergency Response Plan provides for continuous emergency preparedness, including an annual Exercise.
The purpose of the Plume Exposure Emergency Preparedness Exercise is to activate and evaluate major portions of the emergency response capabilities and other aspects of the Emergency Plan and associated Emergency Plan Implementing Procedures, in accordance with NUREG-0654, and with Nuclear Regulatory Commission (NRC)
Regulation 10CFR50.47(b) and Appendix E. This Exercise will be with the participation of the State of New York, and the Counties of Wayne and Monroe in order to assess State and Local Government Agency Emergency Response. The conduct and evaluation of the Exercise provide additional training for the Plume Exposure Pathway emergency response organization personnel and a means to further enhance Rochester Gas and Electric Corporation's emergency response capability.
This Exercise Manual has been developed to provide the basis for the conduct of a simulated radiological accident at the Ginna Station facility located in Ontario, New York. This manual is to be utilized by the Exercise Controllers to initiate, control, and evaluate the activities of the participants in the Exercise. Exercise" la ers" will no have rior knowled e of the na ure of the simula ed incident or an r s thereof such as radiolo ical lume release information includin times content size and weather attern used.
This Exercise Manual is the control mechanism for the conduct of the Exercise and consists of two parts, Part I provides a general description and overview of the emergency Exercise. Part II contains the scenario and time schedule of simulated plant conditions. The Exercise Manual is subject to a limited, controlled distribution.
1993 PLUME EXPOSURE EMERGENCY PREPAREDNESS EXERCISE SCENARIO DEVELOPMENT COMMITTEE "
Thomas Alexander Wes Backus Richard Beldue Richard Biedenbach Dan Hudnut James-Knorr Frank Orienter Peter Polfleit James Regan Richard Watts James Zulawski
" As authorized by the Emergency Planning Milestone Committee
GINNA STATION 1993 PLUME EXPOSURE EMERGENCY PREPAREDNESS EXERCISE TABLE OF CONTENTS FOREWORD INTRODUCTION SCENARIO DEVELOPMENT COMMITTEE TABLE OF CONTENTS LIST OF FIGURES 1.0 SCOPE AND OBJECTIVES 1.1 Scope 1.2 Onsite Objectives 1.3 Summary of Proposed Activities 1.4 Offsite Proposed Activities 2.0 EXERCISE INFORMATION 2.1 Exercise Participants 2.2 Exercise Organization 2.3 Emergency Response Facilities 2.4 Exercise Conduct 2.5 Precautions and Limitations 2.6 Evaluation and Critique 3.0 TRAVEL INFORIVIATION 3.1 Directions to Ginna Station 3.2 Directions to EOF, ESC and JENC 3.3 Accommodations
4.0 REFERENCES
ABBREVIATIONS-ACRONYMS 4.1 References 4.2 Abbreviations-Acronyms 5.0 CONTROLLER AND EVALUATOR INFORIVIATION 5.1 Controller Instructions 5.2 Evaluation Instructions 5.3 Personnel Assignments 5.4 Evaluation Packages 5.5 Public Information, Rumor Control 5 Spouse Phone Questions 6.0 SCHEDULE OF EVENTS
GIN NA STATION 1993 PLUME EXPOSURE EIVIERGENCY PREPAREDNESS EXERCISE TABLE OF CONTENTS (Cont'd) 7.0 EXERCISE SCENARIO 7.1 Initial Conditions 7.2 Onsite Sequence of Events 7.3 Simulator Set Up Instructions 7.4 Simulator Use Guidelines 8.0 IVIESSAGE FORIVIS AND PLANT DATA SHEETS 9.0 ONSITE RADIOLOGICALAND CHEIVIISTRY DATA 9.1 Radiological Summary 9.2 ln-Plant Radiological Data 9.3 . Post-Accident Sampling Results 10.0 METEOROLOGICAL AND OFFSITE RADIOLOGICAL DATA 10.1 Meteorological Data 10.2 Field Data and Maps 10.3 Field Air Isotopic Data
GINNA STATION 1993 PLUME EXPOSURE EMERGENCY PREPAREDNESS EXERCISE TABLE OF CONTENTS (Cont'd)
LIST OF FIGURES SECTION 3.0 Figure 3.1 Directions to Ginna Station Figure 3.2 Map of Rochester and Vicinity Figure 3.3 Map of Rochester Central Business District Figure 3.4 Directions to State Emergency Operations Center, Albany Figure 3.5 Map of State Office Building Campus, Albany SECTION 9.0 Figure 9.1 Assumed Source Term Figure 9 2
~ Release Vent Concentrations Vs Time Figure 9 3
~ Letdown Monitor Reading Vs Time Figure 9.4 Containment Radiation Vs Time Figure 9.3 RCS Concentrations Vs Time SECTION 10.0 Figure 10.1 Direction of Plume Figure 10.2 Plume Map (0-1 Mile)
Figure 10.3 Large Plume Map (0-10 Mile)
GINNA STATION 1993 PLUME EXPOSURE EMERGENCY PREPAREDNESS EXERCISE TABLE OF CONTENTS (Cont'd)
LIST OF TABLES SECTION 1.0 Table 1 ~ 1 Proposed Onsite Activities SECTION 5.0 Tabl'e 5.1 RG&E Onsite Controller Organization SECTION 7.0 Table 7.1 Simulator Set-up Data for Exercise Scenario (LATER)
Table 7.2 Simulator Set-up Data (Rad Monitor Readings) (LATER)
Table 7.3 Simulator Use Guidelines (LATER)
SECTION 9.0 Table 9 ~ 1 Assumed Release Quantities Table 9.2 Equilibrium Reactor Coolant Activity Table 9.3 Post-Accident Reactor Coolant Samples Table 9.4 Post-Accident Containment Atmosphere Samples Table 9.5 Post-Accident Containment Sump Samples Table 9.6 Continuous Air Monitor Readings (Auxiliary Bldg & TSC)
Table 9.7 Air Sample Results in TSC and Control Room SECTION 10.0 Table 10.1 Forecast Information Table 10.2 Plume Arrival/Departure Times Table 10.3 Radiological Survey/Sampling Data (In Plume)
Table 10.4 Post-Plume Ground Survey Data (cpm)
Table 10.5 Post-Plume Micro-R/hr Data Table 10.6 Air Sample Isotopic Analysis Data 1-8
SECTION 1.0 SCOPE AND ORIECTIVES
SCOPE AND ONSITE OBJECTIVES - PLUIVIE EXPOSURE PATHWAY
~Sco e The 1993 Emergency Preparedness Plume Exposure Pathway Exercise will be conducted on a full-participation basis and will simulate accident events culminating in a radiological accident resulting in the activation of onsite and offsite facilities. The Exercise will involve events that test the effectiveness of the Ginna Station Emergency Preparedness Program and the integrated capabilities of certain elements of the State of New York, Wayne County and Monroe County emergency organizations. The Exercise will include the mobilization of state and local resources to adequately verify their capability to respond to an accident at the Ginna Nuclear Power Plant.
Onsite Ob ectives for the 1993 Ginna Evaluated Plume Ex osure Pathwa Exercise The major objective of the Exercise is to demonstrate the response capabilities of the Rochester Gas and Electric Corporation Emergency Organization. Within this overall objective, numerous individual objectives are specified as follows:
Demonstrate the ability to mobilize, staff and activate Emergency Response Facilities promptly.
Demonstrate the ability to fully staff facilities and to maintain staffing on an around-the-clock basis through the use of relief shift rosters tlimited shift changes may occur to allow for operational restrictions).
Demonstrate the ability to make decisions and to coordinate emergency activities.
Demonstrate the adequacy of facilities and displays and the utilization of procedures to support emergency operations.
Demonstrate the ability to communicate with all appropriate locations, organizations, and field personnel.
Demonstrate the ability to mobilize and deploy Radiation Survey Teams.
1-1
Demonstrate the appropriate equipment and procedures for the determination of ambient radiation levels.
Demonstrate the proper use of appropriate equipment and procedures for measurement of airborne radioiodine concentrations as low as 1.0 E-7 uCi/cc in the presence of noble gases.
Demonstrate the ability to project dosage to the public via plume exposure, based on Plant and field data, and to determine appropriate protective measures, based on plant conditions, Protective Action Guidelines, available shelter, evacuation time estimates, expected release duration, and other appropriate factors, Demonstrate the ability to notify offsite officials and agencies within 15 minutes of declaration of an emergency.
Demonstrate the ability to periodically update offsite officials and agencies of the status of the emergency based on data available at Ginna Station.
Demonstrate the ability to notify emergency support pools as appropriate (Le., INPO, ANI, etc.).
Demonstrate the ability to notify onsite personnel using plant alarms and public address systems.
Demonstrate the organization's ability to assess plant parameters and symptoms indicative of degrading plant conditions, and relate such symptoms to prescribed Emergency Action Levels.
Demonstrate the organization's ability to properly classify emergency conditions.
Demonstrate the organizational ability and resources necessary to manage an accountability of personnel within the restricted area.
Demonstrate the organizational ability and resources necessary to control access to the site.
Demonstrate the ability to continuously monitor and control emergency workers'xposure.
1-2
Demonstrate the adequacy of facilities and displays to support the Joint Emergency News Center operations.
Demonstrate the ability to brief the media in a clear, accurate, and timely manner.
Demonstrate the ability to provide advanced coordination of information released to the public.
Demonstrate the ability to establish and operate rumor control in a coordinated fashion.
Demonstrate the adequacy of in-plant post-accident sampling techniques and analysis.
Demonstrate the ability to develop a preliminary action plan to support plant recovery.
Demonstrate the ability to respond to information requests from simulated NRC staff during the course of the Exercise .
Demonstrate the ability to effect a timely shift change of key emergency response staff positions during the Exercise.
Demonstrate the ability to conduct a post-exercise critique which adequately characterizes licensee performance based upon controller and observer assessments.
Summar of Pro osed Activities Table 1.1 provides a list of proposed RGSE activities.
1-3
TABLE 1.1 1993 GINNA STATION EMERGENCy PREPAREDNESS EXERCISE PLUIVIE EXPOSURE PROPOSED ONSITE ACTIVITIES RG&E Notification of Agencies Actual Call Up of Personnel Actual Activate Organization Actual Maintain Security Actual Plant Evacuation & Accountability Actual Conduct Dose Assessment Actual Protective Action Recommendations Actual Operate Joint Emergency News Center Actual Dispatch Field Survey Teams Actual-3" Obtain PASS Sample Actual Shift Change - Key Personnel Actual "
Field teams will be deployed and will demonstrate appropriate field monitoring techniques and communications with respective emergency response facilities. A minimum of 1 onsite and 2 offsite teams will be deployed.
Shift change will include principal positions in the TSC, OSC, EOF and JENC.
P 1-4
SIMULATIONS o Respiratory protection and protective clothing will be simulated by onsite/offsite survey teams. In-Plant teams will don respiratory protection and protective clothing prescribed by Health Physics and Chemistry personnel according to postulated scenario plant conditions.
o In general, Exercise participants should follow applicable plant procedures as closely as possible, and will be stopped by Controllers before actual equipment is manipulated (except PASS). Simulated repairs and other corrective actions should be described to Controller-
/Evaluators as fully as possible.
o Informational requests from controllers simulating NRC staff .
1-5
SUMMARY
OF PROPOSED OFFSITE OBJECTIVES AND ACTIVITIES P p d ffi bj i d i"ii d it di ~A A.
1-6
A TTACHMENT A OFFSITE EXERCISE OBJECTIVES 1-7
PROPOSED OB JECTIVES FOR GINNA Wayne County Emergency Operations Center (WCEOC)
PEA OBJECTIVE ¹ ARCAs BIL ATI F R E Y PER
- 1. Demonstrate the capability to alert and fully mobilize personnel for None both emergency facilities and field operations. Demonstrate the capability to activate and staff emergency facilities for emergency operations.
S- I TD L W R VIR
- 2. Demonstrate the adequacy of facilities, equipment, displays, and None other materials to support emergency operations.
IR T NA D
- 3. Demonstrate the capability to direct and control emergency None operations.
- 4. Demonstrate the capability to communicate with all appropriate None emergency personnel at facilities and in the field.
W R R
- 5. Demonstrate the capability to continuously monitor and control None radiation exposure to emergency workers.
- 7. Demonstrate the capability to develop dose projections and protective WC-l action recommendations regarding evacuation and sheltering.
E PR TIV D I N
- 9. Demonstrate the capability to make timely and appropriate protective None action decisions (PAD).
PROPOSED OB JECTIVES FOR GINNA Wayne County Emergency Operations Center (WCEOC)
PEA OBJECTIVE ¹ ARCAs E ND TIFI
- 10. Demonstrate the capability to promptly alert and notify the public within None the 10-mile plume pathway emergency planning zone (EPZ) and disseminate instructional messages to the public on the basis of decisions by appropriate State or local officials.
LI INSTRU TIO S ND R EN F RMAT
- 11. Demonstrate the capability to coordinate the formulation and None dissemination of accurate information and instructions to the public.
T F A I L AND
- 14. Demonstrate the capability and resources to implement potassium iodide None (KI) protective actions for emergency workers, institutionalized individuals, and, ifthe State plan specifies, the general public.
P NTATI F PROT p p p
- 15. Demonstrate the capability and resources necessary to implement None appropriate protective actions for special populations.
IMP PR T V H
- 16. Demonstrate the capability and resources necessary to implement None protective actions for school children within the plume pathway emergency planning zone (EPZ).
T QT D
- 17. Demonstrate the organizational capability and resources necessary to None control evacuation traffic flow and to control access to evacuated and sheltered areas.
PROPOSED OBJECTIVES FOR GINNA Wayne County Field Activities PVCFA)
PEA OBJECTIVE ¹ ARCAs OBILI ATI N FEMER N P R L
- 1. Demonstrate the capability to alert and fully mobilize personnel for None both emergency facilities and field operations, Demonstrate the capability to activate and staff emergency facilities for emergency operations.
T I Y W E V NME4T
- 2. Demonstrate the adequacy of facilities, equipment, displays, and *WC-16 other materials to support emergency operations.
- 4. Demonstrate the capability to communicate with all appropriate None emergency personnel at facilities and in the field.
E R E YW
- 5. Demonstrate the capability to continuously monitor and control None radiation exposure to emergency workers.
DR Dl MO TI R
- 6. Demonstrate the appropriate use of equipment and procedures for determining field radiation measurements.
ED J N
- 7. Demonstrate the capability to develop dose projections and protective None action recommendations regarding evacuation and sheltering.
ELD RADI I AL IN - I RADI N P RTI A VITY '
- 8. Demonstrate the appropriate use of equipment and procedures for the 4one
~
measurement of airborne radioiodine concentrations as low as 10 '0.0000001) microcuries per cubic centimeter in the presence of noble gases and obtain samples of particulate activity in the airborne plume.
- Field verification is not required.
PROPOSED OBJECTIVES FOR GINNA Wayne County Field Activities (WCFA)
PEA OBJECTIVE ¹ ARCAs MPLEMENTATIONOF PR T VE TIONS - SE FK OR EM RGENCY WO R IONALIZEDI IVID S DTHE E 'ERA P I
- 14. Demonstrate the capability and resources to implement potassium iodide None (KI) protective actions for emergency workers, institutionalized individuals, and, ifthe State plan specified, the general public.
LEMENTATI N F PR T V PE IAL POP LATI N
- 15. Demonstrate the capability and resources necessary to implement None appropriate protective actions for special populations.
NTATI N F V L
- 16. Demonstrate the organizational capability and resources necessary to None implement protective actions for school children within the plume pathway emergency planning zone (EPZ).
- 17. Demonstrate the organizational capability and resources necessary to None control evacuation traffic flow and to control access to evacuated and sheltered areas.
E PTI N ENTE RE I TRATION
- 18. Demonstrate the adequacy of procedures, facilities, equipment and None personnel for the radiological monitoring, decontamination and registration of evacuees.
A E A
- 19. Demonstrate the adequacy of facilities, equipment, supplies, personnel <<KC-5 and procedures for congregate care of evacuees. 'AC-8
- Field verification is not required.
- PROPOSED OBJECTIVES FOR GINNA Wayne County Field Activities (WCFA)
PEA OBJECTIVE ¹ ARCAs MER W R R P T ANDVEHI L Nl R ND D TA ATI N
- 22. Demonstrate the adequacy of procedures for the monitoring and WC-6 decontamination of emergency workers, equipment and vehicles. WC-7 PROPOSED OBJECTIVES FOR GINNA Monroe County Emergency Operations Center (MCEOC)
PEA OB JECTIVE 0 ARCAs I TION OF R
- 1. Demonstrate the capability to alert and fully mobilize personnel for None both emergency facilities and field operations.'emonstrate the capability to activate and staff emergency facilities for emergency operations.
IT S- IP E TD Y NDW R VRON
- 2. Demonstrate the adequacy of facilities, equipment, displays, and None other materials to support emergency operations.
MAND 0
- 3. Demonstrate the capability to direct and control emergency None operations.
I ATI
- 4. Demonstrate the capability to communicate with all appropriate None emergency personnel at facilities and in the field.
Y W RKER XP
- 5. Demonstrate the capability to continuously monitor and control None radiation exposure to emergency workers.
D SE PR JE
- 7. Demonstrate the capability to develop dose projections and protective None action recommendations regarding eva'cuation and sheltering.
PR ECTIVEA I ND I N KI
- 9. Demonstrate the capability to make timely and appropriate protective None action decisions (PAD).
PROPOSED OBJECTIVES FOR GINNA Monroe County Emergency Operations Center (MCEOC)
PEA OBJECTIVE 0 ARCAs LERT AND NOTIFI TI
- 10. Demonstrate the capability to promptly alert and notify the public within None the 10-mile plume pathway emergency planning zone (EPZ) and disseminate instructional messages to the public on the basis of decisions by appropriate State or local officials.
UBLIC INSTR Tl N ND EMER N Y INF
- 11. Demonstrate the capability to coordinate the formulation and None dissemination of accurate information and instructions to the public.
T 8 FP OR EMER E W R IVID A ND T A
- 14. Demonstrate the capability and resources to implement potassium iodide None (KI) protective actions for emergency workers, institutionalized individuals, and, ifthe State plan specifies, the general public.
MPLEMENTAT PE IALP P
- 15. Demonstrate the capability and resources necessary to implement None appropriate protective actions for special populations.
PLE M T I P T TI
- 16. Demonstrate the capability and resources necessary to implement None protective actions for school children within the plume pathway emergency planning zone (EPZ).
FFI AND A TR
- 17. Demonstrate the organizational capability and resources necessary to None control evacuation traffic flow and to control access to evacuated and sheltered areas.
PROPOSED OBJECTIVES FOR GINNA Monroe County Field Activities (MCFA)
PEA OBJECTIVE ¹ ARCAs OB IZATI N F EMER PER EL
- 1. Demonstrate the capability to alert and fully mobilize personnel for None both emergency facilities and field operations. Demonstrate the capability to activate and staff emergency facilities for emergency operations.
ITIES - E IPM NT DISPLAYS AND W RK ENVIR NMENT
- 2. Demonstrate the adequacy of facilities, equipment, displays, and None other materials to support emergency operations.
Nl T
- 4. Demonstrate the capability to communicate with all appropriate None emergency personnel at facilities and in the field.
RE NT
- 5. Demonstrate the capability to continuously monitor and control MC-3 radiation exposure to emergency workers. MC-4 B
- 6. Demonstrate the appropriate use of equipment and procedures for None determining field radiation measurements.
E PROJ I
- 7. Demonstrate the capability to develop dose projections and protective None action recommendations regarding evacuation and sheltering.
RIILDR M 'T - I D P RT IV Y RIN
- 8. Demonstrate the appropriate use of equipment and procedures for the Xone measurement of airborne radioiodine concentrations as low as 30 7 (0.0000001) microcuries per cubic centimeter in the presence of noble gases and obtain samples of particulate activity in the airborne plume.
PROPOSED OBJECTIVES FOR GINNA Monroe County Field Activities (MCFA)
PEA OBJECTIVE ¹ ARCAs PLEMENTATI F P OTE TIVE TI N - E ORE ER EN YW RK R TIT D E ENERAI I
- 14. Demonstrate the capability and resources to implement potassium iodide None (KI) protective actions for emergency workers, institutionalized individuals, and, ifthe State plan specified, the general public.
MPLEMENTATI N F PR IV A I PE IAL POP LA 10
- 15. Demonstrate the capability and resources necessary to implement MC-1 appropriate protective actions for special populations.
L
- 16. Demonstrate the organizational capability and resources necessary to None implement protective actions for school children within the plume pathway emergency planning zone (EPZ).
I ND
- 17. Demonstrate the organizational capability and resources necessary to MC-2 control evacuation traffic flow and to control access to evacuated and sheltered areas.
E PTION ENTER- D ONT
- 18. Demonstrate the adequacy of procedures, facilities, equipment and None.
personnel for the radiological monitoring, decontamination and registration of evacuees.
R
- 19. Demonstrate the adequacy of facilities, equipment, supplies,.personnel None and procedu'res for congregate care of evacuees.
- 20. Demonstrate the adequacy of vehicles, equipment, procedures, and None personnel for transporting contaminated, injured, or exposed individuals.
4
PROPOSED OBJECTIVES FOR GINNA Monroe County Field Activities (MCFA)
PEA OBJECTIVE ¹ ARCAs DI AL ERV S-F
- 21. Demonstrate the adequacy of the equipment, procedures, supplies, and None personnel of medical facilities responsible for treatment of contaminated, injured, or exposed individuals.
MER E YW RKERS E P ENT ND I R 6 AND E NT M T
- 22. Demonstrate the adequacy of procedures for the monitoring and None decontamination of emergency workers, equipment and vehicles.
PROPOSED OB JECTIVES FOR GINNA Lake District Emergency Operations Center (LDEOC)
PEA OBJECTIVE ¹ ARCAs MOBILIZATIONOF EMER EN Y PERSO EL 1 ~ Demonstrate the capability to alert and fully mobilize personnel for None both emergency facilities and field operations. Demonstrate the capability to activate and staff emergency facilities for emergency operations.
FACILITIES - E UIPMENT DISPL Y AND W RK ENVIR N NT
- 2. Demonstrate the adequacy of facilities, equipment, displays, and None other materials to support emergency operations.
IR T ND NTR L
- 3. Demonstrate the capability to direct and control emergency None operations.
ATION
- 4. Demonstrate the capability to communicate with all appropriate None emergency personnel at facilities and in the field.
PROPOSED OBJECTIVES FOR GINNA New York State Emergency Operations Center (SEOC)
PEA OB JECTIVE 0 ARCAs BZTI NF
- 1. Demonstrate the capability to alert and fully mobilize personnel for None both emergency facilities and field operations. Demonstrate the capability to activate and staff emergency facilities for emergency operations.
r IE - P NT D P VI
- 2. Demonstrate the adequacy of facilities, equipment, displays, and None other materials to support emergency operations.
RE TI AND T
- 3. Demonstrate the capability to direct and control emergency None operations.
- 4. Demonstrate the capability to communicate with all appropriate None emergency personnel at facilities and in the field.
- 5. Demonstrate the capability to continuously monitor and control None radiation exposure to.emergency workers.
P ED P T a
- 7. Demonstrate the capability to develop dose projections and protective None action recommendations regarding evacuation and sheltering.
T V T I
- 9. Demonstrate the capability to make. timely and appropriate protective None action decisions (PAD).
PROPOSED OBJECTIVES FOR GINNA New York State Emergency Operations Center (SEOC)
PEA OBJECTIVE 0 ARCAs LERTANDNOTIFI ATI N a
- 10. Demonstrate the capability to promptly alert and notify the public within None the 10-mile plume pathway emergency planning zone (EPZ) and disseminate instructional messages to the public on the basis of decisions by appropriate State or local officials.
P BLI INSTRU TIONS ANDEM R EN Y F RMATI N a
- 11. Demonstrate the capability to coordinate the formulation and None dissemination of accurate information and instructions to the public.
MPLEMENTATI N F PROTECTIVE ACTIO - S FK F R EMERGEN Y WORKER INSTIT TI NAL DIVID AL AND THE GENERAL P B I
- 14. Demonstrate the capability and resources to implement potassium iodide None (KI) protective actions for emergency workers, institutionalized individuals.
and, ifthe State plan specifies, the general public.
(a) This objective will be evaluated for SEOC should the Governor declare a State of Emergency.
PROPOSED OBJECTIVES FOR GINNA Emergency Operations Facility (EOF)
PEA OBJECTIVE 0 ARCAs BILIZATI N F EMER EN R L
- 1. Demonstrate the capability to alert and fully mobilize personnel fo'r None both emergency facilities and field operations. Demonstrate the capability to activate and staff emergency facilities for emergency operations.
FACIL S-E IPMENT Dl P AY DW RKENVIR 'MENT
- 2. Demonstrate the adequacy of facilities, Equipment, displays, and None other materials to support emergency operations.
C MM Nl Tl
- 4. Demonstrate the capability to communicate with all appropriate EOF-1 emergency personnel at facilities and in the field. (State only)
PROPOSED OBJECTIVES FOR GINNA Joint News Center (JNC)
PEA OBJECTIVE ¹ ARCAs 0 ILIZATION F EMER EN P NNEL 1 ~ Demonstrate the capability to alert and fully mobilize personnel for None both emergency facilities and field operations. Demonstrate the capability to activate and staff emergency facilities for emergency operations.
ITIES - E IPM NT Dl PL Y NDWOR NVIRONME T
- 2. Demonstrate the adequacy of facilities, equipment, displays, and None other materials to support emergency operations. JNC- I (State only)
NI ATI
- 4. Demonstrate the capability to communicate with all appropriate None emergency personnel at facilities and in the field.
- 10. Demonstrate the capability to promptly alert and notify the public within 4one the 10-mile plume pathway emergency planning zone (EPZ) and disseminate instructional messages to the public on the basis of decisions by appropriate State or local officials.
- 11. Demonstrate the capability to coordinate the formulation and 4 ~ne dissemination of accurate information and instructions to the public.
R N
- 12. Demonstrate the capability to coordinate the development and N()ne dissemination of clear, accurate and timely information to the news medi~
'I R N Y I F RMATI NTR
- 13. Demonstrate the capability.to establish and operate rumor control brine in a coordinated and timely manner.
SECTION 2.0 EXERCISE INFORMATION
2.0 EXERCISE INFORMATION 2.1 Exercise Partici ants The participants in the Exercise will include the following:
2.1 ~ 1 ROCHESTER GAS AND ELECTRIC CORPORATION A. Facilities Mana ement and Su ort Personnel
- 1. Simulator Control Room
- 3. Operations Support Center (OSC)
- 4. Survey Center (SC)
- 5. Emergency Operations Facility (EOF)
- 6. Joint Emergency News Center (JENC)
- 7. Engineering Support Center (ESC)
B. Emer enc Res onse Teams
- 1. Radiation Survey Teams (RSTs)
- 2. First Aid Team (if necessary)
- 3. Emergency OSC Teams
- 4. Security Force
- 5. Post Accident Sampling System (PASS) Team
- 6. Chemistry/Health Physics Support
- 7. Fire Brigade (if necessary) 2.1.2 OFFSITE AGENCIES/ORGANIZATIONS Participation of the following agencies/organizations is expected:
A. Federal 1 ~ Nuclear Regulatory Commission
- 3. National, Weather Service B. State
- 1. New York State Emergency Management Office
- 2. New York State Department of Health
- 3. New York State Police
- 4. Other Supporting State Agencies
C. Local
- 1. Wayne County
- 2. Monroe County
- 3. Other Supporting County Agencies 2-2
2.2 Exercise Or anization The organization for this Exercise will consist of the Exercise Coordinator, the Controllers, the Players and the Observers, as follows:
2.2.1 The Exercise Coordinator will coordinate Exercise preparations 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 Exercise, and prepare and follow up on an itemized list of corrective actions recommended as a result of the evaluation and critique, 2.2.2 ~C>> lied I I d f f follows:
A. A Lead Controller is assigned to each emergency response facility.
The Lead Controller is responsible for all Controller, Evaluator and Observer activities for that facility and, if appropriate, its associated teams. Controllers for teams or sub areas of a facility report to the Lead Controller of that facility.
B. The Controllers will deliver "Exercise Messages" to the designated Players at various times and places during the Exercise, inject or deliver additional messages as may be required to initiate the appropriate Player response and keep the Exercise action moving according to the scenario and Exercise objectives, observe the Exercise participants at their assigned locations, and prepare evaluation forms. Controllers/Observers submit written recommendations on corrective actions to the Lead Controller, who in turn summarizes all comments for submittal to the Exercise Coordinator prior to the scheduled critique. The Controllers will be provided with a list of instructions in the Exercise scenario.
C. Persons designated as Controllers/Observers for a given function will also be assigned as Evaluators of that function when feasible.
Evaluators will record their observations using an evaluation form and provide recommendations on corrective actions to the Lead Controller in whose facility they evaluate exercise performance on the basis of standards or requirements contained in the appropriate Emergency Plan, Implementing Procedures, and Exercise messages as described herein. They will take steps, whenever possible, to collect data on the time qnd motion aspects of the activity observed for post-Exercise use for implementing improvements.
2-3
Controllers will be iden ified b wearin reen bad es wi h white let erin s a in "Controller".
2.2.3 ~Pla ers include Ginna Station and other Rochester Gas and Electric Corporation personnel assigned to perform emergency functions, as described in the Emergency Plan and Implementing Procedures.
Players from offsite organizations and agencies (county, State and private industry) are participants in the Exercise as described in their respective Emergency Plans and Standard Operating Procedures.
2.2.4 Observers from the Rochester Gas and Electric Corporation and other organizations may be assigned to participate in the Exercise solely for the purpose of observing/evaluating Exercise activity. They will be provided with orientation information and appropriate Exercise publications.
Observers will be a ro riatel identified b wearin arm bands or bad es. Federal a enc observers will be identified b wearin arm bands or bad es wi h le erin s a in "NRC" or "FEMA".
Visitors from the Rochester Gas and Electric Corporation and other organizations may be assigned, on a limited basis, for the sole purpose of observing Exerciseactivities for personal education. They will be provided with orientation information and appropriate Exercise publications.
Visitors will b iden ifi b wearin arm ban or bad es statin "Visi or".
2.2.5 Requests to participate as a Visitor should be made in writing and contain the Visitor's full name, home address, phone number and organization affiliation. Requests to participate as Visitors must be submitted to the RGSE Corporate Nuclear Emergency Planner (CNEP) no later than one week before the Exercise.
2.3 Emer enc Res onse Facili ies During the Exercise, special facilities must be activated to manage, assess and support emergency response.
2-4
RGBcE FACILITIES The Rochester Gas and Electric Corporation Emergency Res p o n s e Facilities are:
A. Simila or Con rol Room The Ginna Simulator Control Room will be used. Control Room emergency response measures will be -exercised--under the direction of the Exercise Shift Supervisor, acting as the Emergency Coordinator, until relieved by the Plant Manager or alternate. The Simulator Control Room is located in the Simulator Building next to the Ginna Training Center.
B. Technical Su ort Center TSC When emergency conditions escalate to an Alert status or higher, coordination of the emergency response will shift from the Control Room to the TSC, located off the Mezzanine Level of the Turbine Building. The TSC Director relieves the Shift Supervisor as Emergency Coordinator and directs activities from the TSC. The TSC is the location from which technical management personnel utilize information on Plant status provided in the TSC to support actions being performed in the Control Room. The TSC serves as the primary communications source to the NRC, OSC, EOF and offsite agencies, and will perform other functions of the EOF until the EOF is activated.
C. 0 erations Su ort Center The OSC, which is located in the TSC, 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 activated for an Unusual Event at the discretion of the Emergency Coordinator.
D. Emer enc 0 erations Facilit EOF The EOF, which is located in the basement of 49 East Avenue in Rochester, will be activated for emergency conditions classified as a Site Area Emergency or General Emergency (optional for the Alert status). The EOF/Recovery Manager directs the activities of the EOF/Recovery Organization from the EOF. I 2-5
The TSC Emergency Coordinator reports to the EOF/Recovery Manager. The EOF is the command post for coordination of response measures with offsite organizations, assessment of radiological and environmental conditions and determination of recommended protective actions for the public. The EOF also provides direction and management of recovery operations.
E. Joint Emer enc News Center JENC The JENC, which is located at 89 East-Avenue. in-Rochester, provides the point of contact for the coordinated release of news and information to the news media and the general public..The JENC is staffed by RGSE Corporation, County, State and Federal officials and will be activated for emergency conditions classified as an Alert, Site Area Emergency or General Emergency.
2-6
24 Exercise Conduct 2.4.1 Overview The Exercise will simulate an abnormal radiological incident at Ginna Station which will start with an Unusual Event and escalate to a Site Area Emergency.
During the course of the Exercise, in order to evaluate coordination with appropriate State and local agencies,-incidents will arise which require response by offsite emergency response organizations. The Exercise will also simulate an offsite radiological release which will require deployment of Ginna.Station, and Wayne County and Monroe County radiological survey teams for offsite monitoring.
The conduct of the Exercise will demonstrate the effectiveness of selected organizations, personnel, functions, and/or activities of the appropriate Emergency Plans and Implementing Procedures. The simulated emergency will then de-escalate. The Recovery Phase will be initiated and the Exercise will then be terminated.
2.4.2 Actions Emergency response actions during the simulated emergency will include: recognition and classification of emergency conditions; assessment of onsite/offsite radiological consequences; alert/notification and mobilization of emergency response organizations; implementation of in-Plant corrective actions; activation/operation of emergency response facilities and equipment; preparation of reports, messages and record-keeping; and recommendation of protective actions.
2-7
Communications The Exercise will also demonstrate the effective use of communications systems. An actual emergency operation usually requires the extensive use of both telephone and radios. The telephone is the primary means of communication and will be attempted first, with radio as a backup, unless radio is the only means available. Separate telephone numbers will be used for Controller communications to prevent the Players from learning in advance of the situation to which they are to be subjected during the Exercise. Close cooperation and coordination among Controllers is essential due to the number of persons assigned to the Controller role.
RGKE offsite radiation survey, teams are equipped with portable radios, and are provided cellular telephones for back-up communications.
Survey team controllers are encouraged to use the cellular telephones if clarifications of controller instructions are required while in the field.
Controllers Lead Controllers will be stationed in the Simula or Con rol Room OSC CC 0 J C dd CC.Dlyy dC I dlfy Exercise messages or initiate free play messages.
A. The Simulator Control Room will be the central point for organization of Exercise messages and is the key to ensuring that the Exercise progresses on schedule, Simulated Plant parameters will be provided to the Simulator Control Room operators either by panel indications displayed in the Simulator Control Room or through plant data and status sheets. Since it is necessary that the emergency escalate to the General Emergency level, it may d y d I
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SECTION 4.0 REI=ERENCES/ABBREVIA TIONS - ACRONYiNS
4.1 References 10 CFR 50.47, 50.54, Appendix E 4.1.2 44 CFR 350.9 4.1.3 NUREG-0654/FEMA-REP-1, Rev. 1, Criteria for Pre ara ion and Evalua ion of Radiolo ical Emer enc Res onse Plans an Pre aredness in S ort of N clear Power Plan 4.1.4 RGSE Nuclear Emergency Response Plan (NERP) 4.1.5 GS Radiation Emergency Plan Implementing Procedures (EPIPS) 4.1.6 GS License and Technical Specifications 4.1.7 GS Piping and Instrumentation Drawings 4.1.8 New York State Radiological Emergency Response Plan 4.1.9 Monroe County Emergency Preparedness Plan 4.1.10 Wayne County Radiological Response Plan 4.1.11 INPO Emergency Preparedness Drill and Exercise Manual 4-1
4.2 Abbreviations - Acron ms A/E Architect Engineer ALARA As Low As Reasonably Achievable AOV Air-Operated Valve ARMS , Area Radiation Monitor(s)
ARV Atmospheric Relief Valve ATWS Anticipated Transient Without Scram BAST Boric Acid Storage Tank CD Civil Defense CFR Code of Federal Regulations CV Containment CR Control Room DOE Department of Energy DOE-IRAP DOE Interagency Radiological Assistance Plan EAL(s) Emergency Action Level(s)
EBS Emergency Broadcast System EC Emergency Coordinator ECL(s) Emergency Classification Level(s)
ENS Emergency Notification System (NRC)
EOC Emergency Operations Center EOF Emergency Operations Facility EPA Environmental Protection Agency EPC Emergency Planning Coordinator EPIP(s) Emergency Plan Implementation Procedure(s)
EPZ Emergency Planning Zone ERF(s) Emergency Response Facility(s)
ERPA Emergency Response Planning Area ESC Engineering Support Center FEMA Federal Emergency Management Agency FRERP Federal Radiological Emergency Response Plan GS Ginna Station HALM High Alarm HP Health Physicist HPN Health Physics Network HVAC Heating Ventilation Air Conditioning INHB Inhibited (Alarm Suppressed)
INPO Institute of Nuclear Power Operations JENC Joint Emergency News Center Kl Potassium Iodide LALM Low Alarm LCO Limited Condition of Operation LOCA Loss of Coolant Accident LWR Light Water Reactor MOV Motor-Operated Valve MPC Maximum Permissible Concentration NERP Nuclear Emergency Response Plan 4-2
4.2 Abbrevia ions - Acron ms Cont'd NRC Nuclear Regulatory Commission OSC Operational Support Center OOS Out of Service (on site)
OOS Out of Sequence (off site)
PAG(s) Protective Action Guide(s)
PAR(s) Protective Action Recommendation(s)
PASS Post Accident Sampling System PIO Public Information Officer PWR Pressurized Water Reactor RCP Reactor Coolant Pump RCS Reactor Coolant System RHR Residual Heat Removal RG &.E Rochester Gas and Electric Corporation RST Radiation Survey Team SC Site Contingency (or Survey Center)
Sl Safety Injection SPING High Range Effluent Monitor TSC Technical Support Center 4-3
SECT/ON 5.0 CONTROLLER AND EVALUATOR INFORMATION
5.0 CONTROLLER AND EVALUATOR INSTRUCTIONS Each Controller and Evaluator should be familiar with the following:
'.a. The basic objectives of the Exercise.
The assumptions and precautions being taken.
- c. The Exercise scenario, including the initiating events and the expected course of actions to be taken.
- d. The various locations that will be involved and the specific items to be observed when at those locations.
- e. The purpose and importance of the evaluation checklist and record sheets.
5.1 Controller Instructions 5.1.1 Controllers will position themselves at their assigned locations prior to the activation of the facility for which they have responsibility (see Section 5.3).
5.1.2 Communications will be tested to ensure satisfactory communications among Controllers prior to Exercise commencement. All watches and clocks will be synchronized with the Lead Simulator Control Room Exercise Controller as part of the communications testing.
5.1.3 All Controllers will comply with instructions from the Lead Controller.
- 5. 1.4 Each Controller will have copies of the messages controlling the progress of the Exercise scenario. No message shall be delivered out of sequence or other than as written unless specifically authorized by the Lead Controller.
5.1.5 Messages controlling the progress of the scenario are noted with a number. Contingency messages are noted with a number followed by the letter "X" (e.g., 10X) ~
5.1.6 Each onsite Controller will have copies of time-related plant data sheets. Data sheets will be distributed only in the Control Room.
Radiological and meteorological data will also be provided at locations where it is normally available.
5-1
5.1.7 Controllers will ~no provide information to the Players regarding scenario development or resolution of problem areas encountered in the course of the simulated emergency.
The Exercise participants are expected to obtain information through their own organizations and exercise their own judgement in determining response actions and resolving problems.
5.1g8 Some Players may insist that certain parts of the see n a ri o a re unrealistic, The Lead Controllers have the sole authority to clarify any questions regarding scenario content.
5.1 g9 Each Controller will take detailed notes regarding the progress of the Exercise and the responses of the Exercise participants at their respective assigned locations. Each Controller will carefully note the arrival and departure time for participants, the times at which major activities or milestones occur and problem areas encountered. The Controllers will retain their notes for the purposes of reconstructing the Exercise chronology and preparing a written evaluation of the Exercise.
5.2 Evaluation Instructions Each Controller/Evaluator will take detailed notes regarding the progress of the Exercise and the response of the Exercise participants at, their respective assigned locations. Each Controller/Evaluator should carefully note the arrival and departure times of participants, the times when major activities or milestones occur and problem areas encountered.
The standards below should be used by the Controller/Evaluator to evaluate assigned areas pertaining to the emergency response. A dual purpose will be served by this rating system. First, the capability of each facility or response area will be evaluated and second, the system will provide a vehicle for guiding and directing improvement.
The rating scale is as follows:
Good - Personnel and equipment generally performed better than expected. Any errors or problems were minor and easily correctable.
g I
- d I g II f d expected. Any errors noted were not severe and could be corrected without undue labor or expense.
I -P I d ~ p g llfP I dg I expectations and there were several significant deficiencies noted.
The area's ability to carry out its functions was diminished.
NA - Not applicable to the situation or not observed.
5-2
Controller/Evaluator comments should consider the demonstration of the following facility and team evaluation elements:
5.2.1 ~Facilit o Accurate and timely determination of emergency action and classification levels.
o Timely activation and staffing for each classification level ~
o Familiarity of personnel with appropriate emergency instructions, duties and responsibilities.
o Timely notification of Rochester Gas and Electric Corporation, local, State and Federal personnel/agencies (information updates performed).
o Adequacy of internal information systems (i.e., message handling, displays, status boards and maps).
o Properly controlled documentation and accurate, timely record-keeping.
o Utilization of correct communications procedures and techniques.
o Capability of facility supervisors/directors to interface with personnel and coordinate facility activities.
o Consideration of personnel safety (exposure control).
o Adequacy of interface between emergency response facilities.
o Adequacy of equipment and supplies.
o Timely initiation of onsite protective/corrective actions.
o Development of protective action recommendations.
o Radiological surveys and assessment of plant damage and hazardous conditions performed.
o Timely request of emergency support services.
o Coordinated, accurate and orderly dissemination of information to the news media.
o Proper assumption of command and control.
5-3
5.2.2 Team o Timely notification and activation.
o Adequacy of staffing.
o Familiarity with appropriate emergency procedures, duties and responsibilities.
o Availability and utilization of proper equipment.
o Performance of contamination/decontamination control.
o Proper interface with emergency support personnel.
o Utilization of correct communications instructions and techniques.
o Availability of referenced documents to team members.
o Utilization of proper radiological control practices (i.e., access control, protective clothing, shielding, stay time).
o Performance of radiological surveys.
o Timely and proper performance of damage assessment.
o Properly maintained survey records and maps.
o Adequacy of briefing sessions prior to dispatch.
o Direction and control by team leaders.
o Timely requests for offsite assistance if required.
o Coordination and interface between emergency response team members.
o Proper interfaces with plant supervisory personnel.
Controllers/Observers will record their comments for the purpose of reconstructing the Exercise chronology and preparing a written evaluation of the Exercise.
5.3 Personnel Assi nments Table 5.1 lists the personnel assignments for the on-site Controller organization.
5-4
Evaluation Packa es The following evaluation packages will be provided to the appropriate Controllers/Observers at the pre-Exercise briefing:
Simulator Control Room Technical Support Center
, Operational Support Center Survey Center Emergency Operations Facility Joint Emergency New's Center Health Physics Personnel Dose Assessment (TSC and EOF)
Radiation Survey Teams (SC and EOF)
Post-Accident Sampling System Fire Brigade Engineering Support Center 5-5
TABLE 5.1 The following personnel have been designated to act as Controllers during the O 1993 Exercise activities (SEE ATTACHED LIST).
5-6
Attachment 2 EXERCISE CONTROLLER LIST
~
Position Personnel Assi ned Exercise Coordinator R. Beldue Control Room Simulator D. Hudnut (Lead)
J. O'oole M. Ruby J. Zulawski Control Room (Real} Day Shift Supervisor in Operations Office Technical Su ort Center Lead T. Alexander Technical 8 Operations B. Zollner T. White Security R. Wood R. Benne Dose Assessment T. Hed es Health Ph sics 8 Chemist B. Thomson General P. Polfleit 0 erations Su ort Center Lead J. Huff J. Knorr Fire D. Biedenbach M. Cavanau h Operations S. Carter R. Jenkins l8C T. Joachimczyk E. McGrattan Mechanical S. Meister G. Gibaud J. Liese Electrical R. Yates R. Marriott Post Accident Sam lin S stem J. Raike
Attachment 2 EXERCISE CONTROLLER LIST Position Personnel Assi ned Surve Center Lead S. Poulton Other Evacuation/Re-Ent A. Jones Red Team D. Gansko Blue Team J. Edler Green Team J. Mazzeo Yellow Team J. Za etis Oran e Team S. Stinson Erner enc 0 erations Facili Lead 8 0 erations W. Backus Communications 8 Data Flow B. Stanfield Dose Assessment Outside Utilit Personnel Surve Teams G. Haverl General R. Watts J. Neis Engineering Support Center C. Herschell Joint Emergency News Center F. Orienter TBD (Outside Utility Personnel)
National Weather Service G. English
GINNA STATION 1993 EMERGENCY EXERCISE 5.5 PUBLIC INFORMATION,RUMOR CONTROL AND SPOUSE PHONE QUESTIONS FOR THE EVALUATED EXERCISE A significant aspect of emergency response is to provide the news media and general public with accurate and timely information about the incident.
Public perception and reaction are influenced by the information relayed to them. To ensure that the Rochester Gas and Electric Corporation Emergency Organization is prepared to deal with outside inquiries during an incident at the Ginna Station, the exercise provides certain elements that test Public Information and Rumor Control activities. During the course of the Exercise, the Joint Emergency News Center (JENC) will be activated and exercised.
The RGSE "Spouse Phone" will also be manned by the RG&E Medical Department.
Exercise Controllers have been selected to test the Rumor Control and News Media Contact Staffs, as well as the JENC. Controllers will act as concerned citizens, employees, employee relatives and as members of the media, posing questions to the staffs. When acting as members of the media, controllers shall make up a name and a media outlet (print or electronic) located outside of the Rochester area. Each time a rumor control message is delivered, a different fictitious name and address will be given.
The phone number to be given will be the number from which the exercise controller is calling so as to allow the county Rumor Control person(s) to return calls with appropriate information, if necessary. The exercise controllers should maintain the theme of each rumor control message and answer inquiries of the counties'umor Control persons appropriately.
The following pages denote questions that these controllers can use. The questions are grouped by time in relation to the events specified in the Exercise Scenario. The Controllers are allowed to use questions previously utilized. The lead JENC Controller shall verify that the exercise is adhering to schedule, otherwise time adjustments will be necessary. Space is provided for controllers to make notes on the response. Controllers need not use the questions herein; free play is encouraged. However, controllers must not get carried away with unusual or pointless questions.
When calling in questions, ~alwa s grecede guestions with "THIS IS AN EXERCISE". If you are playing a reporter at the JENC, develop free play questions based on the information given during the briefing.
Additionally,ask questions about RGSE, the State or counties, Ginna Station, radiation, state/county/utility interface, protective actions, etc. Questions and relevant telephone numbers will be distributed at the special Pre-Exercise Controllers Briefing.
5-9
Pg>> I I 3 2 II f Rggg; 2 II gl C R C IG dll I 3 I I d ldlld lists sample questions for testing the "Spouse Phone" in the RGRE Medical Department.
5-10
GINNA STATION 1993 EMERGENCY EXERCISE ATTACHMENT 1 SAMPLE PUBLIC INFORMATION QUESTIONS TIME 0900 ~ IVly husband works in the Wayne County Sheriff's Office. He said he' heard that there's some sort of problem at the nuclear plant.
~ Is that true?
~ Will this be on the news?
~ How dangerous a situation is it?
~ This is from TV Station WGRC. We'e heard that there is an accident of some kind at the Ginna Nuclear Plant. Can you tell us what is happening?
0915 ~ This is from the Wolf Newspapers. I understand that you have an accident at the Ginna Nuclear Plant. What's going on up there?
~ How bad is the problem?
~ How did the trouble start in the plant?
~ Is it under control?
~ What's the state of the plant?
~ What kind of danger is involved?
0930 ~ This is WBBT AM Radio News. We'e heard that your plant has had a fire and explosion. Can you confirm?
~ Have any workers been injured?
~ If so what is the extent of their injuries?
~ Is the safety of the public threatened?
~ At what time will you have a press conference?
5-1 1
~ Where will it be held?
~ We'd like to send someone to the plant, for interviews and photos..Where do they go?
0945 ~ This is from TV 11 News. We have a report you have some serious problems at Ginna Station. Would you tell our listeners the story?
~ Is the plant experiencing an uncontrolled release of radiation?
~ How do you know?
~ Who is in charge of the emergency?
~ What is his/her title?
~ Can we get a statement from him/her?
1000 ~ This is calling from the Associated Press. Can you give me a summary on the problem at your Ginna Nuclear Plant?
~ Are you under a state of emergency?
~ Was the reactor damaged?
~ Did,you evacuate the site?
~ Why not?
~ Are you going to evacuate the public living by the plant?
~ Is this worse than the 1982 Ginna accident?
~ Where exactly is the plant located?
5-12
1000 Yes, this is , I'm the Webster Town Supervisor. My office is getting flooded with calls from local residents.
~ What is happening at Ginna?
~ Is the plant still under your control?
~ Have the local authorities been notified?
~ Which ones?
~ Are we in Local State of Emergency?
~ Is there any danger to the public?
-1015 This is Channel 9 News. We have some questions on the Ginna problem.
~ What exactly is going on at Ginna?
~ Has the situation been resolved or are things getting worse?
~ Are you evacuating the site?
~ Are you going to tell the public to evacuate the area around the plant?
~ Has Governor Cuomo been notified?
~ Have the sirens been activated?
1015 ~ This is
~ I'e heard you declared an ",ALERT" earlier today.
~ What does that signify--how bad a problem do you have?
~ What time did it happen?
~ How did the problem start?
~ Has anyone been killed?
~ Are there any injuries?
~ The situation appears to be getting worse.. is this true?
~
5-13
1030 . This is . I'm at the news desk at the Times Union.
I'm trying to help write tonight's story on the Ginna disaster.
~ I'm confused about what's going on at Ginna...is the problem a fire or a radiation leak to the atmosphere?
~ Has the problem ended?
~ What is the significance of an "ALERT"?
~ How serious a problem is that?
~ Which government officials been called?
~ What is RGSE doing now?
~ What time did you declare the emergency?
~ Didn't Ginna have a similar problem several years ago?
~ Ginna seems to be having more "technical malfunctions" than other US nuclear plants, how do you explain that?
1045 ~ This is ~
I'm calling from WRTQ Radio in Oswego.
~ How do I get "official" information.. .who's in charge?
~
~ Who do I talk to for getting more information about radiation being released from the plant?
~ Are farmers supposed to be sheltering livestock?
1045 ~ I'e got a small dairy farm in Williamson and I need to know what I should do.
~ Where would I get more stored feed for my cattle if my pasture gets contaminated?
~ I think I heard the sirens...do I need to evacuate' 5-14
1100 ~ I heard that you declared a "General Emergency".
~ When did this happen?
~ How much of the plant has been damaged?
~ Is there is a release of radiation?
~ Has anyone been injured in or around the plant?
~ Is the plant safe or in big trouble?
1115 ~ What does a "General Emergency" mean? Doesn't that mean that no one can go near the plant for the next several weeks?
~ Is this accident similar to or worse than the one you had before?
~ Why didn't we have more warning about this problem before now?
~ When will this problem be over, or don't you know?
~ Will you evacuate people around the plant?
~ In simple terms, what are you doing to control this emergency situation?
~ Will lots of radiation be released, or has it already started?
~ Is this as bad as the disaster at Chernobyl?
1130 ~ My father is in the Hill-Haven Nursing Home in Webster.
~ What will happen to him?
~ How long will this emergency last?
~ How do we keep informed?
~ Is this as bad as Chernobyl?
~ I just heard on my scanner that someone found evidence of terrorist sabotage on a plant safety system, is the plant going to blow up?
5-15
1200 ~ Do you expect that any radiation will be released?
~ Is the radiation like bomb fallout?
~ How dangerous is it?
~ Who is in charge of the emergency?
~ When will the next press briefing be held?
~ Where is the radiation heading?
~ What protective actions have been recommended?
~ Whom should I call for further information concerning the Webster area (or Ontario)?
~ If we'e evacuated, will my house ever be safe to return to?
~ Where are people supposed to go if they evacuate?
1215 ~ What is the problem at Ginna?
~ I'm confused--How did the problem start?
~ Is this plant similar to Chernobyl or TMI?
~ Can it blow up?
~ How much radiation is being released off site?
~ What protective actions are in effect for Wayne (Monroe) County?
~ If people around the plant have to evacuate their homes, when will they be allowed return?
5-16
1215 ~ Are farm animals on pasture grazing safe?
~ What about the apple orchards around the plant, how will they be impacted?
~ Are you releasing radiation?
~ If so what are the levels?
~ Are farmers supposed to take any action to protect their livestock?
~ Who is the best source of truthful information on this emergency?
1230 ~ This is from WRKU Radio in Albany.
~ How serious is the Ginna situation now?
~ Is the problem under control yet?
~ How many people live around the plant?
~ What are you going to do to fix the situation?
~ When is the next press briefing?
~ Can we interview anyone at the plant?
~ Where is your News Center located?
~ How do I get there?
~ Where is the wind going?
~ Who's in charge of the emergency?
~ We heard that there was sabotage resulting in both a fire and serious release of radiation, what can you tell us about how this came about?
1245 ~ I live in Webster on Lake Road. I'm worried about leaving my cats behind if I evacuate my home.
~ Can I take them along with me to a county evacuation shelter?
~ What else should I take along if I go?
~ How many days of pet food should I bring?
5-17
1300 ~ This is TV 25 in Kingston, Ontario. Is it true that your G-e-e-na reactor is suffering a mishap and can you give us an update a-boot the severity of the problem?
~ Briefly, what happened this morning to begin this problem?
~ Do you Americans consider this to be worse than Three Mile Island?
~ Do the authorities believe there's chance that the winds may carry radioactive material across Lake Ontario to Canada?
~ Can you tell our viewers how your reactor is different from ours?
~ For example, will there be heavy water contamination in the Lake?
~ We also heard that there was a toxic leak at the plant, what is your comment?
1315 ~ I hear there's an emergency at the nuclear power plant.
~ What happened and how bad is it?
~ How do we get additional information? I live in Ontario, NY.
1330 ~ I'm of Radio Station WTTY. You'e on our "NEWS LINE" and could you tell our listeners what's happening at the Ginna Nuclear plant?
~ Is the Monroe County Executive going to declare a state of emergency?
~ What does the County Executive intend to recommend to the public?
~ Are there any recommendations for people living within a few miles of Ginna?
~ Should Monroe or Wayne County residents take any kind of proactive measures because of the problem we'e hearing about on the news?
1345 ~ Is there a security problem at Ginna?
~ Was there sabotage?
~ Is the plant under control?
5-18
ATTACHMENT 2 SAMPLE RUMOR CONTROL MESSAGES FOR WAYNE COUNTY TIME 0910 ~ Could you tell me about the problem at Ginna? I'm a Sodus resident.
~ Is there a chemical or a radiation problem at Ginna?
~ Is the problem at Ginna or Nine Mile Unit II?
~ Is the plant shut down?
0945 ~ I hear there's an emergency at the nuclear power plant.
~ What happened and how bad is it?
~ I'm of Radio Station WOOR. We'd like to tape a short interview ...can you provide the answers?
~ Could you tell our listeners what's going on at the Ginna Nuclear plant?
~ Is the County Executive going to declare a state of emergency?
~ What does the County Executive intend to recommend to the public?
~ Are there any recommendations for people living within a few miles of Ginna?
~ Should County residents take any kind of proactive measures because of the problem we'e hearing about on the newswires?
1000 ~ Has any dangerous radiation leaked yet?
~ How can you be sure? Are you checking it?
~ How can I find out when there is a release?
~ Who is in charge of the emergency?
~ Is the plant shut down at this time?
5-19
1015 ~ My son works at Hardee's in Ontario... he's there now.
~ How will he know about the Ginna problem?
~ Is he safe where he is?
~ Does RGSE have an emergency plan?
~ If so, how does the County figure in it?
~ We'e lost our emergency information handbook and need one right away. Will one of the emergency people you have deliver one to us?
1030 ~ Is there a security problem at Ginna?
~ Was there sabotage?
~ Is the plant under control?
~ What damage was done?
1045 ~ I heard there was an explosion and fire at Ginna. What is really happening?
~ Are you in a general state of emergency?
1110 ~ I live on Lake Road in Williamson. I'm just east of the Town Line with the Town of Ontario. I need some information.
~ If there's an evacuation, I'm going to need help with my two infant twins. Can you help me? We only have one car.
1125 ~ How many nuclear plants are in the area?
~ Which one is having the problem now?
~ Where's our power going to come from if the plant is shut down for a while?
~ Have you guys called for extra help with your problem?
~ Who's running the emergency?
5-20
1145 ~ What station on the radio should we be listening to?
~ I need to talk to the County Executive. What's his number? I need to know what to do.
~ Is RGRE telling us'the truth? We all remember the Ice Storm and how they lied then to save their buttsl 1200 ~ I live in Newark, but I could live 50 miles away and wouldn't feel safe...are you going to let us know'if we need to get out?
~ How?
~ I heard you'e bring all the irradiated people from around the plant to Newark High School...is that true? We'l all be radioactive!
1215 ~ I live near the plant and heard there is an "GENERAL ALERT", and then I heard it called something else. . What's going on?
~
~ Are you checking the radiation levels outside?
~ Did the World Trade Center terrorists do this?
1225 What's this I hear about a fire at Ginna?
~ Was that because of a big explosion or something?
~ How many people got hurt and who's running the plant now?
~ Somebody told me the Ginna workers "bail out" from the plant when there's a problem. Is that true?
1230 ~ Is Cuomo or Clinton sending help?
~ What's happening right now at the Ginna plant?
~ Is the plant burning out of control?
1245 ~ My neighbors are saying that something blew up at the Ginna plant. Is this true?
5-21
1245 ~ Has a State of Emergency been declared?
~ What should the public do to protect itself?
~ My wife and I are concerned because we haven't heard the sirens go off...we live over in Macedon.
~ Shouldn't we hear sirens now or sometime real soon?
~ We don't think you county disaster people are being told everything by RG&E. I can't even get a straight answer on my monthly electric bill What's really going on?
~
1
~ I don't trust the power plant people; they'd lie to save their own skins.
~ Do you have anybody checking on them to make sure they'e trying to control it?
~ Will the County Board of Supervisors look into this accident and stop Ginna from starting up again?
1300 ~ Yeah...l got one question.... Who's going to pay for all the clean-up from this accident? If you think the ratepayers are going to take it you know where again.....you'e dead wrong! What's going to happen?
1315 ~ Should I close my restaurant due to the accident at Ginna Station? I'm over in Ontario Village.
~ What are we supposed to do?
~ Who do I call to find out if we'e going to have to leave?
~ Who will guard my place if we evacuate?
1320 ~ I'm calling from California, I have family in Rochester. ..what's going on
~
at your plant?
1330 ~ What's happening at Ginna?
5-22
1340 ~ I heard that at Ginna a disgruntled employee sabotaged the plant and that's what caused this accident! Have they caught the person yet?
~ Has there been a radiation release?
~ What's happening to all the school kids in the Williamson School District?
I heard the siren but nobody said which way to go. My neighbor says the siren means to leave your house immediately.
~ Is he right?
1350 ~ What do I do? I live on Paddy Road near route 350 in Ontario.
1400 ~ I hear that the Maplewood Nursing Home will keep its patients where they are. My wife works there, but I can't reach her because the phones are busy. Will they be safe there?
1415 ~ I'm leaving now. Where do I go for temporary housing? I live on State Road near Route 250.
1420 ~ I'm calling from Penfield.....has there been a release of radiation from Ginna?
~ I'm calling from Pennsylvania....l live 5 miles from Ginna.....can we return home tomorrow?
1430 ~ What's happening at Ginna?
1435 ~ I'm evacuating now. Which way is safe to travel? We live next to the intersection of Kenyon and Stony Lonesome Roads in Ontario. We need temporary housing. I'e got 4 kids with me.
1445 ~ I am supposed to leave but don'-have a place to stay. Which school can I stay at? I live on Lake Road near County Line Road in Wayne County.
~ How do I get there?
~ Who's going to pay my expenses?
~ Who do I call to get a check for my expenses?
5-23
SAMPLE RUMOR CONTROL MESSAGES FOR MONROE COUNTY TIME 0940 ~ I hear there's an emergency at the nuclear power plant.
~ How serious is the problem?
~ Are schools going to be dismissed early?
~ Can I pick up my two children at the RL Thomas School in Webster?
~ I'm of Radio Station WTZ.. Can=you tell our listeners what' happening at the Ginna Nuclear plant? You'e live on our "MORNING SHOW".
~ Have officials in Monroe County declared a state of emergency?
~ What is Monroe County doing to assist in this emergency?
~ Will you have a press conference?
~ Has there been a problem at the Ginna Plant?
0950 ~ I live down on Plank Road near Jackson Road....Have any chemicals or radiation been released, can they get into the drinking water?
~ Is the problem under control?
~ Should we leave our home because of the mishap at the plant? We'e very concerned about this.
~ What's the problem at your plant?
~ When will the emergency be over?
~ What caused the problem at Ginna?
1000 ~ My daughter and a friend are out shopping in Irondequoit.
~ How are they going to be warned about the plant problem?
~ We live in West Webster on Backus Road...are we safe?
~ Are you going to block off the roads...my daughter needs to be able to drive back homel 5-24
1010 ~ What's happening at the nuclear plant?
~ Is the problem I'e been hearing about at Russell Station or Ginna?
~ Who caused the accident?
~ My mother works in the library in Webster.
~ How do they know there's problem?
~ Are they safe?
~ I can't get through to the library..the line is busy.
~ What do you recommend I do?
1015 ~ We live in Penfield Village...are we far enough away?
~ Is the plant under control now?
~ Will we lose our power because of the accident?
~ ls there a brochure we'e supposed to have to tell us what to do?
~ Who.is in charge of your emergency?
~ Is it under control?
1020 ~ I'm calling from Consolidated Edison....could you give me some information about the event this morning at Ginna?
1025 ~ We'e lost our emergency information handbook and need one right away. Which Zone do we live in?
~ We live on Shoecraft Road near State Road - are we going to have to evacuate? We'e very close to Ginna!
~ Where are we supposed to go if we'e told to leave?
1030 ~ What happened at Ginna this morning?
~ What do I do if the sirens blow?-
~ Are all RGSE's plants under attack?
~ What happened this morning?
~ Where can I buy a radiation instrument to check the outside?
5-25
1100 ~ I have some milk goats out in our field. .out on County Line Road
~
by State Road. What do I do with the goats? Bring 'em inside?
~ We live in a one-story wood-frame house. The calendar we received from RGRE talks about "sheltering". Isn't that supposed to apply only to brick buildings with thick walls? We don't even have a basement!
~ Is the Ginna plant running now?
~ Will you be blowing the sirens?
~ If so, what do we do?
~ I need to know what's going on and what to do.
~ My neighbors are frightened . ~ ..we live on Holt Road near Woodhull
~ Can we go outside? Are we in danger?
~ Are you people checking the radiation?
~ What are we supposed to do when sirens go off?
1115 ~ My neighbor's a cop....we says you'e got a security problem. How bad is it?
~ How many security people are at Ginna?
~ Have you called for help?
~ Did the sabotage cause the chemical release?
~ Did terrorists blow up Ginna?
~ Were employees or outsiders involved in the destruction of safety equipment?
~ Are the plants in Oswego having problems too, or is it just Ginna?
1130 ~ We hear that emergency shelters are open now....what do we bring if we need to stay for awhile and how much will it cost?
~ How do we get checked for radiation? My whole family is feeling nauseated and weak.
5-26
~ Is Wayne County going to be declared a disaster area?
~ Is this accident as bad as Chernobyl or TMI?
~ Where do the school kids go? My daughter goes to State Road Elementary School.
~ Should I close my business due to the accident? Who will pay for the lost income'? (The business is on Empire Blvd. near Bay Road).
1200 ~ Are schools closing in Fairport...my kids are at the High School?
~ What are we supposed to do? - we live on Route 31 ~
~ What should I do for-my chickens'to protect them from radiation?
~ I heard Ginna is melting down. Is it true that State people are coming to take over?
~ We heard the Governor is coming to take charge of Ginna.
~ How wide an area will be evacuated - 20, 30 miles?
~ How far is Ginna from Fairport?
~ Should Fairport residents leave their homes?
~ Is there a plan for nuclear emergencies?
~ Is it finished?
~ Who wrote the plan and who approved it?
~ Is RGSE responsible for the accident that happened?
5-27
1230 ~ I heard the siren but now what do we do? We live just down the road from Ginna...and I don't see anyone leaving the plant....are they all dead?
~ Would you send out the sheriff's department to check?
~ What's happening at the Ginna plant?
~ I'm leaving now. Can I pick my son? He's got a job at Taco Bell in Webster.
~ I live in East Rochester...we just had a problem a few weeks ago with the drinking water, heavy metals in the water or something.
~ Are we going to have to boil our drinking water again because of the plant's radiation?
~ Can my pets be outside, can they drink water that's outside?
1300 ~ I think I am supposed to leave but don't have a place to stay. I live in Monroe E-R-P-A Number 4.
~ Which county shelter can I stay at?
~ How do I get there?
~ Who's going to pay my expenses?
~ I heard the accident at the Ginna Station is just a false rumor, What' going on?
~ I live exactly 5 miles southwest of the plant....there's never been a problem before and I'm not going to leave now. I'm sure the media's just blowing this out of proportion.
~ Why haven't you made the announcement on radio?
~ Who's going to guard all the neighbor's houses after they run away to the shelters?
~ Is the Ginna emergency over yet?
~ Is the Ginna reactor shut down?
~ Is the plant burning?
5-28
1330 ~ What is the Ginna problem that occurred this morning?
~ I'e heard people are being asked to leave. Is that true?
~ Were we supposed to hear the sirens?
~ What radio station or T.V. channel should we have on?
~ Who is running the reactor at Ginna? I hear the safety equipment was tampered with this morning by someone in the plant.
~ Where is the emergency information in the phone book. I can't find it.
~ What should we take if we leave our home?
~ How do we get transportation if we don't have a car and need to evacuate? We live on Holt Road near Lake Road.
~ Is the accident over with at Ginna?
~ Who's going to pay for the mess you created?
1345 ~ Is there contamination on the ground now from Ginna?
~ My homeowners insurance states I'm not covered for nuclear accidentsl What do I do now?
~ Who will check my home and property to make sure there's no radiation?
We live on Jackson Road.
~ I'm calling from Buffalo...l got my family out of our house in Webster this morning. When will it be safe to go home again?
~ Can we be checked for nuclear radiation somewhere, on our way home?
~ Who can we get to check our farm pond to see if there's any contamination?
~ I'e got a well on my property (about 6 miles west of Ginna on Lake Road). Can we still drink from our well?
~ Who can I contact if I have more-questions, and I'm sure I will!
~ I'm calling from England.....what kind of plant is Ginna?
~ Has there been a release to the atmosphere?
~ Was there iodine in the release?
5-29
1400 ~ How long will people who evacuate from Monroe ERPA 1 have to stay away from home?
~ Can homeowners go back and check their homes in the meantime?
~ What if there's a fire in one of our houses? Are you just going to let it burn?
~ Are residents supposed to take potassium iodide?
~ If we can't get the potassium, can we take salt tablets?
~ What is happening at Ginna now?
~ We caught some trout just east of the plant this morning, around 8 or 9 am.
~ What should we do with the fish?
~ Is my boat contaminated now and am I?
5-30
ATTACHMENT 3 SAMPLE PRESS CORPS QUESTIONS
~ What happened to the turbine at Ginna?
~ Was there a fire...is it out....what's the damage?
~ Is it true a leak occurred?
~ What kind of leak was it - chemical or radiation?
~ Isn't it true the plant is always releasing to the atmosphere?
~ Is the reactor stable and under control?
~ Is this plant similar to Indian Point?
~ Were any workers injured or contamiriated?
~ .How much radiation was released around the plant?
~ What protective actions are in effect for Wayne (Monroe) County?
~ How many people live in Wayne (Monroe) County?
~ What are you going to do to manage the situation over the next several hours?
~ How long will the emergency be in effect?
~ When is the next press briefing?
~ How many media representatives are at the News Center?
~ What agencies are at the News Center?
~ Where is the wind heading now?
~ What is the weather forecast? What effect will that have on your recommendations?
~ Who's in charge of the emergency?
~ Please explain the relationship of the State, the two Counties and.RGKE in terms of how decisions are made during this emergency.
5-31
~ Who makes the decision the activate the sirens, who decides to evacuate or shelter, and how is that decision reached?
~ How can we be sure that the best interests of the public are paramount in the decision-makers mind?
~ How does the County Executive and County Chairman get the technical information they need to make informed decisions?
~ For any news organization wishing to take footage of Ginna, who do we see at the plant gate?
~ How will home-bound, mobility impaired or nursing home patients be protected?
~ What exactly does "sheltering" involve..does. this apply to any type of home?
~ When can people who have sheltered, stop sheltering?
~ What effect will the release of radioactivity have on Lake Ontario fish?
~ What impact will the radiation released have on unborn babies?
~ How many cancer deaths are there likely to be in Wayne and Monroe counties as a result of this accident?
~ When do you expect to enter "Recovery" ? What does that mean exactly?
~ Will there be any further radioactive releases?
~ Will the sirens be sounded any further?
~ How do tourists know how to protect themselves?
How is the plant getting power now to run its safety systems?
~ Will the shareholders or ratepayers absorb the cost of this mishap?
~ Will Ginna need to be decommissioned?
~ Is this the same type of problem that Ginna experienced in 1982?
~ Who will pay for all the damage to personal property from this accident?
~ After cleaning up the radioactive waste from this accident, where does it all get sent? Has RGSE significantly added to the State's low-level waste crisis?
5-32
~ Why doesn't RGSE distribute potassium iodide to the publica...do RGSE people get it?
~ How close have you come to a meltdown' How do you know the extent of damage to the Ginna reactors 5-33
ATTACHMENT'4 SAMPLE "SPOUSE PHONE" QUESTIONS 0930 ~ This is Rick Watts's wife calling....do you have any information concerning a problem at Ginna? I just heard something on the radio about a fire.
1005 ~ Do you have any news on Ginna? My husband works in the warehouse....l don't want to bother him, but am just checking to see that everything's okay.
1015 ~ My husband works at Ginna, and is there now. He works in the Training Center (Jim Huff).
~ Has there been a fire?
~ Is it out yet?
~ Can I drive to the plant and drop off some sandwiches for Jim if he' got to stay overnight?
1045 ~ My sister called me this morning and said there was a problem at the plant, and said she'd keep me posted. I haven't heard anything from her for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
~ She said she might be sent to sent to work in the EOF. Is everyone there now?
~ Will the workers have to stay at the plant?
~ I need to get through to the EOF to ask her what arrangements I should make concerning her kids at day care...since I'm.at work. Her name is Barb Butler.
1100 ~ My son-in-law works at Ginna as a Trainer (Jim Knorr).
~ Where are the plant workers now... have they left the plant?
~ Is the plant under control now?
5-34
~ How long will the emergency last?
1115 ~ My father, Wesley Backus works in Operations at Ginna.
~ What's happening at the plant?
~ How bad is it?
~ Are the workers in danger? My father works around the back-up safety equipment.
~ 're Ginna employees allowed to call home?
~ If he can, have Wesley Backus call home so I can stop worrying.
1130 ~ My husband works in the Ginna Training Department. I can't reach him at Ginna. His name is Sam Poulton.
~ My neighbor told me there was a problem with an explosion at the plant, and that there's a fire too. Is that true?
~ Has everyone evacuated the plant?
~ Were any of the employees hurt?
~ How can I reach my husband? He's on blood pressure medication. I need to know he's all right.
1145 ~ This is Gail Beldue. My husband, Dick is either at Ginna Station or East Avenue today. I need to get a message to him. We live 3 miles from the plant and may need to evacuate.
~ Do you know for sure if residents will have to evacuate?
~ If we evacuate, tell Dick that I will go to my parents house.
~ Tell him I hope he's okay.
1200 ~ My wife is a secretary at Ginna Station, and I'e heard they'e had an emergency. How serious is it?
~ How long is this accident expected to go on?
~ Do you know if workers have evacuated the plant?
5-35
~ Are the workers all okay?
~ Can I pick my wife up? If so, where do I meet her?
1230 ~ My dad works at the plant..could you tell us what's happening?
5-36
SECT/ON 6. 0 SCHEDUCE OF EVENTS
1993 GINNA PLUME EXPOSURE PATHWAY EXERCISE SCHEDULE OF EVENTS DA TE TIME PERSONNEL GROUPS ACTIVITY 1 1/15 9-1030 AM ALL IEOFJ PLA YER BRIEFING 11-12 ALL (JENCJ PLA YER BRIEFING 3-4 PM ALL PLANT PLA VERS PLA YER IBROOKWOODJ BRIEFING 1 1/16 8-11 AM AS ASSIGNED CON TROLLER
/BROOK WOODJ BRIEFING 1-5 PM NRC TEAM BADGING IBROOKWOODJ BRIEFING 1 1/17 ALL 1993 EXERCISE 1 1/18 8-10 AM CONTROLLERS PRE-CRITIQUE IBROOKWOODJ MEETING 1 1/18 10-11 OPEN RGE CORPORA TE IBROOKWOODJ CRITIQUE 1 1/18 11-12 OPEN NRC CRITIQUE.
IBROOKWOODJ 1 1/19 8-12 AM FEMA/NYS/CO/RGE PRE-CRITIQUE MEETING (OFFSITE EXERCISE ACTIVITIESJ 1 1/19 OPEN FEMA CRITIQUE I89 EAST A VE BSMTJ 6-1
SECT/ON 7.0 EXERCISE SCENARIO
NARRATIVE
SUMMARY
The scenario begins with the R. E. Ginna Nuclear Power Plant operating at approximately 98% rated thermal power. The Plant has been operating at this power level continuously for approximately 180 days. Initial conditions of note are:
~ Offsite power 34.5 KV circuit 751 is out for pole replacement and cable repair due to a tractor trailer truck hitting a pole. Subsequently normal power was restored to buses 14 and 18 from offsite power 34.5 KV circuit 767.
~ The "B" Safety Injection Pump is held and disassembled because of high vibration on the pump's outboard bearing. The "B" Safety Injection Pump electrical breaker "b" contact has been jumpered.
~ "B" Charging Pump is held for plunger replacement and the maintenance is approximately 50%
completed.
~ Thermographic checks have detected a hot spot on Bus 14 Station Service Transformer.
~A0730 a loud bang is heard outside the Control Room door to the turbine building, and annunciator I-27 (ROTOR ECCENTRICITY OR VIBRATION) alarms almost immediately. An Auxiliary Operator sent out to check the turbine-generator reports that a turbine blade has penetrated the ¹2 LP turbine casing at its southeast corner and the turbine blade is lying by the Control Room door. An Alert is declared.
At 0805 a fire is detected in the Charging Pump Room. The fire brigade is activated. The "C" charging pump trips. Operators control pressurizer level and seal injection flow with the remaining charging pump. The fire is extinguished. There should be no change of emergency classification.
~A0810, a LOCA inside Containment occurs (with initial assumed leakage = 10,000 gpmi. All safeguards equipment operates normally except the "B" safety injection pump, which is out for corrective maintenance. A Si e Are Emer enc is declar At 1005 with the tripping of the 480-volt safeguards bus, ail safety injection to the core is terminated.
A General Emer enc is declared. This will warrant licensee-recommended protective actions.
At 1050 a release above Technical Specifications begins.
~At 250 the release is terminated and offsite radiological levels begin to decrease rapidly.
Recovery and re-entry discussions begin at a roxima el 1315 hrs.
The Exercise is terminated at approximately 1400-1500 hrs.
NOTE: 'An'::::ac uLaf,",:;shift:,:::::,ch~~ge$'of~,:.ksy:;;:,:EffO!::pasftj~anp~~wl!!porn'i vb'ei'ca'goIp'liteerd':::ib jr':.:Ajt'.:20~0vhrs 7-1
GINNA STATION 1993 EMERGENCY PREPAREDNESS EXERCISE INITIALCONDITIONS The R. E. Ginna Nuclear Power Plant is operating at approximately 98% rated thermal power. The Plant has been operating at this power level continuously for approximately 180 days.
Equilibrium primary Coolant Isotopic activity as of 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> (11/17/93) is provided in Table 9.2 of scenario section 9.3. Total activity is 2.56 Microcuries/Gram. Chemistry Log Sheet available from controller.
The Reactor Coolant'System (RCS) total leakage is 0.250 GPM as of 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> this morning. Identified RCS leakage is 0.092 GPM.
General Weather conditions are partly cloudy with no current precipitation . For purposes of the exercise, additional meteorological information in the simulator control room should be obtained from the plant process computer system (PPCS) ~
Offsite power 34.5 KV circuit 751 is out for pole replacement and cable repair due to a tractor trailer truck hitting a pole on Slocum Road North at 0600 this morning. The "A" emergency diesel generator started and energized safeguards buses 14 and 18. Subsequently, normal power was restored to buses 14 and 18 from offsite power 34.5 KV circuit 767 and the "A" emergency diesel generator was stopped and aligned for auto standby.
The "B" Safety Injection Pump is held because of high vibration on the pumps outboard bearing. The high vibration was detected yesterday (11/16/93) during the performance of PT-2.1Q (Safety Injection System Quarterly Test). The pump's outboard bearing is disassembled, cleaned and new bearings have been checked out of QA Storage. The pump is now awaiting re-assembly and an A-52.4 has been submitted for the "B" Safety Injection Pump. The "B" Safety Injection Pump electrical breaker "b" contact has been jumpered per EM-777 (MOV-871 and 871B Control Circuit Jumpers).
"B" Charging Pump is held for plunger replacement. The pump was held yesterday morning (11/16/93) at 0700 and the maintenance is approximately 50% completed.
A preventive maintenance analyst, while doing thermography on Bus 14 during the early morning hours, reports to the shift supervisor that he has found a hot spot on Bus 14 Station Service Transformer. He also informs the shift supervisor that he will talk to maintenance later this morning about planning a Bus 14 outage to check out the transformer.
7-2
GINNA STATION 1993 EMERGENCY PREPAREDNESS EXERCISE ONSITE SEQUENCE OF EVENTS APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION AND MESSAGE ¹ 0700 -00/1 5 Initial Conditions established
(¹1 C).
0715 00/00 Announcement to Commence Annual Emergency Exercise (¹1).
0730 + 00/1 5 A loud bang is heard outside the Control Room door to the turbine building and annunciator I-27 (ROTOR ECCENTRICITY OR VIBRATION). Alarms almost immediately (¹4).
ANTICIPATED RESULTS Con rol Room Operators should perform the actions of AR-I-27 and transition to AP-TURB.3 (Turbine Vibration) and perform the action of tripping the turbine as vibration on ¹6 bearing is higher than the trip criteria of 14 mils.
Operators transition to E-0 (Reactor Trip or Safety Injection) and perform the applicable actions and then transition to ES-0.1 (Reactor Trip Response) and perform its applicable actions.
Operators should send an auxiliary operator out to check the main turbine - generator (¹5).
7-3
APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION AND MESSAGE ¹ 0732 +00/17 Annunciator F-21 (COND Hl PRESS 20" Hg OR LOSS OF BOTH CIRC WTR PMPS) alarms and condenser vacuum is 19" Hg and decreasing (¹6).
ANTICIPATED RESULTS
~C Operators performing the applicable actions of ES-0.1 ~
0740 + 00/25 The Auxiliary Operator sent out to check the turbine-generator reports that a turbine blade has penetrated the ALERT ¹2 LP turbine casing at its southeast corner and the turbine blade is lying by the Control Room door (¹7) ~
ANTICIPATED RESULTS Control Room Operators performing the applicable actions of ES-0.1 (Reactor Trip Response).
Appropriate notifications should be made per EPIP 1-5.
If an ALERT is not declared in approximately 15 minutes, a contingency message should be given out to declare it
(¹9x) ~
7-4
APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION AND MESSAGE ¹ 0805 +00/50 Fire zone Z-01 (AUX BLDG 235-8 BSMT E. CHP ROOM)
Alarms (¹11).
ANTICIPATED RESULTS Control Room Operators should sound the fire alarm and activate the fire brigade per SC-3.1.1 (¹12).
Operators should inform the TSC of the Charging Pump Room fire alarm.
Operators should be transitioning to 0-2.2.
0807 +00/52 The "C" charging pump trips out. Annunciator G-25 (MOTOR OFF CTR SECT PMPS EXCEPT MAIN AND AUX FEED PMPS) alarms (¹13).
ANTICIPATED RESULTS Control Room Operators should control pressurizer level and seal injection flow with the remaining charging pump.
-0815 -+01/00 Fire Brigade captain, after arriving at the Charging Pump Room, reports that the fire appears to be on the "C" charging pump motor with much smoke present and they are fighting the fire (¹14).
ANTICIPATED RESULTS Control Room NOTE: Offsite fire fighting assistance is not participating.
if assistance is requested, controllers will intercede to prevent off-site fire department response.
Operators should be performing the applicable actions of 0-2.2 .
Operators should inform TSC of the fire on the "C" charging pump.
7-5
APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION AND MESSAGE ¹ TECHNICAL SUPPORT CENTER TSC should be assuming command and control at approximately this time.
TSC, when operational, should check into the loss of 34.5KV circuit 751 problem.
TSC, when operational, should evaluate the fire in the Charging Pump Room.
EMERGENCY OPERATIONS FACILITY EOF may be activating at this time due to plant conditions.
0825 + 01/10 Fire Brigade captain reports to the Control Room that the fire in the Charging Pump Room is extinguished and that it was on the "C" charging pump motor. He also reports that the "A" charging pump is running normal with no apparent damage from the fire (¹15).
ANTICIPATED RESULTS Control Room Operators should inform the,TSC of the fire being extinguished on the "C" charging pump and the condition of the "A" charging pump.
TECHNICAL SUPPORT CENTER TSC should re-evaluate the emergency classification per EPIP 1-0. There should be no change of emergency classification.
7-6
APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION AND MESSAGE ¹ 0910 +01/55 The following events occur simultaneously (¹21):
SITE AREA 'ressurizer level and pressure decreases uncontrollably.
EMERGENCY
' Safety Injection Actuation occurs automatically from pressurizer Lo pressure.
'ontainment pressure is increasing. ~
'afety Injection Flow is greater than 100 GPM.
'll safeguards equipment operates normally except the "B" safety injection pump. It is out for corrective maintenance.
ANTICIPATED RESULTS Control Room Operators perform the appropriate actions of E-0 (Reactor Trip or Safety Injection).
Operators should inform TSC of the loss of coolant accident.
Operators should transition to E-1 (Loss of Reactor or Secondary Coolant) and then to CR-FR-P.1 (Response to Imminent Pressurized Thermal Shock Condition) and then back to E-1 and start performing applicable actions.
TECHNICAL SUPPORT CENTER TSCjjho'ii!d:;:."dec!-'ri:'a',":"'TE~A'REA'::~EME GENC~Y",ii .
Evalii'atio'nj Sll,":.:t'ota!':::::f!oN::.';>."':.'l:00.':,::!6P M':,6i'ina!F4='824'/Fl-.',,826'Y wv YANCE: r5:cwk~xviicA+%cN446 u%xR:mÃwÃv4cwv'.GN 9? ~ AaFRSN>xA&vm+ "v~%rwM Appropriate notifications should be made per EPIP 1-5.
7-7
'PPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION AND MESSAGE ¹ TSC should be expediting the maintenance on the "B" safety injection pump.
If a Site Area Emergency is not declared in approximately 15 minutes, a contingency message should be given out to declare it (¹26x).
EOF should be activating at this time, if not done earlier.
0915 +02/00 The "B" RHR pump trips out, Annunciator J-9 is received in Control Room (¹23).
ANTICIPATED RESULTS Control Room Operators should try to restart the "8" RHR pump 5 times per AR-J-9. It will not restart.
Operators should notify an auxiliary operator to check the "B" RHR pump and motor. An auxiliary operator may already be in the Auxiliary Building per step 18C of E-1.
Operators should notify the TSC of the tripping and failure to restart of the "B" RHR pump.
Operators performing the applicable actions of E-1.
Technical Su ort Center TSC should send a team into Auxiliary Building to check out the "8" RHR pump trip problem if the auxiliary operator-not already in there.
7-8
APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION AND MESSAGE ¹ TSC should be evaluating the loss of safeguards equipment and be expediting repairs as quickly as possible.
TSC should be informing the EOF of plant status, actions being taken and any required needs.-
EMERGENCY OPERATIONS FACILITY EOF should be evaluating plant conditions and taking actions as required.
0920 +02/05 The "A" emergency diesel generator trips out.
Annunciator (J-24) is received in the Control Room
(¹24).
ANTICIPATED RESULTS Con rol Room Operators should send an auxiliary operator out to the "A" Emergency Diesel Generator Room to check the local alarm panel and the emergency diesel generator.
Operators should inform the TSC of the "A" emergency diesel generator tripping out.
0935 + 02/20 The auxiliary operator sent out to the "A" Emergency Diesel Generator Room to check the local alarm panel and the emergency diesel generator, reports to the Control Room/TSC that the local alarm panel indicates a "lube oil low pressure "alarm and there is a large amount of oil on the floor by the large lube oil filter on-the east side of engine, and the engine oil level is extremely low (¹25).
ANTICIPATED RESULTS
~C Operators should inform TSC of the "A" emergency diesel generator problem.
7-9
APPROPRIATE SCENARIO
'IME TIIVIE 'VENT DESCRIPTION AND MESSAGE ¹ TECHNICAL SUPPORT CENTER TSC should send a repair team out to evaluate and repair the "A" emergency diesel generator problem.
0950 +02/35 Radiation levels start to increase slowly in the Auxiliary Building (¹30).
ANTICIPATED RESULTS Room 'ontrol Operators performing the applicable actions of the E-1 (Loss of Reactor or Secondary Coolant).
Operators should inform the TSC of increasing radiation levels in the Auxiliary Building.
TECHNICAL SUPPORT CENTER TSC should be evaluating plant conditions and taking actions where required.
TSC should be informing the EOF of plant status, actions being taken and any required needs, TSC should be evaluating the increase of radiation in the Auxiliary Building as to its source and its effect on the personnel in the Auxiliary Building.
EMERGENCY OPERATIONS FACILITY EOF should be evaluating plant conditions and taking action as required.
EOF Dose Assessment should be evaluating the increasing radiation levels in the Auxiliary Building.
REPAIR TEAMS Performing actions as required to return equipment to service as soon as possible.
7-10
APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION AND MESSAGE ¹ 1000 + 02/45 The auxiliary operator and/or TSC team in the Auxiliary Building to check the Auxiliary Building Sub Basement per step 18C of E-1 and the "B" RHR pump trip problem reports to the TSC/Control Room that the "B" RHR pump motor has a burned insulation smell and it is hot to the touch. He/they also report(s) that while in the Auxiliary Building Sub Basement, he/they observed a small amount of water dripping from the large pipe between Containment and MOV--850A. He/they also report(s) that after closer inspection of the dripping water, he/they observed what looked like a three (3) inch long crack at the bottom of the pipe. He/they also inform the TSC/Control Room that they are evacuating the Auxiliary Building as radiation levels have started to increase.
(¹22,31).
ANTICIPATED RESULTS C R If the Control Room is informed, the operators should inform the TSC of observed dripping water and crack on the pipe between Containment and MOV-850A.
Operators performing the applicable actions of E-1 (Loss of Reactor or Secondary Coolant) ~
When TSC requests Control Room to close MOV-851A, Control Room should request TSC to send a team into the Auxiliary Building to turn the breaker on for MOV-851A as it is turned off during operations.
NOTE: If breaker is urned on rior to Bus 14 tri in he breaker will tri as the valve comes off i s back seat.
TECHNI AL SUPPORT CENTER TSC should be evaluating the dripping and cracked pipe and request Control Room to close MOV-851A to isolate the leak from Containment.
TSC should be evaluating the increasing radiation levels in the Auxiliary Building and possibly evacuate the Auxiliary Building.
7-1 1
APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION AND MESSA E ¹
. TSC should be evaluating plant conditions and taking actions where required.
TSC should be informing the EOF of plant status, actions being taken and any required needs.
EMERGENCY OPERATIONS FACILITY EOF should be evaluating the increasing radiation levels in the Auxiliary Building and taking action as required.
1005 + 02/50 Repair Team sent out to check the "A" emergency diesel generator problem reports that a gasket has blown out on the lube oil line between the engine lube oil pump and the large lube oil filter. They estimate it will take approximately two and one half hours to repair and refill the engine with oil.
ANTICIPATED RESULTS TECHNICAL SUPPORT CENTER TSC should inform the "A" emergency diesel generator repair team to expedite repairs.
TSC should inform the EOF of The "A" emergency diesel generator problem and the estimated repair time.
EMERGENCY OPERATIONS FACILITY EOF should be assuming command and control at approximately this time. Preparations for an actual shift change of key ERO personnel will begin shortly after EOF assumes command and control.
1005 +02/50 480 Volt.safeguards Bus 14, trips out. Annunciators (J-GENERAL 29, J-7, J-9) alarm. All safety injection to the core is EMERGENCY terminated (¹33).
7-1 2
APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION AND IVIESSAGE ¹ ANTICIPATED RESULTS Con rol R om Operators should inform the TSC immediately of the loss of Bus 14 and safety injection to the core.
Operators should try to start the "C" S.l. Pump on Bus
- 16. If they do, the breaker will not close. They may also transfer the "B" instrument bus to maintenance supply.
TECHNICAL SUPPORT CENTER TSC should inform the EOF of the loss of Bus 14 and safety injection to the core.
TSC should be evaluating the time to core uncovery and request that the EOF also evaluate this time projection.
TSC may send a team into the Auxiliary Building to turn on the breaker for MOV-851A.
TSC may send a team into the Auxiliary Building to check on the loss of Bus 14.
TSC should try to expedite the repair of the "A" emergency diesel generator.
f<'OC'A.".";lldentifi'e'diijn'si'de!C the',.RCS~
TSC should be evaluating possible methods of water injection to the core, such as cross-tying Bus 14 and Bus 16 or using the "B" reactor coolant drain tank pump. If TSC decides to cross-tie the Buses 14-16, one of two tie-breakers will not close. If TSC decides to use the "B" reactor coolant drain tank pump, the suction strainer will plug after approximately 2 minutes of operation and will have to be cleaned prior to any further use (¹33).
7-13
APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION AND MESSAGE ¹ EMERGENCY OPERATIONS FACILITY ga",~~~g~~~c'4'.~wxMC~t'pw't'j sf'wgc'ip.'xr wpaeYM~xDYpceat ates'. Ys +ox<~~<'~iwtara+Yceot %'i~sr Mpx+ttwMpw
~v'F,"'.":,':a'I'tejgevaju8t~ng)Piiqt,:,:.cori'!'tiogs"',:::Pooulo~'aeclsar8:.,"8
'GENE.'K!EMER E "::iri~',ai:"jord Rieec'terr'Coofa'NMTai~n" I'n'o!ECCS::;,'deiftre ray!to;:,.the'!RCSjt%I Appropriate notification should be made per EPIP 1-5.
EOF should be making immediate Protective Action Recommendations in accordance with EPIP 2-1, "Protective Action Recommendations".
If a GENERAL EMERGENCY not declared in approximately 15 minutes, a contingency message should be given out to declare it (¹42x).
REPAIR TEAMS Performing actions as required to return equipment to service as soon as possible.
~ 1015 ~ 03/00 Core exit thermocouples and R-29, R-30 start increasing and RVLIS starts decreasing (¹41).
ANTICIPATED RESULTS Control Room Operators should inform the TSC of the increasing core exit thermocouples, the increasing radiation in Containment, and the decreasing RVLIS.
Operators should perform the applicable actions of CR-FR-C.1 (Response to Inadequate Core Cooling) when required.
TECHNICAL SUPPORT CENTER TSC should be evaluating plant status and taking actions as required.
TSC should inform the EOF of the increasing core exit thermocouples, the increasing radiation in Containment, 7-14
APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION AND MESSAGE ¹ and the decreasing RVLIS.
TSC should inform the EOF of the general plant status, actions being taken and need required.
TSC may realize by this time that in order to recover core cooling, they will need to complete repairs on the "A" emergency diesel generator, tie it into Bus 14, and start all available safety injection pumps, even though they may not be completely sure of why Bus 14 tripped out.
The thermography report given in the initial conditions should give them confidence that the problem is in the transformer connections and not the Bus.
TSC should also realize that once they energize Bus 14, MCC-1C will be energized and they can now close MOV-851A when the breaker's AC power is turned on, thus terminating the radioactive leak source from Containment to the Auxiliary Building.
TSC may also evaluate the possibility of back feeding Bus 14 from Bus 13 using the 14-13 breaker.
EMERGENCY OPERATIONS FACILITY EOF evaluating plant status and taking action as required.
1050 + 03/35 Radiation levels increase substantially in the Auxiliary Building, This is due to the leaking pipe between Containment and MOV-850A opening up where the crack
.AW~~C)~~WRNMCAV~. N(~yVP~Q~Pi" ~~pi"'j fh~g(~AWAV'~~AVg~
is. A".i'i.-'issue ~86ovi:;:i:'e'cn'riicai::S- e'eitic5tiorie".:be iris ANTICIPATED RESULTS Control Room Operators may transition to ECA-1.1 (Loss of Emergency Coolant Recirculation) due to loss of both RHR pumps.
TECHNI AL SUPPORT CENTE TSC should be expediting the turning on of the AC power breaker to MOV-851A.
7-1 5
APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION AND MESSAGE ¹ TSC should be expediting the recovery of AC power to Bus 14.
TSC should inform the EOF of the increased radiation levels in the Auxiliary Building.
TSC should inform the EOF of plant status, actions being taken, and needs required.
EMERGENCY OPERATION FACILITY EOF should be evaluating plant conditions and taking actions as required.
EOF Dose Assessment should be evaluating the plant vent release and making protective action recommendations to the Recovery Manager.
The EOF/Recovery Manager, after evaluating the EOF Dose Assessment recommendations, should recommend protective actions to offsite agencies as required.
REPAIR TEAMS Repair teams should be expediting repairs as conditions permit.
1100 +03/45 Annunciator L-10 (AUX BLDG SUMP PUMP AUTO START) Alarms (¹46).
ANTICIPATED RESULTS Control Room Operators should perform the applicable actions of AR-L-10.
Operators should inform the TSC of the operation of the Auxiliary Building sump pump.
TECHNICAL SUPPORT CENTER TSC should evaluate the Auxiliary Building sump pump operation and the possibility of the leak in the pipe 7-1 6
APPROPRIATE SCENARIO TIME 'IME EVENT DESCRIPTION AND MES AGE ¹ between Containment and MOV-850A getting worse.
EMERGENCY OPERATIONS FACILITY EOF evaluating plant status and taking actions as required.
1110 +03/55 Annunciator L-10 (AUX BLDG SUMP PUMP AUTO START) Alarms (¹47).
ANTICIPATED RESULTS Control Room Operators should perform the applicable actions of AR-L-10.
Operators should inform the TSC of the operation of the Auxiliary Building sump pump, Operators should be performing the applicable actions of FR-C.1 (Response to Inadequate Core Cooling). When they attempt to start the RCP's they trip out immediately.
TECHNICAL SUPPORT CENTER TSC should be evaluating the plant status and taking actions as required.
1120 +04/05 Annunciator L-10 (AUX BLDG SUMP PUMP AUTO START) Alarms (¹49).
ANTICIPATED RESULTS Control Room Operators should perform applicable actions of AR-L-10.
Operators should be performing the applicable actions of FR-C.1 (Response to Inadequate Core Cooling).
7-1 7
APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION AND ME SAGE ¹ 1125 + 04/10 Power Control informs the Control Room that offsite 34.5KV circuit 751 is ready to be restored to service
(¹50).
ANTICIPATED RESULTS Con rol Room Operators should inform the TSC that circuit 751 is ready to be restored to service.
Operators should, if directed by the TSC, restore circuit 751 to service per 0-6.9.2 .
1130 + 04/1 5 Annunciator L-10 (AUX BLDG SUMP PUMP AUTO START) Alarm (¹51).
ANTICIPATED RESULTS Control Room Operators should perform the applicable actions of AR-L-10.
Operators should be performing the applicable actions of FR-C.1 (Response to Inadequate Core Cooling).
TECHNICAL SUPPORT CENTER TSC should be expediting the return of the "A" emergency diesel generator to service.
EMERGENCY OPERATIONS FACILITY EOF Dose Assessment should be evaluating the release from the plant vent and making protective action recommendations to the Recovery Manager as necessary.
The Recovery Manager, after evaluating the EOF Dose Assessment recommendations, should make protective action recommendations to offsite agencies as neccessary.
7-1 8
APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION AND ME AGE '¹ 1140 +04/25 Annunciator L-10 (AUX BLDG SUMP PUMP AUTO START) Alarms (¹52).
ANTICIPATED RESULTS
~R Operators should be performing the applicable actions of AR-L-10 1145 + 04/30 Repair Team working on the "A" emergency diesel generator reports to the TSC that the emergency diesel generator repairs should be completed in approximately fifteen minutes (¹53).
ANTICIPATED RESULTS TECHNICAL SUPPORT CENTER TSC should be planning the recovery of core cooling and the termination of the release from the Auxiliary Building when the "A" emergency diesel generator is returned to service.
TSC should request operations to check the "A" emergency diesel generator line-up as much as they can to expedite the return to service of the D/G, TSC should inform the EOF of the estimated time that the "A" emergency diesel generator will be ready for return to service.
1150 +04/35 Annunciator L-10 (AUX BLDG SUMP PUMP AUTO START) Alarms (¹54).
ANTICIPATED RESULTS
~R' R Operators should perform the applicable actions of AR-L-10.
7-19
'APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION AND MESSAGE ¹ 1155 +04/40 Repair Team working on the "A" emergency diesel generator reports to the TSC that it is ready to be returned to service (¹55) ~
ANTICIPATED RESULTS Con rol Room Operators, when requested by the TSC, should line up the "A" emergency diesel generator per T-27.1 (¹56).
Operators should be performing the applicable actions of FR-C.1 (Response to Inadequate Core Cooling).
TECHNICAL SUPPORT ENTER TSC should request that the Control Room have the "A" emergency diesel generator lined up for normal operation and to allow it to tie into Bus 14.
TSC should inform the Control Room to start all safety injection pumps and Containment recirc fans available as soon as Bus 14 is energized by the "A" emergency diesel generator.
TSC should inform the Control Room to close MOV-851A as soon as MCC-C is energized if MOV-851A AC ower breaker was urned on.
1200 +04/45 Annunciator L-10 (AUX BLDG SUMP PUMP START)
Alarms (¹57).
ANTICIPATED RESULTS Con rol Room Operators should be performing the applicable actions of AR-L-10.
7-20
APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION AND MESSAGE ¹ 1210 + 04/55 Annunciator L-10 (AUX BLDG SUMP PUMP AUTO START) Alarms (¹58).
ANTICIPATED RESULTS Control Room 1215 + 05/00 Operators should be performing the applicable actions of AR-L-10.
Auxiliary Operator lining up the "A" Emergency Diesel Generator informs the Control Room/TSC that the "A" emergency diesel generator is lined up per T-27.1 (¹59).
ANTICIPATED RESULTS Control Room Operators should start the "A" diesel generator and ensure it ties into Bus 14.
Operators should start the "A" and "C" safety injection pumps, the "A" RHR pump and the "A" and "D" Containment recirc fan coolers. All equipment starts except the "C" safety injection pump (burned out motor).
Operators should attempt closure of MOV-851A, if the AC power to the breaker has been previously turned on.
If the AC power to the breaker has been previously turned on then. the value will come off its back seat and the breaker will trip out. Indication of this will be, mid-position indication of value will not change. If the AC power to the breaker has not been turned on then no valve closure should be attempted at this time.
Operators should inform the TSC of S.l. pumps and Containment recirc fan coolers starting.
Operators should inform TSC of MOV-851A failure to close if the AC power was previously turned on to the breaker.
7-21
APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION AND MESSAGE ¹ Operators should be performing the applicable actions of FR-C.1 (Response to Inadequate Core Cooling and then return to E-1 (Loss of Reactor or Secondary Coolant).
TECHNICAL SUPPORT ENTER TSC should send a team into the Auxiliary Building to turn on the AC power to MOV-851A. If the AC power to the valve breaker had been turned on previously, the TSC may send an electrician with this team to check the breaker (¹60) ~
TSC should be evaluating plant conditions, checking on progress of repair teams and taking action as required.
TSC should be informing the EOF of plant status and actions being taken for plant recovery.
EMERGENCY OPERATIONS FACILITY EOF should be evaluating plant conditions and taking actions as required.
EOF should be requesting the Engineering Support Center to perform a core damage assessment.
EOF Dose Assessment should be tracking the release plume.
The Recovery Manager, after evaluating the EOF Dose Assessment recommendations, should update protective action recommendations to offsite agencies as required.
io'm'p'lii'i'iikby".:.":~ppiox'imit'ety)thi~::xiii'i'y".
REPAIR TEAMS Repair Teams should be expediting repairs as conditions permit.
1220 + 05/05 Annunciator L-10 (AUX BLDG SUMP PUMP AUTO START) Alarms (¹61).
7-22
APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION AND MESSAGE ¹ ANTICIPATED RESULTS Control Room Operators should be performing the applicable actions of AR-L-1 0.
Operators should be performing the applicable actions of E-1 (Loss of Reactor or Secondary Coolant).
1235 +05/20 Annunciator L-10 (AUX BLDG SUMP PUMP AUTO START) Alarms (¹63).
Plant vent reading are decreasing due to Containment pressure reduction, reducing the leak out of the pipe between MOV-850A and Containment and also due to the resumption of core cooling reducing the radiation levels in Containment (¹65) ~
ANTICIPATED RESULTS Con rol Room Operators should be performing the applicable actions of AR-L-10.
Operators should be performing applicable actions of E-1 (Loss of Reactor or Secondary Coolant).
Operators may realize, at this time, that the Auxiliary Building sump pump operation interval is increasing and should inform the TSC of this.
TECHNICAL SUPPORT CENTER TSC should be expediting sending a team into Auxiliary Building to check and/or turn on the AC power breaker for MOV-851A.
TSC should be evaluating plant status and taking action as required.
7-23
APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTI N AND MES AGE ¹ TSC may be evaluating the Auxiliary Building sump pump down interval change.
TSC should be informing the EOF of plant status and actions being taken for plant recovery.
EMERGENCY OPERATIONS FACILITY EGF should be evaluating plant conditions as required.
EOF Dose Assessment should be tracking the release plume and coordinating/recommending protective action recommendations to the Recovery Manager.
The Recovery Manager, after evaluating the EOF Dose Assessment recommendations, should update protective action recommendations to offsite agencies as required.
REPAIR TEAMS Repair Teams should be expediting repairs as conditions permit.
1245 +05/30 The team sent into the Auxiliary Building to check and/or turn on the AC power breaker for MOV-851A reports the following, de endin on he si uation:
If the AC power breaker for MOV-851A ~wae no previously turned on, then the team will turn it on and report this to the TSC.
If the AC power breaker for MOV-851A was previously turned on and then tripped, the team will report their findings to the TSC and await. further instruction. After evaluation the TSC should request the breaker be reset and turned on. This should be done by the team (¹60).
ANTICIPATED RESULTS Control Room Operators should close MOV-851A when requested by the TSC. MOV-851A will be considered closed at 1250 hours0.0145 days <br />0.347 hours <br />0.00207 weeks <br />4.75625e-4 months <br />, isolating the leak on the pipe between CV and 7-24
APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION AND MESSAGE ¹ MOV-850A. NOTE: MOV-851A will be con i ered clo 1250 h rs for cen ri ur ose .
Operators should inform the TSC of MOV-851A closure.
TECHNICAL'UPPORT CENTER If the as power breaker for MOV-851A was previously turned on and then tripped, TSC should evaluate this and most probably decide the following: the breaker could have tripped starting the closing cycle of the valve due to not being operated for a long period of time, or the breaker may not have been completely reset the first time by the Auxiliary Operator. Based on the above and the emergency conditions that exists, the TSC should have the. team reset and turn on the breaker for MOV-851A and then request the Control Room close MOV-851A.
If the AC power breaker for MOV-851A ~wae no previously turned on, TSC will request the Control Room to close MOV-851A.
1300 + 05/45 With the leak from Containment isolated, the Auxiliary Building sump pump is no longer operating at short intervals and the plant vent radiation readings are beginning to decrease significantly (¹65).
ANTICIPATED RESULTS Control Room Operators should be performing the applicable actions of E-1 (Loss of Reactor or Secondary Coolant).
TECHNICAL SUPPORT CENTER TSC should inform the EOF of the closure of MOV-851A and the decreasing plant vent radiation readings.
TSC evaluating plant conditions and taking action as required.
TSC should be checking on progress of repair teams.
7-25
APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION AND MESSAGE ¹ TSC should be informing the EOF of plant status and actions being taken for plant recovery.
EMERGENCY OPERATIONS FACILITY EOF should be evaluating plant conditions and taking actions as required.
EOF Dose Assessment should be tracking the release plume and coordinating/recommending protective action recommendations to the Recovery Manager.
The Recovery Manager, after evaluating the EOF Dose Assessment recommendations, should update protective action recommendations to offsite agencies as required.
REPAIR TEAMS Repair teams should be expediting repairs as conditions permit.
~ 1315 + ~06/00 Recovery/Re-entry discussions may commence. This should include preliminary discussions about short term and intermediate term concerns, including preliminary designation of the recovery organization.
State and counties may also conduct parallel discussions.
Recovery/Re-entry interface between TSC/EOF and offsite agencies should be demonstrated as time allows.
After all exercise objectives have been demonstrated, the
~1400-1500 + ~06/45- exercise will be terminated.
07/45 7-26
0 SEC TION 8. 0 MESSAGE FORMS AND PlANT DA TA SHEETS
MINISCENARIOS (1) "B" Safety Injection- pump outboard pump bearing replacement, 0715 Hours (2) "B" Charging pump plunger replacement, 0715 Hours mechanics .
(3) Checking Turbine Generator noise and vibration problem, 0730 Hours auxiliar
~oerator (4) Charging Pump Room fire, 0805 Hours fire bri ade .
(5) "C" Charging pump fire repair, 0825 Hours mechanics electricians and !8 C .
(6) Checking AuxiliaryBuilding sub-basement for RHR system leakage per E-1 and "B" RHR pump trip problem, 0910 Hours auxiliar o erator TSC team (7) Checking "A " emergency diesel generatorlocal alarm panel and the Emergency Diesel Generator, 0920 Hours auxiliar o erator .
(8) "A" emergency diesel generator problem, 0935 Hours i e fitters and
""'"'**I.
(9) Checking Bus 14 tripping out problem, 1005 Hours electricians .
t (10J Checking "Cts Safety Injection pump breaker on Bus 16 problem, 1005 Hours alii*i (11J Turning on AC power breaker for MOV-851A, 1005 Hours auxiliar o erator TSC team.
(12) Bus 14-16 cross-tie breaker problem, 1005 Hours electricians .
(13) Possible back feeding Bus 14 from,Bus 13 using 14-13 tie-breaker problem, 1005 Hours electricians .
f14J Possible line up of the "B"RCDT pump to CNNT sump "B" or the RWST, 1005 Hours TSC Control Room and auxiliar o erator .
(15) Cleaning the "Bts RCDT pump suction strainer, 1005 Hours i efitter .
(16) Line up of "A emergency diesel generator per ts T-27. 1, 1155 Hours Auxiliar
~oerator (17) Check andlor turn on the AC power breaker for MOV-851A, 1215 Hours auxiliar o erator and or electrician .
CONTROLLERS FOR MINI-SCENARIOS A. AUXILIARYOPERA TOR CONTROLLERS
- 1. 0730: Checking Turbine-Generator for noise and vibration problem.
- 2. 0910: Checking AuxiliaryBuilding sub-basement for RHR system leakage per E-1 and "B" RHR pump trip problem.
- 3. 0920: Checking "A "Emergency Diesel Generator Loca/A/arm Panel and the Emergency Diesel Generator.
- 4. 1005. Turning on AC power breaker for MOV-851A.
- 6. 1 155: Line-up of the "A "Emergency Diesel Generator per T-27. 1.
- 7. 1215: Check and/or turn on the AC power breaker for MOV-851A fan electrician may be involved also).
B. ELECTRICIANS CONTROLLERS
- 1. 0825: "C" Charging pump fire repair.
- 2. 1005: Checking Bus 14 tripping out problem.
- 3. 1005: Checking "C" Safety Injection Pump failure to start on Bus 14 and 16 problem.
- 4. 1005: Bus 14-16 cross-tie breaker problem.
- 5. 1005: Possible backfeeding Bus 14 from Bus 13 using 14-13 tie breaker problem.
- 6. 1215: Check andlor turn on the A C power breaker for MOV-851A (An Auxiliar 0 erator ma be involved also .
C. MECHANICS CONTROLLERS
- 1. 0715: "B" Safety Injection Pump outboard bearing repair.
- 2. 0715: "B" Charging Pump plunger replacement.
- 3. 0825: "C" Charging Pump fire repair.
- 4. 0935: "A" Emergency Diesel Generator Repair.
D. I AND C CONTROLLER
- 1. 0825: "C" Charging Pump fire repair.
E. FIRE BRIGADE CONTROLLERS
- 1. 0805: Charging Pump room fire.
F.. PIPE FITTER CONTROLLERS
- 1. 0935: "A" Emergency Diesel Generator problem.
- 2. 1005: Cleaning of "B" RCDT suction strainers.
Time 0700 Message: IC GINNA STATION 1993 EVALUATED EXERCI E MESSAGE FORM Si I <<C << IR Simulated Plant Conditions; See the Attached Sheets
~essa<ee: """THIS IS AN EXERCISE" >>"
FOR CONTROLLER USE ONLY Controller Notes:
- 1) Review initial conditions and Plant Status Sheets with the Exercise operating crew.
- 2) Review Exercise precautions/limitations and any Exercise activities that are normal (pre-staging, simulated notifications, extent of participation of offsite agencies, etc.).
- 3) Ensure that the operating crew understands that the Exercise is not to interfere with safe plant operations.
- 4) Explain that abbreviation "OOS" means "out of service," i.e. repairs must be made before the equipment can be used.
Antici ated Resul s:
- 1) Participants should review conditions, plant data, and other procedures as applicable.
GINNA STATION 1993 EMERGENCY PREPAREDNESS EXERCISE INITIALCONDITIONS The R. E. Ginna Nuclear Power Plant is operating at approximately 98% rated thermal power. The Plant has been operating at this power level continuously for approximately 180 days.
Equilibrium primary coolant isotopic activity as of 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> (11/17/93) is provided in table 9.2 of Scenario Section 9.3 . Total activity is 2.56 microcuries/gram. Chemistry log sheet available from controller.
The Reactor Coolant System (RCS) total leakage is 0.250 gpm as of 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> this morning. Identified RCS leakage is 0.092 gpm.
General weather conditions are partly cloudy with no current precipitation. For purposes of the Exercise, additional meteorological information in the Simulator Control Room should be obtained from the Plant Process Computer System (PPCS).
Offsite power 34.5 kv circuit 751 is out for pole replacement and cable repair due to a tractor trailer truck hitting a pole on Slocum Road, north at 0600 this morning. The "A" Emergency Diesel Generator started and energized safeguards buses 14 and 18. Subsequently normal power was restored to buses 14 and 18 from offsite power 34.5 kv circuit 767 stopped and aligned for auto standby.
The "B" Safety Injection Pump is held because of high vibration on the pumps outboard bearing. The high vibration was detected yesterday (11/16/93) during the performance of PT-2.1Q (Safety Injection System Quarterly Test). The pumps outboard bearing is disassembled, cleaned and new bearings have been checked out of a QA storage. The pump is now awaiting re-assembly. An A-52.4 has been submitted for the'"B" Safety Injection Pump. The "B" Safety Injection Pump electrical breaker "b" contact has been jumped per EM-777 (MOV-871 and 871B Control Circuit Jumpers).
"B" Charging Pump is held for plunger replacement. The pump was held yesterday morning'11/16/93) at 0700 and the maintenance is approximately 50% completed.
A preventive maintenance analyst, while doing thermography on Bus 14 during the early morning hours, reports to the shift supervisor that he has found a hot spot on Bus 14 station service transformer. He also informs the Shift Supervisor that he will talk to maintenance later this morning about planning a Bus 14 outage to check out the transformer.
1993 EVALUATED EXERCISE Time: fgbb 0+fg sh'z87 MAJOR PARAMETER ENGINEERED 8AFEGUARDS Reactor'hutdown YES 0 Hi h Head S.I. Pum s N-31 N-32
~CPS o CPS FI-924 ~GPM FI-925 ~> GPM N-35 8~-0 AMPS 1A. INS RV TB OOS N-36 AMPS 1B. INSERV STBY Avg. Nuclear Power ~ I 1C. INSE V TB OOS RCS Pressure ZZ PSIG BAST Level =
PRZR Level ~ 2 B
1A RCP'UNNIN A RCP S/G Level UNNIN STOPPED
/STOPPED Low Head FI-626 1A. INSERV 8.
0
. Pum s TB G M OOS REC RC 1B S/G Level 1B. INSE V B OOS RECI C 1A S/G Pressure ~O~PSIG RWST Level = ~~~4 1B S/G Pressure PSIG Turbine/Generator ONLIN OFFLINE Containment 8 ra Pum s 4 KV Buses NERG D DEENERGIZED FI-931A~GPM 480V Buses ZE DEENERGIZED FI-931B~GP DC Batteries AQgVOLTS BQgUOLTS 1A. NSE U TB OOS Cnmt Pressure ~2. PSIG 1B. INSERV T OOS Cnmt Sump A Level Cnmt Sump B Level
~ 0 FEET INCHES NaOH Tank Level = ~%
" Loop Hot Leg 0. 'F Containment Recirc Fans A Loop Cold Leg &~2- 'F 1A. SER STB OOS Loop Hot Leg ~O~QF 1B NSERV STBY OOS 1'N B
B Loop Cold Leg ~ QF 1C. INSER S OOS RVLIS .l ERV TB OOS
- CET ~~QF Post Accident Dampers OPEN CLOSED S/G A Total Aux Flow S/G B Total Aux FW FW Flow ~C7 GPM GPM Service W .Pum s 1A. NSER STBY OOS DIESEL GENERATORS 1B. I SER STBY 0 S 1C. INSER STBY OOS A. RUNNING UNLOADED TB OOS 1D. INSERU TB OOS B. RUNNING UNLOADED TBY OOS A&B Header Pressure PSIG TSC RUNNING ED OOS Security RUNN UNLOADED B OOS Com onen colin Water Pum s lA. INSER STBY 00 ENGINEERED SAP DS 1B INSERV TB OOS Surge Tank Level =
Aux. Feedwate um s 1A. INSERV OOS 8tandb Aux. Feedwater Pum s 1B. INSERV TB OOS 1C. INS V TB 00 Turb. Driven CST Level ~0 INSERV TB FEET OOS 1D. INSERV B OOS
- CET = Average of-Selected Core Exit Thermocouples gled CF/~+Gi+6 /GYPS gZ Sq~q>>S "g',8~gWg Pmp A'S:Lcm'
t(QV 17) 1'993 Oa'" R. E..'i~iA S! t(ULATOR PAGE TRitlD CROUP ASSIGN",Ft(T S)JtWARY GR):"'P: EVENT! PROCEDORc: EPIP 1-5 PLANT STATUS POINT ID DESCRIPT I 0)J VALUE DUAL E. U.
1 A~)AS 2! '"!'ATED TRANSIEt)) M/0 SCRAJt ti'0 AThS 6009 2 RXT P A TD< TriP "PEA)(ii STATUS NGT TP IP 6009 3 N31 SQB E RANGE DETECTG)', ll.";! !.00000+00 It<HB CPS 4 N32 SDURCF RANGE DETECTOR )Y- 2 :.00000+00 INHB CPS 5 ti'35 It)TTciRNEDIATE RANGE DETECTOR N-35 8.12829-04 !NHB A!(P 6 N35 INTERt)ED I ATE RANGE DETECTOR N-36 8. 12829-04 INHB ANP 7 NP AVERACi tlL'CLEAR PONER 98.08 GOOD 0/
8 PRCS REACTOR COOLANT SYSTEt) AVG PRESS 2248. 6009 PSIG a c(~
LPIR cgcoc)loT7EA g)J+c)Gc )
4S,2 6009 /
10 FRY A GP ANT LGDP A AVG FLG)! 98.1 GOOD I/
FRCLB Ri~)C< ~00'NT iu"= = ..<6 F'N 97.3 C~ZD /
12 RXT16 RCPA BRiAXER WdJSE RX TRIP NO) TRIP 6009 RXT!7 RCPB EREAXER CAU)-"w RX TRIP NGT TRIP 6009 TiSUBTC I tÃJRE TC UBCOGLED "AS@IN 47.4 GDD>>
P%
LSGA ST(') GEN A t(ARRQ)t RANGE AVG LEVEL 52.1 G009 LSGB STt( GEN B NARRGN RANGE AVG LEVEL 52.1 6009 /
ST):- .=( A AVciRASE PRES%RE 701. GOOD PSIG 18 PSGB Sit =='-' 4)JERASE PRESSURi 701. GGQD PSIG GENS( P Gitt)i-"RATGR ON Lit(i:".".i-'XER !G!372 t61 TRIP C<09 20 BSR2 6":tFRATOR ON LINE BFEAXER 9X!372 NG: TRIP 6009
)1 BUS!!A BUS !!A SUPPLY BP)FAKER tl01 TRIP 6009 B)JS1!B BU" llB SUPPLY BREAKER NOT TRIP 6009 23 BUS!2A NGT TERNIhATED DN PPCS (7/!9/91) tlDT TRIP DEL BUS!2B )
tlQT ER~))IhATED ON PPCS (7/19/91) NOT TRIP DEL Bi!A!2A BUS l!A TQ 12A TIE ERE)NER TRIPPED 6009 81!PI TPIFFiD 6009 PCV cga)l) qgii+i )i) AV)'RAEc cc cSUcc .24 6009 PSIG 2S LSIU. /PA CcYA;'(Nit(T S')t')P t! gv=".AEE LEVEL 2.0 6009 FiET L0942i SL~~c .""
LEUcL 8 ItiCHES (TRAIN A) LG~~R GGGD L0943E cLt~i ." EV:-L 8 INCH"S (TRA!t( 9)
LG'r)ER 6049
) PA4oD 8) ~ 8 LEVE) 78I:KHci(TRAltl A) LOPER 6009 L0943D SU."" "
LEVEL 7S It(C))ES (Kit)t B) LOW""R G009 L09420 .- LEVc 113 tlCHES(TRAIN A) LOVER GGDB 3- LO943C SL')'-' LEVil. 113 lt(CHES(TRA!N B) LO)tiR GD09 L0942B ":.':;~,"-. 'VEL 180 I NCH=6(TRAIN A) LONER 6009)
L0943B St! c "=
LEVc'80 INCHES(TRAItl B) LO)(ER GGGD 37 LP942A LO)liR 6009 38 L0943A c)J~:" LE()EL 214 IN'.HES(TRAIN B) LSliP 6009 3o T0409A R".L>>'. HGT LEG TEt& RATL'."= 60!.1 C~ZD DEGF 40 T04!OA P;L: HGT LEG TE)(PERATLr 601.1 "6009 DcGF 41 T0450 W). '-'OLD LEG TEhPiRATURE 44.2 6009 DcGF JA
'i R'B COLD LEG TEtiPERATL-":.E 544.1 6009 DEGF
)045'AV)GA)AID R L-'AVG (THGT/TCGLD lilDi RNG) 572.7 GOOD DEGF 4w TAVGBt'I0 .'-
)AVG (Tb')T/;COLD ViIDi Rh6)
RC 572,5 G009 DEGF LRV Ri-'."'.:;9 V SSEL AVERAGE LEVEL 99.1 6009 /
46 TCCDRE iii! 1)SCORE TC AVcRAS= TEtLP - 600,6 600>> D" 6F FAUXFWA S/6 .-'GTA'UX XFii:CATcR F 0,( 0, Gl)09 GPN 48 FAUXFWB S/6 ":OTA) PJX FEEDVATcER FLGN 0. GCCD GPtt
))o BNR081 ~i"" "'XILIPRY FE~t'4))".T""R PUt(c A 0 F 6009 y BXR082 t')TR P~";ILIARY FEEDAATER PUk" B OFF 6009 51 voAD c" "..-i rUt(P )cNi SL)P ) Y VALV" A CLOSED G009 V3504 AU! c) oUK~ STEAN SUPPLY VALVi B CLOSED GGDD
hR 17~ 1993 Ob:5~ R.:. Gite'A SI)%PATOR 2 TREND GROUP ASSIGViCtsT PJ,",NAR'>'AGE GRX~: =iENT! PROCE&iw",'PIP 1-5 PLANT STAT%
POia/T rD DESCRIPTION VALUE lcUAL E. U.
53 FSIA SAFET'i IW:ECTION S.'.~,'>'n~<<Tiara LOOP A AViG FLO'A 0. 6OOD GPN 4 iSIB 'DP B NG FLOA 0. 6000 GPN 55 P21b0 SERVICE RATER FNPS A 4 B HEADER 84. GOOD PSIG 56 P2lb1 SB,'iCE NTER PU"iPS C h D HEADER 75. GOOD PSi6 57 BKR041 SEE"liCE @TER PUt'iP A ON GOOD 5S BkR042 :-~V!C= RATER PUK? B OW GOOD 59 F~R043 SERVICE WATER PUtlP C ON GOOD b0 Bc<R044 SEr7viC= VJATER PfNP D OFF GOOD
t(R,'!7i 1993 R, E. 614iA Slt(ULATOR PAGE 1 TREtfD 6RQUY ASSIGNt(EtiT S<JYiitARY GROUP: EV="h!2 PRO!".EDL'8='. EPIP 1-5 .LANT STATUS POItfT ID DESCRIPTION !/ALUE 0UAL E. U.
l F0619 CDPQffitIT COOLING LOOP TOTAL FL(l 1427, LALN GPti LR~~T REFL!SLING WAT~D STORAGE TANt( LVL 94.5 C'009 /
3 <AS033 33 FOOT LEVEi MItlD SFEED drQ GOOD NPH 4 ((9033 33 . OQT LEVEL Witi'9 DiiiCTION 320. GKO DEG.
NT033 33 ~DOT LEVEL TENPE! ATURE 44,4 GKO DiGF 6 WT250 250 FOOT LEVEL TEtfPERATURE 43,8 6009 DEGF l t<fDT2 2;0 TQ 33 FOOT LEVEL D=iTA !ENP eO GOOD DEGF 8 Rp} ARi>> 1-COtfTROL RC<0rt 9.33255-02 GQQO tS/HR R02 AREA 2-CQt(TAINYENT 4.62382+00 GOGO NR/1$
lP R05 kii<'- 5-SPEfG FUEL PIT F 01975-01 GQOO NR/HR 1! R09 AREA 9-LETDD~<t LINE Y'fITQR 2.91742+01 6MO NR/HR i rz lk R34 A.'Z-'4 - AU!( BLDG CV PRAY PUY~ 1 01742 00 F C<09 /8/HR 13 R35 AR=~ 35-PASc -"AY<PL"" PA!FL }.09648>00 6009 NR/HR
~ ~
R}0A CQ<MTAlffNit(T IODINE NCiNITOR R!OA }.72782~02 GQQO CPN
<5 R}1 ceNI'AIfiYif(T AIP, PARTlcULATE 1.60555+02 6009 CPtt
~ Q R!2 CO'PAPAIN:"icit(T GAS tG'f: CR 2.63785+02 6009 CPN 17 R!0B PLA'lT Vit!T IODINE tier(ITDR R!OB 8.74732~00 GOQO CPN
!8 R}3 AUÃ Bi-DG E)(HAUST AIP, PARTICU< ATE 2.55932<02 6009 C!'N 19 R14 AUj( BLDG EI(HAUST GAS Yet(ITOR 5.52712+01 GOOD CPN 20 R18 LID:.'ID ttASTE DISPOSAL aGNITGR }.06844~03 GKO CPN 21 R!'9 ST==". 'ENERATOR BLO<~!,0'~f DRAIN 2.04}73~03 6009 CPN l)R
~ 4 R29 A.":""<<.':9-CC<NTAIt'.".Et(T HIGH RAN"-: 9.75!30-0! GKO R/HR Cv R30 A>>c.- 3>-CONTA!r;Nit,'~ HIGH RANGc 9.75130-01 6009 R/HR 2d R!5 CC,"":-USER AIR Ea":CTCR i>'HAUST }.35480v03 6009 CPN i5 R12A5 CV V"-NT CHAfl 5-LO)f Rf!!) - 6AS 4 ~05}' GOOD UCI/CC R!ZA6 CV V=.'lT CHAN 6-ApcA 6-"'i'fA 2.67992-02 GKO NR/HR 27 R!2A7 C'"f~i CHAN 7-i"<ID EAf(i GAS 4.205M 6009 UCI/CC 28 R!2A9 CV ",:-".! CHAN 9"H!iH RAf<GE GAS 9.99987"04 C<09 UCI/CC l)P'0< R14AS PLA,:'17 'f'EtfT CHA<'LO"'AI(GE CAS 2.30991-06 6009 UOI/CC R!4A/ PLA,"l Vif(T CHAfl 7-NID P>>USE GAS 4.62984-06 GQQO UCI/CC 31 R!4A9 PLA'! i ')ir(T CHAN 9-HIGH RA!<Gc GAS 9.10997-04 GOGO UCI/CC R!5A5 AIP. i:ECTC<R CHAN 5-LQ'-'ANGE CAS 6.22985-06 GOQO UCI/CC 33 R}M7 AIR =.'iCTOR CHAM 7-tiiD RAMGE GAS }.80975"05 6MO UCI/CC 34 AIR <ECTCR CH>>nrt c-H!I R>>s><GE GAS }.52999-03 GOQO UCI/CC 35 R31 AR:-A 31 STEAN LItfi A (SPING) 1.0!004-02 6009 %/HR R32 A;".EA 32 STEAN LINE 8 (SP!tfG) }.01004-02 6009 Ya/HR vC'0 CVH C'! PvDRD<3 it MriCEt<~!PAT!0ti I/
~ 0 6MO TCV03 CV B-':SEYit(T LEVE! 6FT !"t~Z 03 67.9 6009 9" GF TCV07 Si.p GQDO DEGF 40 'CV08 CV GPERY<EDIATE LVL 6FT TEY>> (f8 81 ~ 0 "K09 DE6F Pg Zl TCV09 CV ItJTERiiEDIATE LVL 6""T TBP N S}.0 6009 DEGF 42 TCV}0 CV !MT RN DIATE LVL 6FT TEN ft}0 81.0 6009 D"6F 43 TCV}7 CV Opi>>AT!ti'6 Li'fi'L 6FT TEY<P C}7 94.1 GOGO DiGF
Time: 0715 Message: 1
<<tNN BTAT10 1993 EVALUATED EXERCISE MESSAGE FORM
<< I <<L IR Simulated Plant Condi ions: See.the Attached Sheets
~Messa e: <<<< "THIS IS AN EXERCISE"" Make the following PA announcement after sounding the "Attention" signal:
"Attention; Attention all personnel. The Ginna Nuclear Station is now starting its 1993 Emergency Preparedness Evaluated Exercise, All Exercise messages must be started and ended with
'THIS IS AN EXERCISE',"
Announce twice. FOR CONTROLLER USE ONLY Controller Notes:
- 1) Ensure that the PA announcement is made.
Antici ated Results:
- 1) Simulator Control Room makes the PA announcement.
1993 EVALUATED EXERCISE Time: ~/I MAJOR PARAMETERS ENG1NEERED SAFEGUARDS Reactor Shutdown YES 0 Hi h Head S.X. Pum s N-31 G CPS FI-924 0 GPM N-32 O CPS FI-925 Z5 GPM N-35 AMPS 1A. INSERV OOS N-36 ~
- AMPS 1B. INSERV STBY 00 Avg. Nuclear Power 'K.l 'PS ~ lc. INSERV OOS RCS Pressure IG BAST Level =
PRZR Level el A RCP UNNI STOPPED Low Head S.I. Pum s B RCP UNNING/STOPPED FI-626 M 1A S/G Level 1A. INSERV TB OOS RECIRC 1B.S/G Level Ze 1B. INSERV TB OOS RECIRC 1A S/G Pressure 0/ PSIG RWST Level = 1B S/G Pressure PSIG Turbine/Generator ONLI OFFLINE Containment 8 ra Pum s 4 KV Buses ER /DEENERGIZED FI-931A~GPM 480V Buses ENERGIZE /DEENERGIZED FI-93 1B~GPM DC Batteries A~SOVOLTS B~BO VOLTS 1A. INSERV S OOS Cnmt Pressure a 2.(o PSIG 1B. INSERV STB OOS Cnmt Sump A Level ~~FEET NaOH Tank Level = Cnmt Sump B Level o0 INCHES A Loop Hot Leg Contai ecirc Fans A Loop Cold Leg 8 SZ-OF 1A. STBY OOS B Loop Hot Leg 'F 1B. V STBY OOS B Loop Cold Leg 1C. SE S Y OOS RVLIS 1D. INSERV B OOS
- CET Ma.~ 'F Post Accident Dampers OPEN LOSED S/G A Total Aux FW Flow C2 GPM S/G B Total Aux; FW Flow C> GPM Service Pum s 1A. SERV STBY OOS DXESEL GENERATORS 1B. S STBY OOS 1C. NSE S OOS A. RUNNING UNLOADED OOS 1D. INSERV OOS B. RUNNING UNLOADED Y OOS AGB Header Pressure 8 PSIG TSC RUNNING UNLOADED TB OOS Security RUNNING UNLOADED STB OOS Com onent Coolin Water Pum s 1A. NSERV STBY OOS ENGINEERED SAFEGUARDS 1B. INSERV TB OOS Surge Tank Level = ~D Aux. Feedwater um s 1A. INSERV STB OOS Standb Aux. Fe water Pum s 1B. INSERV STBY OOS 1C. INSERV T OOS Turb. Driven NSERV TB OOS 1D. INSERV TB OOS CST Level ~%F T
- CET = Average of Selected Core Exit Thermocouples
t(GV !7< 1993 07: 13 F;. E, GIt'.(A Slf"iULATOR PAGE TRB(D GROUP ASSIGN<it(T SU)<NARY GRDCE: EVii"T! PROCEDUF,=,'PIP!-5 PLANT STATUS PQIi(T 'D DESCRIPTIOt( VALLi>> MAL E. U. ATWS ANTICIPATED TRAt(:"IEt(T W/0 SCRI'< t(0 ATViS 6009 RXT RiA"TOR TRIP BRENER STATUS NOT TRIP 6009 t!3f SGiSCE RAtiK DETiCTOR V.-31 1.00000+00 It(HB CPS N32 SOUKE RANcE DETiECTGR N-32 !,000(&00 INHB CPS 5 555 INicPJ(EDIATE RANKLE DETECTOR N-35 S.!2829-04 It(HB Al(P N36 INTcRt'.EDIATE RANGE DET>> TOR N-36 8.12829-04 IhHB A!(P 7 NP AV=wAGE NKLEAR PGWEK 98.08 6009 / 8 PiF~ REA:.TOR CCG ANT SYSTEtl AVG PRESS "248. 6009 PSIG 9 U'1R PRESSURIIER AVENGE L""bcL 48.1 G009 10 FRCLA RFACTOR COOLAt!T LOOP A AVG FLN 9S.! GGGD / FRCLB REA"TGK CGP. ANT LMP 8 AVG FLOW 97.3 GM9 /
<2 RXT!6 RCrA BREA"ER CAUSc RX TRIP t(QT TP,IP GOOD f3 RXT!7 RCPT "RcAi(cr( "AUSc R'/ TRIP tlOT TRIP 6009 !4 TSUBTC Ital=.E TC SUKOGi cD t4RGIN 47,4 600>> DEGF lg LSGA STt( EcN A NARROW RA!(6c AVG LEVE 52.1 GMD /
16 LSGB STt< Fit". 8 NArROW RANGE AUG LEVEL 52.1 G009 /
- / PSGA ST<" 6<<:N A AVERAGE PRESPJRE 701. GOOD PSIG 18 PSGB STN EEN 8 AVERAGE PRESSURi 701. 6009 PSIG
<q GENBXRf 6~'GATOR ON i IN": BREA)E'ER 16!372 NOT TRIP GMD <<0 Cd(BKR2 CENERATGR ON LINE BREA)(ER 9X!372 NQT TRIP GOOD 21 BUS!!A BUS ffh SUPPLY BREAXER NOT TRIP KOD 2f BUS!18 BUS .'!B SLiPPLY BREAXER NOi TRIP 6009 >>d BUS12A t(OT TERt(INATED Gtt PPCS (7/!9/913 tlGT TRIP DEL 24 BiJS128 N<OT TERtflt@TED ON PPCS (7/19/91) NOT TRIP DEL 25 Bi!A!2A BUS !!A TO !2A T!E BRENER TRIPPED 6M9 26 8!f8128 BUS !!8 TO !28 TIE BRENER TRIPPED GOOD
>>l PCV CGN A: t(i"<ENT AUERA = PRESSURE ,26 GG09 PSIG 28 LS(IPA C<3)(TAIS"ct(T SUltp A AVEKAGE LEVEL 2,0 6009 FEET 29 L0942E SUN~ i~ LEVEL 8 INCHES (TRA!tv A) LOi)ER 6009 IO L0943E SiJ r 8 LEVEL 8 It(CHicS (TRAIN 8) LG((ER GOOD 31 LO'?429 SU!F' LEVEL 78 lt<CHcS (TRAIN A) LOWcR G009 L0943D SURF 8 LiVEL 78 !NCHES (TRAIt( 8) LONER GMD 33 L0942C SPP: LEVEL 113 INCHES(TRAIN A) LONER 6009 34 L094iC SU<~< 8 LEVEL !13 It(CHES(TRAIN 8) LOWER 6009 35 L09428 PN 8 LcVEL 180 INCHES(TRAIN A) LQ)tER 6MD 36 L09438 SL~ "" LiVEL 180 INCHES(TRAIN 8) LGWcR 6009 37 L0942A SU
> ERATURE 601.1 6009 DiGF 4(I T0410A RCLB HOT LEG TEt'PERATUFc 601 ' -6009 DEGF 41 T0450 RCLA COLD LEG TEt(FEPATNE 544.2 6009 DEGF 42 T0451 RCLB CO(.D LEG TEt(PERATURE 544,1 KO9 DEGF 43 TAVGAWID RCLA TAVG (T)6T/TCO' WIDE Rt(S) 572.7 6009 DEGF TAVGBWID RCLB TAVG (THQT/TCOLD WIDE Rt(G) 572.6 GOOD 886F 45 LRV RECTOR VESSF AVERAGE LEVEL 99.1 GGOD / 46 TCCGPE Ei ~ ! INCORE TC AVERAGi TEt(P 600.6 600~ 986F FAUXFWA S/6 A TOTAL A(JX FEEDPTcR FLOW 0. 6009 Gpt( FAUXFWB S/6 TOTAL NJX FEEDWATcB FLOW 0. GMD GPt( BRROSf i'>< >>a V3504 AUX >>~~ PUt(P STEAt( SUPPLY VALVc 8 CLOSED 6009 NOV 17i 1993 07'3 R. E. GINA SIP"LATOR PAGE 2 TREND GROUP ASSIGiiIiEt1T Ski"iARY GROUP; EVENTI PROCEDURE: EPIP 1-5 PLANT STATUS POI < '8 DESCRIPTION VALL'E QUAL E. U. 53 FSIA SAFETY IN'ECTION LOOP A AVG FLLC 0. GOOD PN 54 FSIB SAF"TY IN.'ECTION LOOP 8 AVG FLOW 0. GOOD GPN i 5 P2160 SBJ'l!CE 4'ATER PUMPS A h 8 H"ADER 84. COOn PSIG 55 P2161 SERVICE WATER PUMPS C 0 O HEADER 75. GOOD PSIG 57 MR041 SERVICE WA ER PU1LP A ON GOOD 58 BKR042 SERVICE WATER PiNP 8 ON GOOD 59 BNR043 S"RVICE N'ATER PUhP C ON KOD 60 BnR044 SE%>ICE WATER PUL'~ 8 OFF GOOD ti'OV 17i 1993 07: 14 R. F. Git'lA SI"GATOR TR"t)9 GRIP ASSIGNYiit!T
SUMMARY
6 EL~: EV=WT2 PROCEDU"i: EPIP 1-5 PLANT STATUS POINT fD DES RIPTIOW VALUE E. U. F0619 CC~"i. QWENT COO'NG LQQP TOTAI FLW 1427. LALII PN 2 LRNiT RE%" iNG WATER STQPAGEETAttk LVL 94.S GQQD 3 WS033 33 FOOT LEVEL W!AD SPEED 5.1 6009 WD033 33 FOOT LEVEI WfND DIRECTiOW 321. GOOD IFG. WT033 33 FGDT LEVEL TEMPERATURE 44.2 GOOD IZING 6 MT250 250 FOOT LEV: TEMPERATURE 43.4 GOOD DEGF 7 WDT2 250 TO 33 FOOT LEVcL E+~ TA <<.8 GQQD D"=6F TEN'RiA 8 R01 1 "COt!TROL ROON 9.33255-02 GOOD NR/HR 9 R02 AREA 2-CONTA IWNEIIT 4.62382400 GCGD
}0 R05 AREA 5-SPENT FUiL PIT 3,0!995-01 GOOD R09 AREA ""-LETDONW L!tfi I'iQNITOR 2.9}742~0} GOOD NR/HR 12 R34 AREA 34 - AUX BLDG CV PRA7 PUi'~~ }.04}}2+00 6009 NR/HR I~
R35 AREA 35-PASS SAMPLE PANEL }.09648~00 6009 ts/HR 14 R}OA COi'ITAiNiiENT IODINE tl0"t!TQR R}OA 1.6548}w02 6009 CPM
!5 Rll CONTAINMENT AIR PARTICu ATE 1.60555+02 GOOD CPN 16 R12 CM'P.INtlit!T 6AS t!0iNITOR 2.63785+02 GOOD CPN 17 R108 F'WiT VENT IODItfi NOW!TOP, R}09 8.63474~M GOOD CPN 18 R}3 AUX BLDG EXHAUST AIR PARTICULATE 2.55932>02 GOOD CPM }9 R14 AUX ~ DG EXHAUST GAS iiugITOR 5.64774+01 GQQD CPN R}8 LNUI 'ASTE DISPOSAL tXINITOR 1,05925+03 GOOD CPN R!9 STEAN CitiiRATOR DLQWDQl'N DRAIN 2.!}348~03 6009 CPN 22'3 R29 AF A 29-CQtJTAIt/NittT HIGH RANGE 9.75130-01 600D R/HR R30 Ac;="A 30-KWTAIk'"iitiTHIGH RANCE 9.75130-01 C<09 R/HR 24 R}5 CON'"N -R AIR JECTOR cXPAUH 1.45797+03 6009 CPM 25 R!2A5 CV VENT CION 5-LOW RANEE GAS 4.20511-03 6009 UCI/CC 'lg, R}2A5 CV VENT CiiAtt 6-AREA GANA 2.67992-02 GQQD NR/HR 27 R12A7 CV VENT CSN 7-NID RANK GAS 4.20511"05 GOOD KI/CC ')8 R}2A9 CV Vit!T CHAN 9"HiGH RANGE GAS 9.99987-04 6009 UCI/CC R}4A5 PLA'iT VENT CHAtk 5-LOW PfitiGE GAS 2.30991-06 GOOD Kl/CC 30 R!4A7 i. VENT CHAN 7-MiID PPNGE 64S 4.62984-05 GOOD UCI/CC 31 R14A9 PL(ii V t<T CHAW 9 HIGh'ANGE CAS 9.10997-04 GQQD KI/CC J R}SA5 AiR EJECTOR C%'I 5-LOS RAiNGE GAS 5.22'?85-05 6009 KI/CC R15A7 AIR EJ CTOR CHAN 7-I"iID RANGE CAS }.80975-05 6009 KI/CC 34 R}SA9 AIR E.ECTOR Catt 9-HI ANGE CAS 1.52999-03 6009 UCI/CC 35 R31 kR""~;l STEAN LIIIE A ! BRING) }.01004-02 GOOD t8/HR R32 N=A 32 STEA"i Lftii 8 (PING! 1.01004-02 6009 IQ/HR 37 CVH CV HIiROGEW CQtiCEt)TRATIQN ,0 GRID X 38 TCV03 CV BASEMENT LEVEL hei TEMP tt3 68.6 6009 DEGF 3D TCV07 CV !INTERMEDIATE LVL 6F't TEIIP 47 81.5 6009 DE6F 40 TCVOB CV itITERNEDIATE LVL 6FT TEMP tt8 81 ' "6009 IFGF 4} TCV09 CV INTERiNEDIATi LVL 6FT TEMP Ã 81.5 GOOD DEGF 42 TCV}0 CV INTcRNEDIATE LVL hFT TEMP !I}0 81,5 6009 DEGF 43 TCV17 CV i"FERATItF~ LEVL hFT 7ciiP 5}7 94.4 GOOD DEGF
TIme: 0715 Message: 2 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM Mh replacement. i keg""et ylj i Pp 1 dt ig Simula ed Plant Conditions; See Attached Mini-Scenario ~essa<ee: "<<"THIS IS AN EXERCISE>>"" FOR CONTROLLER USE ONLY Controller Notes:
- 1) Provide information verbally when appropriate actions are simulated or investigations are conducted.
Antici ated Results:
- 1) As per Mini-Scenario.
ROCHESTER GAS AND ELECTRIC GINNA STATION 1993 EVALUATED EXERCISE MINI SCENARIO TITLE: "B" Safe In'ection Pum Ou board Bearin Re lacement. Scenario expected start time: 0715 INITIALCONDITIONS: "B" Safety Injection Pump is held in accordance with "A" procedure A-1401. Bearing is disassembled, with shaft cleaned up for new bearing installation. Bearing obtain from inventory control "QA" storage. METHOD OF INITIATION: Start of work day crew begins preparation to replace bearing on pump, lubricating new bearing in Machine Shop. INDICATIONS: CONTROL ROOM: Trouble card submitted by RST on pump high vibration readings during PT-2.1Q (Safety Injection System Quarterly Test) ~ Machine shop initiated work package for outboard bearing replacement on "B" safety injection pump. EXPECTED SEQUENCE OF ACTIONS: Machine Shop crew will start work for day on bearing assembly at 0730 Bearing will be reinstated per M-11.12.1 (Safety Injection Pump, Mechanical Inspection). After completion of maintenance RST to conduct test. Pump returned.to service after test completion 24 hours from scenario start. REPAIR TIME: Bearing installation will take 8 hours to complete after crew renews work, before given to RST to test. FINAL CONDITIONS: Pump bearing in final stages of reassembly.
Time: 0715 Message: 3 GINNA STATION 1 93 EVALUATED EXERCISE MESSAGE FORM M t i ling "BeCt gigPPPI gRpl Simulated Plant Conditions: See Attached Mini-Scenario ~Messs e: '""THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Controller Notes:
- 1) Provide information verbally when appropriate actions are simulated or investigations are conducted.
An ici ated Results:
- 2) As per Mini-Scenario.
GINNA STATION 1993 EVALUATED EXERCISE MINI-SCENARIO ACTIVITY: "B" Char in Pum Plun er Re lacement. Scenario expected start time: 0715 INITIALCONDITIONS: The pump was held yesterday=for* repack of plunger due to leakage requirements. The replacement of the spare repacked plunger assemblies is 50% complete, repacked units need to be installed. METHOD OF INITIATION: Normal work day start will have the machinist on the job as initial conditions for exercise. INDICATIONS'ONTROL ROOM'uxiliary Building, Auxiliary Operator reported excessive leakage on the pump two days ago and a trouble report written for the Machine Shop to repack the "B" Charging Pump. Hold request and work order for machine shop have been processed to repack the pump. LOCAL: Operator when calculating leakage from the charging pumps determined the "C" charging pump leak rate was high and a trouble report was written against the pump. EXPECTED SEQUENCE OF ACTIONS: Work crew from the Machine shop was removed from this job to help change the bearing on the "B" Safety Injection Pump. Work order is active and SWP for task is active, pump is disassembled and needing spare plunger placed in the pump and torqued down, REPAIR TIME: When a crew returns to the task it will take 6 hours to complete the pump to restore to service. FINAL CONDITION: Pump is in some state of repair, not completed at conclusion of Exercise.
Time: 0730 Message: 4 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM .MMMf'. 8 I <<c IR Simulated Plant Conditions: See Attached Sheets ~ll/lessa e: <<<< "THIS IS AN EXERCISE""" ' loud bang is heard outside the Control Room door to the Turbine Building. 'nnunciator I-27 (Rotor Eccentricity or Vibration) alarms. FOR CONTROLLER USE ONLY Controller Notes:
- 1) Simulator Control Room Controller to bang door just prior to the simulator operator starting event.
Antici ated Results:
- 1) Operators should perform the actions of AR-I-27 and transition to AP-Turb.3 (Turbine Vibration) and perform the actions of tripping the turbine as vibration on ¹6 bearing is higher than the trip criteria of 14 mils.
- 2) Operators should transition to E-0 (Reactor Trip or Safety Injection) and perform the applicable actions and then transition to ES-0.1 (Reactor Trip Response) and perform its applicable actions.
- 3) Operators should send an Aux'iliary Operator out to check the main turbine-generator.
1993 EVALUATED EXERCISE Time: ~O~O MAZOR PARAMETERS ENGINEERED SAFEGUARDS Reactor Shutdown YES 0 Hi h Head S.I. Pum s FI-924 N-31 N-32 N-35 CPS CPS AMPS FI-925 1A. G'P GPM INSERV TB OOS N-36 AMPS 1B. "INSERV STBY 0 Avg. Nuclear Power ~ I 1C. INSERV TB OOS RCS Pressure PSXG BAST Level = PRZR Level ~ 3 A RCP UNNIN STOPPED Low Head S.I. Pum s B RCP RU N /STOPPED FI-626 C3 M 1A S/G Level 1A. INSERV TB OOS RECIRC 1B'S/G Level 2 1B. INSERV STB OOS RECIRC 1A S/G Pressure 70 PSIG RWST Level = 1B S/G Pressure 6 PSXG Turbine/Generator ,ONLIN OFFLINE Containment 8 ra Pum s 4 KV Buses NERG Z /DEENERGIZED FI-931A~GPM 480V Buses E 1ZE /DEENERGIZED FI-931B~GPM DC Batteries A~t VOLTS B)REVOLTS 1A. INSERV T OOS Cnmt Pressure o 2~PSIG 1B. INSERV STB OOS Cnmt Sump A Level Na I FEET NaOH Tank Level = Cnmt Sump B Level XNCHES o Loop Hot Leg A Loop Cold Leg B Loop Hot Leg B Loop Cold Leg A'2'F Oa G 'F OF
'F Containment Recirc Pans 1A.
1B. 1C. NSERV STBY OOS INSERV STBY OOS INSER STBY OOS RVLIS 1D. IN RV TB OOS
*CET S/G A Total Aux FW Flow
~~'FD GPM Post Accident Dampers OPEN CLOSED 9/G B Total Aux FW Flow ~GPM Service Water Pum s 1A. RV STBY OOS DIESEL GENERATORS 1B. SER STBY OOS 1C. STBY OOS A. RUNNING UNLOADED OOS 1D. INSERV TB OOS B. RUNNING UNLOADED STBY OOS A&B Header Pressure k PSIG TSC RUNNXNG UNLOADED OOS Security RUNNING UNLOADED STB OOS Com on'en oolin Water Pum s 1A. NSERV STBY OOS ENGINEERED SAFEGUARDS 1B. INSERV TB OOS Aux. Feedwater Pum s Surge Tank Level = ~Q 1A. INSERV B OOS Standb Aux. Feed ater Pum s 1B. INSERV TBY OOS 1C. INSERV TB OOS Turb. Driven INSERV TB OOS 1D. INSERV TB OOS CST Level FEET
*CET = Average of Selected Core Exit Thermocouples
NOV 17> 1993 ,07l28 R E 6 1(>:lA SIMiULATQR PAGE 1 TREtlD GRQU ASS!6)>'Mit(T StU>> t(ARY GRQLPl EVENT! PROCEDUR":: EPfP 1-5 PLAt(T STATUS POItlT fD DESCRIPT I Qtl VALUi QUAL E. U. ASS AtlTIC!PATED TRANSIENT )t/0 SCRAt( NO AT4S GOOD 2 RXT REACTOR TRIP BREAKER STATUS tlQT TRIP C~aQD 3 N31 SQ(PCE RAt(GE DTECTGR hl-31 1.00000+00 It(HB CPS 4 N32 SGLtRCE RANGE DETECTOR tl"32 l. 00000<00 it'HB CPS 5 N35 INt"RtlcDIATE RANGc DcTECTOR N-35 8. 12829-04 INHB ANP 6 tl36 ItlTERMEDIATE RANci DiTECTGR tl-36 8.!2829-04 ItlHD 7 NP At>ERASE NXLF4R PG'ilcR 98.09 6009 / 8 PRCS RcA"TOR CQQLA!(T SYSTEM NG PRESS 2248. GOOD PSIG t LPI>% PRESSLRIIER AVERAGE LEV=L 48.3 6009 >/ 10 FRCLA REACTOR COOLANT LO>GP A AVG FLON 98.1 KQD /
>1 FRCLB RiACTGR COOLANT LGQF 8 AVG FLOW 97.3 GKD X t'2 RXT16 RC>..<<. PREAKER CAUSE RX TRIP tiGT TRIP KQD RXT17 RCPB B>tEAKER CAUSE RX TRIP tlQT TRIP 6001) >A TSUBTC ItloDRE TC SUBCOQLED MARGItl 47.4 KQ>> DE6F 15 LSGA STii Gil( A NARROW" RANGE AV6 LEVEL 52.1 GOOD /
Ib LSGB STM GEN 8 tlARROW R4tlGc NG LEVEL 52.1 GOOD 17 PSGA STM Gitl A AVERAGE PRESSURE 701. GOOD PSIG
!8 PS68 STM Citl 8 AV"RAGE PRESSURE 701, 6009 PSIG GcENBKRl GitFRATQR ON LINE BRiAXFR 161372 NGT TPIP 6009
',70 GENBKR2 Gc>>ERATQR Otl LINEB>REAKER 9X!372 tlQT TRIP GGQD 21 BUS11A BL(c l!A SLtPPLY BREAKER tlQT TRIP GOOD BUS118 BUS !18 SUPPLY BFiEAKER NQT TRiP 6009 BUS!2A NOT TERMlt(ATED 0)t FPCS (7/19/91) tlQT TRIP DEL BUS!28 iNOT TERMINATED Otl PPCS (7/;9/91) NOT TRIP DEL 2d 811A!2A BUS 1!A TC 12A T!E BRcNER TR! FPiD KQD 26 8118128 BUS 1fB TQ 128 Tfi BREAKER TR!FPED 6009 r>
/ PCV CO(P>AINMit(T AVERAGE PRESSURE .26 GQQD PSIG 28 LS(IPA CGNt A!NMEt!T S>Ji"iP A At/ERASE LEVEL 2.1 6009 FiET 29 L0942E St&' LEVEL 8 It>CHcS (TRAitl A) LG)>ER KOD 30 L0943E SNF 8 LEVEL 8 INCH 8 (TRA!tl 8) LOVER 6009 31 L0942D SU"P 8 LEVEL 78 !NCHES (TRAItl A) LGtlc& 6009 32 L09439 S(t~ 8 LcVEL 78 fNCHcS (TRAItl 8) LQ)tER CO>09 33 L0942C SU>P 8 LEAL 113 ItlCf:cS(TRA!tl A) LO)>ER 6009 3'i L0943C SIP 8 LEVEL 113 it.HES(TRAItl 8) LG)'ER 6009 35 L09428 SU~ 8 LEVcL 160 It>CHES(TRAltl A) LO"ER KQD 36 L09438 SLttP 8 LEVEL 180 ItZHES(TRAIt( 8) LONER 6009 37 L0942A SUNUP 8 LEUcL 214 ItlCHES(TRAIN A) LG)>ER GOOD 38 L0943A SU>~ 8 LEVcL 214 Itl".HES(TRAItl 8) LONER 6009 39 T0409A RCLA HOT LEG TEMPERATURE 601 F 1 GOOD DEGF 40 '0410A RCLB HOT LEG TEMviRATUPcE 601.1 6GOD KGF T0450 RiLA COLD LEG TE)>FERATURE 544 ' GQ>09 DEGF T0451 RCLB COLD LE6 TEt(FEFATlRE 544.1 6009 DcGF 43 TAVGAI(ID RCLA TAVG (T),"OT/TCGLD WIDE RNS) 572.7 KQD DEGF 44 TAVGB)tfD Rl+Z TAVG (THQT/TCOLD >>>IDE RtlG) 572.6 GOOD 9"6F t5 RJC OR VESSc'UERASc 'V L 99.1 6009 46 TCCORE Ei.l itlCOFc TC AVERAGE TEMP 600.6 600>> DE6F 47 FAUXF(lA S/6 A :OTAL AtUX FEED"AT":R FLO(( O. GGQD GPM 48 FAUXFMB S/G :" ":GT4t AUX FEc9y>TciR FLQ'A 0. 6009 GPM 49 BKROB! MTR At.tXILIARY FEEL;.>ATicR PLiMP P C-,"F GQQD 50 BKR082 MI R AUXILIARYFEEE4AIER FL0'iP 8 OFF GQQD 5'i V3r"5 AUX .cw PU"F STEAlt SUPPLY VALVi A Ct 0SED GGQD 52 V3504 AUX . 4>
PUMP STEA)l SU PLY VALVc 8 CLGci9 KQD
NV 17'993 07 >: R. E. City SItIL&TQR PAGE 2 TREt8 GROJ" ASSIGN)tEttT SUi"GAMY GROUP: E)EttTI PROCEDL'RE: EPIP 1-5 FiN<T STATUS POIttT 19 DESCRIPTIOtl VALUE CUAL E. U. FSIA Sn,=STY It(.'ECTIOti'OOP A AVG FLN 0. 6009 GPt1 54 F BIB SP""TY It)3ECTION LOOP B AV6 FLOW 0. 6009 GPN 55 P2 150 SERVICE t'ATER PUMPS A 6 B HEADER 84. GOOD PSIG 56 P 2161 S""%ICE RATER PUllFS C L D F""ADER 75. 6009 PSIG 57 BNR041 6""RVICE @TER PutP A ON GOOD 56 NR042 SERV:CE t ATER Pur~ B 6009 Ot'i< So BVR043 SERV1CE HATER PUtiP C GOOD 50 IIR044 S=RV!2 MATER PUttP 9 0&% 6009
t(OV 17< 1993 07; 29, R c 6 it<RA 8INULATOR TR~t<<9 GRGsJP ASSIGttNEhT PJN<ttARY GRO()P.'FVcNT2 PROCEDUR""l EPIP 1-5 PLAttT STATUS POlttT ID OESCRIPTIRt VA<LLrE E. U. 1 F0619 CO~GNEtti COO': IttG LOOP TOTAL FLW 1427. LALN GPN 2 LRWST RE 0='NG VATER STORAGE TA)C LVL 94 5
~ 6009 >>/
3 ttS 033 33 FOOT LEVEL WlttD SPccD 5.1 GOOD ttPH 4 M9033 33 FOOT LEVEL ttlttD DI!scCTIOtt 317>> 6009 DEG. 5 WT033 33 FOOT LEVEL TBPERATURE 43.8 KQD DEGF, 6 MT250 250 ! QOT LEVEL TENPERA7JRE 43.1 600D DEGF
/ NDT2 250 TO 33 FOOT LEVEL DELTA TEt!J'REA
-7 GOOD DEGF 8 R01 }-CQt(TROi ROON 8.75992-02 GOOD NR/HR 9 R02 AREAs 2-COttTAIttNE!ti 4.75882~00 GOOD NR/HR 10 R05 AREA 5-SPENT FUEL PIT 3,09030-01 6009 NR/HR R09 AREA 9-LETDQN L!tsc NOÃITOR 2.75423<0} GGQD t8/HR i?
<>> R34 AREA 34 - AU)( BLDG CV VRN PUNP } 01742+00 F 6MD ta/HR 13 R35 Abc/-; 35-PASS SANPLE PAPL }.09648~00 G009 NR/HR 14 R10A COttTAIt <Et(T IODINE NOttITOR R}OA 1.69093+02 GOOD CPN
!r
~ >>< R}1 CC4<tlAI ttiNiENT AIR PART ICL> ATE 1.60 55+02 6009 CPN 16 R}2 CGltTAItiNEt(T GAS tiGttITGR 2.63785~02 GOGO CPN j7 R108 PLOT VEtti IODINE NGttITOR R}09 8.23426<00 GOGO CPN ie R13 AUK B: BG E)(HAUST AIR PNTICU!ATE 2.55932+02 6009 CPN
03 GOOD CPM 21 Ri'9 STc-""; GEttERATQR BLNBQ!~".t DRAIN 2.00678+03 GOOD CPN
>> R29 AREA 29-CG<<tTAIttt(Ettl HIGH RANK 9.75130-01 6009 R/HR R30 AREA 30>>CO!tTAIt<f=ttT HIGH RAts'c 9.75130-0} GQOD R/HR 24 R}5 CCCr/EttSER AIR EJECTOR EXHAUST }.46428>03 GOOD CPN 25 R}2A5 CV VEtsi Ct!Jst'"LG) RA'l~ CAS 4,205}1 05 GOOD UCIICC
'?6 R}2A6 CV VE!.< CHAN 6"AREA GN"A 2,67992?-02 GOM N/HR
'?
/ R}2A7 CV V t<T CRAtt 7-MID RA!iGE GAS 4,20511-05 GOOD UCI/CC 28 R}2A9 CV V=NT CHAit 9-HIGH RÃE GAS 9.99987"04 6009 XI/CC 29 R}445 PLktT VEttT CHAN 5-LQ'O'A!i'.E GAS 2.JO991,"06 6009 UCI/CC 30 R}4A7 FLNli 's!EttT CHA<Y 7-NID RANGE GAS 4.62984-06 GOOD XI/CC 3! R14A9 PL@. V <Vi CHAtt 9-HIGH RPJtGE GAS 9.}0997-04 GOOD UCI/CC u>> R}5A5 AIR =JECTOR CHAN 5-LOn'A'<GE GAS 6.2'?985-06 6009 Xl/CC 33 R}5A7 AIR EJECTOR CHAN 7-NID RAttGE CAS }.80975-05 GOOD UCI/CC R}5A9 AIR EJECTOR CHAN 9-HI PAlt<uE GAS 1.52999-03 6009 XI/CC R31 AP""-"..3} STEANi LINE A (SeittG) 1 01004-02
~ GOOD YR/HR 36 R32 AREA 32 STFAN LItic 8 (cbitt6) 1.01004-02 GOOD %/HR 37 CVH CV H'(DROGEtt CQ<<CEttTRATIGtt .0 6009 I 38, TCV03 C'/ BASENE!ti LEVEL 6FT TEt<P tt3 68.7 6009 DECF
!b TCV07 CV lttTERNEDIATE LVL 6cT TEt& t!7 81.6 GQQD DEGF 40 TCV08 CV It<TERNEDIATE LV! 6FT TEt<<P 48 81.6 GOGO DcGF 4} TCV09 CV Il)TER¹DIATE LVL 6FT TENP t!9 81.6 GOOD DEGF 42 TCV}0 CV It<TERNEDIATE LVL b T TcNb tt}0 8!.6 GOOD DEGF 43 TCV17 CV QPERATI!(G LEVL bF! !ctP 0}7 94.4 DEGF
Time 0730 1 9 all
~N NT Tl ~
EVALUATED EXER I E Message: 5 MESSAGE FORM A ill Egg<< <<k<<gl -g Simulated Plant Conditions: See the Attached Mini-Scenario ~Meaaa e: """TH)S lS AN EXERCISE+"" FOR CONTROLLER USE ONLY Controller Notes: E
- 1) Provide information verbally when appropriate actions are simulated or investigations are conducted.
Antici ated Results:
- 1) As per Mini-Scenario
GINNA STATION 1993 EVALUATED EXERCISE MINI SCENARIO TITLE: he kin T rbine n r r nois n vibr ion roblem. Expected Scenario start time: 0730 INITIALCONDITIONS: Turbine generator on line. IVIETHOD OF INITIATION: A loud bang is heard outside the Control Room door. Control Room requests that Auxiliary Operator check out the Turbine Generator for abnormalities. INDICATIONS: CONTROL ROOM: ~ Alarm window I-27 "Rotor Eccentricity or Vibration"
~ Bearing vibration indication
~ A turbine blade has penetrated the ¹2 LP turbine casing at its southeast corner and is lying by the Control Room door.
~ Sound of air rushing into condenser through the penetration.
~ Feel of turbine generator vibrating EXPECTED SEQUENCE OF ACTIONS' Investigate Turbine Generator for signs of abnormalities
~ Notice penetration of turbine casing.
~ Notice turbine blade lying by Control Room door.
~ Notice turbine generator vibrating.
~ Notice sound of air rushing into condenser through the penetration.
~ inform Control Room of findings no la er than 0740.
FINAL CONDITIONS: Turbine Generator is tripped and comes to rest and all condenser vacuum is lost.
Time: ~732 Message: 6 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM 8 I C I R Simulated Plant Conditions: ~Messa e: """THIS IS AN EXERCISE""" 'Annunciator F-21 (Cond Hl Press 20" Hg or Loss of Both Circ Wtr Pmps) alarms FOR CONTROLLER USE ONLY Controller Notes: 1i ~Wh n operators check condenser vacuum, inform them that it is 19" and decreasing, Antici ated Results:
- 1) Operators continue to perform the applicable actions of ES-0.1 .
Time: 0740 Message: 7 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM ~M: M I <<R IR Simulated Plant Conditi ns: ~ll/lessa e: """THIS IS AN EXERCISE" >>>> Auxiliary Operator checking the turbine generator informs Control Room of conditions er mini-scenario messa e ¹5 b 0740. FOR CONTROLLER USE ONLY Controller Notes:
- 1) Auxiliary Operator sent out to check the turbine generator must report his findings to Control Room by this time (i.e. 0740).
Antici ated Results:
- 1) Operators should be performing the applicable actions of ES-0.1 (Reactor Trip Response) ~
- 2) An ALERT should be declared in accordance with EPIP 1-0, "Ginna Station Event and Evaluation and Classification," EAL:Hazards Being Experienced or Projected; Turbine Blade Failure which Penetrates the Turbine Casing.
~
Time: 0745 Message: 8 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM ~NI: 8 I C << IR Simulated Plan Conditions: See the Attached Sheets Messacee: """THIS IS AN EXERCISE" >>>> FOR CONTROLLER USE ONLY Antici ated Results:
- 1) Operators should be performing the applicable actions of ES-0.1 (Reactor Trip Response).
1993 EVALUATED EXERCISE Time: 697& MAZOR PARAMETERS ENGINEERED SAFEGUARDS Reactor Shutdown YES NO Hi h Head S.I. Pum s N-31 ~SCPS FI-924 GPM N-32 ~~~CPS FI-925 ~GPM N-35 ~e~/AMP S 1A. INSERV TB OOS N-36 ANPS 1B. INSERV STBY OS Avg. Nuclear Power 1C. INSERV STB OOS RCS Pressure PRZR Level
~$
~iO
- 2. PSXG 4
BAST Level = A RCP UNNING STOPPED Low Head S.X. Pum s B RCP UNNIN STOPPED FI-626 GPM 1A S/G Level ~20. 9 1A INSERV OOS RECXRC 1B S/G Level 1B. INSERV TB OOS RECXRC 1A S/G Pressure ~Z.2. PSIG RWST Level = 1B S/G Pressure D/ PS G Turbine/Generator FFLIN Containment S ra Pum s 4 KV Buses ERGI DEENERGIZED FI-931A O GPM 480V Buses EN ERGIZE DEENERGIZED FI-931B~GPM DC Batteries A OLTS B~lo VOLTS 1A. INSERV B OOS Cnmt Pressure ~2PSIG 1B. INSERV TB OOS Cnmt Sump A Level ~ FEET NaOH Tank Level = Cnmt Sump B Level INCHES Loop Hot Leg ZQ2 F
'F Containment Recirc Pans A Loop Cold Leg 1A. SERV STBY OOS B Loop Hot Leg ~E~'F 1B. STBY OOS B Loop Cold Leg ~TI 20.F 1C. SER STBY OOS RVLIS ~b~ 'F ~ 1D. XNSERV STB Post Accident Dampers OOS
- CET 2 OPEN CLOSED S/G A Total Aux FW Flow ~~GPN S/G B Total Aux FW Flow ~~GPM Service Water Pum s 1A. NSE STBY OOS DIESEL GENERATORS 1B. ERV STBY OOS 1C. SERU STBY OOS A. RUNNING UNLOADED 8 OOS 1D. XNSERV TB OOS B. RUNNING UNLOADED TSC RUNNING UNLOADED TB BY OOS OOS A&B Header Pressure ~5 PSIG Security RUNNING UNLOADED STB OOS Com onen olin Water Pum s 1A. SERV STBY OOS ENGINEERED SAFEGUARDS 1B. XNSERV TB OOS Aux. F water Pum s Surge Tank Level =, ~W 4 1A. INSER STBY OOS Standb Aux. Peedwater Pum s 1B. NSERV STBY OOS 1C. XNSERV TB OOS Turb. Dr1ven INSERV STB OOS 1D. INSERV TB OOS CST Level 2 SO FEET
- CET = Average of Selected Core Exit Thermocouples
I NOV f7( 1993 07:44 R. E, GitW4 BI("ULATOR PAGE 1 TREt(D GROUP ASSIGN"(ENT PJt(("(ARY GRP~~: EVENii PRGCEDURc: EPIP 1-5 PI.ANT STATUS Polt(T ID DESCRIPTION VRL li E. U. AT)S ANTICIPATFD TRANSIE)IT W/0 BCRAN ATNS ALRt( 2 RXT ROTOR TRIP BREAKER STATUS RX TRIPPED ALRN 3 t)31 BPJRCE RAIIGE DiTECTGR t>>-3! !.27057+N 6009 CPS t]32 SOURCE RANGE DETECTOR ti(-32 1.27497+04 6009 CPS 5 N35 It)T"R)FDIATE RANEE DETiCTOR N-35 3.41977-11 6009 ANP 6 N36 It(TER)'cDIAT" RANEE DETECTOR t(-36 2.96481-ff GM9 fk":P 7 N, AVERAA NUCLEAR PGA"R .00 6009 / 8 PRCS REA".TGR COMIT SYSTEN AVG PRESS 2!32. GMD PSIG LPIR PRESSURIZER AVERACE LEVEL 25.0 6009 /
!0 FRC' RECTOR COOLANT LOOP A AVG FLOiA 97.1 Goon /
FRC' RcACTOR CGGLAVi LOOP B AVG FLG(( 96.3 600D / (Q
>>~ RXT!6 RCPA BREAKER CA(J":E RX TRIP t(OT TRIP 6009 f3 RXT!7 RCPB BREAKER CAUSE R)( TRiP NO. TRIP Goon !4 TSUBTC It(COPE TC SUB"GOLED tlARGIN 93.9 600>> DEGF 15 LSGA STtf Git( A NARRON RANCE AVG LEVFL 20.4 / !6 LSGB STt) GEN B t(AKA RA)t.i AVG LEVEL 21 ~ 6 LNRI( \/
17 PSGA STi( Gitt A AVERAGE PREBJRE 1022. GM9 PSIG
!8 PSGB SW G=N B AVERAGE PRESSURE 1019. 6009 PSIG GEtSKR GitFRATOR GN Lite BREN(R 161372 TRIPPED ALRt(
20 GEt(BKR2 GEN'.RATGR GN LINE BREAKER 9X!372 TRIPPED 21 BUS!1A B(J. !!A SUPPLY BREAKER TRIPPED 22 BUSlfB BUB f!B SUPPLY BREAKER TRIPPED 23 BUS!2A NOT TERt(IN4TED ON PPCS (7/19/'?1) t)QT TRIP 24 BUS!2B NOT TERNINATED Gtt( PFCS (7/!9/91) NOT TRIP DEL B!1A!2A EUB ilA To !24 TfE BRBZER NOT TRIP 26 Bl!B!29 BUS '.lB To f2B TIE BRENER NQT TRIP ALRi"( (7 PCV CGNTAINNENT AVERAGE PRiSBURE ,24 6009 PSIG LB(@PA CONI'AINNENT BUt(P A AVER46E LEVEL 2,f GX9 FEET 29 ).094 2i BSP B LEVEL 8 INCHES (TRAIN A) LONER Goon 30 L0943E SUN B LEVEL 8 INCHES (TR4IN 9) LONER GOOD 31 L0942D SU~ B LEVEL 78 ft("HES (TRAIt) A) LONER 32 L09439 SU@' LEVEL 78 IN."HEB (TRAItt B) LONER 33 L0942C S(~>>" B LEVEL 113 INCHES(TRAIN A) 34 L0943C BUN B LcYEL 1!3 INCHES(TRAItt B) LONER GOOD 35 L0942B SUN 8 LEVEL 180 Iti'CHES(TRAIN A) LONER GOOD 36 L0943B SUtP B LEVEL 180 INCHES(TRAIti 8) LQNER 6009 37 L0942A BUN B LEVEL 214 It(CH"S(TRAIt( A) LONER Goon 38 L0943A S'J~(F' LEVEL 214 INCHES(TRAIN B) LONifi 39 T0409A RCL4 HOT LEG TE)(PERATURE 551 ' DEGF 40 T0410A RCLB HGT LiG TEt)PERAT(IK~. 551.9 6009 DEGF 41 T0450 RELA COLD LEG TEttPERATURE 550.4 Goon DEGF T0451 RCLB COLD LEG TE)(PciRATURE 550.2 .Goon DEGF 43 TAVGA))ID RCL4 TAVG (TENT/TCGLD NIDE RNG) 55!.2 DE6F 44 TAVGBNID RCLB TAVG (THOT/TCGLD 'AIDE RNG) 551.1 6009 DEGF 45 LRV REACTOR VESSEL AYERAGE LEVEL 99.2 Kon 46 TCCORE Ef.i It)CORE TC AYERAGE TEi".P 551.7 600>> DEGF 47 FAUXFNA S/G A TOTAL AUX FEiDNATER FLG(( 163. GO09 GPI( 48 FAUXF((9 S/6 B TOTAL AUX FEEDNATiR FLON 171. GOOD GPtf 49 BKR081 t(TR AUXILIARYFEEDMATER PUt(P A GN GO09 50 BKR082 NTP. AUXILIARY FEED(PATER PiNP 9 ON coon 51 V3505 AUX P>>) PUN'TEAN SUPPLY VALVE A CLOSED 6M9 52 V"504 AUX FW PUil STEA)f BUFPLY VALVE B CLOSED,
NOV 17~ 1993 07'.44 R. E. Gi@lA SItkiLATOR PAGE 2 TREND GROUP ASSI Gtt~+EttT SUtlNRY GROUPS EVENT1 PROCEDURES EPIP 1-5 PLANT STATUS POINT ID DESCRIPT IC4 VALL'E KAL E. U. 53 FSIA SkcETY INJECTION LOOP A AVG FLOW 0. 6009 PN 54 FSIB SUETY INJECTION LOOP 8 AVG FLOW 0. GCCD GPtt 55 P2160 SBNICc WATER PUtFS A Iti 8 HEADER 84. 6009 PSIG 56 P2161 SJPICE WATER PUttPS C h 9 HEADER 75. 6009 PSIG 57 ECR041 SERVICE WATER PUtiP A Otf 6009 58 BKR042 SERVICE WATER PUttP 8 ON 600D 59 BKR043 SERVICc WATER PUNP C ON G009 60 BttR044 SERVICE WATER PUNP D OFF 6009
hGV 17i 1993 07:45 R. E, GINA slril" ATGR PAGE TRFND GROUP AKIGVBfT SUN)(ARY BROLLY" EVit'T2 PROCEDURE'PIP 1-5 PLANT STATUS POItJT ID DEKRIPTI0W VALUE QUAL E. U. 1 F0619 CGtl-'GtliNT CODLING LGG? TOTAL FLW 1438. LALri Ptf 2 LRNST REFT fNG WATER STORAGE TA)JK LVL 94.5 G009 NS033 33 FQQT LEVE'IND SPEED 5.2 6009 MPH 4 89033 33 FOOT LE&it N? tJD DIRECTION 317. 6009 DEG. 5 iAT033 33 FGGT LEVEL TENPERATURE 43.8 6009 DEBF 6 WT250 250 FOOT LEV=i TBu"ERATUR 43,1 DEGF 7 MDT2 250 TO 33 FOOT LEVci. DELTA TEriP -7 BC'609 DEGF 8 Rnl AR="4 I-CONTRO: RR 8.81048-02 6009 ts/HR 9 802 ARcEA -CEJTAINtJENT 4.75882%0 G009 t(R/HR fn R05 AREA 5-SPFNT FUEL PIT 3.14412<1 GGQD ts/HR 11 R09 AREA 9-LETDGRI LINE riG)JITOR 2.75423%f 6009 N/HR AREA 34 - AU)( BLDG CV PRAY PUriP lg R34 lw 1.02920~00 6009 ts/HR 13 R35 AREA 35-PASS Sk"i?LE PAttiL 1.09648+00 6009 N/HR 14 R10A CGi%'AIN<SNT IODIJJE tiGNITGR R10A 1.69093t02 GQGD CPN 15 Rfl CO;~VAieaJT AIR PARTICt! ATE 1.57806+02 GGQD CPtf R12 CGNTAINt(ENT GAS riGtJITGR 2,59268q02 GOOD C?tt i7 RlOB PLNT VENT IODINE- MONITOR R109 8.23426+M 6009 CPtt 18 R13 U)( BLDG EEHPdST AIR PNTICUl ATE 2.48313+02 6009 CPN 19 R14 AU)( BLDG E)(MAUBT GAs ripJITGR 5. 64774%1 6009 CPtf 20 R18 LIQUID hAST DISPOSAL ICiJITOR 1.01888+03 6009 C?tt 2f R19 STEAN GBBATOR BL1:i>PJ DRAIN 2.00678+03 6009 CPtt 22 R29 kRcA 29-CGNTAItJNENT HIGH RAtKE 9. 751 4-01 6009 R/HR 23 R30 AREA 3i)-CQ'iiJTAItJi'lit(T HIGH RANGE 9.75130-0f 6009 R/HR R15 CONDENSER AIR EJECTOR E)(HAUST 1.45797+03 6009 CPtt 25 R12A5 CV VENT CHAtJ 5-LGW RA)JGE GAS 4.205f1-05 6009 XI/CC 26 R12A6 CV VENT C)LAJJ 6-AREA GAYi"iA 2.67992-02 6009 ts/HR 27 R12A7 CV VENT CHAW 7-ttID RANK GAS 4.20511-05 6009 UCI/CC 28 Rf2A9 CV VitJT CHAN 9-HICH RID'JE BAS 9,99987-04 6009 XI/CC R1495 PLANT VENT Cl(AN 5-LGit RAtlGE GAS 2.30991-06 6009 XI/CC 30 R14A7 PLA!JT VEti'1 CHAti'-t'ilD RAtJGE GAS 4.62984-06 6009 UCI/CC 31 R14A9 PLA!JT Vit(T CHAN 9-HIGH RANG 6AS 9.10997<4 6009 XI/CC 3r> R15A5 AIR EJiCTGR CHA)J 5 ~0Ã RAtJCc GAS 6.22985-06 6009 XI/CC 33 R15A7 AIP, iJECTCR CHAN 7-HID RANGE GAS 1.80975-05 G009 XI/CC 34 R15A9 AIP. EJECTOR D(Atl 9-HI RANGE GAS 1.52999-03 6009 XI/CC 35 R31 AREA 3f STEAil LINE A (BRING) f.01004"02 6009 ts/MR 36 R32 A%A 32 STEAN LItE 8 (6?Its) 1.01004-02 K09 N/HR 37 CVH CV H'$9RQGcEN CQtcCEt(TRATION .0 GQQD 7. 38 TCV03 CV BASPiitiT LcVEL 6FT TEN? 03 70.7 6009 DEGF 39 TCV07 CV IhTERNEDIATi LVL 6FT TEt(P tti 82.0 6009 DiGF 40 Tcv08 CV INTERNiDIATE LVl 6FT TEt(P J(8 82.0 6009 DEGF Tcv09 CV INTERi"iEDIATE LVL 6FT TEt(P JJ9 82,0 6009 DE6F TCV10 CV INTiRI'iEDIATE LVL 6FT TEri? Jtfn 82.0 6009 DLGF 43 TCV17 CV OPERATIC LEVL EFT TEtl? ttf7 93.5 GG09 DEGF
Time: 0755 Message: 9x GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORIVI ~f: Si I<<C <<IR Simulated Plant Conditions: Sp i /E 1 YC di ~Messa e: """THIS IS AN EXERCISE""" Declare an ALERT in accordance with EPIP 1-0, "Ginna Station Event Evaluation and Classification", EAL: Hazards Being Experienced or Projected; Turbine Blade Failure which Penetrates the Turbine Casing. FOR CONTROLLER USE ONLY Controller Notes: tl Deliver only if an ALERT has not been declared. Do Not deliver if amer enc classification discussions are in ro ress. Antici ated Results:
- 1) Deliver contingency message if alert not declared or is not being discussed.
Time: ~OI~O Message: 10 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORIVI MMM t: 8
<<C << I R Simulated Plant Conditions: See Attached Sheets
~Meaaa e: <<<< "THIS IS AN EXERCISE>><<<< FOR CONTROLLER USE ONLY Controller Notes: Antici ated Results:
- 1) Operators, should be performing the applicable actions of ES-0.1 (Reactor Trip Response).
1993 EVALUATED EXERCISE Time: QPOG MAJOR PARAMETERS ENGINEERED SAFEGUARDS Reactor Shutdown ~YES NO Hi h Head S.I. Pum s N-31 Z2$ CPS FI-924 C> GPM N-32 %le CPS Fl-925 H GPM N-35 I~O/-AMP 5 1A. XNSERV T OOS N-36 /~~IAMPS 1B. XNSERV STBY 0 Avg. Nuclear Power 1C. INSERV TB OOS RCS Pressure PSIG BAST Level = PRZR Level A RCP NX STOPPED Low Head S.I. Pum s B RCP RUNNIN /STOPPED FI-626 PM 1A S/G Level 1A. INSERV OOS RECIRC 1B S/G Level ~a ~ o 9 1B. INSERV TB OOS RECIRC 1A S/G Pressure /0/8 PSIG RWST Level = 1B S/G Pressure O 5 PSXG Turbine/Generator NE FFLIN Containment S ra Pum s 4 KV Buses ENERGIZE DEENERGIZED FZ-931A~GPM 480V Buses NERGIZED DEENERGXZED FI-93 1B C'PM DC Batteries A~OVOLTS BUBO VOLTS 1A. INSERV OOS Cnmt Pressure Cnmt Sump A Level Cnmt Sump B Level o~<QPSIG G/ FEET INCHES 1B. INSERV TB NaOH Tank Level = ~4 OOS A Loop Hot Leg 'F Containment Recirc Fans A Loop Cold Leg 5I. 'F 1A. NSER STBY OOS B Loop Hot Leg Std& OF 1B. ER STBY OOS B Loop Cold Leg .5 'F 1C. NSER STBY OOS RVLXS 1D. INSERV TB OOS
- CET ~069 OF Post Accident Dampers OPEN LOSED
~6 S/G A S/G B Total Total Aux Aux FW FW Flow Flow ~~ GPM GPM Service lA.
ater Pum s STBY OOS DIESEL GENERATORS 1B. SE STBY OOS 1C. ER STBY OOS A. RUNNING UNLOADED TB OOS 1D. INSERV TB OOS B. RUNNING UNLOADED S B OOS A&B Header Pressure PSIG TSC RUNNING UNLOADED TB OOS Security RUNN NG UNLOADED STB OOS Com onent Coolin Water Pum s 1A. NSER STBY OOS ENGINEERED SAFEGUARDS 1B. 'NSERV TB OOS Surge Tank Leve Aux. Feedw Pum s 1A. SERV OOS Standb Aux. Feedwater Pum s 1B. R TBY OOS 1C. INSERV OOS Turb. Driven INSERV TB OOS 1D. INSERV B OOS CST Level ~baaLFEET
- CET = Average of Selected Core Exit Thermocouples
t OY 17 i 1993 07 a gQ R. E. GINNA SIt(ULAT(S PAGE TREt(D GROUP ASSIGNtlit(T SUi'L4iARY GROL'P: EVENT! PRocEKRE: EPIP 1-5 PLANT STATUS POI"(T iD DESCRIPTION YALUc QUAL ED U. 1 AT(iS ANTICIPATED TRANSIENT W/0 SCRN AT))S ALRt( 2 RXT REKTOR TRIP BREAKER STATUS RK TRIPPED ALRtt 3 N31 SOLACE RANGE DETECTOR t1-31 2.25683e02 600D CPS 4 t(32 SMCE RAtiGE DcHECTGR ti~32 2.15030e02 6009 CPS 5 N35 It)TERiirDIATE RAt(GE DETECTOR N-35 1 04232-11
~ GOOD NP 6 t(36 INTER,"~cDIATE RANGc DcTECTOR N-36 1,03753-11 GOOD A%'
7 NP A'/ERASE t(UCLEAR PO'wcR .00 6009 8 PRCS REACTOR CGOLNT SYSTEtl AVG PRESS s.2't 1 ~ 6009 PSIG 9 LPIR PRESSURIIER AVERAGE LEVcC 20.3 6009 / 10 FRCLA REA"-TOR COOLANT LOOP A AY6 FLON 97.3 C<09 / FRCLB RFA".TGR COOLANT LOOP 8 AVG FLGiN 96.5 6009 7 12 RXT!6 RCPA BREAKER CAUSE RK TRIP NOT TRIP GOOD RXT17 RCPB BRFAKER CAUSE RK TRIP NOT TRIP GOOD TSUBTC It(CORE TC SUBCOOLED t'ARGIN 102.2 600>> DEGF 15 LS6A STtt GEN A ttARROM RAiNGE AYG LEVEL 28.8 LWt( / 16 LSGB STN GEN 8 t(ARROW RANGE AYG LEVEL 29.0 LNRtt / 17 PSGA STt( Git( A AVcRAGE PRESSURi '018 GOOD PBIG
!8 PSGB STtt GEN 8 AVERSE PRESSURE 1015. GOOD PSIG 19 GcNBKR1 GiiERATOR ON LINE BREAKER 1G137 TRIPPio ALRt(
20 GENBKR2 GitFZATGR GN LIiNE EREAKFR 9K!372 TRIPPED ALRt( 21 BUS!1A BUS !!A BLPPLY BticAKER TRIP PiD ALRt( 22 BUS!18 BUS !!B SLiPPLY BREAKER TRIPPED ALRtt 23 BUS12A t(OT ! ERt(lt(ATED Ott PPCS (7/!9/91) t(OT TRIP DEL BUS128 NOT TERttlt(ATED Ott PPCS (7/19/91) tlOT TRIP DEL 25 811A!2A BUS 1 lA TO 12A TIE BRcENER ttoT TP,IP ALRi"i 811812B BUB 118 TG 128 TIE BRBNER t(OT TRIP ALRt( 27 PCV Cot(TAIt(t(ih7 AVcRAGE FRccSURE ~ 24 6009 PSIG 28 LM'iPA CQ'(TAINNENT BJt(P A AYERACE LEVEL 2.1 6009 FEET
/)9 L0942E BUYi 8 LEVEL 8 INCHES (TRAIN A) LoiJER 6009 30 L0943E Uii & LEVEL 8 INCHES (TRAIN B) Lot)ER 6009 31 L09420 BEP 8 LEVEL 78 INCHES (TRAIN A) LG)liR 6009 32 L0943D BEP 8 LEVEL 78 ItlCHES (TRAIN 8) LoiAER GOOD 33 L0942C SU."P 8 LEVEL 113 INCHES(TRAItt A) LONER 6009 34 L0943C SU% 8 LEVEL 113 INCHES(TRAIN 8) LONER 6009 35 L09428 PJ~i 8 LicVEL 180 IWCHEB(TRAIN A) LG)'ER 6009 36 L09438 BUi~ 8 LEVEL 180 INCHEB(TRAIN 8) LO'iER 6009 37 L0942A SU(P 8 LcYEL 214 It(CHES(TPAIN A) Lot(E GQQD 38 L0943A SUYL-' LEVEL 214 INCHES(TRAIN 8) LO)lER 6009 39 T0409A RCLA HOT LEG TEt(PERATK 550.6 GOOD DcGF 40 T0410A RCLB HOT LEG TEtlPEc RATUR 550.6 "6009 DEGF 41 T0450 RCLA Coi 0 LEG Tct(PiRATURE 549 7 ~ 6009 DEGF 42 T0451 RCLS COLD LEG TBlPBQTLRE 549.3 GOOD DEGF 43 TAVGA))ID RCt A TAVG (THOT/TCOLD l'IDE Rt(6) 550,1 6009 DEGF 44 TAVBBt(ID RCLB TAVG (THOT/TCOLD MiDE RNG) 550.0 6009 DEGF 45 LRV RFA".TGR VESSci AUiRAGE LEVEL 99 4 ~ 6009 /
TCCORi El,i IN"ORE TC AVERAGE TEt(P 550,6 600>> DE6F 8/ FAUKFNA S/6 A TOTAL AUK FEEC4ATciPi FLO'A 163. 6009 GPM 48 FAUXFMB B/6 8 TOTAL NJK FEEDlATcR FLO'A 172. GOOD GPH 49 BKR081 tiTR AUXILIARY FEEDMATER PUlP A Gft 6009 50 BKR082 NiTR AUXILIARYFEED'iATER PUtP 8 Ott V3505 AUK FN PU".,P STEAtl SUPPLY VALVE A CLOSED V3504 AUK .">>t PUt(P STEAN SUPPLY VALVE B CLOSED C.
tlOV 17~ 1993 07158 R. E. GieA SINUATOR PAGE 2 TREt6 SOUP ASS!CADENT SUGARY SOAP; EY""tiTl PROCEOLiR-.-; EPIP 1-5 PLAli'T STATUS POINT 19 BESCRIPT ION 5'A'E OUAL E. U. 53 FSIA SALTY IWJECTIOtt LOOP A AVG FLOW 0. 6009 GPtt 54 FSIB SAFETY INiECTIOtt LOOP 8 NG FLOW 0. GOOD PN 55 P21b0 SERVICE WATER PUtl?S A h 8 HEA9ER 84. 6OO9 PSIG 5b P21bl SLUICE WATER RNPS C h 9 HEA9ER 75. GO09 PSIG 57 BKR041 SER'PICE WATER PUttP A Ott 6OO9 58 Bl(R042 SERVICE WATER PUltP 8 Ot< COOO 59 8/R043 SERVICE WATER PUP C ON GOO9 60 BNR044 SER'i'ICE WATER PUttP 8 OFF 6609
t(GU 1?i 1993 07:58 R. E. Git"(A SINiULATQR PAGE TREND GROUP ASSIGNt(it(T SUNNARY GROUP: EV=NT2 PRQCEDUR":: FPIP !"5 PLAriT STATUS POINT ID DESCRIPTION VALUi (EQUAL E. U. 1 F0619 CQtPQ)I"t(T COOLING LOOP TGTA'LW 1427. LALI( GPN LRWST RiFU""'ti6 WATER STORACE TAI(X LVL 94.5 6000 0/ 3 WS033 33 FOOT LEVEL Wit(D SPEED 5.5 K00 t9'H WD033 33 FOOT LEVEL WIND DIRECTION 339. 6000 DEG, 5 WT033 33 FOOT LEVEL TE('iPERATURE 43.5 6009 DEGF 6 WT250 250 FOOT LEVEL TENPFPATURE 42.4 6000 DEGF 7 WDT2 250 TG 33 FOOT LEVEL DELTA TEt(P "1.1 6009 DEGF 8 R01 AREA I-CONTR(X. ROO'I 8.75992M 6000 NR/HR 9 R02 AREA 2-CONTAIN)IEcNT 4,49262+00 6000 NR/MR 10 R05 AREA 5-SPENT FUFL PIT 3.09030-01 GOOD NR/HR 11 R09 AREA 9-LETDOWN Lit(i NQt>ITGR 2.660?2+01 6000 NR/HR 12 R34 AREA 34 - AUX BL06 CV PRAY PUt(P 1.01742+00 6000 t(R/HR 13 R35 AREA 35-PASS SAMPLE PAtFL I 09648~00
~ GOOD NR/HR 14 R!OA CQNEAlt(NEWT IODINE t(0i"ITQR R1OA 1.62648~02 6000 CPN
'15 R!1 CQNTAINNENT AIR PART ICLMTE 1.51138<02 6009 CPN 16 R!2 CONTAIt(NEt(T GAS tfOt(ITOR 2.61516+02 6000 CPN 17 R!OB PLNT VENT IODINE t(Ot(ITOR R!OB 8,45036+00 6009 CPN ie R!3 AUX BLDG EXHAUST AIR PARTICULATE 2.55932+02 6000 CPtt 19 R!4 A1JX BEG EXHAUST GAS NiONITOR 5.40910401 G000 CPN 20 R!8 LI9.iiD WASTE DISPOSAL tX)NITGR 1.06844+03 GOOD CPN R19 STEAN GENERATOR BLOWDOWN DRAIN 1.99813+03 GOOD PN 22 R29 AREA 29-CONTAINNit(T HIB{ RAh'6" 9.75130-01 6000 R/HR 23 R30 At(ccA 30-CQNTAIt(NEWT HIG)( RANGE 9.75130<1 6009 R/HR 24 R!5 CONDENSER AIR EJECTOR EXHAUST 1,40241+03 6000 CPN QC R12A5 CV Viti: CHAN 5-LOW RAN-"'AS 4.20511-05 GOOD Xl/CC 26 R!2A6 CV VENT CHAN 6-AREA GANA 2, 6?CP-(P 6000 ta/HR 27 R!2A7 CV V tiT CHAN 7 NID RAt& GAS 4.20511-05 K09 Xl/CC 28 R!289 CV VFN; CHAr( 9-HIGH RANGE GAS 9.99987"04 6000 XI/CC R!4A5 PLNT VEt(T CHAti'-LQW RAt(SE GAS 2.3099!-06 6009 XI/CC 30 R!4A7 PLNT VENT CHAN 7-NID RANK GAS 4.62984-06 6000 Xl/CC 31 R!4A9, PLANT VFNT CMAt( 9-HIGH RAN6E 6AS 9..'0997-04 6000 Xl/CC 39 R!595 AIR E 'ECTGR CHAN 5 LGW RPi(6E GAS 6.22985-06 6000 XI/CC 33 R!5A7 AIR EJECTQP. CHAN 7-NID RANGE CAS 1 80975-05
~ 6009 XI/CC 34 R!5A9 AIR EJECTOR Ct(At( 9"Hl RAt<GE GAS 1.52999-03 6009 XI/CC 35 R31 AREA 3! STEAN Llh'E A (SPING) 1.01004-02 6009 NR/MR 36 R32 AREA 32 STEP~~i Llt(c B (BRING) 1 01004-02 G009 %/HR 37 CVH CV HYDRQGEtk CONCENTRATION .0 6000 X 38 TCV03 CV BASEtIENT LcViL 6FT T="I'iP (t3 71.8 GCGD DEGF 39 TCV07 CV INiiRNiiDIATELVL 6FT TENP N7 82.5 K09 DEGF 40 TCVOB CV INTERNEDIATE LVL 6FT TENP NB 82,5 6000 DE6F 41 TCV09 CV It(TERNiiDIATE LVL 6FT TENP t(9 82.5 6000 DEGF 42 TCV!0 CV li'ITERt(EDIATE LVL 6FT TENP (IIO 82.5 6000 DEGF 43 TCV17 CV Q."":RATING LEVL 6FT TENP Il? 93.1 6000 DEGF
Time: 0805 Message; 11 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM MMMf: s t C << IR Simulated Plant Conditions: ~Massa e: <<<< "THIS IS AN EXERCISE""" The following fire zone alarms: Z-01 (Aux Bldg 235-8 Bsmt E. Chp Room) FOR CONTROLLER USE ONLY Controller Notes: Antici ated Results:
- 1) Operators should sound the fire alarm and activate the fire bridge per SC-3.1.1 ~
- 2) Control, Room should inform the TSCaf the Charging Pump Room fire alarm.
- 3) Operators should be transitioning to 0-2.2 ~
Time: 0805 Message: 12 GINNA STATION 1993 EVALUATED EXERCISE MESSA E FORM ~IN f: Ct gigP pR Fi .Fi Bigd Simulated Plant Conditions: See Attached Mini-Scenario Messacee: <<<<<<THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY ~OII N
- 1) Provide information verbally when appropriate actions are simulated or investigations are conducted.
Antici ated Results:
- 1) As per Mini-Scenario.
GINNA STATION 1993 EVALUATED EXERCISE MINI-SCENARIO TITLE: Char in P m Room Fire Fir Bri ade. Expected Scenario start time: 0805 INITIALCONDITIONS:
"C" Charging Pump Running METHOD OF INITIATION:
Fire zone Z-01 (Aux Bldg 235-8 Bsmt E. Chp Room) alarms in Control Room. Control Room sounds the fire alarm and activates the fire brigade per SC-3.1,1 at 0807 hours the "C" charging pump trips out. INDICATIONS: CONTROL ROOM: ~ Alarm window K-31 fire system alarm panel.
~ Fire alarm panel alarm Z-01 "Aux Bldg 235-8 Bsmt E. Chp Room".
LOCAL: ~ Much smoke in area of the "C" charging pump motor. EXPECTED SEQUENCE OF ACTIONS' Investigate Charging Pump Room for signs of fire
~ Notice smoke in area of "C" Charging Pump Motor.
~ Notice "A" charging pump running normalp
~ Notice no other fire related problems in Charging Pump Room.
R hours. b b I <<0 C I .~08 5
~ Extinguish fire using accepted fire fighting practices.
Rp<<II I *I 0Ibd<<b C Itl ~0825
~ Return all fire fighting equipment to its proper storage.
FINAL CONDITIONS'ire is extinguished and reported to the Control Room at 0825 hours end ell fire fighting equipment is properly stored.
TIme: 0807 Message: 13 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM MMM: Si I <<C IR Simulated Plant Condi ions; ~Massa e: ""<<THIS IS AN EXERCISE""" The following annunciator is received: '-25 (Motor Off CTR Sect PMPs Except Main and Aux Feed Pmps). FOR CONTROLLER USE ONLY Controller Notes:
- 1) WHEN operators check the control board, inform them that the "C" charging pump switch indicates a white light and the "C" charging pump indicates tripped.
Antici ated Results:
- 1) Operators should perform the applicable actions of AR-G-25.
- 2) Operators should control pressurizer level and seal injection "flow with the remaining charging pump.
- 3) Control Room should inform TSC of "C" charging pump trip.
- 4) Operators should be performing the applicable actions of 0-2.2 .
Time: 0815 Message: t4
~CA 5 5 1993 EVALUATED EXERCISE MESSAGE FORM f: 5 I <<C IR Simula ed Plant Conditions: See Attached Sheets
~essacee: ""THIS IS AN EXERCISE""+ FOR CONTROLLER USE ONLY Controller Notes: 1) 5 IR I =555<< Fire Brigade captain, after arriving at the Charging Pump Room, should report to I II I charging pump motor with much smoke present and that they are fighting the I
"5" fire.
- 2) Offsite,fire fighting assistance is not participating. If assistance is requested, controllers will intercede to prevent off-site fire department response.
Antici ated Results:
- 1) Operators should inform TSC of,the fire on the "C" charging pump.
- 2) Operators should be performing the applicable actions of 0-2.2,
- 3) TSC should be assuming command and control at approximately this time.
- 4) TSC, when operational, should check into the loss of 34.5 kv circuit 751 problerri.
- 5) TSC, when operational, should evaluate the fire in the Charging Pump Room.
- 6) EOF may be activating at this time due to plant conditions.
1993 EVALUATED EXERCISE Time: ~8 MAO'OR PARAMETERS ENGINEERED SAFEGUARDS Reactor Shutdown YES NO Hi h Head S.I. Pum s N-3 1 CPS FI-924 V GPM N-32 ~~CPS FI-925 D GPM N-35 ~~LAMPS 1A. INSERV TB OOS, N-36 ~IMPS 1B. INSERV STBY OS Avg. Nuclear Power 1C. INSERV TB OOS RCS Pressure ~'Q PSIG BAST Level = PRZR Level (Q~ A RCP RUNNIN STOPPED Low Head S.1. Pum s B RCP RUNNING/STOPPED FI-626 C) PM 1A S/G Level 1A. INSERV OOS RECIRC 1B 'S/G Level ~H='B< 1B INSERV OOS RECIRC lA S/G Pressure PSIG RWST Level = 1B S/G Pressure . O PSIG Turbine/Generator ONLINE/ LIN Containment S ra Pum s 4 KV Buses NERGIZE DEENERGIZED FI-931A~GPM 480V Buses NERGIZE /DEENERGIZED FI-93IB~GPM DC Batteries A~OVOLTS B~/VOLTS 1A. INSERV TB OOS Cnmt Pressure ~~PSIG 1B. INSERV TB OOS Cnmt Sump A Level FEET NaOH Tank Level = Cnmt Sump B Level INCHES
" Loop Hot Leg 0 F Containment Recirc Pans A Loop Cold Leg F 1A. ER STBY OOS B Loop Hot Leg OF 1B. STBY OOS
~~~
~
B Loop Cold Leg F 1C. NSERV STBY OOS RVLIS 1D. INSERV TB OOS
~f1'CET F Post Accident Dampers OPEN CLOSE S/G A Total Aux Flow k1 9/G B Total Aux FW FW Flow ~o GPM GPM Service 1A.
ater Pum s STBY OOS DIESEL GENERATORS 1B. N RV STBY OOS 1C. INSERV S Y OOS A. RUNNING UNLOADED TB OOS 1D. INSERV TB OOS B. RUNNING UNLOADED TSC RUNNING UNLOADED OOS 0 A&B Header Pressure OPSIS Security RUNN NG UNLOADED TB OOS Com onent Coolin Water Pum s 1A. NSERV STBY OOS ENGINEERED SAFEGUARDS 1B. INSERV TB OOS Surge Tank Level = Aux. Feedwater Pum s 1A. STBY OOS Standb Aux. Feedwater Pum s 1B. INSERV STB OOS 1C. INSERV OOS Turb. Driven CST Level ~0 INSERV TB FEET OOS 1D. INSERV OOS
- CET = Average of Selected Core Exit Thermocouples
t(OV 17~ 1993 08:13 R. E. GINA SIML4JlTOR TREtiD GROUP ASSIGNNit(T SUiMMARY GROUP: EVENT1 PROCEDURE; EPIP 1-5 PLANT STATUS POINT ID DESCRIPT IQW U ()UAL E. U. 1 ATM ANTICIPATED TRANSIENT l4/0 SCRAN AT))S ALRt( 2 RXT R":ACTOR TRIP BREAKER STATUS RX TRIPPED ALRM 3 N31 SG(HCE RAt(GE DETECTOR ki-31 2.16520+02 GOOD CFS 4 N32 SOiRCE RAt(GE DETECTGR W-32 2. 16520402 600D CPS e A'V N35 IWTGNEDIATE RANK DETECTOR W-35 1.04232-11 GOOD 6 t(36 IWTcPNiiDIATi RANGED E-"TECTOR N-36 1.03276-11 6009 AMP 7 t(P AVERAGE NLGHR FG)tER .00 6009 / 8 PRCS REA"TQR COOLANT SYSTEM AVG PRESS 2247. G009 PSIG 9 LPIR PRESSURIZER AVERAGE LEVcL 18.5 LNRtl / 10 FRY A ROTOR COOLANT LQQi' AVG FLQiN 97.3 6009 I/
'z 1 FRC' REKTOR COOLANT LOOP 8 AVG FLQ)t 96.5 6009 lg RXTib RCPA BREAKER CAUSE RX TRIP ttGT TRIP 6009 13 RXT17 RCPB BREAKER CAUSc, RX TRIP NOT TRIP 6009 14 TSUBTC It@",ORE TC SUF330LED MARGIN 102.6 600>> DEGF 15 LSGA STM GEN A NARROW RANGE AVG LEVEL 34.4 GOOD 0/
LSGB STM GEN B NRttGW RAt(GE AVG I.EVEL K.4 GOOD 17 PSGA STM Gitt A WVAGE FFcSSURc 1019. 6009 FSIG 18 PSGB STN GEN B AVERAGE PRESSURE 1016. 6009 PSIG 19 GBSKRl GEtFRATOR ON LINE BREAKER iG1372 TRIPPED ALfm 20 GENBKR2 C-.GATOR OW LINE BREAKER 9X1372 TRIP PiD ALRtl 21 BUS11A BUS llA SUPPLY BREAKER TRiPPED ALRti 22 BUS11B BU" llB SUPFLY BREAKER TRIPPED ALRt( 23 BUS12A NOT TERNit(ATED QN PPCS (7/19/91) NQt'RIP DEL 24 BUS128 t(OT TERNINATED Ott PPCS (7/19/91) tiOT TRIP DEL B11A12A BUS liA TG 12A T!E BReNER NOT TRIP ALRt( 26 811B129 BUS '11B TQ 128 TIE BRENER NOT TRIP ALfm 27 PCV CO'ATAINMEt(T AVERAGE PRESSURE ~ 24 GOOD PSIG 28 LSUMPA CO)(TAIttt(ENT SUMP A AVERAGE LEVEL 2.2 6009 FEET 29 LO942E SUt>> B LEVEL 8 INCHES (TRAIt( A) LOi)ER GOOD 30 L0943E SLt+' LEVEl 8 ItlCHES (TRAIN 9) LO)tiR 6009 31 L09429 SUPP 8 LEVEL 78 It(CPS (TRAIN A) LO)tER GOOD 32 L09439 cEP B LEVEL 78 ritKHES (TRAIN B) LG)E'ER 6009 33 L0942C SUiV B LEVEL 113 iNCHES(TRAIN A) LO)iER 6009 34 LO943C SUMP B LEVEL 113 INCHES(TRAIN B) LOUR GOOD 35 L0942B SlPiP 8 LEVEL 180 INCHcS(TRAIN A) LO~iER G009 36 L0943B SUMP B LEVEL 180 INCHES(TRAItl 8) LO'"R 6009 37 L0942A SUtP 8 LEVEL 214 INCHES(TRAIN A) LGNiR 38 L0943A SUiP 8 LEVEL 214 IWCHcS(TRAIN 8) LO)tER GOOD 39 T0409A RCLA HOT LEG TBPERATURE 550.8 GQ09 D="GF 40 '0410A RCLB HQT LEG TEMPERATURE 550.8 6009 DEGF 41 T0450 RCLA COLD LEG TEt)PERATiBE 49.9 6009 DEGF 42 T0451 RCLB COlD LEG TEt(PERAT(IE 549.7 G009 DEGF 43 TAVGA)(ID RCLA TAVG (THOT/TCOLD WIDE RWG) 550.3 GQQD DEGF 44 TAVGBMID RCLB TAVG (THQT/TCQLD WIDE RNG) 550.2 6009 DEGF LRV REii"-TOR VESSEL AVERAGE LEVEL 99.4 6009 46 TCCORE Ei.'. INCORE TC AVERAGE TEMP 550.6 GGO>> DEGF 47 FAUXFN S/6 A TOTAL PJX FEED)tATER FLGl( 6009 GPM 48 FAUXFHB S/6 B TOTAL AUX FEED)iATER FLOiA 70. 6009 PN 49 BKRO81 t(TR AUXILIARY FEEDS'ATER PUMP A ON G009 50 BKR082 NTR AiJXILIARY FEED)STER FU)(P B OFF 51 V3505 AUX t% PU(P STEAN SUPPLY VALVE A CLOSED 6009 V3504 AUX Ft'UMP STEAN SUPPLY VALVi B CLOSED GOOD
NOV 17> 1993 08l13 R. E; GINA SINiLATGR PAGE 2 TREttD GROUP AKIGtttlM'Ut~1ARY GROUP: EVENT1 PRXEDUREl EPIP 1"5 PLANT STATUS POINT ID DESCRIPT VALUE QUAL E. U. IGt,'AFETY 53 FSIA Itt3ECTIGtl LGGP A AVG FLOW 0, 6009 GPM 54 FSIB SAFETY IW.'ECTION LGGP B AVG FLOW 0, GGGD PM 55 P2}50 SBVVICE WATER PUttPS A h B HEADER 84. 6009 PSI6 5b P21bl SERVICE MATER PUMPS C 5 D HEADER 75. 6009 PSIG 57 BRR041 SERVICE WATER PUMP A ON GGGD 58 B~R042 SERVICE MATER PUMP B Olt 6009 59 BKR043 c""fNICE WATER PUtlP C ON GOOD e0 Bnm44 SERVICE WATER PUMP 9 GFF 6009
t)OV 17> 1993 08:13 R, E. Bit@A SIMULATOR PA6E 1 TREND GROUP ASSIGNNBlT SUi"DARY BR(K4ENT2 PROCEDL%i: EPIP 1-5 PLANT STAT!JS POINT ID DESCRIPTIGM VALUE E. U. 1 F0619 COi~0hit(T CGGLIN6 LOOP TOTAL FLW 1432. LALt( GPtf 2 LRWST RiFL!ELINB WAl& STORAGE TA31 LVL 94.5 BQQD 7. W~033 33 FQQT LEVEL Wit(D SPEED 7.0 GOOD tfPH 4 N)033 33 FOOT LEVP WIND DIRcCTIGt< 321. 6009 DEG. 5 WT033 33 FOOT LEVEL TEt(PERATURE 42.9 6009 DE6F 6 WT250 250 FOOT LEVP TEi(PERAT!JRE 42.0 6009 DEGF 7 WDT2 250 TO 33 FOOT LEVEL ETTA Tits GOOD DEGF 8 ROl ARc4 f-CGhTR(3: ROQt( 9.44062M 6009 t8/Htt R02 ARiA 2-CQtiTA INNEttT 4.59727+00 GOOD N/HR 10 R05 ARiA 5"SPEt(T FUEL PIT 2 '5121-01 GQQD N/HR 11 R09 AREA 9-LETDG'4 Lit("" MONITOR 2.85101<01 6009 N/HR
.'2 R34 AREA 34 - AU)( BLDG CV PRAY 1.02920+00 6009 ta/HR PUtit'RcEA f3 R35 35-PASS SAMPLE PAtKL f.09648>00 GOOD N/HR 14 R10A CGt(TAIt(t(ENT IODINE HQNITQR R10A 1.62648~02 GOOD CPM 15 Rff CONTAIMHit(T AIR PARTICULATE 1.59f75~02 6009 CPM .'6 R12 COt(TAIN<"i NT GAS NiONITQR 2,68380+02 6009 CPM 17 RIOB PLANT Vit(T IODINE tfAITGR RIOD 8.45036i00 6009 CPtf !8 R13 AUN BLDG E3(HAUST AIR PNTICUATE 2.59268402 6009 CPM 19 R14 AU3( BLDG. E3(HAUST GAS tie((ITGR 5.40910~01 6009 CPtt 20 R}8 LAID WASTE DISPOSAL YDNITQR 1.09175+03 6009 CPM 21 R19 STEAi"~ GEt(ERATOR BLOWDG'4 DRAIN 1.99813+03 GOOD CPtf 22 R29 AREA ~9-Cet(TAIt(t(ittT HI(c( PAt"Sc 9.751~1 6009 R/HR 23 R30 AREA 0-CONTAINS".t(T HIGH RANGc 9.75f30-01 6009 R/HR 24 R15 Ce>CENSER AIR EJECTOR E3(HAUST 1.40241+03 6009 CPtt 25 R12AS CV VENT CHAM 5"LOW RAtitK GAS 4.205f1-05 6009 XI/CC 26 R1246 CV VENT CHAN 6-AREA GAl'C 2.67992-02 GCi09 N/HR 27 R12A7 CV VEN! CHAN 7-<<ID RAtl'= GAS 4.20511-05 6009 XI/CC 28 R1249 CV Vitii CHAN 9-HIGH RAMBc BAS 9.99987-04 6009 UCI/CC 29 R!485 PL%(T VENT CHAtt 5<0M RANGE BAS 2.30991"06 6009 XI/CC 30 R14A7 Pdk(T VENT CHAN 7-ttID RANBc GAS 4.62984-06 6009 KI/CC 31 R14A9 PLANT VENT CHAtl 9-HIGH RANGE GAS 9. 10997-04 GOOD XI/CC 32 R15A5 AIR EJECTOR CHAtt 5<0M RANGE BAS 6.22985-06 6009 KI/CC 33 R15A7 AIR i-CTOR CHAM 7-t,ID RAt(6c GAS 1,80975-05 6009 XI/CC 34 R1549 i AIR JECTCR CHAN 9 HI RANGE GAS 1.52999-03 6009 KI/CC 35 R31 ARFA 31 STEAN LINi A (SPINBt f.01004-02 6009 N/HR 36 R32 ARE;", '2 STEAN LINE 8 (SPINB) 1.01004-02 GOOD N/HR 37 CVH CV HYDROGEN Cot(cicNTRATIOM .0 6009 38 TCV03 CV BA-"it!ENT LciVEL 6FT TEt(P I3 71.8 DEBF TCV07 CV It(TcRttiDIATE LVL 6FT TctP I7 82.3 GOOD DcGF 40 TCV08 CV It(T RtiEDIATE LVL 6FT TEt(P I8 82.3 6009 DEGF 41 TCV09 CV It(TERMEDIATE LVL 6FT TEt(P I9 82.3 DEGF 42 TCV10 CV itt!cRt(EDIATE LVL 6FT TEt(P I10 82.3 DEGF 43 TCV17 CV OPERATING LEVL 6FT TEMP ttf7 92.8 DEGF
Time: 0825 Message: 15 GINNA STATION
'993 EVALUATED EXERCISE MESSAGE FORM MMMf: R I<<C << IR C Simula ed Plant Conditions: See the Attached Sheets
~Meeee e: """THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Controller Notes: 1} Fire Brigade captain should report to Control Room at this time that the fire in the Charging Pump Room is extinguished and that it was on the "C" charging pump motor. He should also report that the "A" charging pump is running normal with no apparent damage from the fire. Antici ated'esults:
- 1) Operators should inform the TSC of the fire being extinguished on the "C" charging pump and the condition of the "A" charging pump.
- 2) TSC should re-evaluate the Emergency Classification per EPIP 1-0. There should be no change of Emergency Classification.
Time: 0825 Message: 16 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM f: M 1 i keg "eC" Ch gigP pM Fi 0 g Simulated Plant Conditions: See the Attached Mini-Scenario ~Messe e: """THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY
- 1) Provide information verbally when appropriate actions are simulated or investigations conducted.
Antici ated Results:
- 1) As per Mini-Scenario.
GINNA STATION 1993 EVALUATED EXERCISE MINI SCENARIO TITLE: "C" Char in Pum Motor Fire. Scenario expected start time: 0825 INITIALCONDITIONS: The reported fire on the "C" charging pump is declared out by the Fire Brigade. Fire captain reports the fire was located in the motor of the charging pump. METHOD OF INITIATION: Control Room reports to the Emergency Coordinator that the fire is out and the "C" charging pump is out of service. INDICATIONS'ONTROL ROOM: Fire Zone 2-01 alarm was responded to by fire brigade, "C" charging pump trip from the fire, and Brigade Captain reports the fire in the motor has been put out. LOCAL: Fire Brigade Captain reports the fire is out to Control Room. EXPECTED SEQUENCE OF ACTIONS: Trouble report is written to repair motor on "C" charging pump. Planner puts together work order and package for major repair to vari-drive procedure M-11.4.4 and motor procedure M-45.0 . Possible trouble-shooting inspection of unit by the planner and mechanic. Check of inventory to see if replacement motor available for unit. REPAIR TIME'ependent on: amount of time to have a new motor shipped in to replace the damaged unit, to have the stator sent out for rewind, or whether a rotor is in inventory control, unit will not be repaired for at least 1 month. FINAL CONDITIONS: Clean up of Charging Pump Room by maintenance shop and b machine shop and electrical shop evaluating the course of action to take for motor repair.
Time: 0825 Message: 17 GINNA STATION 1993 EVALUATED EXERCISE ling MESSAGE FORM MMMf: El <<ii eC" Lt gi gP pM 'Fi 0 g Simulated Plan Conditions: See the Attached Mini-Scenario ~essacee: """THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Controller Notes:
- 1) Provided information verbally when appropriate actions are simulated or investigations conducted.
Antici ated Results:
- 1) As per Mini-Scenario.
GINNA STATION 19S3 EVAI UATED EXERCISE Il MINI-SCENARIO TITLE: Ch r in P m R mFir 1Cchr in m Expected scenario start time: 0825 INITIALCONDITIONS: Charging Pump 1C running, METHOD OF INITIATION: Fire Zone Alarm. Zone 2-01 (Aux Building 235-8 Basement, Charging Pump Room). Charging Pump 1C breaker trips. INDICATIONS: CONTROL ROOM: Fire Alarm Zone 2-01 Annunciator Window:
"J-25" Motor Off: CHP1A "F-14" Charging Pump Speed White (disagreement) light: CHP1A BUS 16/POS15C Amptector: "Instantaneous" trip indication If meggered - 0 Q to ground, 0 Q p to p CHP1A MOTOR: Smell of burnt insulation EXPECTED SEQUENCE OF ACTIONS:
Investigate fire alarm, Zone 2-01, Auxiliary Building
~ Smoke discovered in vicinity of Charging Motor 1C
~ Auxiliary Operator/Electricians check CHP1C o Discover Amptector "instantaneous" button is out Obtain holds, clearances, and test equipment.
Simulate measuring resistance phase to phase and meg gering motor from Bus 16/Pos 15C readings: Megger readings: 0 Q Phase to ground Phase to phase resistance 0 Q FINAL CONDITIONS: Motor requires replacement/rewinding due to shorted windings.
Time: 0825 Message: ~1 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM f: tBCW k g "C'Ct giigP pM Fii0 g Simula ed Plant Condition: See the Attached Mini-Scenario ~IVlesss e: """THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Controller Notes:
- 1) Provide information verbally when appropriate actions are simulated or investigations conducted.
Antici ated Results:
- 1) As per Mini-Scenario.
GINNA STATION 1993 EXERCISE MINI-SCENARIO TITLE: "C",Ch r in P m Room Fir Expected scenario start time: 0825 INITIALCONDITIONS: Charging Pump "C" operational. METHOD OF INITIATION'ire in Charging Pump Room. INDICATIONS: Solenoids 14306S and 14305S are charged and leaking air. EXPECTED SEQUENCE OF ACTIONS: Replace both Solenoids FINAL CONDITIONS: Both Solenoids are replaced and tested.
Time: 0830 Message: 19 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM 8 I C << IR Simulated Plant Conditions: See Attached Sheets ~Messe e: <<""THIS IS AN EXERCISE>>"" FOR CONTROLLER USE ONLY Controller Notes: Antici ated Results:
1993 EVALUATED EXERCISE Time: O'P3 ~ MAZOR PARAMETERS ENGINEERED SAFEGUARDS Reactor Shutdown YES NO Hi h Head S.I. Pum s N-31 / CPS FI-924 GPM N-32 CPS FI-925 O GP N-35 /~~/AMPS 1A. INSERV OOS N-36 ~FN~QAMPS 1B. INSERV S Y 00 Avg. Nuclear Power 0 1C. INSERV STB OOS RCS Pressure / PSIG BAST Level = PRZR Level c A RCP UNNIN STOPPED Low Head S.I. Pum s B RCP UNNIN STOPPED FI-626 GPM 1A S/G Level 1A. INSERV TB OOS RECIRC 1B'S/G Level 29 1B. INSERV S OOS RECIRC 1A S/G Pressure lOIB PSIG RWST Level = ~<~4 1B S/G Pressure PSIG Turbine/Generator LINE/ FFLIN Containment S ra Pum s 4 KV Buses NERGIZED DEENERGIZED FI-931A 0 GPM 480V Buses N G ZED DEENERGIZED FI-931B~GPM DC Batteries A~O B~/VOLTS 1A. INSERV TB OOS Cnmt Pressure PSXG 1B. INSERV S OOS Cnmt Sump A Level FEET NaOH Tank Level = Cnmt Sump B Level CP INCHES A Loop Hot Leg ZO.Z. 0F Containment Recirc Fans A Loop Cold Leg 5'M OF 1A. NSER STBY OOS B Loop Hot Leg F 1B. INSE STBY OOS B Loop Cold Leg PQL 'F 1C. NSERV STBY OOS RVLIS ~F l/OOF 1D. INSERV TB OOS
- CET Post Accident Dampers OPEN CLOSED S/G A Total Aux FW Flow ~G- GPM S/G B Total Aux FW Flow ~~GPM Service Water Pum s 1A. NSERV STBY OOS DIESEL GENERATORS 1B. NS STBY OOS 1C. INSER STBY OOS A. RUNNING UNLOADED TBY OOS 1D. INSERV TB OOS B. RUNNING UNLOADED OOS A&B Header Pressure 5 PSIG TSC RUNNING UNLOADED TB OOS Security RUNNING UNLOADED STB OOS Com onent Coolin Water Pum s 1A. INSER STBY OOS ENGINEERED SAFEGUARDS 1B. INSERV TB OOS Aux. Fe ater Pum s Surge Tank Level = ~0 1A. NSER STBY OOS Standb Aux. Feedwater Pum s 1B. INSERV STB OOS 1C. INSERV OOS Turb. Driven INSERV OOS 1D. INSERV TB OOS CST Level ~ FEET
- CET = Average of Selected Core Exit Thermocouples
t<QV 17>> 1993 08:32 R. E. GIN(A SltSLATOR PAGE 1 TREt(D 6ROUP ASSIGtNEt(T SUt<<"~ARY 6RQUP: EVENT1 PROCEDURE: EPIP 1-5 PLANT STA'PJS POINT ID DES"RIP TIC4 VALUE @NL E. U. 1 ATMS ANTICIPATED TRANSIENT M/0 SCRNI ATMS ALRN RXT REACTOR TRIP BREAKER STATUS RX TRIPPED ALRtt 3 N31 SOItCE RANGE DETECTOR N-31 2.17270~02 600D CPS 4 t(32 SOURCE RAttGE DFTECTQR N-32 2.06300~02 GOOD CPS 5 N35 INTERMEDIATE RANGE DETECTOR N-35 1 04232-11
~ 600D tIP 6 t(36 It(TERYEDIATE RANGE DETECTOR N"36 1.03276-11 6009 AÃP 7 NP AVcMGE NUCLEAR POWER .00 6009 /
8 PRCS REACTOR CO(LP<<(T SYSTBl AVG PRESS 2251. 6009 PSIG 9 LPIR PRESSURIlER AVERAGE LEVEL 19.4 LMRtt / 10 FRCLA REA".TOR COOLA%'OOP A AVG FLOM 97.4 GOOD / 11 FRCLB REACTOR COQLNT LOOP 8 AVG FLQM 96.6 6009 / 12 RXT16 RCPA BREAKER CAUSE RX TRIP t(OT TRIP 6009 13 RXT17 RCPB BREAKER CAUSE RX TRIP NO: TRIP G009
~
4 TSUBTC ItZORE TC SUBCOOLED tlARGIN 103.5 600>> DEGF 15 LSGA STtl G N A NARROM RANGE AVG LEVEL 36.5 GOOD ib LSGB STtt GEN 8 t>>ARROM RAt(GE AVG LEVEL 32.8 GQQD 17 PS6A STtt GEN A AVERAGE PRESPJRE 1018. 6009 PSIG 18 PSGB STtf GEN 8 AVERAGE PRESSURE 1014. 6009 PSIG 19 GENBKR1 GB~~RATQR ON LINE BREAKER 16f372 TRIPPED ALRN 20 GMKR2 GEtFRATOR ON LINc BFEAKER 9X1372 TRIPPED ALRN 21 BUSl iA BUS 11A SUPPLY BREAKER TRIPPFD ALRN 22 BUS118 BUS 118 S5'PLY BREAKER TRIPPED ALRt( 23 BUS12A tiOT TERt(ltlATED ON PPCS (7/f9/91) NOT TRIP DEL 24 BUS128 NOT TEMlt(ATED ON PPCS (7/19/91) NQT TPIP KL 25 811A12A BUS 11A TO 12A TIE BRFAKER NOT TPIP ALRN 26 8118128 PJS !18 TO 128 TIE BREAKER t(QT TRIP A'N 27 PCV CQt(TAIt(tLct(T AVERAGE PRESSURE .23 6009 PSIG 28 LSU!)PA CON'AINttEt)T SUNUP A AV RAG LEVEL 1.4 6009 FEET 29 L0942E SU% 8 LEVEL 8 INCHES (TRA!N A) LQ)tER 6009 30 L0943E SU@' LEVEL 8 It(CHES (TRAIN 8) LORER GQOB 3f L0942D SUi% 8 LEVEL 78 INCHES (TRAIN A) LONER 6009 32 L0943D SU'P 8 LEVEL 78 ft>>'CHES (TRAIN 8) LQMcR 6009 33 L0942C SUiP 8 LE'PJ. 113 It(CHES(TRAIN A) LONER GOOD 34 L0943C SOP 8 LEVEL 113 INCHcS(TRAIN 8) LORER 6009 35 L09428 SU'P 8 LEVEL 180 INCHES(TRAIN A) LONER 6009 36 L09438 SUi%' LEVEL f80 INCHES(TRAIN 8) l.OM R 6009 37 L0942A SU%' LEVEL 214 INCHES(TRAlt( A) LONER 6009 38 L0943A SUi%' LEVEL 214 INCHES(TRAIN 8) LlNER 6009 39 RCLA HQT LEG TEtPERATURE 50.2 GOOD DEGF T0409A'0410A 40 RCLB HOT LEG TEt'FERATURE 550.2 GQQD DEGF 41 T0450 RCLA COLD LEG TEN'ERAT(RE 549.5 GOOD DEGF 42 T0451 RCLB CO' LEG TEt(PERATlRE 549 F 1 6009 DEGF 43 TAVGAM!D RCLA TAVG (THQT/:COLD MIDc RNG) 549.8 6009 DEGF TAVGBMID RCLB TAVG (THOT/!COLD MIDE RNG) 549.6 6009 DcGF 45 LRV REA'QR VESSEL AVERAGE LEVE(. 99.4 6009 / 46 TCCQRE Ef. 1 INCORE TC AVERAGE TEMP 550.0 GOQ>> DEGF 47 FAUXFMA S/G A TOTAL AUX FEEDMATER FLOW 82. 6Q09 GPtf 48 FAUXFt'8 S/G 8 !OTAL AJX FEEC Ai"R FLOW 109. 6009 GPtf 49 Bt(R081 t(TR AUXILIARYFEEDMATER PUMP A Ott 6009 50 BKR082 NTR AUXILIARY FEEDMATER PUMP 8 OFF 6009 51 V3505 AUX FM PUiP STEAN SUPP(.Y VALVE A CLOSED 6009 52 V3504 AUX FM PU",P STEAN SUPPLY VALV." 8 CLOSED GQQD
NOV 17~ 1993 08:32 '. E. GINNA SIMULATOR TREND GRGU? AKIGNHEttT PJi JSRY PAGE 2 GROLtt'VcNT1 >ROCcPPc'PIP 1-5 PLANT STATUS POINT ID DEKRIPTICti'k VALUE QUA' U 53 FSIA ~TY iNJECTION LOOP A AVG FLOM 0. 6009 PH 54 FSIB SAFETY IttJECTIGN LGOP B AVG FLGM 0. 6009 PM 55 P 2160 ScRVICE MATER PUtt?S A 5 B HEADER 84. 6009 PSIG 56 P2161 SBNICE MATER PUtt?S C 5 9 HEADER 75. 6009 PSIG 57 BXR041 S RVICE MATER PUttP A ON 6009 58 BXR042 SERVICc MATER PUtl? B Ott 6009 59 BXR043 SER'VICE,MATER PUMP C GN GOOD 60 BXR044 ScRVICE MATER PLY,P D OFF GOOD
NOV 17i 1993 OB:32 R. E.'GINNA SIMULATOR TREND GR(LiP ASSIGNYZP
SUMMARY
6RQL'P: EVENT2 PRQCEDUREl EPIP 1-5 PLANT STATUS POINT ID DEKRIPT ION VALUE E. U. F0619 CQi'POTENT COOLING LOOP TOTAL FLW 1427. LALM 6PN 2 LR'i(ST REPJELING WATER STORAGE TANK LVL 94.5 GOOD 3 WS033 33 FOOT LEVE! WIND SPciED 6.2 6000 MPH 4 WD033 33 FOOT LEVEL WIND DIRECTION 343. GOOD IFG. 5 WT033 33 FOOT LEVEL Tit. ERATURE 42.6 6000 DE6F 6 WT250 250 FOOT LEVP TEMiPERATL'Ri 42,8 C&9 IFGF 7 iWDT2 250 TCi 33 FOOT LEVEL DELTA TEMP .2 GOOD DEGF 8 R01 AREA 1-COt(TR&'00M 8.75992-02 6000 NR/HR 9 R02 AREA 2-CONTAlt(NEtiT 4.49262+00 6000 NR/HR
!0 R05 AREA 5-SPFNT FUcL PIT 3,09030-01 GOOD MR/HR il R09 ARiA 9-LETDOWN LINE ?%t(ITOR 2, 66072IO! 6000 NR/HR 12 R34 AREA 34 AUX BLDG CV SPRAY PUMP 1.01742+00 GOOD MR/HR 13 R35 AREA 35-PASS SAMPLE PAtKL 1.09648~00 6000 MR/HR !4 R!OA CQNTAINMiENT IODINE tiONITQR R!OA 1.62648<02 6000 CPN 15 Rl 1 COl(TAIt(YirriT AIR PARTICIJ ATE 1.51138+02 6000 CPM !6 R!2 CQtlTAIt(MENT GAS MQt(ITGR 2.61516+02 6009 O' 17 R10B PLANT VENT IODINE t!Ot(ITOR R!OB 8.45036+00 GOOD CPN !8 R!3 AUX B'G EXHAUST AIR PARTICLILATE 2.559 2<02 6000 CPM 19 R!4 AUX BLDG EXHAUST GAS MONITOR 5.40910~01 6000 CPN 20 R18 LIK'ID WASTE DISPOSAL MOt(ITOR 1.059 5+03 GOOD CPN 21 R!9 STcki GLNERATGR BLOWDO'n':l DRAIN 1.99813+03 6000 CPN 22 R29 AREA 29 CQt(TAIt,'MENT HIGH RANGr 9.75130-01 6009 R/HR 23 R30 AREA 30-CQNTAINMEt(T HI% RANGE 9.75130-01 GOOD R/HR 24 R15 CONDENSER AIR EJECTOR EXHAUST 1.40241+03 GOOD CPM 25 R!2AS CV Vitf!'HANMOW RANK GAS 4.20511-05 6000 Kl/CC 26 R12A6 CV VENT CCH 6-AREA GAMMA 2.67992-02 GCiOD MR/HR 27 R!2A7 CV V-N: CHAN 7-t(ID RANK 6AS 4 '05!1-05 GOOD KI/CC 28 R!2A9 CV VENi CHAtt 9-HIGH RAtKE GAS 9.99987-04 6009 KI/CC 2'? R!485 PLOD VENT Cf1-"N 5-LGW RANGi GAS 2.30991-06 KGD KI/CC 30 R14A7 PLNi( VEt(T CfLAtt 7-NID RANGrEGAS 4.62984-06 6009 KI/CC 3! R14A9 PLQ(T VENT CfIN 9-HIGH RAt(6E 6AS 9.10997M GOOD KI/CC 32 R!5A5 AIR E .rCTQR CHAN 5 LQA, RANGE GAS 6.2298~ GOOD KI/CC 33 R!5A7 AIR i:-ECTQR WAN 7-NID RAiNGE GAS 1.80'?75-05 GGOO L",I/CC 34 R!SA9 AIR EJECTOR CHAN 9-Hl RANGE GAS 1 ~ 52999-03 6009 KI/CC 35 R31 ARFA 31 STEAN LIt)E A (BRING) 1 010*4-02 GGQD MR/HR 36 R32 AREA 32 STEA,f LIHE 9 (BRING ! 01004-02 F GOOD MR/HR 37 CVH CV HYDROGEN CONCENTRATION .0 GOOD /
38 TCV03 CV BASEMENT LEVEL 6FT T:MP I3 75.2 6000 IFGF 3'9 TCV07 CV INTERMEDIATE LVL 6FT TEMP I7 83.9 GOOD KGF 40 TCVOB CV It(TERMrEDIATE LVL 6FT TEMP ((8 83.9 6000 DEGF 41 TCV09 CV INTERMEDIATE LVL 6FT TEMP I9 83.9 6000 DEGF 42 TCV!0 CV It(IERNEDIATE LVL 6FT TEtP (f!0 83.9 DE6F 43 TCV17 CV OPERATING LEVL 6FT lcMP (f17 92.5 DEGF
Time: ~084 Message: ~2 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM 8 I<<C << IR Simulated Plant Conditions: See Attached Sheets Messacee: """THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Controller Notes: Antici ated Results:
1993 EVALUATED EXERCISE Time: ~GF '/ MAJOR PARAMETERS ENGINEERED SAFEGUARDS Reactor Shutdown YES NO Hi h Head S.I. Pum s N-31 3 CPS FI-924 & GPM N-32 0 CPS FZ-925 (5 GPM N-35 0 -I AMPS 1A. INSERV TB OOS N-36 / OE./-AMP 5 1B. INSERV STBY 0 Avg. Nuclear Power RCS Pressure PRZR Level
~~ C) e 2 PSXG 1C. INSERV STB OOS BAST Level =
A RCP UNNIN /STOPPED Low Head S.I. Pum s B RCP RUNNIN STOPPED FI-626 Q GPM 1A S/G Level ~T~i 1A. INSERV OOS RECIRC 1B 1A S/G S/G Level Pressure
.~e
/el j PSIG 1B. INSERV STB OOS RECIRC RWST Level =
1B S/G Pressure l SIG Turbine/Generator LXNE OFFLXNE Containment 8 ra Pum s 4 KV Buses NERGXZE DEENERGIZED FI-931A GPM 480V Buses ENERGIZED DEENERGIZED FX-931B 'PM DC Batteries A~bVOLTS Bfno VOLTS 1A. INSERV TB OOS Cnmt Pressure o2 PSIG 1B. INSERV B OOS Cnmt Sump A Level o FEET NaOH Tank Level = Cnmt Sump B Level INCHES
- Loop Hot Leg QKI.<'F Containment ecirc Fans A Loop Cold Leg ~PM 'F 1A. STBY OOS B Loop Hot Leg ~50~'F 1B. SER STBY OOS B Loop Cold Leg 0F 1C. INSE STBY OOS RVLXS 1D. INSERV TB OOS
- CET SD. O' Post Accident Dampers OPEN CLOSED S/G A Total Aux FW Flow 72- GPM S/G B Total Aux FW Flow id~ GPM Service Water Pum s 1A. NSERV STBY OOS DIESEL GENERATORS 1B. ERV STBY OOS 1C. NSERV STBY OOS A. RUNNING UNLOADED TB OOS 1D. INSERV B OOS B. RUNNING UNLOADED STB OOS A&B Header Pressure ~ PSXG TSC RUNNING UNLOADED STBY OOS Security RUNNING UNLOADED STB OOS Com onent Coolin Water Pum s 1A. NSERV STBY OOS ENGINEERED SAFEGUARDS 1B. INSERV TB OOS Aux. F water Pum s Surge Tank Level = ~O 1A. ST OOS Standb Aux. Feedwater Pum s 1B. INSERV TB OOS 1C. INSERV S B OOS Turb. Driven INSERV STBY OOS 1D. INSERV TB OOS CST Level ~0.0 FEET
- CET = Average of Selected Core Exit Thermocouples
t(OV 17~ 1993 08:43 R. E. GINA SIMULATOR PAGE 1 TREIID GRGU ASSIGI(M hT
SUMMARY
GROLc EVENTl PROCEDL!Rc EPIP 1 5 PLANT STATUS PQI"IT !D DESCRIPTION VALUE OUAL E. U. 1 ATWS At(TICIPATED TRANSIENT W/0 SCR(!M ATNS ALRM 2 RXT REA".TOR TRIP BREAKER STATUS RX TRIPPED ALRII 3 N31 SMSCi RAI(GE D TECTOR )I-31 2.1355&02 6009 CPS 4 N32 SESCE RAti&c DETECTOR N 32 2.03469+02 6009 CPS 5 N35 It(TERMEDIATE RANGi DETECTOR N"35 1 04232-11
~ 6009 NP 6 N36 It(TERMiDIATE RAI(GE DETECTOP. N-36 1 03276-11
~ 6009 A:"iP 7 NP AVERAGE NUCLEAR PO)lER .00 6009 Y 8 PRCS REACTOR COOLANT SYSTEM AVG PRESS 2252. 6009 PSIG LPlR PRESSURIZER AVERAGE LEVcC 21.2 6009 /
!0 FRC." A REA"TGR CCC.NT LOOP A AVG FLOW 97,4 6009 Y.
11 FRCLB REACTOR CCQ.A!IT LOOP 8 AVG FLN 96.6 6009 Y. 12 RX716 RCPA BREAKER CAUSE RX TRIP t(QT TRIP 6009 13 RXT17 RCPB BREAKER CAUSc PX TRIP NOT TRIP 6009 TSUBTC ItiCORE TC SUBCOOLED t!A%It< 103.5 GQO>> DEGF IS LSBA STM C=N A t(ARROW RANi" AVC LEVEL 37.7 GOOD Y
!6 LSGB STM GEN 8 NAMW RANCE AVB LEVicL 37.1 GOOD 17 PSGA STM C tl A AVERAGE PRESSJRE 1017. GQOD PSIG PSGB S7M BBl 8 AVBQBE PRESRJRE 1014. CMD PSIG 19 GENBKRI GB'KRA GR GN LINE BREAKER lG!372 TRIPPED ALRM 20 Git(BXR2 GBKRA!GR ON LINE BREAKER 9X1372 TRIPPED ALRII 21 BUSliA BUS 11A SUPPLY BREAKER TRIPPED ALRMi 22 BUS118 BUS 118 SUPPLY BREAKER TRIPPED ALRI(
23 BUS12A NOT TERiMilt(ATED ON PPCS (7/19/91) NGT TRIP DEL 24 BUS128 NOT TERMINATED OiN PFCS (7/19/91) NQT TP,IP DEL 25 Bl!A!2A BUS 11A 70 12A TIE BRENER t]OT TRIP ALRt( 26 8118128 BUS 118 TQ 128 TIE BRiA'(ER t(Q; TP.IP ALRt( 27 PCV CONTAINMit(7 AVERAGE FRESSURE .24 KOD PSIB 28 LSUMPA CGt(TAINMictiT S'JMP A AViRAGE LEVEL 1.4 6009 FEET 29 L0942E SUMP 8 LEVEL 8 INCHES (TRAlt( A) LONER 6009 30 L0943E SUi~ 8 LEVEL 8 INCHES (TRAIt( 8) LONER KQD 31 LO942D SBF 8 LEVEL 78 INCHES (TRAIN A) LONiR KOD 32 L0943D SUtP 8 LEVFL 78 INCHES (TRAIN 8) LONER 6009 33 L0942C SUtp 8 LEVEL 113 INCHES(TRAIt( A) LONER 6009 34 LO943C SNP 8 LEVEL 113 INCHES(TRAIN 8) LONER G009 35 LO9428 SUtP 8 LEVEL 180 INCHES(TRAIN A) LONER GOOD 36 L09438 SUMP 8 LEVEL 180 Iti'CHES(TRAIiN 8) LONER 6009 37 I 0942A SUi'P 8 Li(&c 214 INCI'=S(TRAIN A) LONER GOOD 38 I 0943A PJM' LEVEL 214 INCHES(TRAIN 8) LONER 6039 39 T0409A RCLA HOT LEG TEMPERATURci 50.2 G009 DEGF 40 T0410A RCLB HQT LEG TEMPERATURE 550.2 "6009 DEGF 41 T0450 RCLA COLD LEG TEt(PERATLRE 549.5 DEBF 42 T0451 RCLB COLD LEG Tit!PERATURE 549.1 6009 DE6F 43 TAVGAWID RCL'AVG (THQT/TCQ: D WIDE RNG) 549.8 6009 DEGF TAVBBWID RCLB TAVG (THO7/TCGLD WIDE RNG) 549.6 6009 DiGF 45 LRV REACTOR VESSEi AVERAGE LEViL 99.4 6009 / 46 TCCQRE El.i !((CORE TC AVERAGE TEMP 550.0 600>> DiGF 47 FAUXFWA S/G A TOTAL AUX FEEDNATLR FLS KQD GPt( 72'02. 48 FAUXFWB S/6 8 TOTAL AJX FicDiWA!cR FLN GQQ9 PN 49 Pi(R081 t(TR AUXILIARYFEEDWATER PUMP A Gtf GOOD 50 BKR082 MTR AUXILIARYFEEDWATiR PUMP 8 GFF GQQD 5! V3505 AUX FW Pro STEAM SUPPLY VALVE A CLOScD GQQD 52 V3504 A!JX FW PUhP STEAli SUPPLY VALVE 8" CLOSED GOOD r p f%
NOV 17~ 1993 08:43 R. E. GINA SItfULATOR PAGE 2 TREND GROUP ASSIGtNENT SUtf"fARY 6ROUP: EVBIT1 PROCEDURE: EPIP 1-5 PLAtfT STATUS POINT ID DESCRIPTION VALUE DUAL E. U. 53 FSIA SAFETY INJECTION LOOP A AVG FLOW 0. GOOD GPtf 54 FSIB SAFETY INJECTION LOOP B AVG FLOW 0. GOOD GPtf 55 P2160 SM~ICE MATER PUtiPS A h B HEADER 84. GOOD PSIG 56 P2161 S":FQICE MATER PUtfPS C h 0 HEADER 75. GOOD PSIG 57 BKR041 SERVICE MATER PUtfP A ON GOOD 58 BKR042 SERVICE WATER PUtfP 8 0N 600D 59 BKR043 SEfIIC"" MATER PUtfP C ON GOOD 60 BKR044 SERVICE WATER PUtfP 0 OFF GOOD
0 NOV 17i 1993 08:44 R. E. GIt@A SIML&TGR TREND GROUP ASSIGNMENT SJMIIARY GROUP: EVitIT2 PROCEDURi: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION VALLic QUAL E. U. 1 F0619 CGIPOt(ENT COP ING LGQP TOTAL FLW 1427. LALH 6PM 2 LRIiIST REFJELING MATER STORAGE TA)IX LVL 94.5 G009 7 3 WS033 33 FGGT I.EVB. W}ND SP"'9 5.7 6009 MPH 4 II9033 33 FOOT LEVB WIND DIRECTION 342. 6009 DEG. 5 WT033 33 FOOT LEVB TEtlPERAT!JRE 42.6 6009 DEGF 6 WT250 250 FGQT LEVEL TitPERATURE 42.9 6009 DEGF 7 WDT2 250 TO 33 FOOT LEVEL DELTA TPJ' .3 6009 DE6F 8 R01 }-COt(TR9 ROOM 8.8}048<2 GOOD 0/HR R02 ARE-".. 2-CONTAI!ANENT 4.62382+00 G009 t8/HR 10 R05 AREA 5-SPENT FUEL PIT 3.14412-01 G009 N/HR 11 R09 ARiA 9-LETDOWN LIN" I'iOtiiTOR 2.91742+01 6009 t8/HR 12 R34 AREA 34 - AUX BLDG CV SPRAY PUMiP 1.02920+00 6009 t8/HR 13 R35 AREA 35-PASS SAtIPLE PEEL 1 ~ 09648+00 6009 t8/HR 14 R}OA CQ)ITAIIIMEtlT IQDItIE MOttITGR R}OA 1.65481+02 6009 CPM
!5 Rii CGIITAINMEtIT AIR PARTICLLATE 1 57806+02
~ 6009 CPM 16 R}2 CGiNTAINMENT C<S tfGI'IITGR 2.59268M 6009 CPM 17 R}OB PLANT VENT 109ltti MGttITQR R109 8.63474+00 PN 18 R}3 AUX BLDG EXHAiJST AIP, PARTICULATE 2.483}3%02 CPM R14 AUX BLDG EXHAUST GAS MONITOR 5.64774+01 CPM 20 R}8 LIPJID WASTE DISPOSAL Nt(ITGR }.0}888t03 6009 CPM 21 R}9 STEAM GENiRATGR BLOWiDGWN DRAlti 2.11348+03 GOOD CPM R29 AREA 29-CGNTAINMiti'T HIS RAKE 9.75130-01 6009 R/HR 23 R3Q ARi=". 30-CGMTAItl<itiiT HI&i RA)IGE 9.75}3M} 6009 R/HR 24 R}5 CO)QBISER AIR EJECTOR EXHAUST }.45797+03 6009 CPM 25 R12A5 CV VEt<T Ct!J!J( 5-LGW RANK GAS 4.20511-05 6009 XI/CC 26 R}2A6 CV VENT CHAN 6-AREA GANA 2.67992-02 6009 t8/HR 27 R12A7 CV VENT! C85 7-MID RANK GAS 4.20511-05 6009 XI/CC 28 R}2A9 CV VEN; CHAN 9-HIGH RANGE 6AS 9.99987-04 6009 Xl/CC 29 R}4A5 PLANT VENT CHAt< 5-LGW RANGE 6AS 2.3Q991-06 GG09 XI/CC 30 R14A7 PLWT VEIIT CHAN 7-MID RANGE GAS 4.62984-06 6009 Xl/CC 31 R}4A9 PLANT ViNT CHAtJ HIGH RANG"" GAS 9.10997-04 6009 XI/CC 32 R}5A5 AIR EJECTA CHAN 5<0M RAtIGi GAS 6 22985-06 GQQD
~ Xl/CC 33 R}5A7 AIR EJECTOR CHAN 7"MID RANGE GAS 1.80975-05 6009 Xl/CC 34 R15A9 AIR EJECTA CHAN 9 HI RANGc GAS 1.52999-03 6009 XI/CC 35 R31 AREA 3.'TEAM LINE A (SPING) } 01004-02 F t8/HR 36 R32 AIIEA 32 STEAM Llt(E 9 (BRING) 1.01004-02 t8/HR 37 CVH CV HYDROGEN CGNCENTRATIQtI .0 /
38 TCV03 CV BASEMEtlT LEVEL 6FT TEMP II3 86.3 6009 DEGF 39 TCV07 CV INTERMEDIATE LVL 6FT TEMP II7 89.4 G009 DEGF 40 TCV08 CV ltITiRMEcDIATE LVL 6FT TEMP II8 89.3 6009 DEGF 41 TCV09 CV INTERMEDIATE LVL 6FT TEMP II9 89.4 GGD9 DEGF 42 TCV10 CV INTERMEDIATc. LVL 6FT TEMP II}0 89.3 6009 D=GF 43 TCV}7 CV OPERATING LEVL 6FT TEMP tt}7 92.4 DEGF
Time: 0910-0915 Message: 21 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM
~f'. RI I R << IR Simulated Plant Conditions: See Attached Sheets ~essacee: """THIS IS AN EXERCISE"""
The following annunciators are received:
'-20 (Pressurizer Lo Press Trip 1873 psi)
'-19 (Pressurizer Lo Press Sl 1750 psig)
FOR CONTROLLER USE ONLY Controller Notes:
- 1) All safeguards equipment operates normally except the "B" Sl Pump. It is out for maintenance.
- 2) Sl flow is greater than 100 GPM.
Actions Ex ected:
- 1) Operators should perform the immediate and subsequent actions of E-0 (Reactor Trip or Safety Injection).
- 2) Operators should inform TSC of the loss of coolant accident.
- 3) TSC should declare a SITE AREA EMERGENCY in accordance with EPIP 1-0, "Ginna Station Event Evaluation and Classification," EAL: Reactor Coolant Leakage (RCS); LOCA identified inside Containment ~n Sl total flow ) 100 GPM using Fl-924/Fl-925. Appropriate notifications should be made per EPIP 1-5.
- 4) TSC should be expediting the maintenance on the "B" Sl pump.
- 5) EOF should be activating at this time, if not done earlier.
1993 EVALUATED EXERCISE Time: OV/~ MAJOR PARAMETERS ENGINEERED SAFEGUARDS Reactor Shutdown ES NO Hi h Head S.I. Pum s N-31 CPS FI-924 8 GPM N-32 CPS FI-925 GPM N-35 AMPS 1A. NSER STBY OOS N-36 AMPS 1B- INSERV STBY 0 Avg. Nuclear Power 1C. XNSER STBY OOS RCS Pressure 7CH PSIG BAST Leve PRZR Level Q.o g A RCP RUNNXNG TOPP Low Head S.I. Pum s B RCP RUNNING STOPPED FI-626 GPM 1A S/G Level 1A. NSER STBY OOS RECIRC 1B S/G Level 1B. NSER STBY OOS RECIRC 1A S/G Pressure ~~OPSIG RWST Level = 1B S/G Pressure PSXG Turbine/Generator ONLINE/ FFLIN Containment S ra Pum s 4 KV Buses NERGIZE DEENERGIZED FI-931A 0 GPM 480V Buses NERGIZE /DEENERGIZED FI-931B GPM DC Batteries A~BOVOLTS Bl OVOLTS 1A. SER STBY OOS Cnmt Pressure PSIG 1B. INSERV STBY OOS Cnmt Sump A Level o FEET NaOH Tan Level = ~% Cnmt Sump B Level
" Loop Hot Leg A Loop Cold Leg 3~
(2 'F
.3 INCHES oF Containm 1A.
Recirc Fans NSERV STBY OOS B Loop Hot Leg ~//~'F 1B. SERV STBY OOS B Loop Cold Leg OF 1C. S R STBY OOS RVLIS .3 4 1D. INSERV STBY OOS
- CET ~o-~O'F Post Aces en Dampers PE CLOSED S/G A Total Aux FW Flow ~9GPM S/G B Total Aux FW Flow ~~GPM Service Water Pum s 1A. NSER STBY OOS DIESEL GENERATORS 1B. I STBY OOS 1C. STBY OOS A. UNNING UNLOADED STBY OOS 1D. STBY OOS B.
TSC R RUNNING U OADED S BY ING UNLOADED TB OOS OOS A&B Header Pressure ~pl PSIG Security RUNNING UNLOADED STB OOS Com onent Coolin Rater Pum s 1A. NSER STBY OOS ENGINEERED SAFEGUARDS 1B. INSERV STB OOS Aux. w ter Pum s Surge Tank Level = ~~ 1A. ERV STBY OOS Standb Aux. Feedwater Pum s 1B. INSERV STBY OOS 1C. INSERV B OOS Turb. Driven INSERV TB OOS 1D. XNSERV TB OOS CST Level ~a~FEET
- CET = Average of Selected Core Exit Thermocouples
NOV 17i 1993 09'5 R. E. GINNA SII"iULATOR PAGE 1 TREND GROUP ASSIGIINENT SUGARY GRGL!P: EVENT1 PROCEDURE: EPIP 1-5 PLANT STATUS POII(T ID DESCRIPTION VA'i E. U. 1 ATMS ANTICIPATED TRANSIENT M/0 SCRAN ATWS AI.RN 2 RXT REA"TGR TRIP BREAKER STATUS RX TRIPPED ALRN 3 N31 SOISCE RANGE DETECTOR N-31 1.27497+04 6009 CPS t132 SGlHCE RAt(GE DETECTOR N-32 1.27937~04 G009 CPS 5 N35 INTERNEDIATE RANGE DETECTOR N-35 4.46682-10 6009 ANP 6 N36 INKFFDIATE RANBE DETECTOR t("36 3.64755-10 G009 ANP 7 NP AVERACE NUCLEAR POWER F 00 6009 / 8 PRCS RiACTOR COOLANT SYSTEN AVG PRESS 704. HALN PSIG 9 LPIR PRESSURIIER AVERAGc LEViL .0 LALN 10 FRCLA REKTOR CCCLA."O'OOP A AVG FLQM .0 It(HB i/ 11 FRCLB REA. TGR CGOLNT LOOP 8 AVG FLGM .0 It(HB 12 RXT16 RCPA BREAKER CAUS" RX TRIP TRIPPED ALRtl 13 RXT17 RCPB BREAKER CAUSE RX TRIP TRIPPED ALRtl 14 TSUBTC It,%RE TC SUBCOGLcC) NARGIN -8.9 LAL>> D=GF 45 LSGA STN Giti' NARROW RA%E AVG LEVEL 38.8 6009 / 16 LSGB STN GEN 8 NARROW RAhGE AVG LEVEL 43.6 GOOD X 17 PSGA STN CEN A AVERAGE PRESSURE 1010. 6009 PSIG
!8 PSGB STN icEN 8 AVERAGE PRESSURE 1002. 6009 PSIG 19 GENBKR1 GitKRA!OR GN LINE BREAKER 1G1372 TRIPPED ALRN 20 Git(BKR2 GBFRATOR ON LINE BRcEAKcER 9X1372 TRIPPED ALRN 21 BUS11A BUS 11A SIMPLY BREAKER TRIPPiD ALRtl 22 BUS118 BUS 118 SUPPLY BREAKER TRIPPED ALRI(
BUS12A NOT TERNINATEB ON PPCS (7/19/91) t/OT TRIP DiL 24 BUS128 t(OT TERNINATED ON PPCS (7/19/91) t(OT TRIP DcEL 25 Bl }A12A BUS 11A TO 12A TIE BREAKER NOT TRIP ALRN 26 8118128 BUS 118 TQ 128 TIE BREAKER NQT TPIP ALf4 27 PCV CQNTAIt(tiENT AVERAG" PRcESSURE 28. Z HALI( PSIG 28 LSUNPA COtlTAI)INENT SUNP A AVERAGE LEVEL lb.2 KALI! FEET 29 LO942E SUtP 8 LEVEL 8 INCHES (TRA!N A) LGMcER 6009 30 L0943E SUtP 8 LEVEL 8 INCHicS (TRAiN 8) LOWiR 6009 31 L0942D SUtF' LEVEL 78 INCHES (TRAIN A) LOWER 6009 L0943D SUi%' LEVEL 78 INCHES (TRAIN 8) LOMER GOOD 33 L0942C SUP 8 LEVEL 113 INCHES(TRAIN A) LOMER 6009 34 LO943C SUNUP 8 LEVEL 113 ItKHES(TRAIN 8) LBERR 6009 35 L09428 SUtP 8 LB'80 INCHES(TRAIN A) LOWER G009 36 L09438 SUtP 8 LEVEL 180 INCHES(TRAIN 8) LOWER G009 37 L0942A SUtt? 8 LEVEL 214 It<CHES(TRAIN A) LOMER G009 38 L0943A SU"P 8 LEVEL 214 It(CHcS(TRAIN 8) LOWER GOOD
'i9 T0409A RCLA HGT LEG TEtiPERATURE 512.7, 6009 DE6F 40 T0410A RCLB HOT l.EG TENF'ERATUR-" 516.9 6009 DEGF 41 T0450 RCLA COLD LEG TEIZERATURE 354.3 6009 BiGF 42 T0451 RCLB COLD LEG TEYiPERAT(BE 201.3 6009 DEGF 43 TAKAMiD RCLA TAVG (THOT/TCGLD MIDE RNG) 433.5 6009 DE6F 44 TAVGBMID RCLB TAVG (THOT/TCGLD MIDE RNG) 361.6 GOOD DE6F 45 LRV REACTOR VESSEL AVERAGE LEVEL 54.3 LALN /
46 TCCORE El.l Ih ORE TC AVERAGE TBP 507.0 600>> BE6F FAUXFMA S/6 A :OTAL AUX Ftt'DMATER FLOW 49. 6009 GPiN Fs FAUXFMB S/6 8 TOTAL AUX FEEOMATER FLOW 51. 6009 GPN 49 BKRO81 NTR AUXILIARYFEEDMATER PUIIP A Ot( G009 50 BKR082 tlTR AUXILIARYFEEBMATER PU)IP 8 GN 6009 51 V3505 AUX FM PUI(P STEA)I SUPPLY VALVE A CLOccD GOOD 52 v3504 AUX FM PUtiP STEAN SUPPLY VALVE 8 CLOSED 6009
NGV 17) 1993 09:15 R. E. GIt5A SIMLVTOR PAGE 2 TREND GROUP ASSIGIENT I)")MARY GRGL'P: EVEt<T1 PRXEDURE: EPIP 1-5 PLANT STATUS POINT ID, DFS"RIPTIGN VALUE QUAL E. U. 53 FSIA SAF""TY INECTIOM LOOP A AVG FLOW 163. GOOD GPM 54 FSIB SAFETY IN:ECTION LOOP B AVG FLOW 281. GOOD PM 55 P 2160 SERVICE MATER PUttPS A <<" B HB&R 87. GOOD PSIG 56 P2161 SENICE WATER PUMPS C h D HEADER 86. GOOD PSIG 57 BKR041 SBNICE MATER PUttP A GVi GOOD 58 BKR042 SERVICE MATER PUtfP B Ott GOGO 59 BKR043 SERVICE MATER PUMP C GN KGD 60 BKR044 SHNICE MATER PUttP D GW ROD
t(QV 1?i 1993 09'16 R. E. GINA SIMULATOR PAGE TREND GROUP ASS IGNNBIT PJN'IARY GROIP: EVEt(T2 PROCEDURE: EPIP 1-5 PLAtIT STATUS POINT ID DESCRIPTION VALLEY MAL E. U. 1 F0619 CGi%'ONENT CGQ'NB LOOP TOTAL FLM 884. LALN GPN 2 LRMST REFUELING MATER STORAGE TAII LVL 93.5 6000 / 3 MS033 33 FOOT LEM Mlt(D SPEED 6.0 K00 NPH 4 MD033 33 FOOT LEVEL MIND DIRECTION 356. 6000 DEG. 5 MT033 33 FOOT LEVEL TEMPERATUR." 43.3, GOOD DEGF 6 MT250 250 FOOT LEVEL TEMPERATURE 43.9 6000 DEGF 7 MDT2 250 TO 33 FOOT LEVEL H.TA TEMP ~ 6 6009 DEGF 8 RO! AREA I-COI(TR(X. ROOM 8.75992"02 6000 t8/HR R02 AREA 2 CQI(TAIIENT 7.80727403 HALN ts/HR 10 R05 AREA 5-SPENT FUEL PIT 3,09029~M 6000 N/HR
!1 R09 AREA 9"LETDOWN LINE tlONITOR 2.66072+01 6000 tm/HR 12 R34 AREA 34 - AUX BLDG CV SPRAY PUMP 3.14412+00 GGOD %/HR !3 R35 AREA 35-PASS SL(PLE PANEL 1.096484N GOD0 ta/HR 14 R!OA COWTAItlMB1T IODINE I',OWITQR R!OA 9.66051+06 HALI( CPM !5 Rli COt(TA!NNENT AIR PART ICIJ ATE 9.57744+06 HALM C%
16 R!2 CGWTAIt(MEt(T GAS MONITOR 1.01303407 HEt(6 CPN
!7 R!OB PLWT VENT IODINE MONITOR R!OB 8.45036~N 6000 CPM 18 R13 AUX BLDG EXHAUST AIR PNTICULATE 2.55932+02 GOOD CPN
!9 R!4 AUX BLDG EXHAUST GAS M(NITOR 5,40910<01 6000 CPM 20 R!8 LIKIID MASTE DISPOSAL NNITOR I 05925403
~ 6000 CPN 21 R19 STEA!I GEt(ERATQR BLOMDOW DRAIN I ~ 99813<03 6000 CPN 22 R29 AREA 29-CGWTAINNEWT HI% RANGE 8.N638~00 6000 R/HR 23 R30 AREA 30-CGt(TAIti&t(T HIGH RANGE 8.00638+N 6009 R/HR 24 R15 COtlDENSER AIR EJECTGR EXHAUST 1 ~ 40241~03 6000 CPN 25 RIZA5 CV VEt(T CHAW 5-LGM RAI(K GAS 4.20511-05 G000 UCI/CC 26 R!2A6 CV VENT CHAN 6-AREA GAtIA 2. 67992<2 6000 t8/HR 27 R12A7 CV VENT CHAN 7-N!0 RAtlGE GAS 4.2051!-05 K00 UCI/CC 28 R!2A9 CV VENT CHAN 9-HIGH RANE 6AS 9.99987-04 6000 UCI/CC 29 R14A5 PU5T VEt<T CHAt) 5-I.OM RANGE GAS 2.30991-06 UCI/CC 30 R!4A7 HA"IT VENT Cf!AW 7-NID RAt(GE GAS 4.62984M 6000 UCI/CC 31 R14A9 PLANT VEt(T Cf!At( 9-HIGH RANGE GAS 9.l099?M GOOD UCI/CC 32 R!5A5 AIR EJECTOR CHAW 5-LGM RANGE GAS 6.2298~ 6000 UCI/CC 33 R15A7 AIR EJECTOR CHAt( 7-M!0 RANGE GAS 1.80975-05 K09 UCI/CC 34 R!5A9 AIR EJECTOR CHAW 9 HI RANGE GAS 1.52999-03 G000 UCI/CC 35 R31 AREA 3! STEAN'LINE A (SPlt(6) !.01004-02 6009 NR/HR 36 R32 AREA 32 STEAN LINE B (SPING) 1.01004-02 6000 N/HR 3? CVH CV HYDROGEN COt(CEt(TRATIOt( .0 G000 /
38 TCV03 CV BASENEt(T L"VEL 6FT TEMP (I3 203.1 6009 0""GF 39 TCV07 CV It(TERNEDIATE LVL 6FT TEtIP II? 215.8 K09 DEGF 40 TCVOB CV IWTERI(EDIATE LVL 6FT TEMP I8 215.7 GC00 DEGF 41 TCV09 CV INTERMEDIATE LVL 6FT TEtlP I9 215.8 DEGF 42 TCV!0 CV INTERNEDIATE LVL 6F'T TEMP IIO 2!5.7 DEGF 43 TCV!7 CV QPERATItiG LEVL 6FT TEMP ttl? 228.2 DEGF
Time: 0910 Message: 22 GINNA STATION 1993 EVALUATED EXER ISE MESSAGE FORIVI MMMI:A III ygg <<ITBBT B gl gA ll yB Igl gg BB "8" for RHR System leakage per E-1 and RHR pump trip problem. Simulated Plant Conditions: See the Attached Mini-Scenario ~Messa e: """THIS IS AN EXERCISE>>>>>> FOR CONTROLLER USE ONLY Controller Notes:
- 1) Provided information verbally when appropriate actions are simulated or investigations conducted.
Antici ated Results: 1 j As per Mini-Scenario.
GINNA STATION 1993 EVALUATED EXERCISE MINI-SCENARIO TITLE: Checking Auxiliary Building Sub-Basement for RHR system leakage per E-1 and "B" RHR Pum ri roblem. Expected scenario start time: 0910 hours INITIALCONDITIONS:
'CS has experienced a large break LOCA.
'A" and "B" RHR pumps running.
METHOD OF INITIATION:
'tep 18 of E-1 dispatches an Auxiliary Operator/TSC Team to check the Auxiliary Building Sub-Basement for RHR System leakage.
't is expected that this action will be requested in conjunction with the checking of the tripping of the "B" RHR pump at 0915 hours.
INDICATIONS: CONTROL ROOM:
'larm window J-9 (Safeguard Breaker Trip).
EXPECTED SEQUENCE OF ACTIONS' Investigate Auxiliary Building Sub-Basement for signs of RHR system leakage.
= 'otice water dripping from the large pipe between Containment and MOV-850A.
Notice, after closer inspection of the dripping water, what appears to be an approximately 3 inch crack at the bottom of the pipe.
'otice that radiation levels in the area are increasing rapidly.
'nvestigate "B" RHR pump for signs of any problems:
'otice burnt insulation smell.
'otice motor is hot to the touch.
'eport all of the above observations to the Control Room/TSC at 1000 Hours i.e. no before or no a er ~
FINAL CONDITIONS: Observations are reported to Control Room at 1000 Hours and Auxiliary Operator/TSC Team leaves the area immediately due to increasing radiation.
Time: 0915 Message: 23 I GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM MMM: M I C << IC Simulated Plant Conditions:
~Messa e: <<<<<<THIS IS AN EXERCISE"""
The following annunciator is received:
~ J-9 (Safeguard Breaker Trip)
'OR CONTROLLER USE ONLY Controller Notes:
- 1) When board operators check Control Board, inform them that the "B" RHR pump switch light indicates a white light.
- 2) Operators should attempt to restart the "B" RHR pump 5 times per AR-J-9. IT Wll I NOT RESTART.
Antici ated Results:
- 1) Operators should try to restart the "B" RHR pump 5 times per AR-J-9. IT WILL NOT RESTART.
- 2) Operators should notify an Auxiliary Operator to check the "B" RHR pump and motor. An Auxiliary Operator may already be in the Auxiliary Building per step 18C of E-1.
- 3) Operators should notify the TSC of the tripping and failure to restart of the "B" RHR pump.
- 4) Operators performing the applicable actions of E-1.
- 5) TSC should send a team into Auxiliary Building to check out the "8" RHR pump if Auxiliary Operator not already in there.
- 6) TSC should be evaluating the loss of safeguards equipment and be expediting repairs as quickly as possible.
- 7) TSC should be informing the EOF of plant status, actions being taken and any required needs.
- 8) EOF should be evaluating plant conditions and taking actions as required.
Time: 0920 Message: 24 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM ~Mf: 8 I C tR Simulated Plant Conditions: ~INesse e: +""THIS IS AN EXERCISE""" The following annunciator is received:
~ J-24 (Emergency Diesel Gen I A Panel)
FOR CONTROLLER USE ONI Y Controller Notes:
- 1) When board operators check Control Board, inform them that the "A" Emergency Diesel Generator indicates no voltage.
Antici ated Results:
- 1) Operators should send an Auxiliary Operator out to the "A" Emergency Diesel Generator Room to check the local alarm panel and the Emergency Diesel Generator.
- 2) Operators should inform the TSC of the tripping out of the "A" Emergency Diesel Generator.
Time: 0920 Message: 25 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM A iOp <<1
*ii~li i9 "A'" E ki g yO'i I G L Alarm Panel and the Emergency Diesel Generator.
Simulated Plant Conditions: See the Attached Mini-Scenario ~Messe e: """THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Controller Notes:
- 1) Provide information verbally when appropriate actions are simulated or investigations conducted.
Antici ated Results:
- 1) As per Mini-Scenario.
GINNA STATION 1993 EVALUATED EXERCISE MINI-SCENARIO TITLE: Checking "A" Emergency Diesel Generator Local Alarm Panel and the Emer enc Diesel Genera or. Expected scenario start time: 0920 Hours INITIALCONDITIONS' "A" Emergency Diesel Generator running due to a'safety injection activation at 0910 hours.
'afety Injection was activated due to an RCS large break LOCA.
METHOD OF INITIATION:
'A" Emergency Diesel Generator trips out at 0920 due to low level lube oil pressure.
'ontrol Room requests Auxiliary Operator to check the local alarm panel and the emergency diesel generator.
INDICATIONS'ONTROL ROOM:
'larm window J-24 (Emergency Diesel Generator 1A Panel).
'o voltage on "A" Emergency Diesel Generator.
LOCAL:
"Lube Oil Low Pressure" A'larm.
EXPECTED SEQUENCE OF ACTIONS:
'nvestigate "A" Emergency Diesel Generator local alarm panel an "A" Emergency Diesel Generator for signs of trouble.
'otice on Local Alarm Panel a "Lube oil low pressure" alarm.
'otice a large amount of oil on the floor by the large lube oil filter on the east side of engine.
'otice engine oil level extremely low if he checks engine oil level.
'eport all of the above observations to the Control Room/TSC at
~9935 9 FINAL CONDITIONS:
Observations are reported to Control Room/TSC at 0935 hours.
Time: 0925 Message: 28X GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM ~f: E g YG d Simulated Plant Conditions: ~IVlesss e: "+ "THIS IS AN EXERCISE" >>" Declare a SITE AREA EMERGENCY in accordance with EPIP 1-0, "Ginna Station Event Evaluation and Classification; EAL: Reactor Coolant Leakage (RCS): LOCA Identified Inside Containment and Sl Total Flow ) 100 GPM using Fl-924/FI-925, FOR CONTROLLER USE ONLY Controller Notes: 11 ll lylfG RG GYR d d 1 d. if emer enc classification discussions are in ro ress. Antici ated Results:
- 1) Deliver contingency message if SITE AREA EMERGENCY not declared or is not being discussed.
Time: ~09 0 Message: 27 GINNA STATION 1993 EVALUATED EXERCISE IVIINI-SCENARIO <<<<<<t: << I<<C << Itl Simulated Plant Conditions: See Attached Sheets ~Messe e: <<" <<THIS IS AN EXERCISE" >>" FOR CONTROLLER USE ONLY Controller Notes: Antici ated Results:
- 1) Operators performing the applicable actions of E-1.
1993 EVALUATED EXERCISE Time: 873< MAZOR PARAMETERS ENGINEERED SAPEGUARDS Reactor Shutdown ES NO Hi h Head S. . Pum s N-31 OO CPS FI-924 5 GPM N-32 ~~CPS FI-925 GPM N-35 ~o-/I AMPS 1A. INSERV STBY OOS N-36 ~o~iAMPS . 1B. INSERV STBY Avg. Nuclear Power Q? 1C. NSER STBY OOS RCS Pressure ~3PSXG BAST Leve = 0 PRZR Level QF0 A RCP RUNNING STOPPED Low Head S.I. Pum s B RCP RUNNING STOPPED FI-626 OO GPM lA S/G Level ~ZS~ 1A. NSER STBY OOS RECIRC 1B S/G Level 1B. INSERV STBY 0 RECIRC lA S/G Pressure gj~6 PSIG RWST Level = 1B S/G Pressure >'f PSIG Turbine/Generator 0 LINE/ FFLINE Containment S ra Pum s 4 KV Buses NERGIZE DEENERGIZED FI-931A 0 GPM 480V Buses NERGIZE /DEENERGIZED FI-931B A GPM DC Batteries A~90 VOLTS B~3d VOLTS 1A. STBY OOS Cnmt Pressure ~ I PSIG 1B. NSER STBY OOS Cnmt Sump A Level la 2 FEET NaOH,Tank evel = QQ Cnmt Sump B Level
" Loop Hot Leg )7/~9 OFINCHES Containment Recirc Pans A Loop Cold Leg i0 .8 'F 1A. STBY OOS B Loop Hot Leg g73'I 'F 1B. INSERV STBY OOS B Loop Cold Leg ~ + OF 1C. S R STBY OOS RVLIS 1D. INSER STBY OOS
- CET 0F Post Accident Dampers OPEN CLOSED S/G A Total Aux FW Flow ~GPM S/G B Total Aux FW Flow ~/ GPM Service Water Pum s 1A. STBY OOS DIESEL GENERATORS 1B. STBY OOS 1C. STBY OOS A. RUNNING UNLOADED STBY OS 1D. S STBY OOS B. RUNNING UNLOADED STBY OOS A&B Header Pressure PSIG TSC RUNNING UNLOADED TB OOS Security RUNNING UNLOADED TBY OOS Com onent olin Water Pum s 1A. SER STBY OOS ENGINEERED SAPEGUARDS 1B. INSERV TB OOS Aux. Fee ater Pum s Surge Tank Level = ~>
1A. STBY OOS Standb Aux. Feedwater Pum s 1B. NSERV TBY OOS 1C. INSERV OOS Turb. Driven INSERV TB OOS 1D. INSERV STB OOS CST Level ~~~a FEE
- CET = Average of Selected 'Core Exit Thermocouples
NQV 17i 1993 09:29 R. E. GINA SIHL&TQR PAGE 1 TREND GROUP ASSIGtttKt(T S(J)IHARY GROUP: iVENT1 PROCEDURE: EPIP 1-5 PLAttT STATUS POINT !D DESCRIPTION VALL'E ()UAL E. U. ASS At(TICIPATED TRANSIENT N/0 SCRAN AT)IS ALRN 2 RXT REA.TGR TRIP BREAKER STATUS RX TRIPPED ALRt! 3 N31 SQRCE RANGE DETECTOR I(-3} 4.0}328~0} 6009 CPS N32 SOIRCE RANK DETECTOR N-32 4.}543}+0} 6009 CPS 5 t)35 1)ITERHEDI ATE RANGE DETECTOR N-35 1 ~ 00925-1} 6009 Al(P 6 N36 INlcRHiDIATE RANGi DETECTOR N-36 1.00461-1} 6009 AHP 7 HP AVERAGE NL(CLEAR PQ)IER .00 6009 8 PRCS RiACTOR COOLANT SYSTEHi AVG PRESS 39. LALN PSIG LP2R PRESSURI2ER AVERAGc l&S ~ 0 LALt( / 10 FRCLA REACTOR COOLANT LOOP A AVG FLFA ~ 0 i'NHB / FRC' REACTOR CGOLNT LOOP 8 AVG FLN .0 Iti(IB RXT16 RCPA BREAKER CAUSE RX TRIP TRIPPED ALRN
!3 RXT}7 RCPB BREAKER CAUSL RX TRIP TR!PPED ALRII i4 TSUBTC ItiZR TC SUBCOOLED t}4%IN 5.7 L'kR>> DEBF !5 LSM STH GEN A t(ARRO)t RANGE AVG LEVcJ. 42.7 GOOD /
ib LSBB STH BEI'i' t)ARRO'A RAN6E AVG LEVciL 47.7 6009 7 (7 PSBA STH BEN A AVERAGE PRESSJRE 885. 6009 PSIG 18 PSGB STH Bitt 8 AVERAGE PRESSURE 869. 6009 PSIG GER! BcC=RATGR GN LINE BRcEAKER !61372 TR!PPED ALRt( 20 BEIL((KR2 GitKRATQR ON LINE BREAKER 9X}372 TR!PPED ALRH 21 BUS1 }A BUS 11A SL'PPLY BREAKER TRIPPED ALRH 22 BUS}}B BUS 118 SUPPLY BREAKER TRIPPED ALRII BUS}2A IQT TcRHINATED ON PPCS (7/!9/91) NOT TRIP OEL 24 BUS128 NOT TERHINATED Ot( PPCS (7/19/91) t(0":( TRIP DEL 25 Bl}A}2A BUS!!A TG 12A T!E BRiAKER t(OT TF(IP ALRN 26 8! 18128 BUS 118 TO 128 T!E BREAKER t(QT TRIP A'N 27 PCV CONTAII,'Hit(T AVERABc PRESSURE 4.91 HALH PSIG 28 LSU;"PA CGNTAINHENT SUt}P A AViRA6E LEVEL 3}.2 HEtiB FiZT 29 L0942E S(JP 8 LEVciL 8 INCHES (TRAIN A) HIBHEP, It(!(9 30 L0943E SU~>>' LEVEL 8 INCHES (TRA!t( 8) HIB)( INHB 3! L0942D SU"P 8 LEVEL 78 !NCI:"S (TRAIN A) HIBIKR ALRN 32 L09439 SU% 8 LEVEL 78 INCHES (TRAIN 8) HI6HEP. ALRII 33 L0942C SUHP 8 LEVEL l}3 INCHES(TRAII( A) LOMER 6009 34 L09430 SUN' LEVEL 113 INCHES(TRAIN 8) L04'ER 8009 3J L09428 SSP 8 LEVEL 180 INCHcS(TRAIN A) LO)lER 6009 36 L09438 SUtP 8 LEVEL 180 INCHES(TRAIN 8) LQ)iciR G009 37 L0942A PJ'S 8 LEVEL 214 Iti HES(TRAIN A) LG)IER 6009 38 L0943A SUtP 8 LEVciL 214 ItiCHES(TRAIN 8) LONER 6009 39 T0409A RCLA HOT LEG TEHPERATSK 271.5 G009 DEGF 40 T04}OA RCLB HOT LEG TEHPERATURE 273.9 6009 I)=BF 41 T0450 RCLA COLD LEG TENPERATLRE 148.8 G009 DEGF 42 T0451 RC(LB COLD LEG TENPERATURE 131.2 6009 DEGF 43 TAVGAMID RCLA TAV6 (THOT/TCO( 9 WIDE RNG) 210.1 6009 DEBF 44 TAVGBNID RCLB TAVG (THOT/TCOLD HIDE RNB) 202.5 6009 DEGF 45 LRV RHETOR VESSEiL AVcERABE LEVEL 74.4 LALN 46 TCCORE E}.l ItiiCGPE TC AVERAK TEHP 265.1 600>> DFGF 47 FAUXFNA S/G A TOTAL AUX FEEDS(ER FLGN 0. C009 GPH 48 FAUXFNB S/G 8 TOTAL AUX FEEDKA(cR FLM }7. 6009 GPt! 49 BKR081 HTR AUXILIARYFEED'AATER FUI(P A GN GOOD 50 BKRO82 t!TR AUXILIARYFEEOWATER FU)IP 8 ON 6009 51 V3505 AUX Fti PUNP STiAN SL(PPLY VALVE A CLOSED 6009 52 V3504 A(JX FM PUK STEAN SUPPLY VALVE 8 CLOSED 6009 P5
t/OV 17i 1993 09:29 R. E. Glt5A SlttULATOR PAGE 2 TREND GRQUP AssIGOEhT BURRY GROUP: LVENT1 PROCEOLSE: EPIP 1-5 PLANT STATUS POINT fn DESCRIPTION VALUE QUAL E. U. 53 FSIA SAFETY INJECTION LOOP A,AVG FLOM 185. GOOD GPtt 54 FSIB SAFETY Itt'ECTION LOCiP B AVG FLOM 380. GOOIl Ptt 55 P21h0 SERVICE MATER PUttPS A h B HEADER 87. GOOD PSIG 56 P2161 SERVICE MATER PUttPS C 5 O HEADER 86. GOOD PSIG 57 BNR041 SERVICE MATER PUttP A ON GOOD 58 BKR042 SERVICE MATER PUttP B ON GOOD
,59 BKR043 SERVICE MATER PUttP C ON GOOD 60 INR044 SERVICE MATER PUtlP D ON Goon
NOV 17> 1993 09:30 R. E. Gite SIMULATOR PAGE 1 TRFND GROUP A%16ttMENT SUtlMARY 6ROL'P: EVENT2 PROCEDLtRE: EPIP 1"5 PLANT STATUS POINT fD DESCRIPTION VALUE E. U. 1 F0619 COMPONENT COOLING LOOP TOTAL FLW 892. LALtl GPN 2 LRWST REFUELIWG WARD STORAG"" TANK LVL 78.1 GOOD X 3 WSO33 33 FOOT LEVEL WIND SPEED 5.6 6009 AH 4 WD033 33 FOOT LEVP WIND DIRECTIOtl 295. 6009 D="G. 5 WT033 33 FOOT LEVEL TEMPERATURE 43.3 GOOD DF6F 6 WT250 -.250 FOOT LEVP TENPERATURE 44.0 GOOD DE6F 7 WDT2 250 TO 33 FOOT LEVEl. DELTA TEllP ~ 7 GOOD DEGF 8 R01 AREA I-COWTRO'OON 8.81048-02 GOOD l8/HR 9 R02 AREA 2-CONTAlt(MENT 8.26987+03 HALN %/HR
!0 R05 ARiA 5-SPEt(T FUiL PIT 3.14412+00 GOOD t8/HR 11 R09 AREA 9-LETDQW LINE NONITOR 2.66072+01 GOOD NR/HR 12 R34 ARE 34 - AU)( BLDG CV SPRAY PL%i
~ 2.90068+00 GQQD t8/HR 13 R35 AREA 35"PASS SAMPLE PANEL 1.09648400 GQQD t8/HR 14 RIOA CONTAINMENT IODINE MONITOR R10A 9.66051+06 HALN CPN 15 R11 CGWTAI tST AIR PARTI'TE 9.95683~06 HALN CPN 16 R12 CONTAINMENT GAS MONITOR 9.99992+06 HENG CPN 17 RIOB PLNT VB4T IODINE MONITOR R10B 1.23027%1 6009 CPN
!8 R13 AUX BLDG EXMST AIR PARTICULATE 2.48313%2 6009 CPN 19 R14 AUX BLDG EXHAUST GAS tlQNITGR 7.03879tOI I
GOOD CPN 20 R18 LIQJID WASTi DISPOSAL NQtlITQR 1.0917&03 GOOD CPN 21 R19 STEAN GEtFRATGR BL(LDOW DRAIN 1.99813+03 6009 CPN 22 R29 ARE 29<Qt(TAIWMENT HI% RA)LK 8.00638+00 6009 R/HR 23 R30 AREA 30-CONTAINMENT HIGH RANGE 8.00638400 6009 R/HR 24 P.15 COND" tlSER AIR E JiCTOR EXHAUST 1.40241+03 GOOD CPtl 25 R12A5 CV VB(T CHAN 5-LOW RAtiGE GAS 4.20511-05 GOOD XI/CC 26 R12A6 CV VENT C84 6-AREA GAMA 2.67992-02 GQGD )8/HR 27 R12A7 CV VENT CHAW 7 NID RANGE GAS 4.20511-05 6009 XI/CC 28 R12A9 CV VENT CHAN 9-HIGH RAKiE 6AS 9.99787-04 GOOD UCI/CC 29 R14AS PLOT VENT CH4tt 5-LGW R4NGE GAS 2.30991-06 GQGD UCI/CC 30 R14A7 PLANT VENT CHAtl 7-NID RANGE GAS 4.62984-06 GOOD XI/CC 31 R14A9 PLANT VENT CK4N 9-HIGH RAN6i GAS 9. 10997M 6009 XI/CC 32 R15A5 AIR EJECTOR CHAN 5 LGW RANGE GAS 6.22985-06 GOOD XI/CC 33 R15A7 AIR EJiCTGR CHAN 7-tlID RANGE GAS 1.80975-05 GOOD XI/CC 34 R15A9 AIR EJECTCR CLIW 9-HI PANGE GAS 1.52999-03 GOOD XI/CC 35 R31 AREA 31 STEAN LIR"" A (SPIt(6) 1.01004-02 6009 NR/HR 36 R32 ARE 32 STEAN LIRE B (SPING) 1.01004-02 GOOD t8/HR 37 CVH CV HYDROGEN COt(CB(TRATIGW .0 6009 I/ 38 TCV03 CV BASENEWT LEVH. 6FT TEMP I3 138.4 GOOD 9" GF 39 TCV07 CV INTERMEDIATE LVL 6FT TEMP l)7 135.9 GOOD DEGF 40 TCV08 CV IWTERYiEDIATE LVL 6FT TBP 58 135.6 6009 DEGF 41 TCV09 CV IWTERNEDIATE LVL 6FT TEMP ()9 135.9 6009 DE6F 42 TCV10 CV IWTERNEDIATE LVL 6FT TEMP I10 135.6 DEGF 43 TCV17 CV OPERATING LEVL 6FT TEMP l)17 133.1 6009 DEGF
Time: 1000-1 500 Message: 27.1 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM
- TECE g C Pt .Eggtg TM g dg pp M tt
~Massa e: """THIS IS AN EXERCISE"""
Please provide appropriate responses to the following questions/issues raised by simulated NRC staff:
- 1. What is the status of emergency?
- 2. What if any PAR's have been recommended?
- 3. NRC response team members will be arriving in Rochester; please assure adequate working space at EOF (2 people), TSC (2 people) and JENC (1).
- 4. Please provide qualified staff member to man the HPN line in the EOF.
- 5. Please have most recent radiological and meteorological data provided via the HPN line or by fax.
- 6. How many EBS messages have been issued?
~ What PARS have been implemented by the Counties and NYS?
FOR CONTROLLER USE ONLY Controller Notes:
- 1) Deliver throughout the Exercise between 0930-1400 hrs . per Controller discretion.
- 2) Deliver by telephone call or by speed message.
Actions Ex ected:
- 1) TSC Emergency Coordinator or EOF/Recovery Manager should be responsive to information requests, but should not allow the simulated NRC staff member to prevent them from attending to their principal duties.
Time: 0935 Message: 28 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM RpiTRpiigAEgyOi IG<<P Simulated Plan Conditions: See the Attached Mini-Scenarios ~essacee: <<<<<<THIS IS AN EXERCISE" <<" FOR CONTROLLER USE ONLY Controller Notes:
- 1) Provide information when appropriate actions are simulated or investigations conducted.
Antici ated Results:
- 1) As per Mini-Scenarios.
GINNA STATION 1993 EVALUATED EXERCISE MINI-SCENARIO TITLE: "A" Emer enc Diesel Generator. Scenario expected start time: 0935 INITIALCONDITIONS: The diesel generator tripped on a "Lube Oil Low Pressure" at 0920 after being started at 0910 from a safety injection activation. METHOD OF INITIATION: Remote alarm in the Control Room on "A" Diesel Generator. Auxiliary Operator reports on Low Pressure on Lube Oil was cause for trip, this is reported to Emergency Coordinator of Diesel failure. INDICATIONS: CONTROL ROOM: Alarm on "A" Diesel Generator LOCAL: "Lube Oil Low Pressure" alarm at 45 psi indicator flashing. Oil on floor near lube oil filter and under engine. EXPECTED SEQUENCE OF ACTIONS: Trouble report written for repair of "A" Diesel Generator. Planner and Mechanic sent to Diesel Room to trouble shoot problem with unit. Team reports back of flange failure at 1005 hours, work order developed to replace gasket and refill the engine with lube oil. Maintenance crew sent to Diesel Room to clean up the oil spill. (1/~ hours to complete) Inventory control personnel make arrangements to go to warehouse off site to bring in lube oil for Diesel Delvac 1240. Security will need to be contacted to allow for transporting oil through gate. Procedure M-15.2 "A" or "B" Diesel Generator Minor lns ection
and Maintenance Chan e Flex Hos on Lube Oil S s em. M-37.130 Dis ssembl S. Re ssem I of Pi e Flan e Connec ions. Steam Fitters and Machinist go to shops for tools and gasket material to replace failed gasket and return oil to sump. Gasket is replaced by fitters in a 1 hour time frame. The machinist add oil to engine after oil arrives from warehouse. (1 hour to pump in 225 gals of cold oil). Oil level in sump returned to proper level, line up of engine made by operation to put unit back into service. REPAIR TIME: The repairs to the engine to be completed by 1145, estimate of 2/2 hours to complete. (Note: this time frame may not be long enough due to the oil being stored in offsite warehouse in real conditions.) FINAL CONDITIONS: 1A Diesel Generator is back in service supplying power for the scenario. (1155 hours)
GINNA STATION 1993 EVALUATED EXERCISE MINI-SCENARIO TITLE: "A" Emer enc Diesel Genera r Problem from L w Lube Oil
~Press re.
Scenario expected start time: 0935 INITIALCONDITIONS: Started automatically because of Safety Injection actuation, tripped out at 0920 hours. METHOD OF INITIATION: Tripped out, operations sent out Auxiliary Operator to investigate. INDICATIONS:
" "A" Emergency Generator tripped out at 0920 hours.
" Auxiliary Operator checks local alarm, low lube oil pressure.
" Located large amount of oil on floor the large lube oil filter by on side of the engine. 'ast EXPECTED SEQUENCE OF ACTIONS:
" Repair team investigation finds oil leak on flange between pump and oil filter.
" Reports to TSC at 1005 hours approximately 2/~
hours for repairs, and obtains holds as required for maintenance,
" Fitters simulates installing new gasket.
" Inventory Control transporting oil from storage.
" Mechanics simulates replacing oil as required.
" Maintenance to clean area as required for safe operation.
FINAL CONDITIONS: At 1145 hours the repair team will report to TSC that the Generator repairs on "A" Diesel will be completed in approximately 15 minutes. At 1155 hours the repair team will report that repairs are completed.
Time: 0945 Message: 29 GINNA STATION 1993 EVALUATED EXERCISE IVIESSAGE FORIVI 5 I 5 << IR Simulated Plant Conditions: See the Attached Sheets Messa<ee: >>" >>THIS IS AN EXERCISE" >>>> FOR CONTROLLER USE ONLY Controller Notes:
- 1) At 0935 hours the Auxiliary Operator checking the "A" Emergency Diesel Generator trip problem reports his observations to Control Room/TSC. See 25.
Antici ated Results:
- 1) Operators should inform TSC of "A" Emergency Diesel Generator problem.
- 2) TSC should send a repair team out to evaluate and repair the "A" Emergency Diesel Generator problem.
R') RR IRR
1993 EVALUATED EXERCISE Time: MAZOR PARAMETERS ENGINEERED SAFEGUARDS Reactor Shutdown YE NO Hi h Head S.I. Pum s N-31 CPS FI-924 GPM N-32 N-35
~L
~0~(AMPS CPS FI-925 2. 3 GPM 1A. INSER STBY OOS N-36 /~~/AMP S 1B. INSERV STBY 0 Avg. Nuclear Power CI 1C. NSER STBY OOS RCS Pressure E PEXG BAST Leve PRZR Level O A RCP RUNNING 0 Low Head S.I. Pum s B RCP RUNNING S OPPE FI-626 / 00 GPM 1A S/G Level . r 1A. R STBY OOS RECIRC 1B S/G Level 1B. INSERV STBY S RECIRC 1A S/G Pressure PSIG RWST Level =
1B S/G Pressure 2 PS G Turbine/Generator ONLINE/ FLINE Containment 8 ra Pum s 4 KV Buses ENERGIZE /DEE RGIZED FI-93 1A~~~GPM 480V Buses NE GIZED DEENERGIZED FI-93 1B & GPM DC Batteries A~VOLTS B/ZO VOLTS 1A. R STBY OOS Cnmt Pressure o~fPSIG 1B. INSERV STBY OOS Cnmt Sump A Level ~MFEET NaOH Tank Level = ~G 4 Cnmt Sump B Level +'$00/)INCHES
" Loop Hot Leg 2 OF Containment Recirc Pans A Loop Cold Leg @g,Z OF 1A. ER STBY OOS B Loop Hot Leg ;M4M'F 1B. NSE STBY OOS B Loop Cold Leg ~( 2 OF 1C. NSER STBY OOS RVLIS 8'I e 1D. INSER STBY OOS
- CET 0F Post Accident Dampers PE CLOSED S/G A Total Aux FW Flow & GPM S/G B Total Aux FW Flow f GPM Service Water Pum s 1A. SER STBY OOS DIESEL GENERATORS A,. RUNNING UNLOADED STBY OS 1B.
1C. 1D.
'ER SER SE STBY 0 S STBY OOS STBY OOS B. RUNNING UNLOADED OOS A&B Header Pressure PSIG TSC RUNNING UNLOADED T OOS Security RUNNING UNLOADED TB OOS Com onent Coo1in Water Pum s 1A. NSERV STBY OOS ENGINEERED SAFEGUARDS 1B. INSERV TB OOS Surge Tank Level =.,
Aux. Feed ter Pum s 1A. SERV STBY OOS Standb Aux. Feedwater Pum s 1B. INSERV STBY OOS 1C. INSERV B OOS Turb. Driven INSERV STB OOS 1D. INSERV TB OOS CST Level ~ FEET
- CET = Average of Selected Core Exit Thermocouples
t(OV 17i 1993 09:44 R E GI I't(A SItiULATQR PAGE 1 TREND GROUP ASSIGNNEhT SUt(NARY 0 POINT ID GROI': EVEt(TI PROCEDURE: DESCRIPTIQN EPIP 1-5 PLANT STATUS E. U. 1 ATWS ANTICIPATED TRANSIENT W/0 SCRAN ATWS ALRtf 2 RXT REA TOR TRIP BREAKER STATUS RX TRIPPED ALRtf 3 N31 SMCE RAtiK DETECTOR )i~31 4.12570+01 GOOD CPS 4 N32 SOIKE RANGE DETECTOR N-32 3.71962+01 6009 CPS 5 tf35 It)Tc&tKOIATE RAt<SE DETECTOR N-35 1 '0925-11 GOOD M'P 6 N36 INTERt(EDIATE RANGE DETECTOR N-36 1.00461-11 6009 7 tP AVERAGE NUCLEAR POWcR . (X) GQQD / 8 PRCS REACTOR COOLANT SYSTEN AVG PRESS 34, LALN PSIG 9 LP1R PRESSURIZER AVERAGE LEVEL ~ 0 LALtf 10 FRCLA REiACTGR CGQLAi'T LQQP A AVG FLOW ,0 IN)I / 11 FRCLB RBKTOR COOPT LOOP 8 AVG FLOW ~ 0 INHD X 12 RXT16 RCPA BREAKER CAUSE RX TRIP TRIPPED ALRN 13 RXT17 RCPB BREAKER CAUSE RX TRIP TRIPPED ALRtf 14 TSUBTC INCGRE TC SUKOGLED t(AKilN 16.8 LWR~ DEGF 15 LSGA STtk GEN A NARROW RANGc AVG LEVEL 43.1 GQOD Y. 16 LSGB STtt Gal 8 tNSGW RANGE AVG LEVEL 48.1 GQOD i/ 17 PSGA STN GEN A AVERAGE PRESPJRE 847. 6009 PS16 18 PSGB STt( GEtii 8 AVERAGE PRESSURE 825. GOOD PSIG 19 GENBKRI GENERATOR Otk LINE BREAKER 1G1372 TRIPPED ALR)f 2Q GMNR2 6B&~ATGR Gt( LINc BREAKER 9X1372 TRIPPED ALR)( 21 BUS11A BUS 11A SUPPLY BREAKER TRIPPED ALRt( 22 BUS/8 BUS 118 SL'PPLY BREAKER TRIPPED ALR(( 23 BUS12A t<QT TERtfltiATED ON PPCS (7/!9/91) NQT TRIP DB 24 BUS128 NOT TERNINATED GN PPCS (7/19/91) NQT TRIP DEL 25 811A12A BUS 11A TG 12A TIE BREAKER ttQT TRIP ALfm 26 8118128 BUS 118 TQ 128 TIE BREAKER t(QT TR!P ALRt( 27 PCV CONTA It(t(ENT AVERAGE PRHSURE .96 H((Rt( PSIG 28 LS(NPA i".QNTAINl'~ENT M(P A AVERAGc LEVEL 31.2 HBi6 FLET L0942E SUN' LE4EL 8 It(CHES (TRAIN A) HIGHER IM 30 L0943E SUl.. 8 LEVEL 8 ItlCHES <TRAIN 9) HI6HER It(HB 31 L'0942D SUiP 8 LEVEL 78 It)CHES (TRAIN A) HI6HER INHB 32 LO9439 SL& 8 LEVEL 78 ItiCHcS (TRAIN B) HI6HER ItBD 33 L0942C SCP B LEVEL 113 INCHcS(TRAIN A) HIGHER ALRt( 34 L0943C SU%' LE4EL 113 INCHES(TRAIN B) HIER ALRl'i 35 L0942B SUi%' LEVEL 180 INCHES(TRAIN A) LO)lER GOOD 36 I 09438 SUtF' LEVEL 180 !NCHES(TRAIN B) LQ)(ER 6009 37 LO'942A SNP 8 LEVEL 214 INCHES(TRAIN A) LONER GOOD 38 L0943A SU%' LE4EL 214 INCHFS(TRAIN B) LOWER 6009 39 T0409A RCLA HOT LEG TEt(PERATURE 254.2 6009 DEGF 40 T0410A RCLB HOT (.EG TE)(PERATUK 269.7 "6009 DEGF 41 T0450 RCLA COLD LEG TPiPERAT(JK 158.4 GOOD DEGF T0451 RCa COLD LEG TE)(PERATm 142.2 6009 DEGF 43 TAVGAWID RCLA TAVG (THQT/TCOLD WIDE RNG) 206.3 GQQD DEGF 44 TAVGBWID RCLB TAVG <THQT/TCOLD WIDE Rt(G) 206.0 GOOP KGF 45 LRV REA"TOR VESSEL AVERAcc LEVEL 78.1 LALN 46 TCCORE Ei.l INCGRE TC A'/ERAGE TEiiP 248.4 6001 DEGF 47 FAUXFWA '/6 A :OTAL AUX FEEDMATER FLOl( 0. 6009 GPtf 48 FAUXFMB S/6 8 TOTAL AUX FEEOMATER FLOW 6009 GPt( 49 BKR081 t)TR AUXILIARYFEEDWATER PUtiP A ON 6009 5Q BKR082 NTR AUXILIARY FEEDWATER PUN' ON , GOOD 51 V3505 AUX FW PUP STEA)) SUPPLY VALVE A CLOSED GOOD 52 V3504 AUX FW PU!P STEA)l SUPPLY VALVE 8 CLOSED 6009
ttOV 17~ 1993 09'44 R. E. GIWQ SItCLATGR PAGE 2 TREIS GROUP ASSIGAi&7 SUttttARY 6ROLtP: EVENT1 PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTIOtt VALUE OUAL E. U. 53 FSIA S~c INJECTION LOOP A AVG FLOW 163. GOOD GPtt 54 FSIB SAFETY INACTION LOOP 8 AVG FLOW 293. GGGD GW 55 P2 160 SBSICE WATER PUttPS A 4 B HEADER 87. GOOD PSIG 56 P2161 SERVICE MATER PUttPS C 4 9 HEADER 86, GOOD PSIG 57 BKR041 SPLICE MATER PUttP A ON GOOD 58 BKR042 SERVICE WATER PUttP B ON GOOD 59 BKR043 SERVICE MATER PUttP C ON GOOD 60 BKR044 SERVICE MATER PUttP 9 Ot4 GOOD
NOV 17~ 1993 07:45 P,. E. GINNA SltLLATOR TREtlD GROUP ARIGNNEhT
SUMMARY
GROUP: FViNT2 PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DEPAIPTION VALUE QUAL E. U. F0619 CEPONENT CGO'NG LOOP TOTAL FLW 892. LALN PN 2 LRMST REFUELING MATBt STORAGE TAlC LVL 59.9 GOOD / 3 MS033 33 FDOT LEVEL MIND SPEED 5.4 6009 NPH 4 MD033 33 FOOT LEVB MIND DIRECTION 8 600D DEG, 5 MT033 33 FOOT LEVB. TENPERATURE 43.5 GOOD DE6F 6 MT250 250 FOOT LEVB TENPiRATURi 45.0 GOOD DEGF 7 MDT2 250 TO 33 FOOT LEVEL DELTA TB(P 1.5 600a DEGF 8 R01 AREA I-COtlmO ROON 9.33~ 6009 t(R/HR 9 R02 NB 2-CONTAIeENT 8.03526+03 HALN NR/HR fo ROS AREA 5-SPENT FlCL PIT 3.03739~00 GOOD NR/HR ff R09 AREA 9-LETD(M Lit(i MONITOR 2.91742+01 GOOD )S/HR 12 R34 AREA 34 - AUN BLDG CV SPRAY PUNP 3.01995+00 GOOD NR/HR 13 R35 AREA 35-PASS SANPLE PAWL 1.09648+00 GOOD NR/HR f4 R10A CONTAINMENT IODItti NOtlITOR RiOA 9.87i3686 HALN PN 15 R11 CONTAINNENT AIR PARTIC(LATE 1.01741+07 HBiG CPN 16 R12 COtfTAIt(NENT GAS NONITGR 1.02182+07 HENG CPN 17 R103 PLNlT VENT IODItii l'iOtfITOR R103 2.90486+01 GOOD PN 18 R13 AU)( BLDG EXHAUST AIR PNTICULATE 2.55932+02 GOOD CPN R14 AU)( BLDG EXHAUST GAS NNITGR 1.24990+02 GOOD CPN 20 R18 LIQUID MASTF DISPOSAL Nt(ITOR 1 '6844+03 Gm PH 21 R19 STEAN GENBQTOR BLOMDON DRAiN 2.!1348<03 GOOD CPN 22 R29 AREA 29-CONTAIt(NEtfT HI% RANGE 8.00638~00 GOOD R/HR 23 R30 AREA 30-CGtfTAItlNcJ(T HI% RANK 8.00638~00 GOOD R/HR 24 R15 CGtlDEtlSER AIR EJECTOR EXHAUST 1.45797+03 GOOD CPN 25 R12A5 CV VB(T CS)N 5-LOM RANK GAS 4.20511-05 GOOD KI/CC 26 R12Ab CV VEN", CHAN 6-AREA GAlW 2,67992"02 GOOD ts/HR 27 R12A7 CV VEtlT Cath 7-NID RA)<K GAS 4.205f1-05 GOOD KI/CC 28 R12A9 CV VENT CHAtl 9+IGH RAtÃaE 6AS 9.99987-04 6000 XI/CC 29 R14A5 PLA'i~i VENT CHAtt MOM PLUNGE GAS 2.3099&5 GOOD KI/CC 30 R14A7 PLOT VENT CHAtf 7-NID RANGE GAS 4.62984-06 6000 XI/CC 31 R14A9 Pfu) Vite CHAN 9-HIGH RANGE GAS 9.10997-04 GOOD KI/CC 32 R15A5 AIR EJECTOR CHAN 5-LOM RAN6E GAS 6.22%&06 GOOD XI/CC 33 R15A7 AIR EJiCTGR NAtl 7-NID RAtfGE CAS 1.80975-05 GOOD KI/CC 34 Rf5A9 AIR EJECTOR CHAN 9-Hl RANGE GAS 1.52999-03 6000 XI/CC 35 R31 AREA 31 STEAN l.llF A (SPlt(G) 1.01004M GOOD NR/HR 36 R32 AREA 32 STEAN LINE 8 (SPING) 1.01004M 600D NR/HR 37 CVH CV HYDR06EN CGNCEt(TRATION .0 GOOD )( 38 TCV03 CV BASBHT LcVEL 6FT TENP N3 98.5 GGGD KGF 39 TCV07 CV INTERNEDIATE LVL 6FT TENP t)7 94,0 GOOD DEGF 40 TCV08 CV IhiERNEDIATE LVL 6FT TENP t)8 93.9 =GOOD DEGF 41 TCV09 CV IHTERNEDIATE LVL 6FT TENP ()9 94.0 GOOD DEGF 42 TCV10 CV It(TERNEDIATE LVL 6FT TENP ttfo 93,9 GOOD DE6F 43 TCV17 CV OPERATltiG 'VL 6FT TENP l)17 89.4 6000 DEGF
Time: 0950 Message: ~0 GINNA STATION 93 EVALUATED EXER I E MES A E FORM MMM t: 8 I <<C << IR C Simulated Plant Conditions: ~Massa e: <<""THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY
- 1) If operators check Auxiliary Building Radiation Monitors, inform them that they are beginning to increase slowly.
Antici ated Results:
- 1) Operators performing the applicable actions of E-1.
- 2) Operators should inform the TSC of increasing radiation levels in the Auxiliary if they notice them increasing, 'uilding
- 3) TSC should be evaluating plant conditions and taking actions where required.
- 4) TSC should be informing the EOF of plant status, actions being taken and any required needs.
- 5) TSC should be evaluating the increase of radiation in the Auxiliary Building as to its source and its effect on personnel that may be in the Auxiliary Building (assuming they are cognizant of the increase).
- 6) EOF should be evaluating plant conditions and taking actions as required.
- 7) EOF Dose Assessment should be evaluating the increasing radiation levels in the Auxiliary Building (assuming they are cognizant of the increase).
- 8) Repair teams should be performing actions as required to return equipment to service as soon as possible.
Time: 1000 Message: 31 GINNA STATION 19 3 EVALUATED EXER ISE MESSAGE FORM .MMMf: ~ I C << I R L Simulated Plant Conditions: See the Attached Event 2 Sheet ~essacee: """THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Controller Notes:
- 1) The Auxiliary Operator and/or TSC Team in the Auxiliary Building to check the Auxiliary Building Sub-Basement per step 18C of E-1 and the "B" RHR pump trip problem reports his observations to the Control Room/TSC. (See message ¹22).
Antici ated Results: If the Control Room is informed, the operators should inform the TSC of dripping water and crack on the pipe between CNMT and MOV-850A. 'bserved
- 2) Operators performing the applicable actions of E-1.
- 3) When TSC requests Control Room to close MOV-851A, Control Room should request TSC to send a team into Auxiliary Building to turn the breaker on for MOV-851A as it is turned off during operation. ~No e: if breaker is turned on rior o Bus 14 ri in the breaker will ri as valve comes ff of i s backsea .
- 4) TSC should be evaluating the dripping and cracked pipe and request Control Room to close MOV-851A to isolate the leak from Containment.
- 5) TSC should be evaluating the increasing radiation levels in the Auxiliary Building and possibly evacuate the building.
- 6) EOF Dose Assessment should be evaluating the increasing radiation levels in the Auxiliary Building.
NQY 17> }993 10:00 R. E. GINA SIÃJLATGR PAGE 1 MND GROUP ASSIGtOBiT PJMt(ARY 6ROUP: EVENT2 PROCEDURE: EPIP 1-5 PLAt(T STATUS POINT ID DESCRIPT I 0W VALUE QUAL E. U. 1 F0619 COMPONENT CGQ'NG LOOP TOTAL FLM 892. LALI( 'PM 2 LRMST REFUELING MATE STORAGE TAtII( LVL 41.0 6009 >/ 3 MS033 33 FOOT LEVEL MIND SPED 7. 1 6009 tPH 4 MD033 33 FOOT LEVEL MIt(D DIRECTION 17. 6009 IH. 5 MT033 33 FOOT LEVEL TEMPERATURE 43.5 GOQ9 KGF 6 MT250 250 FOOT LEVEL TEt"J'ERATURE 43.5 6009 KGF 7 MDT2 250 TO 33 FOOT LEVEL DELTA TPJ'REA
.0 6009 DEGF 8 Rol }-CONTR(X. ROON 9.44062M GOOD MR/HR 9 R02 AREA 2-CONTAIeEIIT 8.03526+03 HALN t8/HR 10 R05 AREA 5-SPENT FUEL PIT -""95121+00 6009 MR/HR }} R09 NFD 9 LETDQMN LINE MONITOR 2.91742+01 G009 t8/HR 12 R34 AREA 34 AUX BLDG CV SPRAY Pttt(P 2.98539+00 6009 t8/HR 13 R35 ARB ~ASS SAttf'LE PN8 }.09648%0 GOOD t8/HR 14 R}OA CQttTA ItltIENT IQDIt(E MQltITQR R10A 9.87}36~06 HALtt CPtt 15 Rll CGtiTAIt(>>ENT AIR PARTICK ATE 1 ~ 00867+07 HENG CPM 16 R}2 CQNTAIL"&T GAS tlONITGR 1.03962+07 HENS CPtt .'7 R}OB PLANT VEt(T IODINE MONITOR R}09 4.98310<0} G009 CPtt 18 R}3 AUX BLDG EXHAUST AIR PNTICUATE 2.59268+02 6009 CPM R}4 AUX BLDG EXf%JST GAS tt(X>IITGR 1.95828+02 6009 PN 20 Ris LIQUID MASTE DISPOSAL NNITOR 1.01888+03 6009 CPM 2} R19 STLAtt GENERATOR BLQMDGN DRAltt 2.!}348+03 GOOD CPM 22 R29 ARB 29"CONTAINS(T HIKE! RAtIGE 8.00638400 6009 R/HR 23 R30 AREA 30-CONTAINMENT HI&I RAtiGE S.OO638+OO 6009 R/HR 24 R15 CQtL>~NSER AIR EJECTOR EXHAUST 1 ~ 45797+03 6009 CPM 25 R}M CV Vigil CPJttl 5-LOM RAtiK GAS 4.20511-05 G009 UCI/CC 26 R}286 CV VENT CHAN 6-AI(EA GANA 2.67992-02 6009 t8/HR 27 R}2A? CV V=>(T CM 7-MID RANK GAS 4.205}}M GOOD UCI/CC 28 R}'ZA9 CV VENT CHAN 9-HIGH RANGE 6AS 9.99987-04 6009 XI/CC A9 R14A5 PLAUDIT VENT CHAN MOM RANGE GAS 2.3099}M GOOD tt"I/CC 30 R14A? PLANT VFNT Ct(AII 7-MID RANGE GAS 4.62984-06 G009 UCI/CC 31 R14A9 PAINT VENT CHAN 9-HIGH RANK CAS 9.!099?M 6009 UCI/CC 32 R}5A5 AIR EJECTOR Ct(AN 5-LGM RANGE GAS 6.22985-06 G009 UCI/CC 33 R}5A7 AIR EJECTOR CHAW 7-I>ID RANGE GAS }.80975-05 GOOD UCI/CC R15A9 AIP, EJECTA CHAN9-HI RAt>C< GAS 1.52999-03 6009 KI/CC 35 R31 AP..A 3} STEN LINE A (Plt(G) }.01004-02 6009 tS/HR 36 R32 AREA 32 STEAM LltitE 9 (SPINGt 1.01004-02 6009 t8/HR 37 CVH CV HYDRQGBt COtiCENTRATIQN ~ 0 6009 38 TCV03 CV BASEYBIT L""VEL 6FT TEY>P tt3 82,3 6009 DE6F 39 TCV07 CV IWTERtIEDIATE LVL 6FT TEtIP (I? 81.? . GOOD DEGF 40 TCV08 CV INTERtIEDIATE LVL 6FT TEMP IIB 8}.7 =6009 DEGF 41 TCV09 CV ItITERMEDIATE LVL 6FT TEYiP II9 81.7 G009 DEGF TCV}0 CV It>~icRMEDIATE LVL 6FT TEttP tt}0 81.7 6009 DEGF 43 TCV}7 CV OPERATING LEVL 6FT TB>P tt}7 81.3 6009 DEGF
Time: 1005 Message: 32 GINNA STATlON 1993 EVALUATED EXER ISE MESSAGE FORM f: TCCC Simulated Plant Conditions: ~essacee: >>>> "THlS lS AN EXERCISE>>"" FOR CONTROLLER USE ONLY Controller Notes:
"A" Emergency Diesel Generator problem 1)
C
¹28.
f fff f Repair team sent out to check the f .Cf <<ff f pf f .f Antici ated Results:
- 1) TSC should inform the "A" Emergency Diesel Generator repair team to expedite repairs.
- 2) TSC should inform the EOF of the "A" Emergency Diesel Generator repair team to expedite repairs.
- 3) TSC should inform the EOF of the "A" Emergency Diesel Generator problem and the estimated repair time.
- 4) EOF should be assuming command and control at approximately this time.
Time: 1005 Message: 33 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM Si I C I R Simulated Plant Conditions: ~essacee: """THIS IS AN EXERCISE""" The following Annunciators are required: J-29 (480V Transformer Trip)
'-7
'-9 (480V Main or the Tie Breaker Trip)
(Safeguard Breaker Trip) FOR CONTROLLER USE ONLY Controller Notes:
- 1) When Board Operators check the Control Room Board inform them that the Bus 14 high side and low side breaker switches indicate white lights and Bus 14 indicates "0" voltage, Also indications of Safety Injection to the core indicates no flow.
Antici a ed Resul s:
- 1) Operators should inform the TSC of the loss of Bus 14 and Safety Injection to the core.
- 2) Operators should try to start the "C" Sl Pump on Bus 16. If they do, the breaker will keep tripping out. They may also transfer the "B" instrument Bus to the maintenance supply.
- 3) TSC should inform the EOF of the loss of Bus 14 and Safety Injection to the core.
- 4) TSC should be evaluating the time to core uncovery and request that the EOF evaluate this time also.
- 5) TSC may send a team into the Auxiliary Building to turn on the breaker for MOV-851 A.
- 6) TSC may send a team into the Auxiliary Building to check on the loss of Bus 14.
- 7) TSC should try to expedite the repair of the "A" Emergency Diesel Generator.
- 8) TSC should recommend to the EOF that A GENERAL EMERGENCY should be declared in accordance with EPIP 1-0, "Ginna Station Event Evaluation and Classification; EAL: Reactor Coolant Leakage (RCS); LOCA Identified Inside CNMT and no ECCS Delivery to the RCS.
- 9) TSC should be evaluating possible methods of water injection to the core, such as cross-tying Bus 14 and Bus 16 or using the "B" Reactor Coolant Drain Tank pump. If TSC decides to cross-tie Bus 14-16, one of the two tie-breakers will not close. If TSC decides to use the "B" Reactor Coolant Drain Tank pump, the suction strainer will plug after approximately 2 minutes of operation and will have to be cleaned prior to any further use.
- 10) EOF, after evaluating plant conditions, should declare a GENERAL EMERGENCY in accordance with EPIP 1-0, "Ginna Station Event Evaluation and Classification, "EAL: Reactor Coolant Leakage (RCS); LOCA Identified Inside CNMT and no ECCS Delivery to the RCS. Appropriate notifications should be made per EPIP 1-5.
h
- 11) EOF should be making immediate protective action recommendations in accordance with EPIP 2-1, "Protective Action Recommendations".
- 12) Repairs teams performing actions as required to return equipment to service as soon as possible.
TIme: 1005 Message: 34 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM
.>>>>>>: R PI 4 hh hf PL IB 14IB 144 I <
>>> FOR CONTROLLER USE ONLY Controller Notes:
- 1) Provide information when appropriate actions are simulated or investigations conducted.
Actions Ex ected:
- 1) As per Mini-Scenario.
GINNA STATION 1993 EVALUATED EXERCISE MINI-SCENARIO TITLE: Loss of Bus 14 Bus 14 Transformer Expected scenario start time: 1005 INITIALCONDITIONS: Bus 14 energized. Thermography performed on Bus 14 at 0730 indicates a hot spot on transformer high side connection (Phase A). METHOD OF INITIATION: Bus 14 supply breaker opens (52/14SS). INDICATIONS: CONTROL ROOM: 'nnunciator Windows: "J-7" 480V main or tie breaker trip "L-14" Bus 14 under voltage safeguards 'hite (disagreement) lights: 52/14SS Highside breaker 52/14 Lowside breaker '50G" Bus 12A/Unit 15: Bus 14/Unit 18B: Bus 14 Trans: 'o Relay tripped (red flag showing) abnormal indications, "as found" 'hase A'onnection on the transformer is charred and tracking to ground. EXPECTED SEQUENCE OF ACTIONS: ~ Repair team forms to: 'nspect Bus 14 'nspect Bus 14 transformer Check Bus 14, 480V supply breaker indications 'heck Bus 14, 4KV supply breaker indications ~ Obtain holds, clearances, test equipment, and safety equipment. < Simulate meggering station service transformer from Bus 12A/Unit 15 readings: Megger readings: 0 Q phase to ground (phase A) 100 Gig Q to ground (phase BSC) Phase to phase resistance < 1 Q Simulate meggering Bus 14, readings: Megger readings: 150 Gig Q to ground 100 Gig Q (phase-phase) FINAL CONDITIONS: Station service Transform r 14 out of service and requires replacement. Time: 1005 Message: 35 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM ~fg fP:pi y CP ifgg fgf yij*i P p C P gi Simulated Plant Conditions: ~Masse e: <<<<" THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Controller Notes:
- 1) Provide information when appropriate actions are simulated or investigations conducted.
Antici ated Results:
- 1) As per Mini-Scenario
GINNA STATION 1993 EVALUATED EXERCISE MINI-SCENARIO TITLE: Loss Of Safe In'ec ion Pum 1C SIPC Expected scenario start time: 1005 INITIAI CONDITIONS: Safety Injection Pump 1C is not running METHOD OF INITIATION: SIP1C pump fails to start when attempted from either supply (Bus 14 or 16) ~ INDICATIONS'ONTROL ROOM: 'us 16 power supply breaker (SIP1C1) opens 'hite disagreement light, Bus 16 'us 14 deenergized NOTE When Bus 14 is reenergized, if SIPIC2 breaker (Bus 14 supply). is attempted to shut, trips open immediately, white disagreement light. Bus 16/POS13A: 'f 'mptector: "Instantaneous" trip indication meggered - 0 Q to ground, 0 Q p to p 1 SIP1C Motor: 'mell of burnt insulation EXPECTED SEQUENCE OF ACTIONS' Repair team and Auxiliary Operator investigates loss of Sl pump 1C. 'ight smoke discovered in vicinity of Sl motor 1C 'uxiliary Operator/Electricians check SIP1C 'iscover Amptector "instantaneous" button is out > Obtain holds, clearances, and test equipment > Simulate measuring resistance phase to phase and meggering motor from Bus 16/Pos 13A readings: Megger readings: 0 Q Phase to ground Phase to phase resistance 0 Q FINAL CONDITIONS: Motor requires replacement/rewinding due to grounded windings. Time: 1005 Message: ~3 GINNA STATI N 1993 EVALUATED EXERCISE MESSAGE F RM Rpl 6 PP 616B Plgpl B I<<gll 6 Pl Simulated Plant Conditions: ~Messs e: """THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Controller Notes:
- 1) Provide information when appropriate actions are simulated or investigation conducted.
Antici ated Results:
- 1) As per Mini-Scenario
GINNA STATION 1993 EVALUATED EXERCISE MINI-SCENARIO TITLE: Bus 14-16 Tie Breaker Failure Bus 16 Expected scenario time: 1005 INITIALCONDITIONS: Bus tie breaker 14-16 (Bus 16 open) METHOD OF INITIATION: 'oss os Bus 14 and "A" Diesel Generator is out of service, 'SC orders the 14-16 Bus tie breakers closed. Mechanically (Bus 14 5. 16). NOTE'peration of 14-16 Bus tie breaker from control requires jumpering of contracts in the control circuitry. This breaker MUST NOT be repaired and returned to service until Emergency Diesel Generator "A" is supplying Bus 14 (approx 1 220). INDICATIONS: CONTROL ROOM: 'o indications Bus 16/POS12C: 'reaker "trips free" when manually shut and will not latch shut. Bus 14/POS19C: 'mptector: as found. 'reaker operates normally. EXPECTED SEQUENCE OF ACTIONS' Repair forms to: Determine how/if possible to defeat interlocks to operate Bus 14-16 tie breaker (Bus 16) from control. < Form team to operate Bus 14-16 tie breakers locally. 'btain Health Physics coverage and dosimetry. 'btain key for operation of Bus 14 tie breaker. > Simulate operating Bus 14-16 tie breaker (Bus 14). ~ Simulate attempting to operate Bus 14-16 tie breaker (Bus 16). FINAL CONDITIONS: Bus 'l4-16 breaker (Bus 16( open and ~will no shut (will not latch shut). Message: 37 INNA STATION 1993 EVAL ATED EXER ISE MES AGE FORM MMM 1:331TgpplgB1113Tl BR PBI Simulated Plant Conditions: ~Messa e: """THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Controller Notes:
- 1) Provide information when appropriate actions are simulated or investigations conducted.
Antici ated Results:
- 1) As per Mini-Scenario.
GIN NA STATION 1993 EVALUATED EXERCISE MINI-SCENARIO TITLE: Bu 14-13 Ti Breaker F il re B 14 Expected scenario start time: 1005 INITIALCONDITIONS: Bus tie breaker 14-13 (Bus 14) open. METHOD OF INITIATION: Loss of Bus 14 and "A" Diesel Generator is out of service. 'SC orders the 14-13 bus tie breakers closed mechanically (Bus 14 5. 13). NOTE: Operation of 14-13 bus tie breaker (Bus 14) from control requires jumpering of contacts in the control circuity. This breaker MUST NOT be repaired and returned to service until Emergency Diesel Generator "A" is supplying bus 14 (approx 1 220). INDICATIONS: CONTROL ROOM: 'us 14-13 (Bus 13) tie breaker light indicates correctly. Bus 14lPOS19B: 'reaker "trips free" when manually shut and ~will no latch shut. Bus 13/POS10C: 'mptector: as found 'reaker operates normally. EXPECTED SEQUENCE OF ACTIONS: > Repair team forms to: 'etermine how/if possible to defeat interlocks to operate Bus 14-13 tie breaker (Bus 14) from control. ~ Form team to operate Bus 14-13 tie breaker locally. Obtain Health Physics coverage and dosimetry. 0' 'btain key for operation of Bus 14 tie breaker. ~ Simulate operating Bus 14-13 tie breaker (Bus 13). > Simulate attempting to operate Bus 14-13 tie breaker (Bus 14). FINAL CONDITIONS: Bus 14-13 breaker (Bus 14) open and ~will no shut (will not latch shut). Time: 1005 Message: ~i l!IINN BTATI N 1993 EVALUATED EXERCISE MESSAGE FORIVI Ik: * *III ygp <<ITBC T I 5 ACB 5 I MCTSBIA Simula ed Plant Condi ions: See the Attached Mini-Scenario ~Masse e: <<""THIS IS AN EXERCISE" >>" FOR CONTROLLER USE ONLY Controller Notes:
- 1) Provide information verbally when appropriate actions are simulated or investigations conducted.
Antici ated Results:
- 1) As per Mini-Scenario.
GINNA STATION 1993 EVALUATED EXERCISE MINI-SCENARIO TITLE'urnin on AC Breaker for MOV-851A Expected scenario start time: 1005 INITIALCONDITIONS: 0 RCS has experienced a large break LOCA. 'tep 18 of E-1 dispatches an Auxiliary Operator/TSC team to check the Auxiliary Building Sub-Basement for RHR system leakage. 'uxiliary Operator/TSC team observes water dripping and what appears to be a 3 inch long crack at the bottom of the pipe between Containment and MOV-850A. The above observations <<d 1 C << IR ITSl:~DDDl METHOD OF INITIATION: 'he Control Room/TSC may, after learning of the dripping water and cracked pipe, request the Auxiliary Operator/TSC team to turn on the AC Breaker to MOV-851A so it may be closed. INDICATIONS: CONTROL ROOM: 'OV-851A open. LOCAl' MOV-851A AC Breaker locked in off position. EXPECTED SEQUENCE OF ACTIONS: 'btain locked valve key from Shift Supervisor. Proceed to Auxiliary Building operating floor at MCC-1C position 10M. Unlock and turn on AC Breaker to lVlOV-851A. 'eport to Control Room/TSC the AC power to MOV-851A is on. NOTE: Auxiliar 0 rator SC earn con roller will coor ina r with simula pro era orswhenbre keri urned on o M V-851A. FINAL CONDITIONS: 'OV-851A Ac power breaker is turned on and this is reported to the Control RoomlTSC. Time: 1005 Message: 39 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM ~Mf: , TPC/C << IR A*ill ypp Containment Sump "8" or the RWST. << ll l g p "g" RCOTP p Simulated Plant Conditions: See Attached Mini-Scenario Messacee: """THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Controller Notes:
- 1) Provide information verbally when appropriate actions . are simulated or investigations conducted.
Antici ated Results:
- 1) As per Mini-Scenario,
GINNA STATION 1993 EVALUATED EXERCISE MINI-SCENARIO TITLE: Linin u of the "B" RCDT Pum CNMT Sum B or he RWST. Expected scenario start time: 1005 INITIALCONDITIONS: 'CS 't has experienced a large break LOCA. 1005 hours Bus 14 normal supply breaker tripped and the "A" Emergency Diesel Generator could not tie in as it was out for emergency maintenance. 'ecause of the above and other equipment out of service, all safety injection to the core is lost. 'll Safety Injection pumps available are powered by Bus 14. 'he TSC, as an emergency action, may request that the "B" RCDT pump be lined up to pump from either Containment sump "B" or RWST to the core. INDICATIONS: 'o safety injection to the core with progress. a large break LOCA in 'adiation levels are extremely high in the Auxiliar'y Building. EXPECTED SEQUENCE OF ACTIONS: 'ontainment Sump "8'-'ine-up: 'btain a copy of ER-RHR.1 (RCDT Pump Operation for Core Cooling) and simulator alignment of the "8" RCDT pump per the post accident sump recirculation section. 'nform TSC/Control Room when alignment is complete. NOTE: TSC Control Room Auxiliar 0 er or con roller will coordina e with sirnula or o era or when RCDT um from Con ainment sum i simula ed lined u 'WST Line-up: 'sing PAID's 33013-1247 and 33013-1272 sheet 2 of 2, research and simulate lining up "B" RCDT.from RWST to the core. 'nform TSC/Control Room when alignment is complete. MOTE: TSC Control Room Auxiliar 0 era or con roll r will coordinate wi h simula or o era or when RCDT um from RWST is simula ed lin u . FINAL CONDITIONS: 'f "B" RCDT pump is aligned and started, its suction strainer will plug in approximately 2 minutes. Time: 1005 Message: 40 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM ~M: Mp R<<CI P g "B" RCDTP pp i M Simulated Plant Condi ions: See Attached Mini-Scenario ~Massa """THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Controller Notes:
- 1) Provide information verbally when appropriate actions are simulated or investigations conducted.
Antici ated Results:
- 1) As per Mini-Scenario.
GINNA STATION 1993 EVALUATED EXERCISE MINI-SCENARIO TITLE: Cleanin of "B" RCDT Pum Suc ion S rainer Expected scenario start time: 1005 INITIALCONDITIONS'us 14 tripped out and the "A" Emergency Diesel Generator could not tie in, and all safety injection to core is lost. METHOD OF INITIATION: As an emergency action, the TSC may request the Control Room to line up the "B" RCDT pump. INDICATIONS: 'B" RCDT Pump Suction Strainer is plugged. EXPECTED SEQUENCE OF ACTIONS' Operation aligns "B" RCDT pump for service 'ump strainer will plug after two minutes of operation. 'igh levels of radiation in Auxiliary Building. 'itters on standby for cleaning suction strainer. 't FINAL CONDITIONS: 1220 hours "A" Emergency Diesel Generator is supplying Bus 14. 'uction strainer on "B" RCDT pump no longer requires cleaning. Time: 1015 Message: 41 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM I: 8 I<<C << IR Simulated Plant Conditions: See Attached Sheets ~ll/lesss e: <<<< "THIS IS AN EXERCISE" <<<< FOR CONTROLLER USE ONLY ~CII R
- 1) Core exit thermocouples and R-29, R-30 start increasing and RVLIS starts decreasing.
Antici ated Results:
- 1) Operators should inform the TSC of the increasing core exit thermocouples, the increasing radiation in Containment, and the decreasing RVLlS.
- 2) Operators should perform the applicable actions of FR-C.1 (Response to inadequate Core Cooling) when required.
- 3) TSC should evaluating plant status and taking actions as required.
- 4) TSC should inform the EOF of the increasing core exit thermocouples, the increasing radiation in Containment and the decreasing RVLIS.
- 5) TSC should be informing the EOF of the general plant status actions being taken
and needs required.
- 6) TSC may realize by this time that in order to recover core cooling they will need to complete repairs on'the "A" Emergency Diesel Generator, tie it into Bus 14, and start all available Sl pumps, even though they may not be completely sure of why Bus 14 tripped out. The thermography report given in the initial conditions should give them some confidence that the problem is in the transformer connections and not the Bus.
- 7) TSC should also realize that once they energize Bus 14, MCC-1C will be energized and they can now close MOV-851A, when the breakers AC power is turned on, thus terminating the radioactive leak source from Containment to the Auxiliary Building.
- 8) TSC may also evaluate the possibility of back feeding Bus 14 from Bus 13 using the 14-13 tie breaker.
- 9) EOF evaluating plant status and taking action as required.
1993 EVALUATED EXERCISE Time: /D/~ MAiTOR PARAMETERS ENGINEERED 8APEGUARDS Reactor Shutdown YE NO Hi h Head S.I. Pum s N-31 0 CPS FI-924 ~GPM N-32 CPS FI-925 ~GPM N-35 Mm~/ AMPS 1A. INSERV STBY N-36 AMPS 1B. INSERV STBY Avg. Nuclear Power 1C. INSERV STBY OS RCS Pressure V~PSIG BAST Level = ~O PRZR Level Q.O A RCP RUNNING PPE Low 'Head S.I. Pum s B RCP RUNNING TOPPE FI-626 ~GPM 1A S/G Level 4z. 1A. INSERV STBY RECIRC 1B S/G Level e 1B. INSERV S BY 0 RECIRC 1A S/G Pressure PSIG RWST Level = 1B S/G Pressure SIG Turbine/Generator 0 E FFLINE Containment 8 ra Pum s 4 KV Buses NERGIZE DEE RGIZED FI-931A GPM 480V Buses jg8~5 NERGIZED DEEN GIZ FX-931B GPM DC Batteries~~ A~VOLTS B~OVOLTS 1A. INSERV BY 00 Cnmt Pressure ~a~PSIG 1B. INSERV TB OOS Cnmt Sump A Level Cnmt Sump B Level ~2-FEET IG XNCHES NaOH Tank Level = ~% A Loop Hot Leg ~QB~'F Containment Recirc Fans Loop Cold Leg a.OI ~ 'F 1A. IN RV STBY B Loop Hot Leg 883 3 'F 1B. STBY OOS B Loop Cold Leg XB~ 2-2 F 1C. SER STBY OOS RVLIS 87 1D. INSERV STBY 4F Post Accident Dampers OPEN CLOSED S/G A Total Aux FW Flow 0 GPM S/G B Total Aux FW Flow O GPM Service er Pum s 1A. NSERV STBY OOS DIESEL GENERATORS 1B. SERV STBY OOS 1C. NSER STBY OOS A. RUNNING UNLOADED STBY 00 1D. ERV STBY OOS B. RUNNING UNLOADED B OOS A&B Header Pressure (o PSXG TSC RUNNING UNLOADED OOS Security RUNNING UNLOADED B OOS Com onent Coolin Water Pum s 1A. INSERV STBY 0 ENGINEERED SAPEGUARDS 1B. NS STBY OOS Surge Tank Level =, Aux. Peedwat T. Pum s 1A. INSERV ~8 0 Standb Aux. Peedwater Pum s 1B. INSERV OOS 1C. INSERV STBY Turb. Driven INSERV STB OOS 1D ~ INSERV T OOS CST Level ~62 4 F
- CET = Average of Selected Core Exit Thermocouples
~. ~4 - /a-' NQV 17i 1993 10:14 R, E. GINA Sltt(KJ)TGR PAGE 1 TREND GROUP ASS IGt(tB(T SUHt(ARY GRQLPl EVENT1 PRGCEDUR"": EPIP 1-5 PLANT STATUS POP(T ID DESCRIPTIC4 E. U. ATMS ANTICIPATED TRANSIEHT M/0 SCRAtl AT MS ALRl'i 2 RXT RStTOR TRIP BREAKER STATUS RX TRIPPED ALR)f 3 N31 SGU(iCE RANGE DETECTGR H-31 5.00609+01 GOOD CPS tG2 SM(CE RAhGE DETECTOR N-32 3.94456+01 BAD CPS 5 N35 It FRt(EDIATE RAN6E EKTOR N-35 1.00925-11 600!) Al(P 6 tQ6 It(FR)(EDIATE BANK DETECTOR H-36 1.00001"11 Gm NP I HP AVERAGE NUCLEAR POWER ~ (9 GOOD / 8 PRCS Rcjf"TGR COOLANT SYSTit) AVG PRESS 46. LALN PSIG 9 LPIR PlicSSURI lER AVERAGc LE4$ . .0 LAL)( )! 10 FREYA REACTOR COOLANT LOOP A AVG FLOM 2.4 INHB / ~ ll J7 FRCLB RiA"TOR CCQ ANT LOOP 8 AVG FLGiA .0 INHS I/ >>& RXT16 RCPA BREAKER CAUSE RX TRIP TRiPPED ALRtl !3 RXT!7 RCPB BREAKER CAUSE RX TRIP TR! PPED ALRt( f4 TSUBTC INURE TC SUBCOQLED ttAMIN -11.3 LAL>> DEGF !5 LSGA STtl EH A tNRROM RAhGE AVG LEVEL 42.4 6008 / 16 LS68 ST)i Gctl 8 NARROW RANGE AVG LEVEL 48.7 600>> a/ !7 PSGA STH GEN A AVERAGE PRESSURE Bl l. GQQ>> PSIG 18 PS68 STtf GB( 8 AVERAGE PFZSSURE 784. GOO>> PSIG f9 GcCBKRf GEtGQTGR'GN 'HE BREAKER 161372 TRIPPED ALRt( 20 GFNBKR2 GBeRATOR ON LINE BREAKER 9X1372 TRIPPED ALR)( 21 BUS!!A BUS 1!A SUPPLY Bl(EAKER TRIPPED ALR)l 22 BUSl!B BUS 118 SUPPLY BREAKiR TRIPPED ALRN 23 BUS!2A HQT TERtlIHATED OH PPCS (7/f9/91) NQT TRIP DEL 24 BUSI28 tlOT TERNINATED OH PPCS (7/f9/91) NQT TRIP DEL 81!A!2A BUS l!A TO 12A T!E BREAKER t]QT TRIP ALRt( 26 8118128 BUS 118 TG 128 TIE ERQgER t)QT TRIP ALR)( 27 PCV CO'!TAI)Nit!T AVERAC~ P cURE 1.18 HMR>> 28 LS(SPA CQNTAIHt(EtlT SUt!P A AVFRAGE LEVEL 31.2 HENS 29 L0942E SUiV 8 LEVEL 8 ItKHES (TRAIN A) H!6HB? INHB 30 L0943E SU% 8 LEVB 8 Ih'CHcS (TRAIN 8) HI6HER INH8 31 L09420 SUN" 8 LEVEL 78 IHCHES (TRAIN A) HIGHER INHB 32 L0943D SUiP 8 LEVEL 78 fhCHES (TRAIN 8) HI6HER INHB 33 L0942C S PP 8 l cVEL 113 It(CHES(TRAIN A) H!6HER ALRtf 34 L0943C SIJtP 8 LEVEL 113 INCHES(TRAIN 8) HI6HER ALRtl 35 l.09428 SUtF' LEVEL !80 INCHES(TRAIN A) LOWER GOOD 36 L09438 SUlP 8 LEVEL 180 IHCHcS(TRAIN 8) LOWER GOOD 37 L0942A RIP 8 LEVEL 214 INCHiS(TRAIN A) LOWER Gm 38 L0943A SU."P 8 Li'4'EL 214 INCHES(TRAIN 8) LOWER GOOD 39 T0409A RCLA HOT LE6 TEt(PERATURE 293.8 GOOD DEGF 40 T04!OA RCLB HGT LEG TEt(PERATURE 293.3 400!) IFGF 41 T0450 RCLA COLD LEG TENPERATNE 201.5 BAD DEGF T0451 RCLB COLD LEG TEt(PERAME 158.2 BAD KGF 43 TAVGAMID RCLA TAVG (THQT/TCGLD HIDE RHG) 293.8 600>> DEGF 44 TAVGBMID RCLB TAVG (THQT/TCOLD MIDE RN6) 293.3 600>> KGF 45 LRV REACTOR VESSEL AVERAGE LEVEL 51.2 LALH / 46 TCCGRE El. 1 IHCORE TC AVERAGE TE)(P 289.5 600>> DEGF 47 FAUXFMA S/6 A TOTAL AUX FEEDMATER FLGM 0. 6008 GP)l 48 FAUXFMB S/6 8 TOTAL AUX FEEDMATR FLOW 0. 6008 GPtl 49 BKR081 tlTR AUXILIARYFEEDMATER PUt(P A OFF 6000 50 BKR082 NTR AUXILIARYFEEDMATER PUt!P 8 OFF GQQD 51 V3505 AUX FM PUN'TEA)l SUPPLY VALVE A CLOS D 6009 52 V3504 AUX FM PU)F STEAN SUPPLY VALVE 8 CLQScD GQQD NOV 17F93 10'>>14 R. E. GINA Sltl8.ATOR PA6E 2 TREND GROLP ASSIGQLchT SUtt!SRY GROLP; EVENT1 PROCCEDURE; EPIP 1 5 PLANT STATUS POINT Io DESCRIPTION VALUE QUAL E. U. 53 FSIA SAFETY It<.'ECTION LOOP A AVG FLPM 0, 6009 GPtt 54 FSIB SAFETY INJECTION LOOP B AVG FLOW 0. 6009 Ptt 55 P2160 SERVICE MATER PUttPS A 5 B HEADER 87. GOOD PSIG 56 P2161 SERVICE MATER PUttPS C t. 9 HEADER 86, 6009 PSIG 57 BKR041 SERVICE MATER PUttP A GOOD 58 BKR042 SERVICE MATER PUttP 8 6009 BKR043 SERVICE MATER PNP C 6009 60 BKR044 SERVICE MATER PUttP 9 GOOD NQY 17i 1993 10! 15 R. ~ GINtA Sit!Q.ATOR TRcND GROUP ASSIGN!ENT SUtlttARY GROL'P: EVEtlT2 PRQCEDL4?E: EPIP 1"5 PLANT STATUS POINT ID DcSCRIPT ION VALUE E. U. 1 F0619 CQVQNENT Cm ING LOOP TOTAL FLM 884. l ALtl GPtl 2 LRMST REFUELING MAT""R STORAGE TA% LVL 37.1 6009 Y. 3 MSO33 33 FOOT LEVB MIND SPEED 3.0 GOOD ttPH MD033 33 FOOT LEVEL MIND DIRECTION 24. 6009 DEG. 5 MT033 33 FOOT LEVE'EHPERATURE 43.1 GOOD lFGF 6 MT250 2SO FOOT LEVE'EtlPERATURE 43.1 6009 DEGF 7 MDT2 2SO TO 33 FOOT LEVEL DELTA TEt!P .0 6009 KGF 8 R01 AREA 1-CONTR!?'Mi 8.75992-02 6009 tS/HR R02 At?EA "-CQt)7AI"NEttT 7.80727+03 BAD tSIHR 10 R05 AREA 5-SPENT RE PIT 3.14412M BAD tS/HR R09 ARcA 9-LETDOMN Lit= mttiTGR 2.75423>01 BAD N/HR J R34 AREA 34 - AUX BLDG CV PRAY PL4!P 2.95121+00 BAD t8/HR 13 R35 AREA 35-PASS SAMPLE PAL 1.09648+00 600D t8/HR 14 RIOA COtA'AINt!EttT IODINE tGRITOR R10A 9.57744+06 HALN CPit jS RI1 CQiiTAINt!ENT AIR PARTI ClJ ATE 1.03068+07 HENS CPtl 16 R12 CONTAINten GAS tlONITOR 9.49508+06 HALtl CPtt l7 RIOB PLNT YENT I09INE tlQNITOR R109 7.381}4+01 6009 Ptt 18 R13 AUX P DG EXHAUST AIR PAt?TICULATE 2.60390+02 6009 PM 19 R14 AUX BLDG EXHAiJST GAS tiQNITQR 1,98380+02 GQQD CPtl 20 R18 LIQ!ID MASTE DISPOSAL Nt/ITOR 9,97126+02 6009 CPtl R19 STEA>> GEt!ERATGR BLGMEF4'RAIN 2.16895+03 GOOD CPN 22 R29 AREA 29 CQt!TAINHENT H1% RANGE 2.00245%1 HWRtt R/HR 23 R30 AREA 30-CGNTAINiEttT Hi&I RANK 2.00245+01 hARH R/HR 24 R15 COl8ENSER AIR EJECTOR EXHAUST 1.40241+03 6009 CPtl R12A5 CV VEN: CHAN M.QM RANGE GAS 4.2051&5 6009 XIICC 26 R12Ab CV VEttT CNW 6-AREA GAMA 8.00000+00 HMRtt tB/HR 2/ R1287 CV VEN: CHAN 7-tllD PANGS GAS 4.20511M 6009 XI/CC 28 R12A9 CV VEN! CSN 9+I'GH RANGc GAS 9.99987M 6009 "'I/CC 29 R14A5 PLA".T VENT CHAN 5-LCA RANGE GAS 2.30991M 6009 XI/CC 30 R14A7 PLAliT VENT Ct!4N 7-HID RANGE GAS 4.62984-06 6009 Xl/CC 31 R14A9 PLANT YENT CNN 9-HIGH RANGE 6AS 9.10997-04 6009 XI/CC 32 R15A5 AIR EJECTOR 995 5-LGM RANGE 6AS 6.22985-06 6009 XI/CC 33 R15A7 AIR EJECTOR RW 7&ilD RAN6E GAS 1.8097~ 6009 XI/CC 34 RISA9 AIR EJECTOR MN 9+I RAtKE GP3 1.52999<3 GQQD XIICC 35 R31 AREA 3; STEAtt Lit!E A (BRING) 1.01004-02 6009 ttR/HR 36 R32 AREA 32 STEAtt LIE 8 !PIttG> 1.01004-02 6009 NIHR 37 CVH CV HYDROGEN CON CEttTRAT ION .0 6009 1! 38 TCV03 CY BASEt8!T DE 6FT T2P 03 75.6 6009 DEGF 39 TCY07 CV INTERtLcDIATE LVL 6FT TEt!P. N7 83.6 . 6009 IFGF 40 TCV08 CY IttTERt!EDIATE LYl. 6, T TEtP tl8 83.6 =6009 DEGF 41 TCV09 CV IttTERtlEDIATE LVL 6FT TPiP tt9 83.6 GOOD DEGF 42 TCV10 CV IttTERt!EOIATE LVL 6FT TEt!P 110 83.6 GOOD DEGF 43 TCV17 CV GPERATIttG LEVL 6FT TEt!P 417 91.7 GQQD lFGF v ~ (~ Time: 1020 Message: 42X GINNA STATION 1993 EVALUATED EXE I E. MESSAGE FORM ~M:RMR Simula ed Plant Conditions: ~INessa e: <<<<<<THIS IS AN EXERCISE""" 'Declare a GENERAL EMERGENCY in, accordance with EPIP 1-0, "Ginna Station Event Evaluation and Classification, "EAL: Reactor Coolant Leakage (RCS); LOCA Identified Inside CNMT and no ECCS Delivery to the RCS. FOR CONTROLLER USE ONLY Controller Notes:
- 1) Deliver only if a GENERAL EMERGENCY has not been declared. Do not deliver if emer enc classification discussions are in ro ress.
Antici a ed Results:
- 1) Deliver contingency message if GENERAL EMERGENCY not declared or is not being discussed.
Time 1030 Message: ~4 GINNA STATION 1993 EVALUATEO EXERCISE MESSAGE FORM C I R Simulated Plant Conditions; See Attached Sheets ~Massa e: """THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Controller Notes: Antici ated Results:
- 1) Operators should be performing the applicable actions of FR-C.1 (Response to Inadequate Core Cooling).
1993 EVALUATED EXERCISE Time: ~103 MAJOR PARAMETERS ENGINEERED SAFEGUARDS Reactor Shutdown ES NO Hi h Head S.I. Pum s N-3 1 2 xZ CPS FI-924 GPM N-32 N-35 ~CPS I~-i> AMPS FI-925 lA. ~GPM INSERV STBY OOS N-36 l~6-11 AMPS 1B. INSERV STBY 0 Avg. Nuclear Power Q 1C. INSERV STBY OS RCS Pressure IZi PSIG BAST Level = ~/ PRZR Level +~0 A RCP RUNNING TOPPED Low Head S.I. Pum s B RCP RUNNING STOPPED FI-626 ~GPM 1A S/G Level 1A. INSERV STBY 0 RECIRC 1B S/G Level 2. ~ 1B. INSERV STBY RECIRC 1A S/G Pressure ~&6 PSIG RWST Level = 1B S/G Pressure PSIG Turbine/Generator LINE FFLINE Containment S ra Pum s 4 KV Buses NERGIZE DEENERGIZED 9 I-9 3 1A~GPM 480V Busesi98waiT NERGIZED/DEENE GIZE FI-931B (3 GPM DC Batteries A~VOLTS B~SOVOLTS 1A. INSERV S Y OS ~~PSIG Cnmt Pressure Cnmt Sump A Level Cnmt Sump B Level ~l. QI80 2 FEET INCHES 1B. NaOH INSERV TB OOS Tank Level = ~4 A Loop Hot Leg 'F Containment Recirc Fans A Loop Cold Leg +01~ 'FF 1A. V STBY 0 B Loop Hot Leg uMk2- 'F 1B. R STBY OOS B Loop Cold Leg lc. ERV STBY OOS RVLIS 1D. INSERV STBY 0
- CET 'F Post Accident Dampers PEN CLOSED S/G A Total Aux FW Flow & GPM 5/G B Total Aux FW Flow ~I2- GPM Service Rater Pum s 1A. NSERV STBY OOS DIESEL GENERATORS 1B. NS R STBY OOS 1C. NS STBY OOS A. RUNNING UNLOADED STBY OOS 1D. INSER STBY OOS B. 'RUNNING UNLOADED OOS A&B Header Pressure PSIG TSC RUNNING UNLOADED OOS Security RUNN NG UNLOADED B OOS Com onent Coolin Rater Pum s 1A. INSERV STBY 0 ENGINEERED SAFEGUARDS 1B. NSERV STBY OOS Aux. Feedwater Pum s Surge Tank Level = ~D 1A. IN V STBY OS Standb Aux. Feedwater Pum s 1B. NSE V STBY OOS lc. INSERV STBY 0 Turb. Driven INSERV TB OOS 1D. INSERV OOS CST Level Q~eo F
- CET = Average of Selected Core Exit Thermocouples
NOV 17~ 1993 10:28 R. i,. GINNA SitNLATOR PAGE 1 TREND GROUP AKIBNtZNT S~J44(ARY GRGJP: EVENTI PROCEDURE: EPIP 1-5 PLA){T STATUS POINT ID DESCRIPTION VALUi E. U, ATt6 ANTICIPATED TRANSiENT W/0 SCRA)f AT)IS ALRt( RXT RiA"TOR TRIP BREAKER STATUS RX TRIPPED ALRt{ 3 tQI SMCE RAt{GE DETECTGR N-31 6.22297+04 fNRt{ CPS N32 SKRCE RAt{GE DETECTQP. N-32 3.94456+01 BAD CPS 5 N35 lt~cDIATE RANGE DETECTOR N-35 1.78648-10 GOOD At(P 6 N36 It{TER{(EDIATE RANGE KTcECTGR N 36 1.0000!-11 6009 NP 7 tP AVERA6i NUCLEAR POkR .00 6009 y. 8 PRCS REA".TQR COOLANT SYSTEt( AVG PRESS 15. LALt{ PSIG LPIR PRESSURIlER AVc cAGE LEVcC .0 LAL{( 0/ 10 FRC A REACTOR COOLANT LOOP A AVG FLGM .0 lt{HB 7. ll FRCLB ROTOR CGGLAtti LGGc 8 AV6 FLG)I 20.3 INH> 12 RXT16 RCPA BREAKER CAUSE RX TRIP TRIPPED ALR{( 13 RXT17 RCPB BRiAKER CAUSE RX TRIP TRIPPED ALR(( TSUBTC IMCQRE TC SUBCQGLED NRBIN -716.6 LALt DEGF 15 LSGA STt( ~Dc{ A t(%RGA RA){GE AVG LEVEL 41.7 6009 / 16 LSGB STt( GEI( 8 t(ARRQN RANGE AVB LEVEL 21.1 LWR~ 17 PSGA STt{ Girl A AVERAGE PRESSURE 766. 600~ PSI6 18 PS68 Sit{ GEH 8 AVEftAGE PRESRIRE 3. LALN PSIG 19 GENBKRs KtERATOR ON LINE BREAKER 1G1372 TRIPPED ALRI( 20 GBSKR2 GEtERATOR ON LINE BREAKER 9X1372 TRIPPED ALRI( 21 BUSl lA BUS llA SLePLY BR>J(cER TRIPPED ALR)I 22 BUS118 BUS 118 SUPPLY BREAKER TRIPPED ALR{( ')3 BUS12A NOT TERt(INATED ON PPCS (7/19/91) NOT TRIP DEL 24 BUS128 NOT TERl(INATED Ot( PPCS (7/19/91) t(GT TRIP DEL 25 811A12A BUS 11A TO 12A TiE BREAKER NOT TRIP ALRt{ 26 8118128 BUS 118 TQ 128 TIE BRACER NOT TRIP ALR( 27 PCV CQNTAINt(ENT AVERAGc PRHSURE 1.33 Hf(R! PSIG 28 LSIP>PA CGt(TAIN)IEt{T S!J<d' AVER"Gi LEVEL 31.2 )Let)G FEET 29 L09428 SUtP 8 LEVil 8 ItlCHES (TRAiN A) HI6HER INHB 30 L0943E SNP 8 LEVEL 8 INCHES (TRAItt 8) HIGI{ER I t(HB 31 L09420 SUPP 8 LEVEL 78 INCHES (TRAIN A) HIGPZB INHB 32 L09439 SSP 8 LEVEL 78 ! tKHES (TRAIN 8) HIGHER It(HB 33 L0942C RAP 8 LEVEL 113 IN¹S(TRAIN A) HIGHER ALRt( 34 L0943C SOP 8 LBr'EL 113 INCHES(TRAIN 8) HIGHcR ALR{( 35 L09428 SUtP 8 LE'PcL 180 INCHES(TRAIN A) LONER G009 36 L09438 SU5' LEVEL 180!NCHES(TRAIN 8) LG)IER 6009 37 L0942A SUNUP 8 LEVEL 214 It<CH=S(TRAIt( A) LONER GOOD 38 L0943A SSP 8 LEVEL 214 INCHES(TRAIN 8) LQMER 6009 39 T0409A RiLA HOT LEG TEMPERATURE 249,4 .6009 IFGF 40 T0410A RC!!) HGT LEG TE)(PERATURE 249.6 =GOOD DEGF 41 T0450 RCLA COLD LEG TEIIPERATURE 201.5 BAD DEGF T0451 RCLB COLD LEG TENPERATNE 158.2 BAD DEGF 43 TA VGA~A ID RCLA TAVB (THGT/TCOLD WIDE RNG) 249.4 600~ KGF 44 TAVBBWID RCLB TAVB (TNT/TCOLD RIDE Rt(0) 249.6 GGQc DEBF 45 LRV REACTGR VESScii AVERAGE LEVEL 38.4 LALti 46 TCCQRE El 1 INCQRE T" AVERAGc TEtiP ~ 803.0 HAL+ DEGF 47 FAUXFMA S/6 A TOTAL AUX FEED~AATcR FLPA 0. GOOD FN FAUXFWB S/G 8 TOTAL AUX FEED){ATER FLO'A 129. 6009 PN BXRO81 le AUXILIARYFEEDWATiR PUtP A C<F 6009 50 BXR082 t,TR AUXILIARYFEED)IATER PUN 8 Qt( 6009 51 V3505 A!JX FW PUlF STEAtf SUPPLY VALVc A CLOSED 6009 c2 V3504 AUX R{ PUtP STEAII SUPPLY VALVE 8 . CLOScD 6009 ttOV 17i 1993 10'X R. E. GINNA Sit'LMTOR PAGE 2 TREND GROUP ASSIGNYiEt/T PJiiRY GROUPS EVENT1 PROCEDURE: EPIP 1 5 PLANT STATUS POINT ID DESCRIPTION VA'c CUAL E U 53 FSIA SAFcC'Y IN:ECTION LOOP A AVG FLOW 0. 6009 GPtt 54 FSIB SAFETY ItQECTION LOOP B AVG FLOW O. 6009 Gpt1 55 P 2160 SHNICE MATER PNPS A h B HEADER 87. GOOD PSIG 56 P2161 SERVICE MATER PUttPS C & D HEADER 86. 6009 PSI6 57 BKR041 SERVICE MATER PNP A Otf 6009 58 BXR042 SERVICE MATER PUttp B ON GOOD 59 BKR043 SERVICE MATER PUttP C ON GOOD 60 NR044 SERVICc WATER PlNP 0 as 6009 }7>> }993 }0:29 fi. E. GINA SIN}tLATOR TREND GROU, ASS IGNYZttT SUN>>NARY GROUP: BrcNT2 PROCH)UR-" ~ EPTP 1-5 PLANT STA'PJS POINT ID DEKRIPTIQN VALUE ttUAL E. U. } F0619 COtPONENT COOLINS LOOP TOTAL FLW 892. LALN GPN 2 LRWST REFUELING WATER STORAGE TANk LVL 37.1 6009 / 3 WS033 33 FOOT LEVE'}ttD SPEED 3.0 GOOD NPH 4 WD033 33 FOOT LEVB. WIND DIRECTION 4}. GOOD DEG. 5 WT033 33 FOOT LEVc TENPERATURE 43.1 6009 DEGF 6 WT250 250 FOOT LEVE TENPERATURi 43.} 6009 DEGF 7 WDT2 250 TO 33 FOOT LEVEL DELTA TEYP .0 6009 IEGF 8 R01 AREA }~ONTRQ ROON 8.91250-02 GOOD NR/HR 9 R02 AREA 2-COtiTAINtB<T 7.80727+03 BAD tS/HR !0 R05 AREA 5-SPENT FUEL PiT 3.}44}2+00 BAD NR/HR '} R09 At}EA 9-LETDOWN~>>'it>>c NONITQR 2.75423~0} BAD }S/HR ~ Q R34 ARB 34 - AUX BLDG CV SPRAY PL'NP 2.95}2}400 BAD NR/HR 13 R35 AREA 35-PASS SANPLE PA>>'K 1.09648+00 6009 NR/HR }4 R}OA CONTAINNit>T IODIN"" NOttlTQR R}0A }.03068%7 Hite CPt} 15 R}1 COtifAItti~>>chT AIR PARTIC(J ATE }.03068+07 HENS CPN }6 R}2 CQNTAIt<NEtIT GAS NQNITOR }.0}741+07 HENS CPN }7 R}OB PLN.>> VENT IODINi NQttITOR R}09 9.8997440} 6009 CPN }8 R!3 AUX B~~ EXHAJST AIR PNTICULATE 2.4092}~02 GOOD CPN R14 AUX BLDG EXHAUST GAS ttONITOR 5.42468402 6009 CPN 20 R}8 LIKID WASTE DISPOSAL YONITOR 9.'?7}26+02 6009 PN C>> >> a R}9 STiA>>"~ FB}ERATOR BL}tWDQWN DRAIN 2.}9722+03 GCCD CPN e R29 ARiA 29<OtiTAIt}NENT HIGH Rdi'Gi 8.0006}40} HNRtt R/HR R30 AREA 30-CQt}TAINYiENT HIS RANGE 8.00061+01 HWRN R/HR 24 R15 CONDih:ER AIR EJECTOR EXHAUST }.48337+03 GOQ9 CoN "5 R12A5 CV V"l>>:. CHAM 5-LOW RAl>>>>F GAS 4.205!1-05 GOQD UCI/CC 26 R}286 CV V""~i": CNtt 6-AKA GMcA 8,00000~m Wm tS/HR 27 R12A7 CV Vit>>T CHAN 7-t>>19 RANGE GAS 4.20511-05 GQQ9 UCI/CC 28 R}2A9 CV VENT CNM 9-HIGH RANGE GAS 9.99987-04 GOOD UCI/CC 29 R}4"5 PLNT VENT CNN 5-LCA RANGE GAS }.77994-05 6009 UCI/CC 30 R}4A7 PLCii VENT CNtt 7-NID FAttSE 6AS }.77994-05 6009 UCI/CC 31 R14A9 PLANT VENT CHAN 9"HIGH RAttSE 6AS 9.}0997-04 UCI/CC R}595 AiR i:ECTQR CHAN =LCn'At}GE GAS GOD9'.22985-06 V GOOD UCI/CC 33 R15A7 AIR E-,ECTQR QfAlt 7 YID RAN6i 6AS 1.80975-05 6009 UCI/CC 34 R}5A9 AIR EQECTQR CHAN 9-HI RANGE GAS 1,52999-03 K09 UCIICC 5 R31 AREA 3} STEAN Llt,c, A {SPINz) }.01004-02 GOOD NR/HR 36 R32 AREA 32 STEAN LINE B (PING) !.0}004<2 6009 NR/HR 37 CVH CV HYDROGEN CONCEtlTFAT IQtt .0 GOOD 7 38 TCV03 CV BASENEttT t Rlr"L 6~>> TEY~~ tt3 69.2 GOQ9 DEGF 39 TCV07 CV itfiRNEDIATE LVL 6FT TEYZ tt7 80.9 . GQQ9 }EGF 40 TCV08 CV IttlcR~IATE LVL 6FT TENP 48 80.8 4009 DE6F 4} TCV09 CV INTERNEDIATE LVL 6FT TENP tt9 80.9 K09 }EGF 42 TCV}0 CV IH~ "RNEDIATE LVL 6FT TENP tt}0 80,8 C<09 D=GF 43 TCV17 CV QiiRATING LEVL 6FT TENP C}7 92.5 6009 'EGF Time; 1045 Message: 44 6INNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM I: Ri I R I R Simulated Plant Conditions: See Attached Sheets ~Messa e: <<<< "THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Controller Notes: Antici ated Results:
- 1) Operators should be performing the applicable actions of FR-C.1 (Response to Inadequate Core Cooling).
1993 EVALUATED EXERCISE Time: ~0~~ MAZOR PARAMETERS ENGINEERED SAFEGUARDS Reactor Shutdown ES NO Hi h Head S.I. Pum s N-31 7/3 CPS FI-924 C> GPM N-32 CPS FI-925 ~GPM N-35 ~~OAMPS 1A. INSERV STBY 00 N-36 ~t~lAMPS 1B- INSERV STBY 0 Avg. Nuclear Power 1C. INSERV STBY OOS RCS Pressure PRZR Level PSIG BAST Level = ~) A RCP RUNNING/ TOPP Low Head S.I. Pum s B RCP RUNNING STOPPE FI-626 ~> GPM 1A S/G Level 1A. INSERV STBY 0 RECIRC 1B S/G Level %7s 1B. INSERV STBY RECIRC lA S/G Pressure PSIG RWST Level = 1B 5/G Pressure PSIG Turbine/Generator ONLINE/ FLINE Containment 8 ra Pum s 4 KV Buses NERGIZE /DEE GIZED FI-9 3 1A~GPM 480V Buseslgdgat G EENERGIZ FI-931B C3 GPM DC Batteries Agb VOLTS B~OVOLTS 1A. INSERV STBY 00 Cnmt Pressure '~~PSIG Cnmt Sump A Level Cnmt Sump B Level s /~~INCHES FEET 1B. NaOH Tank Level = ~4 INSERV STB OOS " Loop Hot Leg OF Containment Recirc Fans A Loop Cold Leg ~2,o/, 4F 1A. INS RV STBY 0 B Loop Hot Leg ~~OF ~1':~ 'F 1B. STBY OOS B Loop Cold Leg 1C. INSERV STBY OOS RVLIS 'Bkr 7 Q 1D. INSERV STBY OS
- CET 5K~ M'F Post Accident Dampers OPEN CLOSED S/G A Total Aux FW Flow O GPM 5/G B Total Aux FW Flow ~2. GPM Service Water Pum s 1A. N RV STBY OOS DIESEL GENERATORS 1B. IN ERV STBY OOS 1C. INSERV STBY A.
B. RUNNING UNLOADED STBY OS RUNNING UNLOADED TB OOS 1'SERV A&B STBY Meaaer Pressure OOS OOS @7+Co PsIG TSC RUNNING UNLOADED B OOS Security RUNNING UNLOADED TB OOS Com onent Coolin Water Pum s 1A. INSERV STBY 0 ENGINEERED SAFEGUARDS 1B. NSER STBY OOS Surge Tank Level =.~> Aux. Feedwater Pum s 1A. INSERV STBY 0 Standb Aux. Feedwater Pum s
- 18. ER STBY OOS 1C. INSERV STBY 0 Turb. Driven INSERV B OOS 1D. INSERV TB OOS CST Level g~s ~FEET
- CET = Average of Selected Core Exit Thermocoup1es
NOY 17'993 10'4 R. E. GIt@A SltIULATQR PAK 1 . TRit(D GROUP ASSIGt<<~t(T SUINRY GROL+: EVENTI PROCEP>>.F: EPIP 1-5 PLANT STATUS POINT iD DESCRIPTION: VALUE E. U. AIl6 ANTICiPATED TRANSIT(T W/0 SCRAN ATNS ALRtI 2 RXT RE@".TOR TRIP BREAKER STATUS RX TRIPPED ALRII 3 N31 SMCE RA)IK DETECTDR tf-31 1. 18713p05 HALI( 4 tG2 SEE=" RANK DETECTOR N-32 3.94456+01 BAD CPS 5 N35 INT.=RNEDIATE RAN6E D"=TECTOR N-35 2.64239-10 6008 fNP 6 N36 It~> "P~~DIATE RANGE DiTECTOR N-36 1.00001-11 Gm A!IP 7 NP AVERAGE NUCLEAR POWiR .00 6008 8 PRCS REA TOR COOL@(T SYST>c AYG PRESS LALN PSIG 9 LPER PK~SSURI EER AVERAGE LEVEL .0 LALtI / In FRY RBr"TQR COOLANT LOOP A AYG FLOW 1.0 It(H>> 0/ 11 FRCi3 REACTOR CCCL@T LOOP R AVG FLQM 1.3 ItlHB / 12 RXT16 RCPA BREAKER CAUS'i RX TRIP TRIPPED ALRII '13 RXT17 RCPB BRENER CAUSE RX TRIP TRiPPED ALRII t4 TSUBTC INCORE TC SUBCOOLED NNGIN -820.7 LAL>> DEGF 1U LSGA STtI Kt( A t(ARROW RA%: AVG LEVEl 67.4 HALII 16 LSGB STt'i GiN R t(ARROW RANGc AVG LEVEL 27.9 LWR>> I/ 17 PSGA STtI Gi!( A AVERAGE PRESSURE "4. LALt', PSIG PSGB STN GEI( 8 AVERAGE PRESSURE uV II PS!G l9 GiNBKRI GitKRATOR ON LINE BREAKER 161372 TRIPPED ALRN 20 GENBKR2 GENERATOR OM 't(E BREAKER 9X1372 7RIPPED ALRII 21 BUS11A BUS 11A SUPPLY BREAKER TRIPPED ALRII BUS118 BUS 1!8 SL'PPLY BREAKER TRIPPED ALRII 23 8US12A t(OT 7ERNINATED ON PPCS (7/19/91) NO. TRIP DEL 24 BUS128 t(QT 'tiNIt(ATED QN FPCS (7/!9/91) t(OT TRIP DEL )5 811A12A BUS 11A TQ 12A TIE BRiNER t(QT TRIP ALRN 26 8118128 BUS 118 TO 128 TiE BREAKER NOT TRIP ALRII 27 PCY CQNTAINtIEt(7 AVERAGE PRESSURE .52 GOO>> PSIG 28 29 LSUNPA L0942E CQtFiAIt'ZiTSJtIP A AYERAK LEVEL MP 8 LEVEL 8 INCHES (TRAIt( A) HI6HER 31.2 r'PS HENS INHB FKT 30 L0943E Slat 8 LEVd. 8 It(CHES (TRAIN 8) HI6HEP, INH8 31 L0942D HJt. 8 LEVd 78 INCfiiS (TRAltt A) HIGf&c I WB 32 L0943D SUtP 8 LPr~ 76 it(CHES (TRAltt 8) H16HER INHB 33 L0942C SU% 8 LEVEL 113 INCHES(TRAIN A) HIGHER ALRtt 34 L0943C SU%' LEVEL 113 It(CHciS(TRAIN 8) HIGHER KRW 35 L09428 SUtF' LEYEI. 180 INCHES(TRAIN A) LOWcD 6008 36 L09438 SUPP 8 LEVEL 180 INCH""S(TRAIt( 8) LONER 6008 37 L0942A Rti. 8 LEVEL 214 INCHES(7RAIN A) LONER GQQD 38 LO943A SUtP 8 I.EYEL 214 INCHES(7RAIN 8) LONER C&8 39 T0409A RCL~ HQT LEG TEtPERATURE 215.5 GOOD DEGF 40 '0410A RCLB HOT LEG TEtIPERATLK 215.5 ~8 DEGF 41 T04sn RCLA COLD LEG TE)IPERATNE 201.5 BAD IFM T0451 RCLB COU) LEG TE)IPERATURE 158.2 BAD DEGF 43 TAVGAWID RCLA TAVG (THOT/TCQLD WiDE RNG) 215.5 600>> DEGF TAVGBWID RCLB TAVG (THQT/TCOLD WIDE Rt(G) 215.5 CCO>> DEGF 45 LRV REk TOR VESSEL AVERAGE LEYEL 36.7 LALII K 46 TCCQRE Ei.l INCORE TC AVERAGE TEIIP 852.9 HAL>> DEGF 47 FAUXFWA S/6 A TOTAL AUX FEEDWATER FLOW 0. 6008 VII 48 S/6 8 28, 6008 Ptl 49 FAUXFWB BKR081 TOTAL AUX FEEDMATER FLOW NTR AUXILIARYFEEDWATER PUtIP A OFF 'OOD 50 BKROB2 )ITR AUXILIARY FEEDWATER PUIIP 8 ON 6008 51 V3505 AUX FW Ply STEA)I SUPPLY VALVE A CLOSED 6008 52 Y3504 AUX FW PlÃ'TEA)I SUPPLY VALVE 8 CLOSED GOOD /'" j3 NOV 17i H93 10:43 R. E. GINA SIMULATOR PAGE 2 TREND GROiUP ARIGfffiEfii SUi"iftARY e GROUP; EVENT1 POINT ID PROCED~~E DESCRIPTIOV EPIP 1 5 PLANT STATUS VALUE QUAL E. U. 53 FSIA SAFETY INJECTION LOOP A AVG FLOW 0, GOOD 9'N 54 FSIB SAFETY INJECTION LKP B AVG FLOW 0. GOOD GPN 55 P2160 SERVICE MATER PUMPS A h B KITER 87. GOOD PSIG 56 P2 161 SERVICE MATER PUfFS C h D HEADER 86. GOOD PSIG 57 BKR041 SERVICE MATER PUfft' ON GOOD 58 BKR042 SERViCE WATER PUfP 8 OiV GOOD 59 BKR043 SHNICE MATER PUNP C ON GOOD 60 BKR044 SERVICE MATER PU!i? 0 ON GOOD NOV 17i 1993 10:4'. =. GitWA Slt'iLLATOP, PAR TREND GROUP ASSIGNME)'T SUMNARY GROUP; EVENT2 PRQCEDLRcE: EPIP 1-5 PLANT STATUS POINT !D DES!AIPTIOW VALL!E QUAL E. U. 1 F06}9 COtPOltcNT Coo." ING LKP TOTAL FLN 892. LAN GPN 2 LSGT FcCLING ))ATER STORAGE TAtà LVL 37.1 6009 'i( 3 NS033 33 FQOT LEVEi WIND SPcB) 3.0 6009 NPH 4 t)9033 33 FOOT LEVEL MIND DIfKCTIGN 41. 6009 DEG. 5 MT033 33 FOOT LEVEL TEMPERATURE 43.1 G009 IFGF 6 WT250 250 FOOT LEVEL TEMPERATURE 43;1 6009 DEGF 7 NDT2 250 TQ 33 FOOT LEVEL DELTA TP~ .0 6009 IFGF 8 RO} AREA }-Cot(TRg ROO 9,44062M 6009 t8/HR 9 R02 AREA 2<ot(TAINNcERT 7.80727+03 BAD %/HR 10 R05 AREA 5-SPENT FU9. PIT 3, 14412t00 BAD NR/HR !1 R09 AREA 9-LETDOPa< LItF NONITGR 2,75423t01 BAD l8/)I 12 R34 AREA 34 - AU( BLDG CV S, RAY Pot(P 2.95121+00 BAD N/HR !3 R35 AREA 35-PASS SAMPLE PAtKL 1, 09648t00 6009 ts/HR 14 R}OA CGNTAINNiENT IODltZ NOtiITOR R10A 9.66051t06 HALtI CPN 15 R!1, CGNTAIHNENT AIR PART IC(LATE 9.66051+06 HALN CPN 16 R}2 CO'lTA!t(MEt(T GAS tSNITGR 1.01741+07 HEWS CPN !7 R!OB PLAi7 VENT IODIttE MONITOR R}OB l. 14}56t02 6009 CPN 18 R13 AUK BLDG E)(YAJST AIR PARTICULATE 2.548Bt02 6009 CPN R!4 AU): BLDG E)(HAJST GAS NONITGR 2.55563+03 HALN CPN 20 R}8 LINJID ViASTE DISPOSAL MONITOR 1.01888t03 6009 CPN 2'!9 STEAM GBlERATOR BLO)(DON DRAIN 2,12263t03 G009 CPN fM 0 R29 ARcA 29-CONTAINNEt)T HI(if RANGE 7.99485t02 R/HR P30 AREA 30-CQWTAItNENT HI% RNi'GE 7.99485t02 HALN R/HR 24 R}5 Col(DENSER AIR EJECTOR E)(HAUST 1~ 41457t03 6009 PN R12A5 CV %Bing CSN 5-LOk'At(GE GAS 4.205}!M G009 UCI/CC 26 R!2Ab CV VEW; CHAN 6-AREA GAB% 2.00000tO} O'Rt( N/HR 27 R12A? CV VER! CHAN 7-NID RANGE GAS 4.205}}-05 6009 UCI/CC 28 R}2A9 CV VEWi CHAN 9 HiGH RA'P~c 6AS 9.99987-04 6009 XI/CC 29 R}4A5 PLANT VEtkT CIL4N 5-LOW RANGE GAS 8.24988-04 HNRt( XI/CC 30 R}4A7 PL'Al)T VENT CHAN ?+ID RANGE GAS 8.24988-04 6009 XI/CC 31 R}4A9 PLNT VENT CMAtt 9-HIGH RAt(GE GAS 9.10997-04 GOOD XI/CC 32 R!5A5 AIR EJECTOR CHAN 5-LG)t RAN6E GAS 6.22985-06 6009 XI/CC 33 R}5A7 AIR cJcCTOi RCHAN 7 NID RANGE GAS 1.80975-05 6009 XI/CC 34 R}5A9 AIR EJcCTGR CHAtt 9+I RANGE GAS 1 52999M ~ 6009 XI/CC 35 R3! AREA 3! STEAN I.INEA (SPING) }.0}004M 6009 I)/tl 36 R32 AREA i~ STEAM LINE 9 (c It(6) }.0}004<2 6009 N/MR 37 CVH CV HYDROGEt< COWCEttTRATION .0 GOOD \/ 38 TCV03 CV BASENEt(T LEVEL 6FT TEMP ti3 66.0 6009 DE6F 39 TCVO7 CV Iti HNEDIATE LVL 6FT TEMP ()7 70.6 6009 DEGF 40 TCVOB CV INTERMEDIATE LVL 6FT TE)P 48 70.6 =6009 IFGF 41 TCV09 CV INTERNEDIATE LVL 6FTi TPiP N 70.6 GOOD IFGF 42 TCV10 CV INTERMEDIATE LVL 6FT TEMP NO 70.6 6009 DEGF TCV}7 CV OPERATINS LEVL 6FT TEMP It}7 75.3 6009 DEGF 7 Time: 1050 Message: 45 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM ~Mt: 5 i L Simulated Plant Conditions: See Attached Sheets ~Messa e: <<""THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Controller Notes:
- 1) Radiation levels increase substantially in Auxiliary Building. This due to the leaking pipe between Containment and MOV-850A opening up where the crack is. A release above technical specifications begins, Antici a ed Resul s;
- 1) Operators may transition to ECA-1.1 (Loss of Emergency Coolant Recirculation) due to loss of both RHR pumps.
- 2) TSC should be expediting the turning on of the AC power breaker to MOV-851A.
- 3) TSC should be expediting the recovery of AC power to Bus 14.
- 4) TSC should inform the EOF of the increased radiation levels in the Auxiliary Building.
- 5) TSC should inform the EOF of plant status, actions being taken and needs required.
- 6) EOF should be evaluating plant conditions and taking actions as required.
- 7) EOF Dose Assessment should be evaluating the plant vent release and making protective action recommendations to the EOF/Recovery Manager.
- 8) The EOF/Recovery Manager, after evaluating the EOF Dose Assessment recommendations, should recommend protective actions to offsite agencies as required.
- 9) Repair teams should be expediting repairs as conditions permit.
Time: 1100 Message: 46 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM IN: 8 I C << IR - Simula ed Plant Conditions: See the Attached Sheets ~IVlesss e: """THIS IS AN EXERCISE""" The following Annunciator is received: '-10 (Auxiliary Building Sump Pump Auto Start) FOR CONTROLLER USE ONLY Controller Notes:
- 1) The "8" Auxiliary Building sump pump starts and runs for approximately one minute.
Antici a ed Results:
- 1) Operators should perform the applicable actions of AR-L-10.
- 2) Operators should inform the TSC of the operation of the Auxiliary Building sump pump.
- 3) TSC should evaluate the Auxiliary Building sump pump operation and the possibility of the leak in the pipe between Containment and MOV-850A getting worse,
- 4) EOF evaluating plant status and taking actions as required.
1993 EVALUATED EXERCISE Time: MAJOR PARAMETERS ENGINEERED SAFEGVARDS Reactor Shutdown YES NO Hi h Head S.I. Pum s N-31 CPS FX-924 r2 GPM N-32 CPS FI-925 ~GPM N-35 ~o~iAMPS 1A- INSERV STBY S N-36 ~~AMPS 1B. XNSERV STBY Avg. Nuclear Power Q 1C. INSERV STBY OOS RCS Pressure PRZR Level OG PSIG BAST Level = ~g A RCP RUNNING/ TOPPED Low Head S.I. Pum s B RCP RUNNING/ TOPP D FI-626 (3 GPM 1A S/G Level ~Gv 1A. INSERV STBY 0 RECIRC 1B S/G Level ~B> 1B. INSERV STBY RECIRC 1A 1B S/G Pressure S/G Pressure 5 PSXG PSIG RWST Level = ~LL Turbine/Generator ON NE FFLIN Containment 8 ra Pum s 4 KV Buses ENERGIZED DEENERGXZED FZ-931A~GPM 480V Buseslit'&ov7 ED ENERGIZE FZ-931B~GPM DC Batteries A@@VOLTS B~VOLTS 1A. INSERV S 0 lB. Cnmt Pressure Cnmt Sump A Level Cnmt Sump B Level Q PSZG Ie ~ FEET INCHES INSERV STB OOS NaOH Tank Level = ~4 " Loop Hot Leg OF containment Recirc Fans A Loop Cold Leg s5 0F 1A. INSERV STBY OS B Loop Hot Leg g/CLGL F 1B. NSER STBY OOS B Loop Cold Leg ~K.M OF 1C. R STBY OOS RVLIS 8 0 1D. XNSERV STBY 0 'F
- CET Post Accident Dampers OPEN CLOSED S/G A Total Aux FW Flow O GPM S/G B Total Aux FW Flow ~g GPM Service Water 1A.
Pum s SERU STBY OOS DIESEL GENERATORS 1B. STBY OOS 1C. SERV STBY OOS A. B. RUNNING UNLOADED STBY OS RUNNING UNLOADED TB OOS TSC RUNNING UNLOADED OOS 1D. A&B NSERU STBY OOS Header Pressure ~0 PSXG Security RUNN NG UNLOADED TB OOS Com anent Coolin Water Pum s 1A. INSERU STBY OS ENGINEERED SAFEGUARDS 1B. NSER STBY OOS Aux. Feedwater Pum s Surge Tank Level =, ~Q 1A. XNSERV STBY OS Standb Aux. Feedwater Pum s 1B. SER STBY OOS 1C. INSERV S Y 0 Turb. Driven XNSERV B OOS 1D. INSERV TB OOS CST Level ~ FEET
- CET = Average of Selected Core Exit Thermocouples
NQV li. 1993 lll00 ~ R. E. GINA SIMULATOR PAGE 1 TREND Bf(GUP ASSIGNtfit(T SUi"it(ARY GROUP; cVENT! PROCEDURE: EPIP 1"5 PLANT STATUS POINT ID DES"RIPTIGN OVAL E. U. 1 ATNS ANTICIPATED TWNS!ENT H/0 SCRA)f ATNS ALRI( 2 RXT REACTOR TRIP BREAKER STATUS RX TRIPPED ALRtf 3 M31 SOURCE RAhBE DETECTOR tf-31 1.01976+05 HALI( CPS 4 N32 SO(BCE RANGE DETECTOR N-32 3.94456+01 BAD CPS 5 N35 It(TENEDIATE RANSE DETECTOR N-35 2.02302-10 6009 NP 6 N36 INT"R,IEDIATE RANGE DETECTOR N-36 !.00001-11 GOOD NP 7 tfP AVEAGE NUCLEAR POKER .00 GOOD K 8 PRCS REA"TOR CCQ.NT SYSTEtf AVB PRESS LALtf PSI6 AVERAG" LEVEL LALI( '/. 10 LP2R FRCLA PRESSURI2ER REACTOR COOLS(T LOOP A AVG FLGA 'ALUE2.4.Q IM6 y. F¹8 REACTOR COOLANT LOOP 8 AVG FLO)f .0 It(HD / 12 RXT16 RCPT BRiAKER CAUSE RX TRIP TRIPPED ALRII !3 RXT!7 RCPB BRE'AKER CAUSE RX TRIP TRIPPED ALRtf 14 TSUBTC It'ZRc TC SIS"OQLED t(ARBIN -814.9 LAL>> DE6F !5 LSBA STtf CW A t(AIR)>f RANGE AVB LEVEL 67.7 HALI( 16 LSGB STtf Citf 8 NARRPA RA%"" AVG LEVEL 32.9 600>> 0/ 17 PSBA STtf BEN A AVEABE PRESSURE -5. LM PSIG '8 PSGB STtf BEN 8 AMYLASE PRESSURE -5. LALI( PSIG !9 GB(BKRI BEtKRATGR ON LINi BREAKE 161372 TRIPPED ALRt( 20 GENBKR2 GYRATOR ON LINE BREAKER 9X1372 TRIPPED ALRtf 2! BUS! 1A BUS !1A SIR'LY BREAKER TRIPPED ALR)f 22 BUS!18 BUS 118 SUPPLY BREAKER TRIPPED ALRtf 23 BUS!2A t(OT TERtfltNTED GH PPCS (7/19/91) NOT TRIP DEL 24 ,BUS!28 t'GT TERtf INATED GH PPCS (7/!9/91) t(OT TRIP DEL 25 B!1A12A BUS !!A TG 124 TIE BREAKER tfOT TRIP ALRtf 26 81!8128 BUS 1!B TO 1'28 TIE BREAKER NOT TRIP ALRII 27 PCV COWTAIHtfit(T AVERC~ PKSSURE .11 GOO>> PSIG 28 LB@PA CONTAItlYZhT SUtfP A AViRABE LEVEL 31.2 HEtlB FEET 2'? L0942E SOP 8 LEVEL 8 INCHES (TRAIt< A) HIGHER INHD 30 L0943i SUtf' LEVEL 8 INES (TRAIN 8) HIGHER Itff(8 31 L09429 Sue 8 LEVEL 78 It(CHES (TRAIt A) HIGM INHD 32 L09439 KN' LEVEL 78 It(CH<<ES (TRAIN 8) HIBHE It'IHD 33 L0942C SUtP 8 LEVEL 113 INCHES(TRAIN A> HIGf(ifl ALRtf 34 L0943C SUN 8 LEVEL 113 INCHES(TRAIN 8) HI6HER ALRN 35 L09428 SU~<<' LEVEL 180 INCHES(TRAIN A) LONER 6009 36 L09438 SU". 8 LEVEL !80 INCHES(TRAltf 8> LONER 6009 37 L0942A SUN' LEViL 214 INCH-"S(TRAItf A) LOUR 6009 38 L0943A SU)fr 8 LEVEL 214 It(CHES(TRAIN 8) LONER GOOD 39 T0409A RCLA HGT LEG TEMPERATURE 214.4, GQOD DEGF 40 T04!OA RCLB HOT LEG TEtfPERATIR-" 214.4 =GOOD DEGF 41 T0450 RVD COLD LEG TEt)PERAT5tE 201.5 BAD DEGF 42 T0451 RCLB COLD LEG TEtfPERATNE 158.2 BAD DEBF 43 TAVBAWID RCLA TAVG (Tf(OT/TCOLD WIDE RNB) 214.4 600>> DEGF 44 TAVBB)(ID RCLB TAVB (THOT/TCOLD WIDE RtiYi) 214,4 600>> DEGF 45 LRV REACTOR VESSEL AVERAGE !LEVEL 39.Q LALtf y. 46 TCCGRE El. 1 It(CORE TC AVERAGE TEt!P 845.5 HAL>> D=GF 47 FAUXFWA S/6 A TOTP.'UX FEECCATE FLQI( 0. GOOD Ptf 48 FAUXR)8 S/6 8 TOTAL AUX FEH'yfAT~B FLOH 28. 6009 GPtf 49 BKR081 tfTR AUXILIARYFiEDMATER PUtfP A QFF GQQD 50 BKR082 'ITR AUXILIARYFEEDHATER PUtfP 8 Qtf GOOD 5! V3505 AUX FH PUI(P STEAN SUPPLY VALVE A CLOSED GGQD 52 V3504 AUX FH PU!!P STEN) SL'PPLY VALVE 8 CLOSED GOOD ." -/~/2. NOV 17i 1993 ll!0~ R. E. GINA SIMULATOR PAGE 2 TREND GROUP ASSIGNMENT
SUMMARY
GROUP: EVENT1 PROCEXRE: EPIP 1-5 PLANT STATUS Polt~r ID DESCRIPTION VALLEY QUAL E. U. 53 FSIA SAFHY INJECTION LOOP A AVG FLOW 0. GOOD PM 54 FSIB SAFE INDECTION LOOP B AVG FLOW 0. 600D GPM 55 P2150 SERVICE WATER PtNPS A & B HEADER 87. Gooa PSIG 56 P2161 SHNICE WATER PUtFS C & 0 hcAKR 86. 600D PSIG 57 IWR041 SERVICE WATER PUttP A OH GOOD 58 BKR042 SERVICE WATER PUN& B ON GOOD 59 BkR043 SERVICE WATER PUtP C ON 600D h0 BKR044 SERVICE WATER PUttP 0 ON 600D
hOU 17i 1993 IOl59 R. E. Gite Sit'i'TOR TREND GROUP ASSIGNttchT SUMttARY GRQL>>'; EFJT2 PROCEDLcti EPIP 1 5 PLANT STATUS POINT ID DESCRIPTION VALE E. U, 1 F0619 COtPONENT COB.IN6 LOOP TOTAL FLM 892. LALI'i GPN 2 LRWST REFUELING WATER STORAGE TAX LVL 37.1 G009 X 3 WS033 33 FOOT Lied. MIND SPED 3.0 6009 AH 4 WD033 33 FOOT LEVEL WIND DIRECTIQti'3 41 ~ G009 D:6, 5 MT033 FQQT LEVEL TittPERATURE 43.1 6009 DE6F 6 WT250 250 FOOT LEVEL TEYiPERATURE 43.1 6009 DEGF 7 WDT2 250 TO 33 FOOT LEVEL DELTA .0 G009 ItGF 8.912~2 TEN'REA 8 R01 I-CONTRt)." ROON G009 ta/HR 9 R02 AREA 2-CONTAINttitlT 7.80727+03 BAD lg/HR
!0 R05 PEA 5 SPENT FUcL PIT 3.14412+00 BAD ttR/HR R09 ARiA 9-LETDO'rtN Litle NQNITOR 2.75423401 BAD N/HR
.'2 R34 AREA 34
- AUX BLDG CV SPRAY PLOP 2.95121+00 BAD HR/HR 13 R35 AREA 35-PASS SAHPLE PAWL 1.09648~00 6009 t8/HR 14 RIOA CONTAINttENT IODINE NQNITGR RIQA 1.02182+07 HENG CPH ii5 Rl 1 CQNTAINt'cNT AIR PARTICt i ATE 1 ~ 02182+07 HENS CPN 16 R12 CONTAIeiNT GAS ttQNITGR 9.74430~06 HALH PN 17 RIOB PLNT VENT IODINE ttONITOR R109 1.02772+06 HALl', CPN 18 R13 AUX BLDG EXHAUST AIR PNTIClLATE 2.54829+02 6009 CPtl R14 AUX B'G EXHAiJST GAS tiONITOR 9.78647+06 HAJJt tl 20 R18 LICJID WASTE DISPOSAL N)NITGR 9,8855&05 HALN 9'H 21 R19 STE>",i GENERATOR BLOWDO'4 DRAIN 7.07943~03 HALl', CPN R29 ARcA ~ CCNAIttttBtT HICI RAtRE 1.90134+03 HALtt R/HR 23 R30 PEA 30-CQN'Alh~8tT HIS RAttG"" 1.90134~03 HALtl R/HR 24 R15 COtKiiNcER AIR EJECTOR EXHAUST 1.47698%3 6009 CPN 25 R12A5 CV VihT Cf2Pl MOW RAi!K GAS 4.20511M 6009 KI/CC 26 R12A6 CV VENT CHAW 6-AREA GNN 5.20000~02 HALtt l8/HR 27 R12A7 CV VENT CHAN 7-ttiD RAtK GAS 4.20511-05 6009 KI/CC 28 R12A9 CV VBit CPA< 9+IGH RAQGE GAS 9.99987M 6009 UCI/CC 29 R14A5 PLNT VENT CHAN 5"LN RANGE GAS 9.96974-03 HALf! KI/CC 30 R14A7 FLAN~ VENT CNt( 7-HID RANGE 6AS 8.85986+00 SUt KI/CC 31 R1 489 PLQ" VENT CNN 9+IS RANGE 6AS 8.85986+00 KI/CC 32 R15A5 AIR FJECTOR CHAtl 5-LGW RAN6E CAS 6.229~ 6009 KI/CC 33 R1587 AIR EJECTOR CHAN 7~iilD RANGE GAS 1. 80975-05 6009 KI/CC 34 R15A9 AIR EJECTOR CHAN 9-HI RANGE GAS 1.52999"03 GQ09 KI/CC 35 R31 4REA 31 STEAN LINi A (BRING) 1.01004-02 6009 ta/HR 36 R32 ARcEA 32 STEAN LINE B lSPINS> 1.01004M t8/HR 37 CVH CV HYDROGEN CONCEWTPATION ~ 0 6009 38 TCV03 CV BASBL~NT LEVEL bfT TER~ tt3 64.4 K09 DEGF 39 TCV07 CV IWTERNEDIATE LVi 6FT TEttP 47 65.3 GOOD 0-"GF 40 TCV08 CV INTERMEDIATE LVL 6FT TEHP lt8 65.3 4009 DEGF, 41 TCV09 CV ittTERttEDIATE LVL 6FT TEtP tt9 65.3 6009 DEGF 42 TCV10 CV ItficRttEDIATE LVL 6FT TEHP tt10 65.3 G009 0" GF 43 TCV17 CV OFERATltlG LEVL 6FT TcttP tt17 66.3 6009 DEGF
Time: 1110 Message: 47 GINNA STATI N 1993 EVALUATED EXER I E MESSAGE FORM ~M: M I R << IR Simulated Plant Conditions: See the Attached Sheets ~Massa e: """THIS IS AN EXERCISE""" The following annunciator is received: '-10 (Auxiliary Building Sump Pump Auto Start) FOR CONTROLLER USE ONLY Controller Notes;
- 1) The "B" Auxiliary Building sump pump starts and runs for approximately one minute.
Antici a ed Results:
- 1) Operators should perform the applicable actions of AR-L-10.
- 2) Operators should inform the TSC of the operation of the Auxiliary Building sump pump.
- 3) Operators should be performing the applicable actions of FR-C.1 (Response to Inadequate Core Cooling). When they attempt to start the RCP's they trip out immediately.
- 4) TSC should be'evaluating the plant status and taking actions as required.
Time: 1115 Message: 48 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM I: W I <<C IR Simulated Plan Condi ions: See the Attached Sheets ~Messe e: <<<< "THlS IS AN EXERClSE""" FOR CONTROLLER USE ONLY ~CI I N Antici ated Results:
1993 EVALUATED EXERCISE Tuae: ~/IK MAZOR PARAMETERS ENGINEERED SAFEGUARDS Reactor Shutdown YES NO Hi h Head S.I. Pum s N-31 CPS FI-924 ~GPM N-32 CPS FI-925 ~GPM N-35 giif /0 AMPS 1A. INSERV STBY 00 N-36 ~54- AMps 1B. XNSE V STBY 00 Avg. Nuclear Power 1C. NSERV STBY 0 RCS Pressure ~PSIG BAST Level = ~O PRZR Level A RCP RUNNING/ PPED Low Head S.I. Pum s B RCP RUNNING/ TOPPE FI-626 GPM 1A S/G Level 1A. INSERV STBY RECIRC S/G Level 1B. INSERV STBY RECIRC 1B 1A 1B S/G Pressure S/G Pressure PSIG PSIG RWST Level = ~~4 Turbine/Generator ONLXNE/ FFLIN Containment S ra Pum s 4 KV Buses GIZED DEENERGIZED FI-931A GPM 480V BuseslgdqAwl NE G zED EN FI-9 31B~GPM DC Batteries AQo VOLTS B~i. 0 VOLTS 1A. INSERV STBY OS Cnmt Pressure ~r~PSIG 1B. XNSERV TB OOS Cnmt Sump A Level FEET NaOH Tank Level = ~S Cnmt Sump B Level
" Loop Hot Leg /~~3 INCHES F Containment Recirc Fans A Loop Cold Leg Re/ z OF 1A. INSERV STBY OS B Loop Hot Leg 'F 1B. NSER STBY OOS B Loop Cold Leg DER ~'F 1C. SERV STBY OOS RVLIS 3$ ,0 g 1D. INSERV STBY OS
- CET EQMD GPM F Post Accident Dampers PEN CLOSED S/G A Total Aux FW Flow S/G B Total Aux FW Flow ~g GPM Service Water 1A. NSER Pum s STBY OOS DIESEL GENERATORS 1B. SERV STBY OOS 1C. STBY OOS A. RUNNING UNLOADED STBY OOS 1D. NSERV STBY OOS B. RUNNING UNLOADED TSC'UNNING UNLO DED OOS OOS A&B Header reeeure ~(n PSIG Security RUNNING UNLOADED TB OOS Com onent Coolin Water Pum s 1A. INSERV STBY 00 ENGINEERED SAFEGUARDS 1B. NSERV STBY OOS Surge Tan Level =
Aux. Feedwater Pum s 1A. INSERV STBY 0 Standb Aux. Feedwater Pum s 1B. NSER STBY OOS 1C. INSERV STBY 0 Turb. Driven INSERV OOS 1D. XNSERV STB OOS CST Level FEET
- CET = Average of Selected Core Exit Thermocouples
t(OV 17~ 1993 12! 14 R. E. GINNA SIMULATOR PAGE 1 TREND GROUP ASSIGtttct(T SUNDRY 6RGLP'4PP! PROCEDURE: EPIP 1-5 PLANT STATUS POINi ID DESCRIPTION VALUE E. U. 1 ATWS At(TIC!PATED TRANSIENT W/0 SCRAM ATWS ALRN RXT REA".TOR TRIP BREAKER STATUS RX TRIPPED ALRN 3 tQI SOURCE RAt(C~ DETECTOR N-31 1. OOK&05 HALN CPS 4 N32 SO(RZE RANGE DETECTOR N-32 3. 9445b%1 BAD CPS 5 N35 l¹RNEDIATE RANGE DETECTOR N-35 2.079?1-10 6009 AMP 6 tl3b IMIc&i""DIATERANSc DETECTOR N-3b 1.00001-11 GOOD A!(P 7 NP AVERAGE tLCLEAR PS,"R .00 GOOD X 8 PROS REA"TQR COOLANT(T SYSTEM AVG PRESS i. LALN PSI6 9 LP2R PRHSURIIER AMe. AGE LcKL .0 LALt( / 10 FRC A RiACTQR COOLNP LOOF' AVG FLOW ~ 6 INHB X 11 FRCLB RcACTOR CC9 ANT LKP 8 AVG FLOW 1.3 INHB / 44g
~
RXT!b RCPA BREAKER CAUSE RX TRIP TRIPPED ALRN 13 RXT17 RCPB BRiAKER CAUSE RX TRIP TRIPPED ALRt(
!4 TSUBTC It'ZRc TC SUB GOU3 MARGIN -819.5 LAL~ DEGF 15 LSGA STM GB( A NARROW RA%i AVG LEVEL 68.2, HALN X 16 LSGB STM GEN 8 t(ARROW RAl(GE AVG LEVEL 38.1 I<
17 PSGA STM Gct, A AVERAGE FISSURE -5. LALN PSIG 18 PSGB STM Gest 8 AVERAGE PRESRNE -5. LALN PSIG 19 GENBKP.! EBEPATOR GN Llt/E BREAKER 161372 TRIPPED ALRN 20 GENBKR2 GchsRATOR ON I INc EFEAKER 9XI37> TRIPPED ALRN 21 BUS!!A BUS llA SLiPPLY BREAKER TRIPPED ALRN 22 BUS118 BUS 118 SL9'PLY ERFAKER TRIPPED ALRN 23 EUS!2A NOT 7 RMINATED Otf PPCS (7/!9/91) NOT TRIP DEL 24 BUS!28 t(QT TERMINATED 0)t PPCS (7/19/91) NOT TRIP DEL Bl!AI2A BUS 1!A TQ 12A TIE BREAKER t(OT TRIP ALRN 26 B!18128 EUS !!8 TG 128 T!E ER-"VER NO: TRIP ALRN 27 PCV CONTiAIN"8<i AVEcRA"- PRcSSURE .08 600~ 28 LSD"H CGNTAINMEtr'T SUMP A AVERAGE I sVEL 31.2 HEND
*t OD L09428 SUMP 8 LEVEL 8 INCi(ES (TRAIN A) HI6HcP, INHB 30 L0943E SUNUP 8 LEVEL 8 INCHES (TRAIN 8) HIG)':-R It<HE 3i L09429 SUti' LEVEL 78 INCR S (TRAIN A) HIGH& INHB L09439 SUMP 8 LE4sL 76 INCHES (TRAIt( 8) HIG)<R . INHB 33 LO942C SUNUP 8 LEVEL 113 It&ES(TRAIN A) HIGHER ALRN 34 L0943C S(PP 8 LEVEL 113 It(CHES(TRAIN 8) HI6HER ALRN 35 L09428 SUtP 8 LEVEL 180 Il(NrS(TRAIN A) LOWER 6009 3b L09438 SUtc. 8 LEVEL 180 INCHES(TRAIN 8) LOWER 6009 37 L0942A SUtF 8 LEVEL 214 INCHES(TRAIt( A) LOWER GQQD 38 L0943A SU%' LEVEL 214 ItlCHES(TRAItt 8) LOWER GOOD 39 T0409A RCLA HOT LEG TENPERATLiRE 214.4 6009 DE%'iGF 40 TO4!OA RCLB HOT !.EG TsEMPERAT(R 214.4 =6009 41 TO450 RCLA COLD LEG TE)FERATLRE 201.5 BAD DEGF 42 T0451 RCLB COLD LEG TENPERAT(RE 158.2 BAD DEGF 43 TAVGAMID RCLA TAVG (THOT/TCQLD WIDi RNG) 214.4 GOO~ DEGF 44 TAVGBWID RCiLB TAVG (THOT/TCGLD WIDE RNG) 214.4 600< DE6F 45 LRV REACTOR VESSEL AVERAGE LEVEL 39,0 LNP. X 46 TCCORE El. 1 It(COFE TC AVERA6E TEt'4 823.4 HAL~ Dc.GF 47 FAUXF@ S/G A TOTE. AUX FiEDWATER FLQN 0. 6009 GPM 48 FAUXFWB S/G 8 TOTAL AUX FEED((AT& FLOW 28, 6009 GPM 49 BKR081 MTR AUXILIARY FEEDWATsER PUMP A OFF 600D BKRO82 MTR AUXILIARYFEEDWATER PM' ON GCCD 51 V3505 AUX Ft'UMP STEAN SUPPLY VALVE A CLOSED GOOD 52 V3504 AUX FW FUNP STEAN SUPPLY VALVE 8 . CLQSH) 6009
tlOV 17i 1993 1!:14 R. E. GINA SltiEATOR PAGE 2 TREND GROUP AKIGtlttEttT SUt>NARY GROL'P: LVENT1 PRGCEDLtRE: EPIP 1-5 PLANT STATUS POINT ID DES RIPTIO'1 VA'cE INL E. U. 53 FSIA SAMcY Itt.'ECTION LOOP A AVG FLOW 0. GOOD GPtt 54 FSIB SAFETY INJECTION LOOP B AUG FLOW O. GOOD PN 55 P2160 SERVKE WATER PUttPS A ti B HEADER 87. GOOD PSIG 56 P2161 SHÃICE WATER PUttPS C h D ~c'R 86. GOOD PSIG 57 RtR041 SERVICE WATER PUtP A Gti'N GOOD 58 NR042 SERVICE WATER PUtiP B GOOD 59 BNR043 SERVICE WATER PUttP C Otl GOOD 60 BRR044 SB"ICE WATER PUttP D Gtt GOOD
NOV 1?i 1993 1::15 P.. i. GMlA SIÃLATOR PAGE 1
;REND GRQJP Ass16NriNT sUYNPY BROLLY: EVENT2 PROCEDLt":: EPIP 1-5 PLANT STATUS POPtT ID DES"RIPTIDE VALUE C4A'. U.
1 F0619 CQ'PQ¹ttT CQQ'NB LQQP TOTAL FLM 884. LALtl GPtl 2 LR4ST REPJELINB WATER STORABc TAN LVL 37.0 6009 / 3 NSO33 33 FQOT LEVEL MftlD SPccD 3.1 6009 AH 4 N9033 33 FOOT LEVE'it<9 DIF"CTION 41. GOOD IFG, 5 NT033 33 FOOT LEtt"'ENPERAPJRE 43.1 600D DEGF twlT250 250 FOOT LEVEL TENciRATURE 43.1 6009 DEBF 7 NDT2 250 TQ 33 FOOT LEVEL DELTA Tile .0 GOOD DEBF 8 R01 AREA 1-CQNTRQ'OON 8.81048-02 GOOD NR/HR R02 AREA 2-CONTAINMit/T 7.8072?+03 BAD NR/HR R05 EA 5-SPitP. FUEL PIT 3.! 4412+00 BAD tS/HR fl R09 ARiA 9-LcTDO'AN LitF NQtlITOR 2.75423+01 BAD tS/HR
~ r>
R34 AREA 34 - AUY BLDG CV SPRAV PLiriP 2.95121+00 BAD IS/HR 13 R35 AREA 35-PASS SANPLE PANEL 1.09648+00 GOOD N/HR 14 RfOA CONTAINMENT IODINE tlQNITOR R10A 1.04S64+07 HENG CPN 15 Rfi CQNTAINNitlT AIR PARTI'TE 9.70232+06 HALtl CPN 16 R12 CQllTAINYEtlT GAS YiONITOR 1.02624+07 HEttB PN 17 RiOB PLCtT Villi IODItli t'iOtlITOR RfOE 9.71623~05 HALr, CPtl 18 R13 AN BLD6 EXHAUST AIR PARTICULATi 2.57039402 GOOD CPN R14 AUK BLDG EXHAUST GAS MPtITQR 9.57744m HALN CPN 20 R18 LIE~ID NASTE DISPOSAL NOtlI:OR 9.80051+05 HALN CPN R19 STEA"i GENERATOR BLQtt90'4 DRAItt 6.75108~03 HALN CPN R29 AREA 29-CBiTAItlMBtT HIGH RAltSic 1.60209+03 HALN R/HR 23 R30 ARih 30-ZttTAItOlEtlT HICH RAtPaE 1.60209+03 HALll R/HR 24 R15 CKiiNSER AIR EJECTOR EXHAUST 1.42683%3 6009 CPN R12A5 CV VitlT CHAN 5-LQN RAi'lGE GAS 4.20511-05 GOOD UCI/CC 26 R12Ab CV VEltT Ct'JlN 6-ARK BAiM 5.20000+02 HALN IS/HR R1287 CV VENT CHAN ?+ID RAlS:. GAS 4,20511-05 6009 UCI/CC 28 R12A9 CV VENT CHAN 9-HIGH RtLNGE BAS 9.9998?M 6009 UCI/CC R14A5 PLQiT VHF; CHAt'-LGW RANGE GAS 9.98974-03 HALri XI/CC 30 R14A7 PLANT VENT Catt 7-NID RAGE GAS 8.85986+00 HALN UC!/CC 31 R!4A9 PLAttT VitPi CNN 9-HIGH RAtiSE GAS 8.85986400 Haiti UCI/CC 32 R15A5 AIR EJECTOR CHAN 5-LOlt RANGE GAS 6.229~ 6009 UCI/CC 33 R15A7 JECTQR Cvgl 7 NID RAtlGE GAS 1.80975-05 6009 UCI/CC 34 R15A9 AIR EJECTOR CllAN 9-HI RANGE BAS 1.52999<3 GMD UCI/CC 35 R31 AREA 31 STiAtl LINE A (SPltlB) 3.61997"03 6009 NR/Htt 36 R32 AR""A 32 S EAN LIl-'c B lSPItlB 3.61997<3 K09 t8/ts 37 CVH CV:"MROGEN CONCRATIOtt .0 6009 / 38 TCV03 CV BASEMENT LEVL 6FT TEMP I3 63.7 6009 DEGF 39 TCV07 CV INTERMEDIATE LVL 6FT TEMP %7 64.3 6009 DE6F 40 TCVOS CV INTERMEDIATE LVL 6FT TEYiP tlS 64.3 MOD IFBF 41 TCV09 CV IttTEQG)IATE LVL 6FT TEMP I9 64.3 6009 Di6F 42 TCV10 CV INTERNiDIATE LVi 6FT TEYiP ttf0 64.3 6009 IFBF 43 TCVl? CV OPERATItlG LEVL 6FT TEMP ll17 64.9 6009 DE6F
Time; 1120 Message: 49 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM t: R I <<1'R Simula ed Plant Conditions: See the Attached Sheets ~essacee: """THIS IS AN EXERCISE""" The following annunciator is received: '-10 (Auxiliary Building Sump Pump Auto Start) FOR CONTROLLER USE ONLV Controller Notes:
- 1) The "B" Auxiliary Building sump pump starts and runs approximately one minute.
Antici ated Results:
- 1) Operators should be performing the applicable actions of AR-L-10.
- 2) Operators should be performing the applicable actions of FR-C.1 (Response to Inadequate Core Cooling).
Time; 1125 Message: BO GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM R C I R Simulated Plant Conditions: See the Attached Sheets ~Messe e: "<< "THIS IS AN EXERCISE" >>" The following message is received from Power Control: 'ffsite 34.5KV circuit 751 is ready to be restored to service. FOR CONTROLLER USE ONLY Controller Notes: Antici ated Results:
- 1) Operators should inform the TSC that Circuit 751 is ready to be restored to service.
- 2) Operators should, if directed by the TSC, restore Circuit 751 to service per 0-6.9.2
Time: 1130 Message: 51 GINNA TATION 1993 EVALUATED EXERCISE MESSAGE FORM R I C ill Simulated Plant Conditions: See Attached Sheets ~Messs e: <<" eTHIS IS AN EXERCISEe>>" The following annunciator is received: '-10 (Auxiliary Building Sump Pump) FOR CONTROLLER USE ONLY Controller Notes:
- 1) The "B" Auxiliary Building sump pump starts and runs approximately one minute.
Actions Ex ected:
- 1) Operators should perform the applicable actions of AR-L-10.
- 2) Operators should be perform the applicable actions of FR-C,1 (Response to Inadequate Core Cooling).
- 3) TSC should be expediting the return of the "A" Emergency Diesel Generator to service.
- 4) EOF Dose Assessment should be evaluating the release from the plant vent and making protective action recommendations to the EOF/Recovery Manager.
- 5) The EOF/Recovery Manager, after =evaluating the EOF Dose Assessment recommendations, should make protective action recommendations to offsite agencies.
1993 EVALUATED EXERCISE Time: ~90 MAi70R PARAMETERS ENGINEERED SAFEGUARDS Reactor Shutdown Hi h Head S.I. Pum s N-31 FI-924 ~GPM N-32 FI-925 ~GPM N-35 aL3 8-I> AMPS 1A. INSERV STBY 00 N-36 l~~AMPS 1B. INSERV STBY Avg. Nuclear Power O 1C. INSERV STBY OOS RCS Pressure ~PSIG BAST Level = PRZR Level A RCP RUNNING/ T PPED Low Head S.I. Pum s B RCP RUNNING STOPPED FI-626 C7 GPM 1A S/G Level C 1A. INSERV STBY 0 RECIRC 1B .S/G Level o 1B. NSERV STBY RECIRC 1A S/G Pressure PSIG RWST Level = ~SD 1B S/G Pressure SIG Turbine/Generator ON E/ FFLINE Containment S ra Pum s 4 KV Buses NERGIZED DE GIZED FI-931A GPM 480V BusesigamouT ENERGIZED/DEENERGIZED FI-93 1B (3 GPM DC Batteries Cnmt Pressure A~ ~~~PSIG VOLTS 1A. 1B. INSERV INSERV TB Y 0 OOS Cnmt Sump A Level Cnmt Sump B Level
~o~F EET NaOH Tank Level = ~~%
A Loop Hot Leg g ~
~
INCHES OF Containment Recirc Fans A Loop Cold Leg 2b s 'F 1A. INSERV STBY OOS B Loop Hot Leg / ~ 'F 1B. NSER STBY OOS B Loop Cold Leg $ ~9.2 F 1C. NSERV STBY OOS RVLIS 1D. INSERV STBY OS
- CET OF Post Accident Dampers E CLOSED S/G A Total Aux FW Flow GPM S/G B Total Aux FW Flow ~ GPM Service W Pum s 1A. SERV STBY OOS DIESEL GENERATORS 1B. NSERV STBY OOS 1C. NSER STBY OOS A. RUNNING UNLOADED STBY OS 1D. NSER STBY OOS B.
TSC RUNNING UNLOADED T RUNNING UNLOADED TB OOS OOS A&B Header Pressure ~G PSIG Security RUNN NG UNLOADED TB OOS Com onent Coolin Water Pum s 1A. IN RV STBY 0 ENGINEERED SAFEGUARDS 1B. N E V STBY OOS Aux. Feedwater Pum s Surge Tank Level =, ~D 1A. INSERV STBY 00 Standb Aux. Feedwater Pum s 1B. SER STBY OOS 1C. INSERV STBY Turb. Driven INSERV TB OOS 1D. INSERV OOS CST Level ~s'~FEET
- GET = Average of Selected Core Exit Thermocouples
NGV !7i 1993 !1:31 Fi. E. GINNA SIMULATOR PAGE TRct(9 GnO"c ASSIG>>PÃ SU(>>v>>WY GROUP: EY=NT! PRGCH)URE: O'IP 1-5 Pl.ANT STATUS POINT ID DEKRIPTIGtt VALUE E. U. QUA'LRN ATMB ANT?CIPATH) TRANSIENT M/0 SCRAM ATMS RXT REACTOR TRIP BREAKER STATUS RX TRIPPED ALRN N31 SOlRCE RANGE D TECTOR N-31 1,04111+05 HALN CPS 4 W32 SOURCE'ANGE DETECTOR h~32 3.94456+0! BAD CPS 5 N35 It(TERMEDIATE RANGE DETETOR N-35 2.31206-10 6009 AMP D t(36 INT:RMEDIATE RANG BETE:"TOR N-36 !.00001-11 GOOD NP 7 NP AVERAGE ttXLEAR POMER .00 GOOD / 1 8 PRCS REA".TOR COOLANT SYSTEM AVG PRESS J ~ LALN PSIG 9 LPER PRE"SURIIER AVERACE LEVE .0 LALN '/ 10 FR4 A RiACTOR COOLANT LQGP A AVG FLOM INHE /.
~ >> FRCLB REACTOR COOLNT LOOP 8 AVG FLOM .0 INHB 12 RXT!6 CPA BREAKER CAUSc Py TRIP TRiPPED ALRN RXT17 RCPB BREAKER CAUSE RX TRIP TRIPPED ALRN 14 TSUBTC It(CORE TC SUKGOM t@RuGlN -830.8 LAL>> DEGF !5 LSGA STM GEN A t(ARRGM RAt(t":i AVG LEVEL 67.8 HAUt X 16 LBGB STM ~t( 8 NARROM RN4cc AVG LEVEL 43,9 600>> 7 !7 PSGA STN GEN A A'vchASE PRiSBURE -5 LALN PSIG 18 RuuB STN GEN 8 AY=RAGE PPxSB'JRE -5 LAUI PSIG !9 Git(BKRl Git-RATGR ON LINE BRiAKiR 161372 TRiPPED ALRt(
20 GENBKR2 GctKRATQR ON LINE EPEAKER 9X!372 TRIPPED ALRN 2! BUB!!A BUB .'!A SPPLY BREAKER TRIPPED ALRN 22 BUB!18 BUB 118 SUPPLY BREAKER TRIPPED ALRN
+i'T CV BUB!M OT TERMINATED GN PPCB (7/!9/9 NOT TRIP DEL 24 BUS!28 hOT TERt(It(ATED Qtf PPCB (7/19/91) NQT TPIP DEL B!1A!2A BUB 1!A TO !2A TiE BREAKER NO TRIP N.RI':
26 8!!812B BUB !!8 TG 128 Tii BREAKER NOT TRIP ALRN 27 PCV COt(TAIi[Mct(T AVERAGE PRcSBURE .06 600>> PSIG 28 LSUMPA CONTAINMENT SUMP A AVERAGE LEVEL 31.2 HENS FEET 29 L0942E BUS 8 LEVEL 8 INCHES (TRAIN A) HI6HEP. INHB 30 L0943E SUt.- 8 LEVEL 8 It(LHES (TRAIN 8) HI~ !ttHB 31 L0942D SU~ 8 LEViL 78 It(: t(EB (TRAIN A) HI6HER INHB 32 L0943D SU%' LEVEL 78 INCH S (TRAIN 8) HIGHiR INHB L0942C SUMP 8 LEVEL 113 INCtccB(TRAIt< A) HIGHER ALRN 34 L0943C SUP 8 LEVEL 113 INC(="S(TRAIN 8) HIGHciP, ALRt( 35 '09428 SUPP 8 LEVP 180 It(CHES(TRAIN A) LONER GOOD 36 L09438 BUtF' LEK'80 INCHciB(TRAIN 8) LOMER 6009 37 L0942A SUMP 8 LEVEL 214 It(CHES(TRAIN A) LOMER 6009 38 L0943A SUtP 8 LEAL 214 INCHEB(TRAItt 8) LOM R 6009 39 T0409A RCL4 HOT LEG TEMPERATL% 214.4 6009 DEGF 40 T04!OA RCLB HOT LEG TBPERATURE 214.4 X<09 DEGF 41 T0450 RCL4 CGU) LEG TEt'PEP'>>TNE 201.5 BAD DEGF T0451 RCLB COLD LEG TEt(PERATLR"- 158.2 BAD DEGF 4v TAVGAMID RCLA TAVG (Tf6T/TCOLD MIDc. RNG) 214.4 600>> Dc6F 44 TAVGBMID RCLB TAVG (THGT/TCGLD MIDE RNG) 214.4 GQO>> DEGF 45 LRV REACTOR VESSEL AVERAGE LLVcL 38.9 LALt( 0/ 46 TCCGRE E1.! !NCORE TC AVERAGE TEMP 816.2 HAL>> DE6F 47 FAUXFMA S/6 A TOTAL AUX FEEDMATER FLOM 0. 6009 GPt( 48 FAUXFMB S/6 8 TOTAL NJX FEEDWATER FLOM 28. 6009 GPM 49 BKROB! HTR AUXILIARYFEEDMATER PUttP A OFF GOOD 50 BKR082 MTR AUXILIARYFFcDMATcR PUMP 9 Gll GQQD c'1 V3505 AUn FM PUMP STEAN SUPP' VALVi A CLOS""9 GOOD 52 V3504 AUX FM PU)>>9 STEAN SUPP' VALVE 8 CLOSED 6009
NO'P 17i 1993 11:3! R..:. GIt4A SI%LATOR PAGE 2 TREtQ GRCUF ASSIGtt % SUDSY GRQtPl EV '<Tl PROC~M'~"": EPIP 1-5 PLANT STATUS POINT !9 BES;"RIPTIO VALLE QUAL Ea U. 53 FSIA SAF:"Ti't4ECTION LOOP A AVG FLOW 0. BOOB PN 54 F GIB SAFETY INJECTION LGGP B AVG FLOW 0. 6009 GPtt 55 P2160 SP/ICE WATER PUtPS A 5 B tL-".K>B 87. GOOD PSIG 56 P2151 S:t,itiCs WATER PUtL~S C 5 0 NEAIiER ee. GOOO PSIG 57 BkR041 SK)ICE WATER PUttP '. ON 6000 58 BkRO42 S"WCE WATER PUe B ON GOOB 59 BKR043 SERVICE WATER PUttP C OM GOOD oG BKR044 SERVICE VATER . UYP 9 ON GQOO
NOV 17i 1973 R. E.. Git~~(A SltZATOR PAGE 1 TREt(9 GROUP ASSIGtlNEl(T M~ "u"fARY GRi'UP: EVE!i~i 'ROCEDUR":: EPIP !"5 PLANT STATUS POI"" ID VALUE QUAL E, U. DESCR!PT!Ot'OPGVi"=HT FOb!9 COO'. IN"= LQQP TOTAL FLW 892. UM GPNi LRWST RErd=i ING WATER STO.",A " TAt(K LVL 37.0 600D I/ MSO"3 33 FOOT LEVP WIND SPEED 3,0 6009 lPH W9033 33 FOOT LEVEL Wit(D DIRECTIOi'l 41, 6009 DCG. WT033 33 FOOT LEVrEL TENPERATURE 43.1 6009 DEGF 0 WT"50 250 FQQT Laic TENPERATURE 43.1 6009 KGF 7 l'lDT'O! 250 TO 33 FOOT LEVr DELTA TPJ'REA
.0 6009 DEGF 8 '!-COSIRO: ROO."i 8.?5992-02 6009 tfR/HR 9 RO2 AREA 2-CONTAINNENT 7.8072/+03 BAD tS/HR 10 R05 Ar","< 5-SPEI'iT F(LL PIT 3.14412+00 BAD tfR/HR R09 @Re.4 9-LETDG'AN L!ttE l'iONITOR 2.75423+01 BAD NR/HR 12 R34'35
.ARE-.". 34 - AUX BLDG CV SPRAY PUtlP 2.95121+00 BAD tfR/HR 13 AR=.-'5-PASS SANPLE PAtZL. 1.09b48~00 GOOD tfRIHR 14 RlOA CQ! iAINNENT IODIti=- NONITOR RIOA 9.95b83~0b HALtf CPN fg
~
~ Ril CQNTAMB(T AIR PARTICULATE 1.030b8+07 HENS PN ib R12 COtlTA!NNEtfT GAS NQNITOR 9.49508+Ob HALN CPN 17 R!OB + ANT VEtlT IODINE NQNITOR R!OE 9.92827+05 HALN PN 18 R13 AUX B'6 EXHAUST AIF, PARTICULATE 2.b039&02 GOOD PN R!4 AUX BLDG EXHAUST CAS NNITOR 9.91393~0b HALN CN 20 R!8 LIKIID WASTE DISPOSAL NNITOR 9.54989+05 tfALtf CPM Pp q Rl v STEAt', GENEPATR:." R5~( DRAIti 7.14084+03 HAUt PN 22 R29 AR="A 2=.-CQhTAIt'"i~%'IGH RAt(G.: 1.303!b+03 HALli R/HR 23 R30 r5-"=" 3v-CQl(TAIt~!(T HI GH RANGE 1.303lb+03 HALN R/HR 24 R!5 COtCEt(SER AIR EJECTOR El(HAUST 1.40847+03 6009 CPN i.3 R!2A5 CV VEtti CHAN 5-LOW RAtii=" GAS 4.20511-05 6009 UCI/CC 2b R!2Ab CV VENT CHAN b-AREA GA@1A 5.20000>02 HALtf ts/HR 2/ R1287 C'v'ENT! CHAN 7-NID RNlK GAS 4.2051!M GOOD UCI/CC 28 Rl 4>> CV VEN: CHAN 9-HIGH RANGE GAS 9,99987-04 GOOD LI/CC R14AS . Loci VENT CHAN 5-LON RAt>6= GAS 9.98974-03 HALN UCIICC R!4A7 PLY( VENT CHAN 7"NID R4NK GAS 8.8598b+00 HALN L"I/CC 31 R!4A9 PL%'lT VEt(T CHAN 9-HIGH RANGE GAS 8.8598b400 HNRtt UCIICC 32 R!SA5 AIR FJECTQR CHAM 5"LOW RANGE GAS b.22985-0b 6009 XI/CC 33 R!SA7 AIR EJECTOR CHAN 7-NID RANGE GAS 1.80975M GOOD UCI/CC 34 R! SA9 AIR EJECTOR CHat 9-HI RANGE GAS 1.52999-03 GOOD (L"I/CC 35 R31 AREA 3.'TEAN LINE A (SPIt(6) 3.o!997-03 6009 tS/HR R32 AREA 32 STEAN LINE 9 (SPING) 3.bl997-03 GOOD %/HR 37 CVH C" HYDROGEN CONCENTRATION .0 GOOD /
38 TCV03 CV BASIN NT LEVEL bFT TBF ft3 b3.4 6009 DE6F 39 TCV07 CV ittTERNEDIATE LV!. GFT TEtP ft7 b4.0 GOOD DEGF 40 TCVOS CV ItiTEPNEDIATE LVL bFT TEtfP ft8 b4.0 =GOOD KGF TCV09 CV IHTERNEDIATE LVL bFT TENP ff9 b4.0 GOOD DEGF
- CV!O CV IliTERN."DIATE LVL bFT TENP ft!0 be 0 DE6F 43 TCV!7 CV OPERATItl6 LEVL bFT TENP <<17 b4.b GOOD DEGF
TIme: ~114 Message: 52 GlNNA STATION 1993 EVALUATED EXERClSE MESSAGE FORM MMM f: 8 I <<C IR Simulated Plant Conditions: ~ll/lesse e: "<< "THIS IS AN EXERCISE>>"" The following Annunciator is received: '-10 (Auxiliary Building Sump Pump auto start) FOR CONTROLLER USE ONLY Controller Notes:
- 1) The "B" Auxiliary Building sump pump starts and runs for approximately one minute.
Actions Ex ected:
- 1) Operators should be performing the applicable actions of AR-2-10.
TIme: 1145 Message: 53 GINNA STATION 1993 EVALUATED EXERCISE
~MESSAGE R RM MESSAGE FOR: TSC/Simulator Control Room Simulated Plant Conditions: See Attached Sheets
~Messa e: G"",THIS IS AN EXERCISE""" The following information is received in TSC from repair team working on the "A" Emergency Diesel Generator: 'epairs should be completed in approximately fifteen minutes. FOR CONTROLLER USE ONLY Controller Notes: Actions Ex ected:
- 1) TSC should be planning the recovery of core cooling and the termination of the release from the Auxiliary Building when the "A" Emergency Diesel Generator is returned to service.
- 2) TSC should request operations to check the "A" Emergency Diesel Generator line-up as much as they can to expedite the return to service of the D/G.
- 3) TSC should inform the EOF of the estimated time that the "A" D/G will be ready for return to service.
1993 EVALUATED EXERCISE Time: ~45 MAJOR PARAMETERS ENGINEERED SAFEGUARDS Reactor Shutdown E NO Hi h Head S.X. Pum s N-31 65 CPS FI-924 ~GPM N-32 CPS FI-925 ~GPM N-35 :-lO AMPS lA. INSERV STBY OS N-36 j~c~~AMPS lB. NSERV STBY OS Avg. Nuclear Power lc. INSERV STBY OOS RCS Pressure ~PSIG BAST Level = PRZR Level A RCP RUNNING/ TOPPE Low'Head S.I. Pum s B RCP RUNNING/ TOPPE FI-626 GPM 1A S/G Level 7eb 1A. INSERV STBY 0 RECXRC 1B .S/G Level 1B. INSERV STBY RECIRC 1A 1B S/G Pressure S/G Pressure PSIG RMST Level = ~g Turbine/Generator ON E FFLIN Containment S ra Pum s 4 KV Buses GIZED DE N XZED FI-931A GPM 480V Buses NERGIZED DEENERGIZE FI-93 IB~GPM DC Batteries A~90VOLTS B VOLTS 1A. INSERV S BY 0 Cnmt Pressure PSIG 1B. INSERV TB OOS Cnmt Sump A Level Cnmt Sump B Level
~2- FEET INCHES NaOH Tank Level = ~%
QI A Loop Hot Leg ~MM'F Containment Recirc Fans A Loop Cold Leg 0 IF ~F 1A. INSERV STBY 0 B Loop Hot Leg OF 1B. NSERV STBY OOS B Loop Cold Leg ~ ~ OF 1C. NSER STBY OOS RVLIS ,0 g 1D. INSERV STBY 00
*CET 073 OF Post Accident Dampers PE CLOSED S/G A Total Aux FN Flow ~ GPM S/G B Total Aux FW Flow ~2. GPM Service Water Pum s 1A. NSERV STBY OOS DIESEL GENERATORS 1B. NSER STBY OOS 1C. STBY OOS A. RUNNING UNLOADED STBY OS 1D. STBY OOS B. RUNNING UNLOADED OOS A&B Header Pressure 4 PSIG TSC RUNNING UNLOADED B OOS Security RUNNXNG UNLOADED TB OOS Com onent Coolin Mater Pum s 1A. INSERV STBY 0 ENGINEERED SAFEGUARDS 1B. NSER STBY OOS Surge Tank Level =,
Aux. Feedwater Pum s 1A. XNSERV STBY 0 Standb Aux. Feedwater Pum s 1B. STBY OOS 1C. INSERV STBY OS Turb. Driven INSERV STB OOS 1D. INSERV T OOS , CST Level ~~FEET
*CET = Average of Selected Core Exit Thermocouples
NOV 17. 1o93 }'.l43 i, ". 6!t'<A S!t<ULATGR PAGE 1 TREND 6ROU." ASSIGQtt(T SUtJiARY GROUP: EVE)IT} PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DES"RIPTION VALL!E QUAL E. U. Al~ICIPATED T!?At(S!Et'T W/0 SCRN AT)IS ALRN RXT REA"TOR TPIP BREAKER STRTUS RX TRIPPED A'N 3 t)3} SOKE RAl<uic D:"TECTCR ti~3} }.05559tp5 HALN CPS N32 SOUSE RANGE DETiiTGP t(-32 3.94456+0} BAD CPS ted IHTERNEDIATE RANGE DETECTOR N"35 2.30143-10 GOOD ANP 6 t(36 It(!"RNicDIATE RANGE DETECTOR N-36 1.0000}-}l 6009 A"J'
/ t(P AVERAGE NUCLEAR PO)!cR .00 6009 8 PRCS REACTOR CGGLA)IT SYSTEt< AVu PRESS 1. LALN< PSIG o LPIR PRESSURIIER AVERAGE LEVEL .0 LAL'I /
10 FRCLA RE@",TOR CGGLAt(T LOOP 4 AVG FLG<A .6 It(KE
~ ~
'T((S
,"RCLB PEA"TiV CGOUtVi LOGo 8 AVG FLOW 1.3 INHE \/
tP iC RXTlo ROAR BREAKER CA<JSE RX TRIP TRIPPED ALRN RXT17 R'"ro 'RFAKER MUSE RX T<RIP TRIPPED ALRN
!4 TSUBTC IN%RE TC SUB."COLED t<ARGItt -791,2 LA' DEGF 15 Lou4 STt( Gc'l A NAR!?GW RAl(Gc AVG LEVE 67.6 HALN </
LSGB ST", GEN 8 t(ARROW RAt(SE AVG LEVEL 48.5 600e / 57 PSGA STti 6itl A AVERAGE PFESoJRE -5. LA<EN< PSIG
!8 .PSGB STN GEN 8 AVE(?AGE PRESSURE "5. LA' PSIG !o GEt(BKR! GitKRATQR ON LINE BPEAKER 1G!372 TRIPPED ALRN 2P GE)(EKR2 GENERATOR ON 't<i BREAKER 9X}372 TRIPPED ALRN BUS} lA BU" }}A SUPPLY BREAKER TRiPPED ALRl'<
8;!8 1!8 SLPPLY BREAKER TRIP PiD ALRN Cd 8!08! 2A t(3", ToRt(ItNTED Otl PPCS (7/19/91) NOT TRIP DEL BUS!28 t(OT TERt(ItlATcED GN PPCS (7/!9/91) NOT TRIP DEL 25 811A!2A BUS i}A TO 12A Tii Bii-"KcR NO! TRIP ALRN 26 8118128 BUS 118 TO }28 TIE BREAKER t(OT TRIP ALRN 27 PCV CG)tiAI<'ll'lct(T AVERAGE PRESSURE F 06 600~ PSIG LSPlPA COh! AIhNctiT SUNP A AVERAGE LEVEL 31.2 HENS FEET 20 '94 SUtP 8 LEVEL 8 I))CHES (TRAIN A) HIGHER .'tD(E 30 L0943E PJ<<' LEVP 8 INCHES (TRAIN 8) H 16H""R INHE 3} LO9429 SU%' LE!/EL 78 !NCHES (TRAIN A) HIGH% iNHB d LO9439 SUNP 8 LE!/EL 78 !t(CHcES (TRAIN 8) HIGHER INK E VI !.094 "." SUNP 8 LEV13. }}3 INCHES(TRAIt( A) HIG).cR ALN, L09430 S<JlF LEViL 113 INCHES(TRAIN 8) HIGhD ALRN 35 L09428 SU5' LEVEL 180 INCHES(TRAIN A) LONER 6009 36 L09438 S(9. 8 LEVEL 180 Il(Ci'cS(TRAIN 8) LONR 6009 3/ L0942A SUtc' LEVc! 214 ItKHES(TRAit( A) I OWcl? 6009 38 LO943A SNP 8 LR'r.L 214 ItlCHES(TRAIN 8) LOn'ER 6009 3a T0409A . RCQ HOT LEG TEtIPERATLFe 214.4 6009 DEGF 4p T04}OA RCLB HOT LEG TENPERATURE 214.4 =6009 DEGF 41 T0450 RCLA COLD LEG TENPERATURE 201.5 BAD DE6F 4<+ PCLB COLD LE6 TEt'J'ERATNE T0451 158.2 BAD DEGF T-"VG4WID RCLA TAVG (THOT/TCOLD WIDE RNG) 214.4 6004 DEGF T<<<<+W< I?CLB TAVG (%3T/TCOLD WIDE RNG) 214.4 600~ DEGF LRV RELTOR VESS": AViRAGc
'EVc'i.!
39.0 LALN 46 TCCORE !NCORE TC A</cRASc TENP 807.3 HAL< DEGF 4/ FAUXFWA S/6 A TOTAL NX FEECQATd? r!.Ol! 0. 6009 PN 48 FAUXFWB S/6 8 TOTAL AUX FEEDWATER FLON 28. GOOD GP)I 4o p(opo1 NTR AUX?L!ARY cccD)tATER PUNP A CcF 6009 50 BKROSi t(TR AuXILIARY F~D~ATER FOP 8 GN 6009 51 V3505 AU)( FW PUNP STEAN SUPPLY VALVE A CI.OS ED 6009 52 V3504 AUX FW PUNP STEAN SUPP!.Y VALVE 8 CLOSED 6009 F -/4/
0 NOV ll:4 P.. L ~ 6INNA SIGNATOR BRED'iP ASIGhtE!iT SJNQRY 6RO~P: EVBlTI PROCEDLRE: EPIP !-5 PLANT STAPJS POINT ID DESCRIPTION VcVLiF QUAL E. U. 53 FSIA SAFETY IN'~"- >"N 'ODP A AV"- FLOW 0. 60OD PH 54 FSIB SA~=i') INJECTION LOOP B AVG FLOW 0. GOOD PN SLUICE WATER PUtFS A h B OKER 87. 600D PSIG 5b P21bl SERVICE WATER PtNiPS C h D HEADER Gb. 6000 PSIG 57 58 59 bv BKRD41 8 F4" BKR043 e's SGÃICE WATER PINP A SERVICE WATER PUNP B SERVICE WATER POP C
~rf'>T~ [!Q+>>
fpl% P'N ON ON ON 600D 6000 6009 KZ
h3V 17. 1;:44 ."-,. "". GItQ SIMULATOR TREND GRO!JF ASSN'.'="hT SilttARY pj0'-.P: =VcEtlT2 PR04EQRE, EPIP f-5 PLAttT STAT JS rOltti iD 0" 6'"RIP 7 IO!t VALUc QUAL E. U, hC! vcr C0 COA ONEtlT CO>> ING l.GOP TOTAL FLV 892. LALY PN 2 t.Rt'ST REFiicLING RATER STORAGE TANtt LVi 37.0 GOOD
'85033 33 FOOT LEVEt ttittD SPEED 3.0 GOOD ttPH 4 ND033 33 FOOT LEVEL 4itt9 DIRECTIO;t 41. 6009 DEG.
5 NT033 3~ FOOT LE!/c'E!'!'""RA?OS 43.1 6009 DEGF 6 WT250 0 FOOT LB% TE."ZERATURE 43.1 KOD DEGF I "50 TO 33 FOOT LE!" H.TA T!="8 .0 K09 DEGF 8 Ref HB f<ONTRG: ROO,"i 9.44062-02 GOOD tS/HR 9 Re: AR"". '-CONTAINYEf'! 7.8072?+03 BAD t8/HR Ie P05 AREA 5 SPcNT FU L Pt i 3.14412@00 BAD tS/HR R09 AREA 9-'TDO'~~i LINE tfOttITOR 2.75423~01 BAD tS/HR R34 AREA 34 - AUX BLDG CV SPRAY PL!ttP 2.9512fiee BAD Yitt/HR 13 R35 ARB 35-PASS SANF" E PAteL 1.09648+00 GQQD tS/HR 14 R10A CC!i! AIN!tEtiT IODINE ti0!tITOR R10A 9.66051+06 HALtt CPN f5 R11 C3i',~AirtikttT AiR PARTIC!MTE 9.66051+06 HALtt CPH 16 R12 CQv>AINtfEhT G.-'.S YiOhiTCR 1 ~ 01741407 HFNG Ci'M 17 R10B :"":."iti VEttl IODIttE ttONiTOR R109 9.50877+05 HALYi CPtt gI AiJ< B'G EXHAUST AIR PPRTICULATE
~
R13 2.54829+02 GMD PN 19 R14 AJX PUG EXHAUST GAS YmtITOR f.02182<07 HENS CPN 20 R18 LINID ttASTE DISPOSAL NNITOR 9.80051+05 HALtt CPN R19 STEN 6ENERATOR BLO'ADON DRAIN 6.86868+03 HAS CPtf 22 R29 ARM 29-CONTAIN"tEttT HIPrl RANG 1.30316+03 HALtt R/HR 23 R30 AREA 30-COttTAik".cttT HIGH RAttGE 1.303fbt03 HALYi R/HR 24 Rf ~ CQ!CENSER AIP, E3ECTQR DHAUST '1.41457 03 GOOD Cl'tf 25 P,.'2A5 CV VEtii CHAtt 5-LM RAttà GAS 4.20511-05 6009 XI/CC w> ~ 6 R12A6 CV V:-t. Rh 6-AFEA GAYi"iA 5 20000+02 HAD tS/HR
')7 R12A? "'dti CtN 7-" 9 PAt GP- 4.205ffM 6009 XI/CC 28 R12A9 CV V.",'T CttAN 9+IGH RAhEE GAS 9.99987-04 6009 KI/CC 29 R1485 FLAilT VENT CHAN 5-LG'rl RANGE GAS 9.96974-03 HP'i Xl/CC 30 R14A7 PLNT VENT CNtt 7"tiID RANGE GAS 8.85986+00 HAiit Kl/CC 31 R14A. R.0:i VENT CNN 9-HI6H RANGE GAS 8.85986+M HNFi XI/CC 32 R15A5 AIR E3ECTOR CHAt'ON RANGE GAS 6.22985-06 GOOD Kl/CC 33 R15A7 A!R EIECTGR CHAN 7 tiID RANGE SAS 1.80975-05 GOOD XI/CC 34 R1599 AiR c~cCTCR C"4t'-O'AGE GAS 1.52999"'03 G009 KI/CC 35 AR ~ 31 STENi LINE A (GRINS) 3.61997-03 6009 tS/HR 36 R32 A<EA 32 STEA".i LINE 8 tSt'ItlG) 3.61997-03 GOOD tS/HR 37 CVH
."" '"'DRGGE" CGNCEttTPATIO"'V ~ 0 6009 /
38 TCV03 BASEHEtii!LEVcL 6FT TEtP <<3 63.3 KOD DEGF 39 TCV07 CV INTER!'cDIATE LVL br! TEtP tt? 63.9 6009 DEGF 40 TCV08 V Ih! ERYiEDIAT LVL 6F: TEIP <<8 63.9 =6009 986F 41 TCV09 CV '.NTERYiEDIATEc LVL 6FT TEY!P <<9 63.9 6009 KGF p TCV10 CV iNTERNEDIATE LVL 6FT TEYiP <<10 63.9 6009 DEGF 43 TCV17 CV OPERATING LEV 6FT TEMP <<17 64.5 6009 DEGF
Time: 1=-150 Message: 54 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM
~ I C I R Simulated Plant Conditions: ~Meaaa e: """THIS IS AN EXERCISE" >>"
The following Annunciator is received: r
'-10 (Auxiliary Building Sump Pump auto start).
FOR CONTROLLER USE ONLY Controller Notes:
- 1) The "B" Auxiliary Building sump pump starts and runs for approximately one minute.
Actions Ex ected:
- 1) Operators should perform the applicable actions of AR-L-10.
Time: 1155 Message: 55 GlNNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM TSC Simulated Plant Conditions: ~essa<ee: ""THIS IS AN EXERCISE""" The following information is received in TSC from repair team working on the "A" Emergency Diesel Generator: 'he "A" Emergency Diesel Generator is ready for return to service. FOR CONTROLLER USE ONLV'ontroller Notes: Actions Ex ected:
- 1) Operators, when requested by the TSC, should line up the "A" Emergency Diesel Generator per T-27.1 .
- 2) Operators should be performing the applicable actions of FR-C.1 .
- 3) TSC should request that the Control Room have the "A" Emergency Diesel Generator lined up for normal operation and allow it to tie into Bus 14.
- 4) TSC should inform Control Room to start all Safety injection pumps and Containment recirc fans available as soon as Bus 14 is energized by the "A" Emergency Diesel Generator.
- 5) TSC should inform the Control Room to close MOV-851A as soon as MCC-C is energized, if MOV-851A AC ower breaker was turned on.
Time: 1155 Message: 56 GINNA STATION
. 1993 EVALUATEO EXERClSE MESSAGE FORM T-27.1 il yap li g pl "*" 6 g Di IG <<p Simulated Plant Condi ions: See Attached Mini-Scenario
~Massa e: <<e "THIS IS AN EXERCISEe>>" FOR CONTROLLER USE ONLY .Controller No es:
- 1) Provide information verbally when appropriate actions are simulated or investigations conducted.
Actions Ex ected:
- 1) As per Mini-Scenario.
GINNA STATION 1993 EVALUATED EXERCISE-MINI-SCENARIO TITLE: Linin u he "A" Emer enc Diesel Genera or er T-27.1 Expected scenario start time: 1155 Hours INITIALCONDITIONS:
'CS has experienced a large break LOCA.
'he "A" Emergency Diesel Generator tripped on low lube oil pressure ten minutes after the LOCA.
't 1005 hours Bus 14 tripped out due to a transformer problem.
'ecause of the above events and other equipment out of service, all safety injection to the core is lost. The core is now uncovered and sustaining major damage.
'he maintenance repair team has repaired the "A" Emergency Diesel Generator and has informed the TSC it is ready for return to service.
METHOD OF INITIATION:
'he TSC requests the control room to have the "A" Emergency Diesel Generator expeditiously lined up per T-27.1 .
I N DI CATIONS:
'one EXPECTED SEQUENCE OF ACTIONS:
'btain a copy of T-27.1 .
'erform T-27.1 expeditiously (simulate).
'nform TSC/Control Room at 1215 hours that the "A" Emergency Diesel Generator is lined up per T-27.1 (whether it is or not).
1
FINAL CONDITIONS' The "A" Emergency Diesel Generator is considered lined up and reported to TSC/Control Room at 1215 hours.
'ontroller must no if Sim I or 0 er or 'ust rior to Auxiliar 0 era or notif in Control Room SC.
Time: 1200 Message: 57 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM ,MMM: >> ~ I 'C ' R Simulated Plant Conditions: ~INessa e: >><<>>THIS IS AN EXERCISE>>"" The following Annunciator is received: '-10 (Auxiliary Building Sump Pump auto start). FOR CONTROLLER USE ONLY Controller Notes:
- 1) The "B" Auxiliary Building sump pump starts and runs for approximately one minute.
Actions Ex ected:
- 1) Operators should be performing the applicable actions of AR-L-10.
Time: 1210 Message: 58 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM .MMM: Si I <<C << IR Simulated Plant Conditions: ~essacee: <<""THIS IS AN EXERCISE>>"" The following Annunciator is received: '-10 (Auxiliary Building Sump Pump auto start). FOR CONTROLLER USE ONLY Controller Notes:
- 1) The "B" Auxiliary Building sump pump starts and runs for approximately one minute, Actions Ex ected:
- 1) Operators should be performing the applicable actions of AR-L-10.
Time: 1215 Message: 59 INNA TATION 1993 EVALUATED EXERCISE MESSAGE FORM MMM: 8 I <<C << I R tlSl.'imulated Plant Conditions: See Attached Sheets ~essacee: e "THIS IS AN EXERCISE>> The following information is received in the Control Room/TSC from the Auxiliary Operator lining up the "A" Emergency Diesel Generator: 'he "A" Emergency Diesel Generator is lined up per T-27.1 . FOR CONTROLLER USE ONLY Controller Notes: Actions Ex ected:
- 1) Operators should start the "A" Emergency Diesel Generator and ensure it ties into Bus 14.
- 2) Operators should attempt to start the-,"A" and "C" safety injection pumps, the "A" RHR pump and the "A" and "D" containment recirc fan coolers. All equipment starts except the "C" Sl pump (burned out motor).
- 3) Operators should attempt closure of MOV-851A if the AC power to the breaker has been previously turned on, If the AC power to the breaker has been previously turned on, ~hen the valve will come off its back seat and the breaker will trip out. If the AC power to the breaker has not been previously turned on,
~hen no valve closure should be attempted at this time.
- 4) Operators should inform the TSC of the equipment started on Bus 14.
- 5) Operators should inform the TSC of the failure of the "C" Sl pump to start on Bus 14.
- 6) Operators should inform TSC of MOV-851A failure to close if AC power was previously turned on to the breaker.
- 7) Operators should be performing the applicable actions of FR-C.1 and then return to E-1.
- 8) TSC should send a team into the Auxiliary Building to turn on the AC power to MOV-851A, lf the AC power to the valve breaker had been turned on previously, the TSC may send an electrician with this team to check the breaker.
- 9) TSC should be evaluating plant conditions and taking action as required.
- 10) TSC should be checking on progress of repair teams.
- 11) TSC should be informing the EOF of plant status and actions being taken for plant recovery.
12') EOF should be evaluating plant conditions and taking actions as required.
- 13) EOF should be requesting the engineering support center to perform a core damage assessment.
- 14) EOF Dose Assessment should be tracking the release plume and coordinatinglrecommending protective action recommendations to the Recovery Manager.
- 15) The Recovery Manager, after evaluating the EOF Dose Assessment recommendations, should update protective action recommendations to offsite agencies.
- 16) Repair teams should be expediting repairs as conditions permit.
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1993 EVALUATED EXERCISE Time. MAZOR PARAMET ENGINEERED SAFEGUARDS
'i Reactor Shutdown ES NO h Head S.I. Pum s N-31 >>CPS FI-924 0 GPM N-32 8-l0 CPS FI-925 ~GPM N-35 ( AMPS 1A. SERV TB OOS N-36 lac 8-> AMPS 1B. NS RV S Avg. Nuclear Power 0 1C. NSERV TBY OOS RCS Pressure Q PSIG BAST Level =
PRZR Level A RCP RUNNING/ OPPE Law Head S.I. Pum s B RCP RUNNING OPPE FI-626 & GM 1A S/G Level 1B S/G Level 1A S/G Pressure Tet
/, '4 PSIG 1A.
1B. RWST
'TBY Level V
=
OOS REC RC 00 RECIRC 1B S/G Pressure SIG Turbine/Generator E/ FFLINE Cantainmen S ra Pum s 4 KV Buses NERGI D DEE IZED FI-931A GPM 480V Buses ENERGIZED/DEENERGIZED FI-93 1B~GP DC, Batteries A)REVOLTS B~IDVOLTS 1A. INSERV OOS Cnmt Pressure DP PSIG 1B. NSE V Cnmt Sump A Level Cnmt Sump B Level
~Z- FEET
~
4/~0~r'B INCHES NaOH Tank Level = B OOS
" Loop Hot Leg ~2l 3; OF Containment Recirc Fans A Loop Cold Leg ,'F 1A. INSERV TB OOS B Loop Hot Leg ~ /3. OF 1B. NS STBY OOS B Loop Cold Leg ~ iP DF 1C. SERV STBY OOS RVLIS ~3~i 1D. INSERV TB OOS
- CET eq'2 e 'F Post Accident Dampers 0 E CLOSED S/G A Total Aux FW Flow V GPM 5/G B Total Aux FW Flow ~2GPM Service Water Pum s 1A. NS STBY OOS DIESEL GENERATORS 1B. STB OOS 1C. IN V STBY OOS A. UNNING UNLOADED S OOS 1D. NSERV STBY 00 B. RUNNING UNLO DED TBY OOS A&B Header Pressure 7 ( PSIG TSC RUNNING 0 DED TB 0 S Security RUNN UNLOADED TB OOS Cam anent Cooli Rater Pum s 1A. TB OOS ENGINEERED SAP DS 1B. SERV STBY OOS Aux. Feedwat 8 Surge Tank Level = ~Q 1A. INS V STB OOS Standb Aux. Feedwater Pum s 1B. NSERV TBY OOS 1C. INS V 00 Turb. Driven NSERV TB OOS 1D. NSERV STB OOS CST Level ~FEET
- CET = Average of Selected Core Exit Thermocouples
0 NOV 17! 1993 12(14 R. E. GII4'IA SIILLATGR PAGE 1 TPEND GRGU? ASSIGN~&7 SUI(l(ARY GROJP: EVE)(71 PROCEDUREI EPIP 1-5 PLANT STATUS PG>>IT;9 KKRIPTIGN VAOlE @NL E. U. 1 ATMS ANTICIPATED TRANSIENT M/0 SCR4Jf AT>IS ALRII 2 RXT REACTOR TRIP BREAKER STATUS RK TRIPPED ALRII 3 N31 SMICE RANGE DETECTOR N 31 6.33138404 HMRII CPS 4 N32 SONCE RANGE DFTECTGR N-32 3.94456+01 BAD CPS 5 N35 INTER>IEDIATE RANGE DiTECTGR N-35 1.34276-10 6009 AIIP 6 N36 I@rRMEDIATc GRANGE DETECTOR N-36 1.00001-11 6009 A,">P
? NP AVcERAGE NL'CLEAR POMER .00 6009 /
8 PRCS REACTOR CGOLAtiT SYSTEM AVG PiKSS 0. LENS PSIG 9 O'R PRESSURIEER AVERAGE LEVEL .0 LALN 10 FRCLA REACTOR CGGLAIT LOOP A AVG FLGM .0 INHB K 11 FRC~ 8 REA".TGR COOLANT LOG," 8 AVG FLGM 1.3 INHB / CQ RXTib RCPA BRFAKER CAUS RK TRIP TRIPPED ALRII 13 RKT17 RCPB BREAKER CAUSi RK TRIP TRIPPED ALfN
'4 TSUBTC INXRE TC SUB%GLED MARGIN -779.5 LAL< I>EGF 15 I SGA STt'i GEN A NARROM RANGE AVG LR'EL 67.1 HALI( X 16 LSGB STI( GEN 8 IIARRGM RANGE AVG LEVEL 61.2 HMRe X 17 PSGA ST)I Gert( A AVERAGr PFZSSUR:" -5. LCD PSIG 18 PSGB STN GrJ( 8 O'ERAGE PRESSURE -5. LAO( PSIG 19 GEIIBKRs GYRATOR Gtt LINE BREAKiR 1G1372 TRIPPED ALRII 20 GENBKR2 GEIEJATOR GN 'NE BRiAKER 9X1372 TRIPPED ALRII BUSilA BUS 11A Sl!PPLY BREAKER TRiPPED ALRII 22 BUS118 BUS 118 SUPPLY Bf(EAKE4 TRIPPED ALRt(
23 BUS12A t(07 TERNINATED ON PPCS (7/19/91> NOT TRIP DEL 24 BUS128 NOT TERMINATED OII PPCS (7/!9/91) NOT TRIP DrEL 811A12A BUS llA TG 12A TIE BREAKER NOT TRIP ALRN 26 8118128 BUS 118 TG 128 TIE BREAKER NOT TRIP ALRN 27 PCV CGI(fAINIIEI(l'VERAGE PRESS!JRE .(8 GOO~ PSIG 28 LSU,"PA CGNTAINIIENT SU!"!P A 4VciWK LEVEL 31.2 HEIPi FEET L0942E SU~r' LEVEL 8 INCHES (TRA!N A) HIGftR IN{9 30 L0943E SUI. 8 LcVEL 8 II(CHES (TRAB( 8) HIGfKR It(f(9 31 L0942D SUtf' LEST 78 It(C>7S (TRAIN A) HI6HER INHB 32 L09439 SUtF' LE%'8 it(CHES (TRAIN 8) HIGfFP, INHB L0942C SUB' LEVEL !13 INCHciS(TRAIN A) HIGHER ALRII 34 L0943C SU!"P 8 LEVEL 113 INCHcS(TRAIN 8) HISHER 'LRt( 35 L09428 SUtf 8 LEI!S. 180 IIICHES(TRAIII A) LONER 6009 36 L09438 SUtF' LEVEL 180 INCHcS(TRAlti') LONER GOOD 37 L0942A UlF 8 LEIIEL 214 INCHES(TRAIN A) LONER 6009 38 L0943A SUtP 8 LEVE'14 INCHES(TRAIt( 8> LONER G009 39 T0409A RCLA HOT LEG TEtFERATURE 213.9 6009 D"6F 40 T041OA RCLB HOT LEG TEI(PERATURE 213 9 6009 DEGF 41 T0450 RCLA COLD LEG TEIIPERAT(RE 201.S BAD DEGF 42 T0451 RCLB COLD LEG TEIFERATIRE 158.2 BAD DEGF 43 TAVGAMID RCLA TAV6 (THGT/TCOLD MIDE Rt(6) 213.9 600~ DE6F 44 TAVGBMID RCLB TAVG (THOT/TCOLD MIDr RNG) 213.9 600~ DEGF 45 LRV REA TOR VESSEL AYiRAGE LEVEL 38.9 LALYi K 46 TCCGRi Elo1 It(!.ORE TC AVERAG"" TEIIP 792.6 HAL~ DEGF 47 FAUXFMA S/6 A TOTA'JK FEEDMATER FLOM 0. 6009 GPII 48 FAUXFMB S/6 8 TOTAL AUK FEEDMATER FLGM 27. GG09 PI( BKR081 tITR AUXILIARY FEEDMATER P(9IP A OFF 6009 50 BKR082 NTR AUKILIARYFEEDMATER PUtP 8 ON 6009 51 V3505 AUK FM PUMP STEAII SL'PPLY VALVE A CLGSH) 6009 52 V3504 AUX FM PUII~ STERh SL4'PLY VALVc 8 CLOSED 6009
/)P
NOV 17~ 1993 1"l]4 R. E. GltflA SItlULATOR PA6E 2 TREND GROUP AKIGlNrAT SUtfARY GROK.: EVENT! PROCEDURE: EPIP 1-5 PLAttT STATUS POINT ID DFSCRIPTION VALUE QUAL E. U. 53 FSIA SAFETY INJECTION LOOP A AVG FLOM 0. GOOD GPN 54 FSIB SAFETY INJECTION LOOP B AVG FLOM 0. 6000 GPM 55 P2ih0 SERVICE MATER PUttPS A 5 B HEADER 87. 6009 PSIG 56 P2161 SERVICE MATER PUttPS C 5 D HEADER 86. GOOD PSIG 57 BKRO41 SERVICE MATER PUttP A ON Gm 58 BKRN2 SERVICE MATER PUttP 8 ON 600D 5S BKR043 SERVICE MATER PUt1P C ON Goan b0 BKRO44 SERVICE MATER PUttP D ON GOOD
tfQV 1?r 1993 12: 15 R. E. GINA SINL'LATQR TRB8 GROUP ASSIGNNB(T SUIPiARY 6ROUP.'VENT2 PROCEDURE: EPIP 1"5 PLAtfT STATUS POINT ID DES"RIPTIQtf VALLE GOAL E. U. 1 F0619 COMPONENT COQLINa LOOP TOTAL FL(f 884. LALN GPN 2 LRIIST REFUELING MAT% STQRAGi TANK LVL 36.8 G009 K 3 MS033 33 FOOT LEVcEL M!t(D SPEED 3.0 GOOD NPH 4 MD033 33 FOOT LiVEL MIND DIRECTION 41. 6009 DEG. S WT033 33 FOOT LEVP TENPiRATURi 43.1 6009 KGF 6 MT250 250 FQQT LEVEL TEN<PERATURi 38.8 6009 DEGF 7 WDT2 250 TO 33 FOOT LEVEL DP TA TEMP -4.3 GOOD DEGF 8 R01 ARFA I-COt(TRQL ROQi"i 8.81048<2 6009 NR/HR 9 R02 AREA 2-CQI(TAINNEHT 7.80727403 BAD )S/HR 10 R05 AREA 5-SPENT FUcL PIT 3.(4412+(e BAD NR/HR 11 R09 AREA 9-LETDOM<f LltF I'iONITOR 2.75423+01 BAD NR/HR
'2 R34 AREA 34 - AUK BLDG CV S.'RAY PU<P 2.95121+00 BAD ta/HR .'3 R35 AREA 35-PASS SA"IPLE PANEL 1,09648<00 GOOD NR/HR 14 R10A CQNTAltfMB(T IQDItfE MONITOR R1CA 1.04864+07 HENS CPN !5 Ril CONTAINMENT AIR PART IC(LATE 9.702%+06 HALN CPN 16 R12 CONTAItfNEt(T GAS NON ITOR 1.02624+07 HEt(6 CPM 17 R10B PLM'ENT IODINE NQI(ITQR RIOB 9.71623~05 HALM CPN 18 R13 AUK BLDG EKHAUST AIP. PARTICULATE 2.57039%2 6009 CPN 19 R14 AUX B(J)G EXHAJST GAS MONITOR 9.57744+06 HALN CPN 20 R18 l NUID WASTE DISPOSAL MONITOR 1. 00577+06 HALN CPtl 21 R19 STEAN GB(ERATQR BLO'ADO%I DRAlt( 6,75108+03 HALN CPN 22 R29 AREA 29"CONTAlt9LctfT HI% RANKc 9.02219+02 HALN R/HR 23 R30 ARc4 30-CQtfTAItfNEt(T HIGH RAI(GE 9.02219+02 HALN R/HR 24 R15 CQtfDENSER AIR EJECTOR EXHAUST 1.42683+03 6009 PN 25 R12A5 CV VBIT CSW 5-LQM RNfK GAS 4.20S11-05 GOOD UCI/CC 26 R12A6 CV VENT CHAN 6-AREA GANA 5.200CO+02 HALN N/HR 27 R12A7 CV KNT CS(tf ?<ID RAI(K GAS 4.20511-05 6009 Xl/CC 28 R12A9 CV t tfT CHAN 9+IGH RAISE 6AS 9.9998?M 6009 XI/CC 29 R14A5 PLANT VBiT CHAN 5-LOM RANGE GAS 9.98974-03 HALN XI/CC 30 R14A7 PUN VEI'iT CHAN 7-NID RAN6E GAS 8.85986+00 UCI/CC 31 R14A9 PL@(T VENT CHAN 9+IGH RAt(GE 6AS 8.85986+(5 HMRN XI/CC 32 R1SA5 AIR EJECTOR CHAN 5-LOM RANGE GAS 6.22985-06 6009 XI/CC 33 R1587 AIR EJECTOR D(Atf 7-NID RANK GAS 1.80975-05 6009 XI/CC 34 RISA9 AIR EJECTOR DQN 9 HI RANGE GAS 1.52999-03 6009 XI/CC 3S R31 KR 3'1 STEAN< Lit<i A (Plt(6) 5.00000+(e HALN %/HR 36 R32 ARFA 32 STEAtl Lit(E B (S IN6) 5.00000+00 HALN %/HR 37 CVH CV HYDROGEtf CQtiCENTRAT IOi'f .0 6009 7 38 TCV03 CV BASENENT MliL 6FT 78P <<3 63.3 6009 DEGF 39 TCV07 CV INTERMEDIATE LVL 6FT TEt'P <<? 64.0 6009 DEGF 40 TCV08 CV INTERt(EDIATE LVL 6FT TENP <<8 64.0 %009 DEGF 41 TCV09 CV INTERMEDIATE LVL 6FT TENP <<9 64.0 G009 DEGF 42 TCV10 CV It(TERNEDIATE LVL 6FT TElP <<10 64.0 6009 DEGF 43 TCV17 CV OPERATING LEVL bFT FJP <<17 64.7 6009 DEGF
TIme: ~121 Message: 60 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM ~f:A ill yOpdl power breaker for MOV-851A. I <<ii 1 keg'dl<<kglAC Simulated Plan Conditions: See Attached Mini-Scenario ~IVlessa e: """THIS IS AN EXERCISE" >>" FOR CONTROLLER USE ONLY: Controller Notes:
- 1) Provide information verbally when appropriate actions are simulated or investigations conducted.
Actions Ex ected:
- 1) As per Mini-Scenario.
GINNA STATION 1993 EVALUATED EXERCISE lVIINI-SCENARIO TITLE: Checkin nd or Turnin on the AC Power Breaker for MOV-851 A. Expected scenario start time: 1215 Hours INITIALCONDITIONS:
'CS has experienced a large break LOCA.
'ecause of a leak from the large pipe between Containment and MOV-850A, it is imperative that the breaker from MOV-851A be turned on so MOV-851A can be closed to isolate the leak from Containment.
'd d d t t t ddd dd been re-energized at approximately 1220 hours.
MOV-851A receives its AC power from MCC-1C position 10M. MCC-1C receives its power from Bus 14.
't is possible that the AC power breaker to MOV-851A was turned on subsequent to the restoration of Bus 14. If this is true, then when power is restored to Bus 14 and the Control Room attempts to close MOV-851A,. the AC power breaker will trip on overload as the valve attempts to come off its backseat.
METHOD OF INITIATIONS:
'SC requests the AC power breaker for MOV-851A be checked and/or turned on.
INDICATIONS:
'f team is to check breaker before they turn it on it will be normal.
'C power breaker for MOV-851A it either locked off or is tripped off.
EXPECTED SEQUENCE OF ACTIONS: Breaker previously turned on and has tripped:
'btain locked valve key.
'roceed to MCC-1C, position 10M.
'nspect breaker for signs of a problem.
'bserve no problems.
'nlock breaker and turn on.
Note: The breaker will be c nsidered urned on at 1245 hours no ooner no la er for cenario ur ose .
'eport the breaker is turned on at 1245 hours to the Control Room/TSC.
Note: Con roller to coordina e this wi h he Sirnula or 0 era or. Breaker not previously turned on:
'btain locked valve key.
'roceed lo MCC-1C, position 10M.
'nlock breaker and turn on.
Note: The breaker will be considered turned on at 1245 hours no sooner no later for scen rio ur oses.
'eport the breaker is turned on at 1245 hours to the Control Room/TSC, Note: Controller to coordinate this with he Simula or 0 era or.
FINAL CONDITIONS:
'he AC power breaker for MOV-851A will be considered turned on at 1245 hours.
'OV-851A will be considered closed at 1250 hours for scenario purposes.
Time: 1220 Message: 61
~GN T TD 1993 EVALUATED EXERCISE MESSAGE FORM
<< I C I il Simulated Plant Conditions:
~Messa e: "<< "THIS IS AN EXERCISE<<>>>> The following Annunciator is received: '-10 (Auxiliary Building Sump Pump auto start) FOR CONTROLLER USE ONLY Controller Notes:
- 1) The "B" Auxiliary Building sump pump starts and runs for approximately one minute.
Actions Ex ected:
- 1) Operators should be performing the applicable actions of AR-L-10.
- 2) Operators should be performing the applicable actions of E-1 (loss of reactor or secondary coolant).
Time: 1230 Message: 62 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM Si t<<C IR Simulated Plant Conditions: See Attached Sheets ~Messa e: "" THIS IS AN EXERCISE FOR CONTROLLER USE ONLY Controller Notes: Actions Ex ected:
- 1) Operators should be performing the applicable actions of E-1.
1993 EVALUATED EXERCISE Time: ~>3> MAJOR PARAMET ENGINEERED SAPEGUARDS Reactor Shutdown ES NO Hi h Head S.I. Pum s N-31 CPS FI-924 ~ GPM N-32 CPS FI-925 2- 2-GPM N-35 AMPS 1A ER STBY OOS N-3 6 .OIS-I AMPS 1B. NSE V STBY 00 Avg. Nuclear Power 1C. NSERV STBY OOS RCS Pressure O PSIG BAST Level = 0 PRZR Level C3 A RCP RUNNING/ DPP Low Head S. . Pum s B RCP RUNNING TOPPE FI-626 2oO GPM 1A S/G Level ,2 1A. ' Y OOS REC RC 1B S/G Level 1B. INS V STBY 0 R CIRC 1A S/G Pressure 1B S/G Pressure 0 Z& PSIG PSZG RWST Level = ~~4 Turbine/Generator ONLI E FFLIN Containment S ra Pum s 4 KV Buses NERGIZE /DEENERGIZED FI-931A 0 GPM 480V Buses ENE ZE /DEENERGIZED FI-931B D GPM DC Batteries A VOLTS BQgVOLTS 1A. NS RV 00 dZ-Cnmt Pressure Cnmt Sump A Level Cnmt Sump B Level
~
QigQ~I<
~ 2 PSZG FEET INCHES 1B NaOH NSERV STB Tank Level = ~4OOS " Loop Hot Leg 2,o7.w OF Containme Recirc Pans A Loop Cold Leg ~l'F o 'F 1A- NSERV STBY OOS B Loop Hot Leg OF 1B NSER STBY OOS B Loop Cold Leg OF 1C. STBY OOS RVLIS ~12.. 1D. NSER STBY OOS
- CET 'F Post Ace> ent Dampers PE CLOSED S/G A Total Aux FW Flow GPM S/G B Total Aux FW Flow ~2GPM Service % Pum s 1A. NSER S BY OOS DIESEL GENERATORS 1B. NSE STBY OOS 1C. STBY OOS A. RUNNIN UNLOADED STBY OOS 1D. SER STBY OOS B. RUNNING TSC RUNNING 0 DED ED TB OOS OOS A&B Header Pressure ~la pSZG Security R OADED TB OOS Com onent Coo1 %ate Pum s 1A. INSERV OOS ENGINEERED SAP DS 1B. NSE STB OOS Aux. Peedwater Pum s Surge Tank Level =. ~G 1A. I RV T OOS Standh Aux. Pe wate Pum s 1B. NSERV TB OOS 1C. S V TB 00 Turb. Driven INSERV 1D. INS RV CST Level ~. TB FE T OOS TB OOS
- CET = Average of Selected Core Exit Thermocouples
17i 1993 12! 2:" R. ". GINA SltfiJLATQR PAGE 1 TREt<9 GROUP ASSIBNt<it<T SUNARY BRGLc'VcNTf PROCEDURE EPIP 1 5 PLANT STATUS POINT I DiSCRIPTIQN E. U. ATWS ANTICIPATED TRANSIEt<T M/0 SCRAJ< ATNS ALRN RXT REA".TOR TRIP BREAKEP. STATUS R)< TRIPPED ALRt< N31 SOLACE RANGE DETECTGP, N-31 2.9?166+01 6009 CPS N32 SMCE RANGE DETECTOR N-32 2.85101401 6009 CPS 5 )<35 INGOT)IATE RANGE DETECTOR N-35 1.00461-11 GOOD NP 6 N36 It<TER)LcDIATE RANGE DETECTOR N-36 1 ~ 00461-11 6009 NP 7 NP AVEf<A!i" NL!CLEAR PONER .00 6009 Ã 8 PRK RE@".TQR CCGA"<T SYSTEt< AVG PRESS 0. Lit<6 PSIG LPIR PRcESSURIZER AViRABE l RIEL .0 ftu X 10 FRCLA ROTOR CQOLRil LOOP A AVG FLN ~ 0 INHB y 11 FRCLB REA".TOR COOLANT LOOP 8 AVG FLOW .0 INHB 0/ 12 RXT16 RCPA'BREAKER CAUSE RX TRIP TRIPPED ALf9< 13 RXTf7 RCPB BREAKER CAUSE RX TRIP TRIPPED ALRN TSUBTC IhZR" TC SUBCODLED HA%IN -1.5 LAL* DEGF 15 LSGA STNi BFN A NARROW'A<Pei AYG LEYJ 66.2 Hf<R)< / fb LSBB STh GEN 8 tlARROA RANGE AYG LEVEL 66.8 Ht<R)< K 17 PSGA STNi GEN A AVERAGE PRESRSE 0. LAu< PSIG 18 PSGB STt< BEN 8 AVERAGE PRESSURE 0. LAN PSIG 19 GEt<BKR1 GENERATOR ON LINE BREAKER 161372 TRIPPED ALRtt 20 GENBKfQ Git&ATQR Oh'INE BREAKEcR9X1372 TRIPPED ALRN 21 BUSllA BUS 11A SUPPLY BREAKcR TRIPPED ALRtf 22 BUS118 BUS 118 SUPPLY BRciAKER TRIPPED ALRtf 23 BL'S12A NOT TcRtilNATED Ot< PPCS <7/19/91) NOT TRIP HIGHER DEL 24 BUS128 t<QT TERtfit<ATED ON PPCS (?/19/91) NOT TRIP DEL 811A12A BUS 11A TQ 12A Ti'E BREAKER NQ! TRIP ALRti 26 8118128 PJS 118 TO 128 TIE BREA<ER NO! TRIP ALRtt 27 PCV COt<TAIt<t<c>! AVERABi PRHSURE .02 6009 28 LSUvPA CQNTAIt<tiEt<T PJiip A AVERAGE LEVEL 31.2 HEh'G 29 L0942E SL>5' LEVEl. 8 It<CHES <TRAIN A) HI6HER Ihf<9 30 L0943E SUP 8 LEVEL 8 INCHES <TRAIN 8) INH9 31 L09429 SUtP 8 LEVEL 78 NQ'cS (TRAIt< A) HIBHP INHE 32 L0943D SU)P 8 LE(tc'8 !t<Cf!"S (TRAlhi 8) HIGHER INH9 33 L0942C SUi~~ 8 LEYciL 113 It<CHES(TRAIh At HI6HER ALRt< 34 L0943C SUtP 8 LEVEL 113 INCHES(TRAIN 8) HIBHiR ALRlt 35 L09428 SiJYP 8 LEVEL 180 INCHcS(TRAItk A) LO)tER 6009 3b L09438 SÃ' LEVEL 180 It<CffiS(TRAIt< 8) LOUR GOOD 3? LO'942A SUPP 8 LEVEL 214 It<CH S(TRAIN A) LONER 6009 38 L0943A SUtP 8 LP(cL 214 INCf!cS(TRAIN 8) LOUR 6009 39 T0409A RCLA HOT LEG TE)PERATUP= 207.2 GOOD DEGF 40 TO410A RCLB HOT LEG TEtfPERATUiK 207.4 5009 DE6F 41 T0450 RCLA COLD LEG TE)fPERAT(RE 197.0 6009 DEGF 42 T0451 RCLB CGiJ) LEG TEt<PERATlRE 119.4 GGG9 DcGF 43 TAVGAWID RO" TAVG (T83T/TCOLD WIDE RNB) 202.1 6009 DE% 44 TAVBB))ID RCLB TAVG <THOT/TCOLD WIDE Rtl6) 163.4 6009 KGF 45 LRV RECTOR ViSSc'YERABi 'YEL 72.9 LALt< X 46 TCCQRE El.f INCQRE TC AVERAGE TEt<P 202.4 600~ DEBF 47 FAUXFMA S/6 A TOTAL AUX FEEC4)ATER FLY( 0. G009 GPtf 48 FAUXF)jfB S/G 8 TQTAL AUX FEEDS'ATcCt FLQN 27. 6009 IPt< 49 BKR081 hTR AUXILIARY FEEPAATER PUttp A Q. F 6009 50 BKR082 NTR AUXILIARYFEEDf<ATER PUt<P 8 Qt< GOOD 51 V3505 AUX FM PUi",P STEA1'i SUPPLY YALVE A CLOSED 6009 52 V3504 AUX FN PUt<P STEAK! SUPPLY VALVE 8 CLOSED GOOD
/ g~ 4/
c
NOV Ij~ 1993 12129 R. E. GINA SIN<ATOR PAGE 2 TREt6 GROUP AKIGteittT SiXAARY GROLP: EVEt<TI PROC="OUR":: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION VALUE OUAL E. U. 53 FSIA Sk~ INJECTION LOOP A AVG FLOW 0. GOOD 8'N 54 FSIB SAFETY INJECTIOtt LOOP B AVG FLOW 232. GOOD GPtt 55 P2 160 SERVICE %TER PlIPS A h B PEAG% 87. 6000 PSIG 56 P2161 SERVICE ttATER PUttPS C tnt 0 HEADER 86. 6009 PSIG 5? BttR041 SHNICE WATER PlNP A ON GOOD 58 BKR042 SERVICE WATER PlIP B ON GOOD 59 BKR043 SERVICE WATER PUttP C , ON GOOD 60 BkR044 SERVICE NTER PUtlP 0 ON 6000
MN. 17i }993 }2:> R. E. GINA SINL4.ATOR TRE8 GPOUP ASSIGtit}EtiT SUJLSRY GRE)7: EVEWT2 PRKEDPF'PIP }-5 PLANT STATUS POINT ID 0""Si".RIP TI 0" YALL~ E. U. QUA'84. 1 F0619 CEMENT G8 ING LGQP TOTAL FLM LALN PN 2 LRMST REFUELING MATcR STORAG" TANK LVL 33.5 6009 3 MS033 33 FOOT LEYE'!ND SPEED 3.0 6009 NPH 4 MDO33 33 FOOT LEVEiM!ND DIRECTION 41. GOOD 0""G. 5 MT033 33 FOOT LEVEL TENPERATURE 43.! G009 DEGF 6 MT250 250 FOOT LEVEL TENPERATURE 38.8 G009 I)"GF 7 MDT2 250 TO 33 FQQT LEVEL DcELTA -4.3 GOOD DEGF TE5'REA 8 ROl f-CONTRQ'OO:"i 9.22572M 6009 NR/HR 9 RQ2 AREA 2-CONTAINNENT 5.099}6~05 HALN l8/HR 10 RO5 AREA 5-SPBlT FUEL PIT 6.34598~04 HALE, N/HR
!! R09 AREA 9-'TDQMN 'tic NOttlTOR 6. 06036+04 HALN NR/HR !2 R34 ARFA 34 - AUX BLDG CV PRAY PUNP 6. 13055~04 HALN NR/HR !3 R35 AREA 35-PASS P4PLE 1,09648%0 6009 N/HR 14 RfOA IODIttE NOti'ITQR R}OA 9.57744~06 Pic'OtiTAItti<ctiT HALN CPN }5 Rll CQNTAINNENT AIR PARTICR,ATE 9.78647<06 HALN CPN 16 R12 CQNTAINNENT GAS NGNITGR 1.04864+07 HEttG CPN }7 R10B PLANT VENT IODINE MQt}ITOR R1QB 1,04562406 HALN CPN 18 R13 AUX BLDG EXHAiJST AIR PARTICULATE 2.41963+02 6009 V,'N !9 R!4 AUX BLDG EXHAUST GAS NONITOR 1.04864+07 KNG CPN R!8 LIE)ID MASTE DISPOSAL NGNITOR 1 ~ 03663+06 HALt} CPN 2} R19 STEAN GB)ERATOR IiLOMDGLN DRAItt 6.80964+03 HMRN CPN 0 22 AREA 29-COttTAINNEt(T HIS 5.0046&02 R29 RANGE HAU'i R/HR 23 R30 AREA 30-CQNTAIt'NEttT HIGH RANGE 5. 0046&02 HALN R/HR 24 R!5 COtQENSER AIR EJECTOR EXMST 1.42069+03 6009 CPN 25 R!2A5 CV VEttT CHAN 5-LOM RANGE GAS 4.2051!-05 6009 UCI/CC 26 R}2Ao CV VENT OA'4 6-AREA GANA 5.20X~2 HALN N/HR 27 R12A2 CV VB)T CHAtt 7-N!9 RANGE GAS 4.205!}M 6009i UCI/CC 28 R12A9 CV YBF> CHAt'-HIGH RAtGE GAS 9.99987-04 6009 fK:I/CC 29 R!4A5 PU67 YENT CHAN 5-LOM RANGE GAS 9.98974-03 HAU! UCI/CC 30 R!4A7 PLANT YB(T Cf@tt 7"NID RhtiiGE GAS 8.85986+00 HALti XI/CC 3! R}4A9 PLY!T VENT CHAN 9"HIGH RANGE GAS 8.85986~00 H)tRN UCI/CC 32 R}5A5 AIR EJECTOR RAM 5 LOM RANGE GAS 6.22985-06 G009 XI/CC 33 R15A7 AIR EJECTOR CHAN 7-tilD RAt<GE GAS 1 ~ 8097~ 6009 UCI/CC 34 Rf5A9 AIR EJECTOR WNt 9-HI RANGE GAS 1.52999-03 6009 KI/CC 35 R3! AREA 3! STEAN LINE A <PING) 5.00000e00 HALN NRIHR 36 R32 AREA 32 STEAN LINE B (PIt!6) 5.00000~00 HALN N/HR 37 CVH CV HYDROGEN CQttCENTRAT ION .0 GOOD X 38 TCVO3 CV BASEST LEtIEL 6FT TcNP I3 63.3 6009 DEGF 39 TCV07 CV INTERNEDIATE LVL 6FT TPiP 47 63.3 G009 DEGF 40 TCVOB CV INTERNEDIATE LVL 6FT TENP I8 63.3 -6009 KGF 4! TCV09 CV INTERNH)IATE LVL 6FT TENP 19 63.3 6009 DE6F 42 TCV10 CV ItiTERNBIATE LVL 6FT TENP tt}0 63.3 6009 DE6F 43 TCVf7 CV PERATlt)G 'VL 6FT TEt'P )t}7 63.4 6009 DEGF
Time: 1235 Message: 63 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM 8 I C I il Simulated Plant Conditions: Messa<ee: <<""THIS IS AN EXERCISE "" The following Annunciator is received: '-10 (Auxiliary Building Sump Pump auto start). FOR CONTROLLER USE ONLY Controller Notes:
- 1) The "A" Auxiliary Building sump pump starts and runs for approximately one minute.
- 2) Plant vent readings are decreasing due to Containment pressure reduction, reducing the leak out of the pipe between MOV-850A and Containment and also due to the resumption of core cooling reducing the radiation levels in containment.
Actions Ex ected:
- 1) Operators should be performing the applicable actions of AR-L-10.
- 2) Operators should be performing the applicable actions of E-1.
- 3) Operators may realize at this time that the Auxiliary Building sump pump operation interval is increasing (decreased leakage) and should inform the TSC of this.
- 4) TSC should be expediting sending a team into Auxiliary Building to check and/or turn on the AC power breaker for MOV-851A.
- 5) TSC should be evaluating plant status and taking action as required.
- 6) TSC may be evaluating the Auxiliary Building sump pump down interval change.
- 7) TSC should be informing the EOF of plant status and actions being taken for plant recovery.
- 8) EOF should be evaluating plant conditions and taking action as required.
- 9) EOF Dose Assessment should be tracking the release plume and coordinating/recommending protective action recommendations to the Recovery Manager.
- 10) The Recovery Manager, after evaluating the EOF Dose Assessment recommendations, should update protective action'recommendations to offsite agencies as required.
- 11) Repair teams should be expediting repairs as conditions permit.
Time: 1245 Message: 64
~GI NA T TIGN 1993 EVALUATED EXERCISE MESSAGE FORM MMM I: 6 I 5 I 6 Simulated Plan Conditions: See Attached Sheets
~Messa e: << "eTHIS IS AN EXERCISE" ~>> FOR CONTROLLER USE ONLY Controller Notes:
- 1) The team sent into the Auxiliary Building to check and/or turn on the AC power breaker for MOV-851A reports the following; de ndin n he si ua ion:
'f the AC power breaker for MOV-851A wa;~nip previously turned on, ~hen the team will simulate turning it on and report this to the TSC at 1245 hours.
'f the AC power breaker for MOV-851A ~wa previously turned on and then tripped, the team will report there findings to the TSC and await further TRG 2 5 . ~65.
instructions. After evaluation the TSC should request the breaker be reset and reported turned on. This should be simulated by the team and reported to the
Actions Ex ected:
- 1) Operators should close MOV-851A when requested by TSC. MOV-851A will be consider d closed com le el at 1250 h urs isola in he leak on the i e be ween C n ainmen and IVlOV-85OA.
- 2) Operators should inform the TSC of MOV-851A closure.
- 3) If the AC power breaker for MOV-851A was previously turned on and then tripped, TSC should evaluate this and most probably decide the following:
'he breaker could have tripped starting the closing cycle of the valve due to not being operated for a long period of time or the breaker may not have been completely reset the first time by the Auxiliary Operator.
'ased on the above and the emergency conditions that exists, the TSC should have the team reset and turn on the breaker for MOV-851A and then request the Control Room to close MOV-851A.
4l If the AC power breaker for MOV-551 A ~wa no previously turned on, TSC will request the Control Room close MOV-851A.
1993 EVALUATED EXERCISE Time.- MAZOR PARAMET ENGINEERED SAPEGUARDS Reactor Shutdown YES NO Hi h Head S.I. Pum s N-3 1 CPS FI-924 O GPM N-32 ~>~CPS FI-925 GPM N-35 $ ~~AMPS 1A. R S BY OOS N-36 l AMPS 1B. NSE V STBY Avg. Nuclear Power 1C. INSE V STBY 0 RCS Pressure BAST Level = 0 PRZR Level A RCP RUNNING/ Low Head S. . Pum s B RCP RUNNING OPPED FI-626 ~O GPM lA S/G Level &6-~ e 1A. NSER S Y OOS R C RC 1B S/G Level 1B. NSERU S B 0 C C lA S/G Pressure ~PSTG RWST Level 1B S/G Pressure PSIG Turbine/Generator ON E/ FFLIN Containment S ra Pum s 4 KV Buses NERG ZE /DEENERGIZED FI-931A ~ GPM 480U Buses ERGIZE /DEENERGIZED FT-931B~GPM DC Batteries Cnmt Pressure Cnmt Sump A Level Cnmt Sump B Level
" Loop Hot Leg A l3QVOLTS B 8~VOLTS
~ 6G
~~FEET G
PSIG INCHES
'F 1A.
1B. NaOH SERV TBY 00 S V T Tank Level = Containment Recirc Pa s
~OOS A Loop Cold Leg 0F 1A. STBY OOS B Loop Hot Leg I oF 1B. S STB OOS B Loop Cold Leg OF 1C. NSERV STBY OOS
. RVLIS ~IO 1D. INS STBY OOS
- CET ~ae ~
'F Post Aces ent Dampers OPE CLOSED S/G A Total Aux FW Flow GPM S/G B Total Aux FW Flow 27 GPM Service Q er Pum s 1A. NSE S BY OOS DIESEL GENERATORS 1B. SER S B OOS 1C. SERV S BY OOS A. RUNNIN UNLOADED STBY OOS 1D. SERV STBY OOS B. R NG UNLOADED OOS A&B Header ressure Qgg(n PSTG TSC RUNNING ED TB OOS Security RUNN UNLOADED B OOS Com onent Coolin Mater Pum s 1A. INSERV TB OOS ENGINEERED SAP DS 1B. ER STBY OOS Aux. Feedwater Pum s Surge Tank Level = ~~
1A. INSERU TB OOS Standb Aux. Fee ate Pum s 1B. ERV TBY OOS 1C. NS V STB 00 Turb. Driven INSERV TB OOS 1D. INSERV TB OOS CST Level ~0~FEET
- CRT = Average of Selected Core Exit Thermocouples
NOV 17~ 1993 R. E. GINA SIHULATGR PAGE 1 TRctG GROU. ASSIGtirUr(T SUl'il(ARY GRQL!u'VE 1 PRQCEDL!Rr: EPIP 1"5 PLANT STATUS POINT iD KS"RIPTIQN VALK E. U. ATMS ANTICIPATED TRAtiSIEt(T M/0 SCRAH ATMS ALRH 2 RXT REACTOR TRIP BREAKER STATUS RX TRIPPED ALRH 3 ti'3f SOURCE RANGE DETECTOR N-31 3.02342+01 GQGD P,S 4 tt32 SOURCE RA)iGE DFTECTOR N-32 3.40015+01 GDOD CPS 5 N35 ItlTERHEDIATc RANGE DETECTOR N-35 1 '0461-11 6009 AHP 6 tGb IurRH-DIATE RAN6 KTECTOR tt-36 1.0046!-11 600!) A!(P 7 NP AVERAGE t<UXEAR PGisER .00 6009 X 8 PRCS REKTOR CC9.4'O'YSTEH AV6 PRESS 2. LEtl6 PSI6 O'R PRESS!JRIEER AVERAGE LEVEL ~ 0 LALli /
!0 FR( A PZA".TOR COOLANT LOOP A AVG FLOM ~ 0 INHB /
11 FRCLB REACTOR COOLS~! LQQP B AVG FLQM .0 INHD 0/ i2 RXT!6 RCPA BRFAKER CAUSE RX TRIP TRiPPED ALRH 13 RXT!7 RCPB BREAKER CAJS RX TRIP TRIPPED ALRH
!4 TSUBTC INCQRr TC SUKOOLED NARGItt 9.4 LMR~ KGF !5 LSGA STH GB~ A t(ARRQM RANGE AVG LEVEL 66.2 HMRH /
fb LS!iS STH Get) B NARRDM RANCE AVG LEVEL 74.1 HALtl /
!7 PSGA STH GE)< A AY~RASE PRcSSURE 0. LALH PSIG 18 PSGB STH GEN AVERAGE PRESSURE 0. LA!H PSIG GENBKR'0 GE(PA! QR QN LINE BREAKER !61372 TRIPPED ALRH GENBKR2 GEtERATGR QN 'tt:- F.":EAKER 9X!372 TRiPPED ALRr, BUS!fA BUS iih SLYLY BRBNER TRIPPED ALRH 22 BUS!!B BUS f1B SL'PPLY BRACER TR!PPED ALRH 23 BUS!2A NOT TERHINATED OM PPCS (7/!9/91) NGT TRIP KL 24 BUS!2B tlOT !cRHINATcD Oh PPCS (7/19/91) NQT TRIP DEL 25 B!1A!2A BUS 1!A TQ 12A TiE BREAKER NOT TRIP ALRH 26 Bf!B!29 BUS 118 TQ 128 T!E BREAKER tiOT TRIP ALRH 27 PCV CQNTAItlHEHT AVERAGE PRESSURE .N GOOD 28 LSUHiPA cQNT!AliNriEHT sUHP A AvERAGE LEAL 31.2 H@@i 29 L09428 SUi~ 8 LE%;~ 8 itlCHrS (TRAIN A) HI6HER iNHB 30 L0943E SLitF' LEVEL 8 ltlCHES (TRAIN 9) HIGH% iNHB 31 L0942D SUP B LEVEL 78 It&~':S (TRAIN A) HI6HER IH)(B 32 L09439 St",P 8 LEVEL 78 ltlCHES (TRAItt B) HIGHER IWE 33 L0942C S&i B LEVE. 113 It(CHES(TRAlti') HIG)irR ALRH 34 L0943C S%' LEVEL 113 INCHES(TRAIN B) HIGfB ALRH 35 L09428 SU.. B ia~! 180 INCHcEs(TRAit, A) L(IER 6009 36 L0943B SU)P 8 LEVrL 180 ItlCH S(TRAIN B) LQ))ER 37 L0942A SL!HP B LEVEL 214 It(CHES(TRAIN A) LONER GOOD 38 LO943A SUNUP B LEViEL 214 It(CHES(TRAIN B) LQMER 6009 39 T0409A RCLA HOT LEG TEHPERATL!)K 191.8 GOOD DEGF 40 T0410A RCLB HOT LEG TEHPERATURcE 191.8 =-GOOD KGF 41 T0450 RCLA COLD LEG TEHPERAT(RE 185.4 DEGF 42 T0451 RCLB COLD LEG TEHPERATm 168.3 6009 KGF 3 TAVGAM!0 RCLA TAVG (THQT/TCQLD MIDE RNG) 188.6 6009 KGF 44 TAVGBMID RCLB TAVG (THQT/TCOLD MIDE RNG) i80.1 6009 KGF 45 LRV PEACTGR VESSEL AVERAGE ! EVEL 81.0 LA!!( X 46 TCCQRE Ei.i INCORE TC AVERA6E TEHP 190.6 600~ KGF 47 FAUXFMA S/6 A TOT4! A!JX FELDMATER FL(I 0. Gl'H 48 FAUXFMB S/6 B TOTA'iJX ~cJNATER FLOM 27. 600D GPH 49 B)(R081 I'iTR AiJ)(ILIARY FEEDMATER PUHP A OFF 50 BKR082 HTR AUXILIARY FEEDMATER PUHiP B ON 51 V3505 AUX FM PUHP STEAH SUPPLY VALVE A CLOSED 52 V3504 AUX FM PUHP STEAN SUPPLY VALVE B CLQcED GOOD
NGV 17> I'7'73 12.'45 R. E. GIt5A SlttULATGR PAGE 2 TPEND GROUP ASSIGNtt>c'T SUttttARY 6ROL'P: EVBT1 PRGCEDLtR":: EPIP 1-5 PLAN'TATUS POINT ID DESCRIPTION VALUE OUAL E, U. 53 FSIA SA.=TY INJECTION LOOP A AV6'FLOW 0. GOOD 8'tt 54 FSIB SAF""TY Itl>3ECTIGN LOOP B AVG FLGtt 232. 6009 PN 55 P2160 SERVICE MATER PUtPS A t>. B HiADER 87. 600D PSIG 56 P2161 SERVICi MATER PUttPS C 1 9 HEADER 86, 6009 PSIG 57 BKR041 SiRVICE MATER PUYrP A ON 600D 58 BKR042 S.:RVICE MATiR PUttP 9 GN GOOD 59 BXR043 SERVICE WATiR PUttP C GN 6009 60 BKR044 SERVICE MATER PUCP 9 ON 6009
NOV 17( 1993 12:46 R. i. GIQtA SIMULATOR TREttD GROUP ASS IGttNEhT SUNM(ARY 6ROUP: EVENT2 PROCEDURE: EPIP 1-5 PLAttT STATUS POINT ID DESCRIPTION E. U. 1 F0619 CQ(('0<cNi COQ'NG LOOP TOTAL FLW 884. LALN GFN 2 LNtS7 REFUELING t(tATBt STORAG" TAttk LVL 27.8 LORN I 3 MS033 33 FOOT L~c N!t!D S~ 3.0 6009 NPH 4 t(t9033 33 FOOT LEVE!. MIND DIRECTIOtt 41. 6009 DEG. 5 WT033 33 FOOT LEVEL TEN'cRATURE 43.1 6009 D:"GF 6 WT250 250 FOOT LEVcii TENPERATIJRE 38.8 6009 IEF 7 NDT2 250 TO 33 FOOT LEYEL DELTA -4,3 6009 DEGF TPJ'REA 8 RO! 1-COttTROL RGONi 8.86136M 6009 NR/HR R02 AREA 2-COtiTAINMEtt7 4.95448%5 HALN NR/HR 10 RO5 APEA 5-SPENT FUEL PIT 3. 19888+04 HALN N/HR
!1 R09 AREA 9-LETDQtt."t Litt"" NGNITOR 3,18053404 HALN NR/HR R34 AREA 34 - AUX BLDG CV SPRAY PtÃP 3.07255+04 HALti NR/HR 13 .R35 APiA 35-PASS SAMPLE PA(M~ 1.09648+00 6009 NR/MR 14 R!OA CGttTA!tlNENT IODINE NOttITOR RiCA 1.02624<07 MENS CPN
!5 Rll CONTAINMENT AIR PAR7ICLLA7E 9.57744+06 HA' R12 COttTAIttMcCIT GAS NONITOR 1.01303+07 fBt6 CPN
!7 R10B PLAUDIT YEttT IODltii tiQNITQR R!OB 1.05014+06 HALN CPN 18 R!3 AUX B'G EXHAUST AIP, PARTICULATE 2. 55932+02 6009 CPN
!9 R!4 AUX PJLG EXIST GAS NNITOR 9.66051+06 HALN CPN 20 R!8 LISJID WASTE DISPOSAL KNITOR 1 04562+03
~ 6009 CPN 21 R19 STEAN GBtERATQR &LOCON DRAIh 1.8972&03 6009 CPN 22 AREA 29-CGttTAIN("LcttT MIGH RAttGE 5.00465~02 HA!!l R/HR 23 R30 ARcA 30-COttTAINN(ENT HIBl RANGE 5.00465+02 HALN R/HR 24 R!5 CQcGB!SER AIR EJECTOR EXHAUST 1.3548&03 G009 PN 25 R!2A5 CY VBtT CHAtt 5-LOW Rk4(GE GAS 6009( KI/CC 26 R12A6 CY VENT CHAL 6-a"EA GAte 2.00000+02 HALt', t8/HR 27 R!2A7 CV YB~! CHAN 7-NID RAttSE 6AS 4.20511-05 6009 KI/CC 28 R12A9 CV VENT CHAh 9+IGH RAttGE 6AS 9.99987M 6009 XI/CC 29 R14A5 PLOtT Vitti CHAtt 5-LQN RANGE GAS 9.98974"03 HALN Kl/CC 30 R!4A7 PLgtT VittT CftAtt 7 NID RANGE GAS 4.42993-01 MA!!1 Xl/CC 31 R!4A'9 P'47 YEtt7 CHAh 9-HIGH RAttGE C+S 4 '2993"01 6009 KI/CC 32 R!5A5 AIR EJECTOR CHAN 5-LN RAtlGE GAS 6.22985-06 6009 XI/CC 33 R15A7 AIR iJECTOR CHAN 7-NID RANG'E GAS 1 '0975"05 GOOD KI/CC 34 R!5A9 AIR EJECTOR CHAtt 9"HI RANGE GAS 1.52999<3 6009 XI/CC 35 R31 AREA 3! S7EAN Llki A (SPING) 2.0000&00 HALN NR/HR 36 R32 AREA 32 STEAM LINc, B (SPIN6) 2.00000+00 HALI! t8/HR 37 CVH CV HYDROGEtt CONCENTRATION .0 G009 /
38 TCVO3 CV BASENENT LiVEL 6FT TENP tt3 65.7 6009 KGF 39 TCY07 CV IttTERNEDIATE LVL 6FT TEMP t!7 64.4 G009 IFGF 40 TCVOB CV INTERMEDIATE LYL 6FT TEMP ttB 64.4 "6009 DE6F 41 TCV09 CV INTFRNEDIATE LVL cFT TEMP tt9 64.4 6009 IFGF 42 TCV10 CV !ttTERNEDIATE LVL 6FT TEMP tt10 64.4 6009 DEGF 43 TCV17 CV OPERATING LEVL 6FT TEtP, 417 63.2 GOOD DEGF
TIme: 'I300 Message: ~E GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM
~ I C << IR Simulated Plant Condi ions: See Attached Sheets
~Massa e: """THIS IS AN EXERCISE""" FOR CONTROLLER USE ONI Y Controller Notes:
- 1) With the leak from Containment isolated, the. Auxiliary Building sump pump is no longer operating at short intervals and the plant vent radiation readings are beginning to decrease significantly.
Actions Ex ected:
- 1) Operators should be performing the applicable actions of E-1.
- 2) TSC should inform the EOF of the closure of MOV-851A and:the decreasing plant vent radiation readings.
- 3) TSC evaluating plant conditions and taking action as required.
- 4) TSC should be checking on the progress of repair teams.
- 5) TSC should be informing the EOF of plant status and actions being taken for plant recovery.
- 6) EOF should be evaluating plant conditions and taking actions as required.
- 7) EOF Dose Assessment should be tracking the release plume and coordinating/recommending protective action recommendations to the Recovery Manager.
- 8) The Recovery Manager, after evaluating the EOF Dose Assessment recommendations, should update protective action recommendations to offsite agencies as required.
- 9) Repair teams should be expediting repairs as conditions permit.
1993 EVALUATED EXERCISE Time: 13GD MAZOR PARAMET ENGINEERED SAFEGUARDS Reactor Shutdown YE NO Hi h Head S.I. Pum s N-31 CPS FI-924 O'PM N-32 CPS FI-925 E2- GPM N-35 ~o8 IA-MP9 1A SERV STBY OOS N-36 AMPS 1B. NSERV STB OS Avg. Nuclear Power Q 1C. INSERV STBY OOS RCS Pressure PSIG BAST Level = PRZR Level CI A RCP RUNNING OPPED Low Head S.I. Pum s B RCP RUNNING 0 D FI-626 D GPM 1A S/G Level 1A. INSERV B 00 RECIRC 1B S/G Level 1B. INSE V S BY 00 ~RECl~C 1A S/G Pressure PSIG RWST Level = ~'.4 1B S/G Pressure PSIG Turbine/Generator NLINE OFFLI Containment S ra Pum s 4 KV Buses NERGIZE /DEENERGIZED FI-931A O GPM I-9 3 1 B~GP 480V Buses DC Batteries Cnmt Pressure Cnmt Sump A Level Cnmt Sump B Level NERGIZE /DEENERGIZED A~SOVOLTS g/ B B~ VOLTS AF O~PSIG FEET 8 /L~ INCHES 1'S F 1A. NaOH SE V RV Tank Level = TB 00 OOS
- Loop Hot Leg OF Containment Recirc Pans e A Loop B Loop B Loop Cold Leg Hot Leg Cold Leg
~2l ZGV.o
~
moe 3. 0F OF QF 1A. 1B. 1C. NS STBY STBY STBY OOS OOS OOS RVLIS 27. 5 1D. INSERV STBY OOS
*CET ~05 '3 F Post Accident Dampers PE CLOSED S/G A Total Aux FW Flow 0 GPM S/G B Total Aux FW Flow 0 GPM Service Rater Pum s 1A. SER STBY OOS DIESEL GENERATORS 1B. SERV STB OOS 1C. NSE V STBY OOS A. UNNIN UNLOADED STBY OOS 1D. NSE STB OOS B. RUN NG UNLO DED OOS A&B Header Pressure @ PSIG TSC RUNNING D BY OOS Security R UNLOADED STB OOS 'om onent Cooli Rater Pum s 1A. NSERV T OOS ENGINEERED SAP DS 1B. NSER STB OOS Surge Tank Level =
Aux. Feedwater Pum s 1A. INSERV OOS Standb Aux. Pee wate Pum s 1B. NSER TB OOS 1C. INSE V B 00 Turb. Driven INS RV B OOS 1D. INSE V B OOS CST Level ~~FEET
*CET = Average oi'elected Core Exit Thermocouples
NGY 17) 1993 13:00 R. i. GINA SltQLATG)" PAGE TREND GROUP ASSIGN)SAT SUNttARY GROS: EVÃt PROrcEDL)oc'PIP 1-5 PLANT STAT)JS POINT ID DEKRIPT ION YALUE E. U. AT)tS ANTICIPATED TRAl(SIEt(T ft/0 SCRANi ASS ALRti 2 RXT RiACTQR TRIP BRiAKER STATUS RX TRIPPED ALRN 3 N31 SWEE RANGE DETECTOR N-31 8.37527+01 6009 CPS tf32 SOLRCi RAttGE DHcCTQR t&32 8.!1894%1 GOOD CPS 5 t)35 INTERNcDIATE RA)tSc DcTECTOR N-35 i.Oi859-ii 6009 Al(P 6 t(36 It(TERNEDIA7i RA)i'Si DE7ECTOR N-36 1.01859-11 6009 7 NP A%RAGE t)UCLEAR PQNER ,00 6009 A%'SIG 8 PRCS RiA"TOR COOLANT SYSTEtt AVG PRESS 2. LEND LPIR PRcSSURIIER AVERAGE LEEK .0 LALN 7 10 FRC A RE@".TOR COOL) '<T LOOP A AVG FLG)f 40.2 INH>> / 11 FRCLB RiACTGR CCCLANT LGQP 8 AVG FLGN ~ 0 INHB /
~
o 4 RXTi6 RCPA BREAKER CAUSE RX TRIP TRIPPED ALRN i ') RXTi7 IV RCPB BREAKER CAUSE RX TRIP TR IPPED ALRN 14 TSUBTC ! t(%RE TC SUBCOGLED NARGIN -54.1 LAL>> IFGF 15 LSGA STH iciN A t'ARROM RANGi AVG LEVEL 66.4 fNRN Ã
)6 LSo8 S7tf Gib 8 NNM)t RA)(6= AVG mW 78.i HALN 7 17 PSGA STN GB) A AVERAGE PRESSURE 2, LALt,'.
PSIG 18 PSaB STt) rD 8 AVERAGE PRESPJRE LA))f PSIG 19 GENBKR! CURATOR Ot( LINc BRiAKER !G!372 TRIPPED ALRN 20 GENBKR2 Gci)IK)tATGR Qtl INE BREAKER 9X1372 7RIPPED ALRN 21 BUSllb BUS 1!A SUPPLY BREAKER TRiPPED ALRN 22 BUS!18 F)!S !18 SUPPLY BREAKcER 7R! PPiD ALRN 23 BUS!2A t(QT TERNlt)ATED Gft PPCS (7/!9/91) t>QT TRIP IFX 24 BUS!28 tST TPt)INTED Oft PPCS (7/!9/91) t87 TRIP DEL 8!1A!2A BUS 1!A TG !2A TIE BREAKER t))Q": TRIP ALRt') 26 8!18128 BUS 1'8 TG 128 T)E Befit'"ER t(DT 78IP O'N 27 PCV CQt() Alt)NB(T ACR/)Gi PPESSU)RE 2.01 Haiti PSIG 28 LSL)NPA CON)Alt<NEcN)T SJt)P A AVERAGc LEYFL 31.2 HEt(6 FEET LO942E SU~ 8 LEYiL 8 INCHES (TRAit( P) HI6HER IN)(B 30 L0943E SLtF 8 LEVEL 8 It)CHES (TRAIti 8) HIS(FR It(HB 3i L09429 SU)~ B LEVEL 78 Iti".HES (TRAIN A) HIGHER INHB
'7'7 L09439 S)J)", 8 L VEL 78 INCHES (TRAItt 8) HISHE rR INN B 33 l.0942C SUNP 8 LEYE'13 It),(ES(TRAIN A) Hlsr)ER ALRtf 34 L0943C S(trP 8 LEVEL 1 i3 It'Cf'cS(TRAIN 8) HIGHER ALRN 35 L0942B SU~ 8 LcVEL 180 INCHcS(TRAItl) A) LG)lER 6009 36 L09438 -").).. 8 LEVci 180 !NCHES(TRAIt( 8) LONER 6009 37 L0942A SU'P . LEVEL 214 INCHES(TRAIN A) LO)!ER 6009 LO943A SURF 8 LEVEL 2!4 INCHES(7RAIN 8) LG'wP KQD 39 T0409A RC)LA HOT LEG TEtPERATURE 216.8 6009 DEGF 40 704!OA RCLB HQT LEG TEtff)ERATUR=" 200.2 -6009 !FGF 41 T0450 RCLA COLD LEG TE)FERATNE 214.8 6009 DE6F 42 RCLB COLD LEG TEE ERATO~ 204.5 6009 IFGF T045.'AVGAMID 43 RCL". TAVG (Tf(07/!COLD f(IDE Rt(S) 215.8 6009 DEGF 44 TAVGB))ID RCLB TAVG (THQT/TCQLD HIDE Rt(6) 202.3 6009 DEGF 45 LRV REA"TOR VEA:.i Aver)AGE LEVEL 27.3 LALti X 46 TCCQRE Ei..: INCQRc TC AVERAGE TENP 303.3 600>> DcGF 47 FAUXFN S/6 A TOTAL AUX F:cDRATER FL(L) 0. GOOD FAUXFWB S/6 8 TOTP'UX FEEMTER FLGr 0. GOOD GPtt BKRO81 NiR A'J.'(ILIARY FEED~ATER PUlP A OFF GOOD 50 BKROS" NTR AUXILIARYFEED)(ATER PU5' GiN 6009 51 V3505 A)JX FN PUNP STEA)i SL)r'PLY VALVE A Ct.OSED GOOD 52 V3504 AUX FW PUNP STEAN SUPPLY VALV 8 CLOSED GOOD
/;$
NOV 17~ 1993 13:M R. E. BIO!A Sll~LATOR PAGE 2 TRBG GROUP ASSIGIENT S'JltNARY 6ROUP: EVENT1 PROCEDURE: EPIP 1"5 PLANT STATUS POINT ID DES"RIPTION VALUE QUAL E. U. 53 FSIA SAFETY IN.'ECTIOlt LOOP A AVG FLOM 0. GOOD GPlt 54 FSIB SALTY IN:ECTION LOOP B AVG FLOW 232. GOOD PN 55 P 160 SERVICE MATER PUllPS A 6 B HEADER 87. 6009 PSIG
'6 P2161 SERVICE WATER PUltPS C 4 D HEADER 86. 6009 PSI6 57 BKR041 SERVICE WATER PUlP A ON 6009 58 BKR042 SERVICE MATER PUhP B ON 6009 59 BKR043 SZVICE Mem PUltP C ON 6009 60 BKR044 SERVICE WATER PurP 9 ON 6009
NGV 17i }993 }'1 ~ 05 R. "". ulNNA SitPJLATGR PA6E 1 TREND GRQU? ASSIGttttiti~i SU"DIARY GROUP: "uVittT2 PROCES}Ri; EP:P }-5 PLAIIT STATUS POI (T 9 DESCRIPTION VALLF E. U. F0619 CWPQt<Et<T COO'NG LOOP TQTAL FLN 6494, 6009 GPM LRMST REFUELING NATE STORAGE TAtR LVL 23.6 LNRII X 3 h'S033 33 FOOT LE(~ MitiD SPED 3.0 GOOD MPH hm33 33 FOOT LEVEi NIND DIRECTIGtt 41. 6009 DEG, NT033 33 FOOT LE(P TEMPERATURi 43.1 6009 DEGF NT250 250 FOOT LE(j~ TEMPERATURu 38.8 6009 DEGF NDT" 250 TO 33 FOOT LEVEL DELTA TEIIP -4.3 6009 DEGF RO} 4REA }-COW( 9 ROQMi 9.44062-02 6009 MR/HR RO2 N ~ o- Gt'TAI"M-N 2.98538<05 NLtt MR/HR 10 RO5 AR":A 5-SPENT FUEL PIT 1 ~ 23027+01 6009 MR/HR R09 AREA 9-LETDOWN LINE MGiNITQR 2.8346&0} G009 MR/HR R34 AREA 34 AUX BLDG CV SPRAY PUtL> 3.42767+01 SFut MR/HR
.'3 R35 AREA 3~PASS oA"(om PANEL 1.09648+00 GOOD N/HR fa5$ R!OA CONTAINi!ENT IODINE MQtiITGR R}CA 9.66051+06 HALtt CPM C ~ 4 Rli CG!(TAItIMEt(T AIR PART ICS.ATE 9.99992+06 HALtt CPM 16 R}2 CQttTAINMENT GAS MONITOR 1.03962+07 HENS CPM !7 R}OB PLANT VEt(T IQDItF. MC>tITOR R!OB 1.0}449+06 NLII CPM 18 R!3 AUK P DG EXHAUST AIP, PARTICULATE 2. 46178+02 6009 CPM !9 P,14 AUt( BLDG E!EXHAUST GAS t(GNITOR 9. 78647+06 HALM CPM 40 R!B LIQUID hASTE .DISPOSAL MONITOR 1.05014+03 6009 CPM 21 R}9 STEAM GENEPATOR Bt ONDGII( DRAIN 1,89725+03 GOOD CPM R29 AREA 29-CGNTAINMEWT Hi& RAVoE 2.99398~02 HALM R/HR 23 R30 AREA 30-CGt)TAINMEtti HI&I RANGE 2,99398+02 HALtt R/HR 24 R15 CGtIDBISER AIR EJECTOR E)(KAUST }.4024}<03 6009 CPM 25 R12A5 CV 'JitiT CHAti'-LON RAt<"='AS 4.20511-05 6009 KI/CC 26 R}2A6 CV VENT Ci'At 6-AREA 6@TtA ".00000+02 HALM %/HR 27 R}?A7 CV VIP. CNtt 7-M!9 RA4'u= GAS 4.20511-05 6009 KI/CC 28 R}289 CV V t'ai CHAtt 9-HIGH RkNGi GAS 9,99987-04 GOOD XI/CC 29 k}4A5 PLklT VEttT Catt 5-LU>> RANG:" uAS 9.98974-03 HALM KI/CC 30 R14A? PL4/Pi VENT CHAN t'iID RANGE GAS 4.42993-01 HALM UCI/CC 31 R}499 PLANT VENT CHAN o-HIGH RANGE 6AS 4.42993-0} 6009 KI/CC f I3 R15A5 AIP, E3ECTOR CHAN 5-LO'A Rk><ui 6AS 6.22985-06 6009 UCI/CC v0 R!5<<7 AIR EJECTOR CHAti 7-MID RANGE CAS 1.80975-05 6009 KI/CC 34 R15A9 AIR EJECTOR CHAN o HI RANGE 6AS }.52999M 6009 XI/CC 35 R31 AREA 3} STEAMi LINE A (SPING) 2 00000>% HM MRIN 3o R32 AREA 32 STEAM LINE 9 (SPING} 2,00000+00 HALt! t8/HR 37 CVH CV HYDRGGEtl CQNCEt(TRAT ION .0 6009 I/
38 TCV03 CV BASEMENT L-"V SFT TBI? <<3 84.4 6009 DEGF 39 TCV07 CV INTERMEDIATE LVi. 6FT TEMP <<7 ~ 92,o 6009 DEGF 40 TCVOB CV ItiTERMEDIATE LVL SFT TBP <<8 93.1 ".6009 DEGF 41 TCVO9 CV '.INTERMEDIATE LVi 6FT 'TEMP <<9 92.9 GOOD DEGF 42 TCV10 CV INTERtfiDIATE LVL hri TEMP <<10 93.1 6009 DEGF 43 TCV!7 CV OPERATING L VL SFT TEMP <<17 101.8 6009 DEGF
Time: 13'I5 Message: 66 GINNA STATION 1SS3 EVALUATED EXERCISE IVIE A E F RM 8 I <<L'R Simulated Plant Conditions: See Attached Sheets ~Massa e: <<" <<THIS IS AN EXERCISE FOR CONTROLLER uSE ONLy Controller Notes: Actions Ex ected:
- 1) Recovery/Re-entry discussions may commence. This should include preliminary discussions about short term and intermediate term concerns, including preliminary designation of the Recovery organization.
- 2) State and counties may also conduct parallel discussions. Recovery/Re-entry interface between TSC/EOF and offsite agencies should be demonstrated as time allows.
1993 EVALUATED EXERCISE Tuse: j3/+ MAZOR PARAMET ENGINEERED SAPEGUARDS Reactor Shutdown YE NO Hi h Head S.I. Pum s N-3.1 CPS FI-924 ~GPM N-32 CPS FI-925 2 'B~ GPM N-35 -/I AMPS lA. RV STBY OOS N-3 6 /.OS-I AMP S 1B. S V STB OS Avg. Nuclear Power 0 1C. INSERV STBY OS RCS Pressure PRZR Level
~PSO IG BAST Level = ~0 A RCP RUNNING TOP Low Head S. . Pum s B RCP RUNNING E FX-626 00 GPM 1A S/G Level 1A NSER ST Y OOS RECIRC 1B. S/G Level ~), I a 1B. INS Level V STBY 00 REC C 1A S/G Pressure PSIG RWST 1B S/G Pressure ~PSIG Containment ra Turbine/Generator E OFFLXNE S Pum s 4 KV Buses NERGI DEENERGIZED FZ-931A 0 GPM 480V Buses ENERGXZE DEENERGXZED FZ-93 1B~GP Batteries A~3VOLTS B f80 VOLTS 1A. NSERV TB 00 DC Cnmt Pressure'~I~PSIG Cnmt Sump A Level FEET 1B.
NaOH S V Tank Level = TB OOS Cnmt Sump B Level (Q~Q.INCHES
" Loop Hot Leg H, 'F Containment Recirc Pans A Loop Cold Leg Pop oF 1A. STB OOS B Loop Hot Leg ~lO +oF 1B. NSER STB OOS B Loop Cold Leg F 1C. NSERV STB OOS RVLIS 3 ~ I 1D. NSERV STBY OOS
- CET 7 oF Post Aces ent Dampers OPEN CLOSED 9/G A Total Aux FW Flow ~GPMC'PM S/G B Total .Aux FW Flow Service Water Pum s 1A R TBY OOS DIESEL GENERATORS 1B. SER STB OS 1C. SER STB OOS A. UNNIN UNLO DED STBY OOS 1D. NSER STB OOS B. RUNNING UNLOADED TSC RUNNING D B OOS OOS A&B Header Pressure ~PSZG Security R UNLOADED TB OOS Com onent Coolin Wate Pum s 1A INSERV STB OOS ENGINEERED S DS 1B. NS STB OOS Aux. Peedwater Pum s Surge Ta evel = ~0 - 4 1A. INSERV STB OOS St ndb Aux. Pe wate Pum s 1B. NSER T Y OOS 1C SE V 00 Turb. Driven INSERV STBY OOS 1D. XNSE V B OOS CST Level ~~e F
- CET = Average of Selected Core Exit Thermocouples
NOV 17r 1993 13'1 R. E. GINA STATOR PAGE 1 TREND GRQ'UP ASSIGt(t(B(T SU4iARY GROUP: EVENT! PROCEDN" EPIP I "5 PLANT STATiJS POlt'IT iD DESCRIPTION YA's" OUAL E. U. ATtlu At(TICIPATED TRAt'SIBIT N/0 SCRAt( ATNS ALN'i 2 RXT REA"TGR TRIP BREAKER STATUS RX TRIPPED ALRt{ 3 N31 SOURCE RANK D""TECTOR N-3! 1.72981+02 GOOD CPS 4 N32 SO(RCE RANGE DcTECTQR 4~32 1.72981+02 6009 CPS 5 N35 It MDIATE RAt(SE DETETQR N-35 1.03276-11 6009 A)P 6 N36 It)T-Rt)EDIATE RANK DETECTOR N 36 1,02330-11 GOOD A."IP 7 NP AVERAGE tNCLEAR PGNER .00 6009 X 8 PRCS REACTOR COOLLY'YSTEt( AVu PRESS 3, LENC PSIG 9 LPlR PRBPJRIlER AViRACc LEVEL ~ 0 LALN X 10 FRC' REACTOR CC@LAltIT LOOP A AYG FLQN 69.9 ItfrfB X 11 FRCLB REACTOR COOLANT LQQP 8 AVG FLN 38.8 INH~ X
!2 RXT!6 RCPA BREAKER CAUci RX TRIP TRIPPED ALR)I 13 RXT17 RCPB BREAI(ER CAUSE RX TRIP TRiPPED ALRN !4 TSUBTC Iti'ZRE TC SUBCGOLED NARuGlN -480.3 LALt DEGF 15 LSGA STH Gcdt A NAIIO'rt RANGi AVG Ls 65.1 HtARII / .'6 LSGB Ski GEN 8 t(ARRO'rt R/N(6c AVu LEVY. 80.1 HAL)I X 17 PS6A STtl Sett A AVERAGE PRcSSURE 0. LALVi PSIG !8 PSGB STt) GEN 8 AVcDAGE PRESSURE 0. LALl( PSIG 19 GENBKRI GchERATGR QN LINE BEAKER 1G1372 TRIPPED ALRII 20 GENBKR2 KteRATOR ON LINE BREAKER 9X!372 TRiPPED ALRt(
21 BUSl!A BUS !!A SPPLY BPrEAKER TRIPPED ALRti 22 BUS!18 BUS 118 SUPPLY BRFAKER TRIPPED ALRN 23 BUSI2A NGT TERNINATED Oti PPCS (7/19/91) NQT TP,IP DiL 24 BUS!28 AT TERNINATED Qt( PPCS (7/'19/91) t(0; TRIP Dii 25 811A!2A BUS I!A TO IM TiE BREAKER tl0"; TRIP ALRII 26 8118!28 BUS 118 TO 128 Tli B.""=AKER tIGT TRIP ALR)I 27 PCV COt(TAINt(Et(T AVERAGc PRESSURE 3.15 HNRI( PSIG 28 LSNPA CONTiAINNENT SU'P A AVERAGE LEYEL 31.2 HENS 29 L094 c SUPP 8 Li()EL 8 It(CrtcS (TRAIN A) HIGF&c, INHB 30 L09438 SUt.. 8 IEIsc' INCHES (TRAit( 8) HIGHcCc It(HB 3! L0942D SUtP 8 'YrL 78 INCHcS (TRAIN A) HIGHER INHB 32 L0943D SU~ 8 Lied 78 itiCPcS (TRAIt) 8) HIGHS It(HB 33 L0942C SU!(r' LEVEL 113 It(CHcS(TRAIN A) HIGHS ALRH 34 L0943C SUtP 8 LEY"L 113 It(CHES(TRAlt( 8) HIGHcR ALRt( 35 L09428 SUli' LEVEL 180 It)CHES(TRAIN A) LONER GOOD 36 L09438 SN, 8 LcYEL 180 INCHciS(TRAIt, 8) LONiR 6009 37 L0942A SU,"P 8 LEVEL 214 It(CHiS(TRAIN A) LONER 6009 38 L0943A SUN' I EYEL 214 ItZHES(TRAIN B) LVAER 6009 39 T0409A RCLA HQT LEG TEt(PERATUic 213.1 GOOD DEGc 40 T04!OA RH9 HOT LEG TEt(PERATiJRci 210.4 ".6009 DEGF 4! T0450 RCLA COLD LEG TBiPERATNE 209.9 6009 DiGF 42 T0451 R"LB COLD LicG TE))PERATLRE 209.4 6009 DEGF 43 TAVGAWID RCLA TAVG (THOT/TCQLD WIDE RIIG) 211.5 6009 DEGF 44 TAVGBNI9 RCLB TAVG (THOT/TCOLD NIDE RNG) 209.9 DEGF 45 LRV RiA.TGR VESSEL AYrRAGc LEVEL 39.1 / 46 TCCQRi El.! It<CORE TC AYB(AGE TEt(P 625.7 gtRe DEGF 47 FAUXFWA S/6 A TOTAL PJX FEEDS'ATiR FLG'A 0 ~ 6009 GPt( 48 FAUXFMB S/G 8 TOTAL AUX FHGNATER FLOÃ 0. G009 GPtt 49 BKR081 t)TR AUXILIARYFEEPAATER PUN.-" A Gr; 6009 50 BKR082 i",TR AUXILIARYFc D(IATER PUIIP 8 Gtt G009 51 V3505 AiJX FM PU)IP STEA)I SUPPLY VALVE A CLOSED G009 52 V3504 AUX FN PU)IP STEA)) SL'PPLY VALVi 8 CLOSED G009
'j'/~3
NOV 17'993 13l15 R. E. GINtA SNiLATOR PAGE 2 TREtG GROUP ASSIGtttHT SL4:"4RY 6ROU,: EVit/Tl ROCEOURi; EPIP 1"5 PLAt,i STATUS 9""SCRIPT POINT IB IOti'ALL~'UAL E. U. 53 FSIA SAF"=TY INiECTIOt> ~ OOP A AVG FLOP 6009 PN 54 FSIR SAFETY INJECTIOW LOOP B AVG FLOP 232. 6009 Ptt 55 P2160 SERVICE tNTER PUTS A ~~ B HEABER 87. 6009 PSIG 56 P2161 SERVICE %TER PUttPS C 5 9 HEA9ER 86. 6009 PSIG 57 BhR041 SERVICE LATER PUtlP A ON 6009 58 ~""P'ICE WATER PUt'~ B 59 BKR042 BKR043 S~D'ICE MATE PUP. C CA>'. ON Oli 6009 6009 60 MR044 EH)ICE STER PUt!P D 6009
E. iGiit'iA SINN AT">
~
tQV !7i 199a !do Xv
~
P,. PAGE 1 TREt i GRGU? ASSIGNIQT SUtt"~ARY GROU',". EV tiT'> PRQFDURE: EPIP !-5 -"LANT STATUS POINT !9 DESCRIPTiQN VALU= QUAL E. U. 1 F0619 COtPONENT COOLING LOOP TOTAL FLW 6493. GOOD 6% LRMST Rt""Lt-"i INB MAT% STORAGE TANK LVL 22.3 LMRti i/ 3 MS033 33 FOOT LEVEL M!ND SPEK 3.1 6009 AH 4 MD033 33 FOOT LEVP MitS DIRECTitON 41. 6009 IFG. 5 MT033 33 FOOT LEVEL TEtt?ERATLIRE 43.! 6009 IFBF 6 MT250 250 ;GQT LEV" TEi.FERATURE 38.8 6009 IFGF 7 MDT2 230 TO 33 FOQ LEVEL DELTA TEN'R=~
-4.3 6009 DEBF 8 Rei !-CGNTRP RDO."i 8.56051-02 6009 t(R/HR RO. A.<<".=A 2-COhTAlht'iEtiT 3.05492+05 HALtt tS/HR 10 R05 AFEA ~-SPEtiT U:.L P.'T 1.31069<01 6009 tS/HR t~ ~S R09 t5E". 9 LETDQMN LltvE t'QiNITGR 3.00262+01 6009 tS/HR R34 A>J".-" 3g - AUy BLDG CV &RA'/ RJYP 1.25!?~I HMRN tg/HR 13 R35 A.'tEA 3H'ASS SA,"t?LE PALP 1.09648+(I GOOD tS/HR R!OA CONTAItNEt)i 1091tiE tati'ITOR R!OA 1.00432+07 HENS CPt!
P.l 1 CGtfiAIN KtiT AIR PARTICULATE ; 78647+06 HA' CPt! 16 R12 CLtNTAIhNEt(T GAS ttDtiITOR '.03068407 HEti6 CPtt t/ R!OB PLA!IT Wc, iT IODIti.: t!QNITQR R!OB 1.02772406 HALL! CPA 18= R13 AU! B DG FÃHAUS. AiP. PARTICULATE ,46178+02 6009 CPt!
!9 R!4 AUi Bt DG EXHiiST GAS ttMTQP, 5.43249te! GQQD CPN 20 R!8 l IBID MASTE DIS?QSA'QNITOR 1.01888+03 GOOD CPt!
r> 1 R!9 "-t="" GENERATOR E'0'~JR! DRAIh 1.9'89 2+03 6009 CPtt 22 P io -'.,=.-'. 2"i-CG.(TAIt<" t"! HIGH RPi.~i= 2.99398+02 HALE( R/HR 23 P~P AR=-'0-CQiiTAiti.BiTHIGH RANK 2.99398+02 HALtt R/HR R'15 CONiDEtS~m AIR EJECTOR EXHAUST 1.39035403 6009 CPN 25 R!2A CV VENT CHAN ~LO'n RANK GAS 4.20511-05 6009 Xl/CC Q~ Ri~&6 "V VEN:. CHAN a-AREA GA~a@ 1.00000I02 HAU', tS/HR 27 R!2A? 4.20511-05 GMD UCI/CC R!2A9 t V V"" C!.At'P GH PAt " GA< 9.99987-04 BGQD KI/CC R!4."5 PLk!T VEt~t CHAti =- GA RANGE GAS 2.3099!~ 6009 KI/CC 30 R!4A7 "'20996-03 6009 KI/CC 3t R!4A9 .P="'!'EtiT CH~i 9-H "-".'. RP3:--" GAS 2.20996-03 KI/CC VC R!5A5 AiR E:ECTOR CHAl'='GMRAt(G" 6AS 6.22985-06 6009 KI/CC v'4 R15A? lc.. 3EL'TQR C'".:AN 7-tilD RA%-" GAS ii80975-05 6009 UCI/CC 34 R!5A9 AIR EJECTOR CHttN 9-HI R46E GAS !.52999-03 6009 KI/CC 33 RS! k>>-"='. 3! STEA" 'NE A (SPIt<6! 1.00000+00 HALH tS/HR 36 R32 ~."~ 32 STER"i 't(E B (SPltiB! 1 00000<M tS/HR 3 i CVtf CV %&QBEN COtiCEhTRATION 6009 X 38 TCV03 CV BASEV~NT LEV= 6~1 TEN? C 7'?.5 GOOD DEGF 30 TCVO? CV INT""RiiEDIATE LV-'FT TP.". 4? 99.7 GOOD DER 40 TCVOS CV ItitERt'iEDIATE LV 6FT FJP 48 99.7 %009 DEGF 45 TCVO9 C" Il~trFN:DIATE LV'FT TEttP !!9 99.? 6009 DEBF TCV!0 CV It!TERt(ED!ATE LV'FT TEt(P tt!0 99.7 GOOD DEG!. 43 TCV!7 CV QPERATINS i":t>> 6F TEtP I!7 120.0 6009 DEGF
Time: 1330 Message: 67 GINNA STATION 1993 EVALUATED EXER ISE MESSAGE FORM Fi I <<C << IR Simulated Plant Conditions: See Attached Sheets Messacee: <<~ "THIS IS AN EXERCISE>>"" FOR CONTROLLER USE ONLY Controller Notes:
- 1) Accident evaluation and response continues.
Actions Ex ected:
- 1) Recovery/Re-entry and declassification discussions should commence per the guidance provided in EPIP 3-4, "Emergency Declassification and Recovery".
Discussions should include but not be limited to the following: A) Preliminary discussions between the EOF and the TSC on the following:
'hort Term plant concerns such as;
- 1. Cool down of the plant
- 2. Repair and return to service of 480 volt Bus 14 transformer.
- 3. Repair and return to service of the "B" RHR pump,
- 4. Repair and return to service of the "B" Sl pump.
- 5. Repair and return to service of the "C" Sl pump.
- 6. Repair and return to service of the Bus 14-16 tie breaker.
'ntermediate term plant concerns such as:
- 1. Core damage assessment.
- 2. Clean-up of Auxiliary Building.
- 3. Clean-up of water in containment.
- 4. Long-term core cooling.
- 5. Radiological release calculations and evaluation.
-B). Preliminary designation of the recovery organization.
C). State and counties may also conduct parallel recovery/re-entry discussions,
- 2) Recovery/Re-entry interface between the EOF/TSC and offsite agencies should be demonstrated as time allows.
1993 EVALUATED EXERCISE Time: ~~0 MAZOR PARAMET ENG1NEERED SAPEGUARDS Reactor Shutdown ~Y(YES NO Hi h Head S.I. Pum s N-31 CPS FI-924 GPM N-32 0 CPS FI-925 0 GPM N-35 I~0-I AMPS 1A. NSER STBY OOS N-36 /~~AMPS 1B. INS RV STBY 0 Avg. Nuclear Power 1C. I SERV STBY OOS RCS Pressure PSIG BAST Level = PRZR Level A RCP RUNNING OPPED Low Head S.I. Pum s B RCP RUNNING STOPPE FI-626 GPM 1A S/G Level 1A. NSER ST OOS RECIRC 1B S/G Level 1B. NSERV STBY 0 RECI C 1A S/G Pressure C'SIG RWST Level = 1B S/G Pressure 0 PSIG Turbine/Generator ONLINE FFLI Containment. S ra Pum s 4 KV Buses NERGIZE /D ENERGIZED FZ-931A C> GPM 480V Buses RGIZED/DEENERGIZED FI-93 1B~GP DC Batteries A~VOLTS BQgVOLTS 1A. NSERV TB OOS Cnmt Pressure ~e'j 2 PSIG 1B. NS RV STB OOS Cnmt Sump A Level Cnmt Sump B Level
~~FEET p~~<LINCHES NaOH Tank Level = ~%
A Loop Hot Leg ~IG 7 OF Containment Recirc Pans A Loop Cold Leg !'ok F 1A. NSER STBY OOS B Loop Hot Leg ~~a'7 DF 1B. NSER STBY OOS B Loop Cold Leg 0F 1C. NSERV STBY OOS RVLIS 1D. SERV STBY OOS
- CET OWAQ OF Post Ace> ent Dampers PE CLOSED S/G A Total Aux FW Flow GPM S/G B Total Aux FW Flow D GPM Service Rater Pum s 1A. SER S BY OOS DIESEL GENERATORS 1B. E S B OOS 1C. SERV STBY OOS A. NING UNLOADED STBY OOS 1D. NSER STBY OOS B. RUNNING UNLO ED TB OOS TSC RUNNING D TB OOS A&B Header Pressure ~PSZG Security RUNN UNLOADED TB OOS Com onent Coolin Rater Pum s 1A. INSERV B OOS ENGINEERED 8 DS 1B. NSER STBY OOS Surge Tank Level =
Aux. Peedwater Pum s 1A. INSERV OOS ~ Standb Aux. Reedwate Pum s 1B. INSERV TB OOS 1C. INSE V 00 Turb. Driven INSERV TB OOS 1D. NS V B OOS CST Level FEET
- CET = Average of Selected Core Exit Thermocouples
17~ 1993 13:31 P.. =. GIM4 SI""GATOR PAGE 1 TREND GRG!!;" AcSSIGMttB)T SXNRY GRQ"?: EVEMTl PRGCcDU((=: EPIP I "5 PLANT STATUS POINT ID DcS"RI PTIGtt VALUE <K)AL i. U. 1 ATMS AMTICIPATED TRANSIENT 4/0 SCRAt( AT)tS ALRtt 2 RXT REACTOR TRIP BR""AKER STATUS RX TRIPPED ALR)t 3 N31 SG(RCE RAt&e DTECTOR N 31 l. 36301+02 6009 CPS 4 tG2 SGURCi RANGE 0""TECTC~. )(~32 1.40119402 6009 CPS 5 t(35 It(T"-RADIATE RANai 0:"TEiTOR N-35 1.02801"11 6009 Al(P 6 t(36 ltfFRNEDIATE RN(ci DETECTOR M-35 1.02330-11 GOOD NP 7 HP AVERAGc NUCLEAR POWDER .00 6009 / 8 PRCS REACTOR LGOLAN SYSTEtt AVG PRFSS 4. LENG PSIG 9 LPIR PRESSURIZER AViRAGE LEWD. .0 LALtt / s'0 FRCLA REA TOR COOLANT LQQP A AVG FLSi .6 INHS 11 FRCLB REACTOR CGiLA!)T LGGP 8 AVG FLG)t ~ 0 INHS 7
.'2 RXT16 RCPA BREAKER CAUSE RX TRIP TRIPPED A(.Rtt 13 RXT17 RCPB BREAKER CAJSE RX TRIP TRIPPED ALRt(
14 TSUBTC It(OGRE TC SUB':03LED NRCIN -169.4 LAL~ DEGF 15 LSGA STV( GEtl( A NA)mOW RAt<GE AVG LE'l(~r 64.3 Ht((Rti I/ 16 LSGB STN GEM 8 t(ARRQ~ RANCE AV6 LEVEL 82.1 HALM K
'7 PSM STtt 6EN A AVEPA"" PPZSSiJRE 0. LALtt PSIG 18 PS68 STN GcC( 8 AVERAGE PRESc()R"= 0. LALtt PSIG 19 GENBKR'i Gc(ORATOR QN LitK B."",EAKER 161372 TRIPPED ALRtt 20 GENBKR2 GitZRATOR GM 'tr= SPEAKER 9r1372 TRIPPED ALRN 21 BUS11A B(JS 11A St)PPLY BF"-VR, TRiPPED ALR)t BUS118 B(JS 118 SUPPLY BREA(~"P TRIPPFD ALRtt 23 BUS!2A t(GT TERttlt(ATED Ou PfiS (7/!9/91) t(0! TRIP DEL 24 BUS128 t(()T TERV(lt(ATED OM PPCS (7/19/91) NOT TRIP DEL 25 811A12A BUS llA TO 12A Tii BREClER t<GT TRIP ALRtt 26 8118129 BL'S 118 TG 128 Tli BREAKER NG! TPIP ALR(t 27 PCV CGWTAIN!(Et(T AVERt(GE PRESSURE 3. 62 H)tR)t PSIG 28 LSU,'(PA CGt<TAINNEt(T SiJl' AVERAGE 1.LVEL 31.2 HENS FEET 29 L0942E SU(&, 8 LEVEL 8 IN'ES (TRAltt A) HI6)& INHS 30 L0943E SUtt 8 LE4cL 8 ItlCHES (TRAlt( 8) HI6HEP, INHS 31 L09429 SU~(' LEVEL 78 ItlCHES (TRAItt A) H16HER It(HS 32 L09439 SU P 8!LEVEL 78 !tG-"S (TRAIN 8) HIGHER It<HS 33 L0942C SU~ 8 LEVP 113 It<;"MES<TRAIN A) HI6H":P. INH9 34 L0943C SU('P 8 LB~J. 113 INCHES(TRAIt( 8) HI6H:R 'NHS 35 L09429 SUP 8 LBrrL 180 It("'.HES{TRAItt A) HIGH ALRt(
36 L09438 SU~i. 8 'V"'80 It)CHES(TRAItt 8) HIGHER A'tt 37 L0942A SUi~ 8 LEVEL 214 INCHES(TRAItl A) LG((ER 6009 38 L0943A SUN' LEVEL 214 It(CHES(TRAIt( 8) LO)tiR 6009 39 T0409A RCLA HQT LEG TEt(PER4TU(RE 210 7 6009 KGF 40 T0410A RCiB HOT LEG TEttPERATU~ 210.7 %009 DEGF 41 T0450 RCLA COLD LEG TEt(PERATNE 214.5 6009 DE6F 42 T 0451 RC( 8 CG' LEG TE)(PERATNE 212.9 6009 DEGF 43 TAVGA))ID RCLA TAVG <THGT/TCQLD WIDE Rt(6) 212.3 6009 D"6F 44 TAVGBWI9 RCZ TAVG (TttOT/TCQ' WIDE R)Pi:) 211.9 6009 DEGF 45 LRV REA"TGR VESSEL AVERAGE 'V="L 34.7 LALtt 46 TCCORE El. 1 INCORE T" AVERAGi Tir,'P 305.6 600> D='GF 47 FAUXF(((( S/6 A TOTAL AUX FERA;"!TER FLG'( 0. 6009 GP(t 48 FAUXFWB S/6 8:OTAL A'JX FEED)(ATER F'N 0. 6009 GPtt 49 BKR081 gR AUXILIARY FEcPAATER PUV(P A OFF 6009 50 BKRO82 t(TR AUXILIARYFEEDS'ATER PUt'. 9 OFF 6009 51 V3505 A(JX R! PUt(J'TEA)l SU-EELY VA'c A CLOSED 6009 52 V3504 A!J)'FR PUlP STEAtl S('rPLY VALV"" 8 CLOS"9 6009
t<OV 17~ 1993:13:3.: . R. E. Sly'A SIN&TOR PAGE 2 TRE!6 GROUP ASSIGNt~ctPi S3t'NARY GROUP.'VENT1 PRO."EDURE: EPIP 1-5 PLANT STAPJS POPIT iD DESCRIPT VALUE QUAL E. U. IGI'~cY 53 FSIA INJECTION LOOP A AV6 FLOW 0. 6000 SPY 54 FSIB SA,HY ItbcCTIOM LOOP 8 AVG FLO'A 408. GOOD 6. X 55 P2150 SERVICE WATER PUtfPS A h B HEAD.R 87, 6000 PSIG 56 P2161 SERVICE WATER PUtrPS C 5 D HEADER 86. 6009 PSIG 57 BKR041 ScRVICE WATER PLttP A 0'< 6009 58 BYR042 SERVICE MATER PUtlP B Oh'N GOOD 59 IIR043 SINCE WATER PU5' 6000 60 BKR044 SERVICE WATER PU'P 8 ON 6000
NQV 17 !993 }3'34 R. E. Glt.".}A SIMULATOR PAGE 1 Toto RiLtP ASSIGNMENT
SUMMARY
GROUP: EVENT2 ; RQCEDURE'P'IP 1-5 PLLT STATUS POINT ID DESCRIPT IOt>> IIL E. U. 1 F0619 COt>>.GCNT COQ'NG LOOP TOTAL FLW 6493. 6009 2 LRNST R>JELIt>>G NATtER STORAGE TAC LVL 20.8 NRN 3 NS033 33 FOOT LEVEL }tits SPED 3.0 G009 MPH N033 33 FOOT LEVB HIND DIKCTIOt>>i 41. 6009 DEG, 5 MT033 33 FQQT LEVEL TEMPtERATtJRE 43.1 GOOD DEGF 6 MT250 250 FQQT LE4~ TEMPERATURE 38.8 6009 DEGF 7 ttDT2 250 TO 33 FQQT LEVFL DELTA TEMP -4.3 6009 DEGF 8 R01 AREA }-COttTRO: ROOM>> 9. }72~ 6009 t8/HR R02 AREA 2-CONTAINt'i NT 3,05492405 HAttt. 18/HR 10 R05 AREA 5-SPEt>>T FUEL PIT 6.2733bi00 6009 t8/HR 1} R09 AR""4 9-LETDQ}t!>> LINE MQti'ITOR 2.93427+0} GOOD MR/HR R34 AREA 34
- AUX BtLDG CV SPRAY PUYP 1.00000+00 6009 t8/HR f3 R35 AREA 35"PASS SAMPLE PANEL }.09648+00 GQ09 t8/HR 14 R}OA CONTiAItltEii IODIt>>E %!>>ITOR R}OA 1.00432+07 HEt!6 CPM t5 R}1 CQi%'Aih~iB>>T AIP. PART ICV ATE 9.78647~06 Htu CPM 16 R!2 COttTAINMEtti GAS MONITOR 1.04864+07 HENS CPM ! 7 R}0B PLANT VENT IODINE tiONITOR R}09 }.02772+06 HAttt CPM 18 Rf3 AtJX BL96 EXHAUtST Afl? PARTICULATE 2.4}963~02 6009 M 19 R}4 AUX BLDG EXHAUST GAS MONITOR 5.599}7+0} 6009 CPM 20 Rle LIKIID HASTE DISPOSA'NITOR 1.01012+03 GOOD CPM R}9 STF>>M GENERATOR Fi KM DRAIN }.98952403 6009 VN R29 AR="A 29-CONTAIttMit}T HIS RAiNGE 2.99398~02 HALI! R/HR 23 R30 K.A 30-COttTAIttMEt>>T HIGtl RANGE 2.99398+02 HALM R/HR 24 R!5 COND NSER AIR EJECTOR EXHAUST }.39035+03 6009 CPM R}2A5 CV VEttT CHAt>> MO~ RANC-': GAS 4.205}}-05 GOOD XI/CC 26 R!2Ab CV VEltT CHAt'"AREA GAi.~A 2.00000~00 GOOD MR/}8 27 R12A7 CY VENT CttA'>> 7-MID Rt'NGE GAS 4,205f}-05 6009 KI/CC 28 R}2A9 CV VENT CHAt>> 9+IGH RANGE GAS 9.99987-04 6009 XI/CC 29 P.}4A5 PLk>>T VENT Ctf-"ttt 5-LOW RANGE GAS 2.3099}-06 GOOD XI/CC 30 R}4A7 PLY@>> Vaa'HAtl 7-MID RANGE GAS =".20996-03 6009 XI/CC 31 R}4A9'!
PLA'>>ti VENT CHAN 9-HIGH MGE GAS 2.20996-03 6009 XI/CC 32 5A5 AIR tECTQR CPA~>>>> 5-LON RANGE GAS 6.22985-06 GOOD XI/CC 33 R}5A7 AIR Ei"=CTOR CHAN 7-t'>>ID RAt>>iGE CAS 1.80975-05 6009 KI/CC 34 R15A9 AIR EJECTOR CHk'>> 9-HI RAttGE GAS 1.52999-03 GOOD XI/CC 35 R3! AK>> 3.'TEAMi LINE A (P'It>>~} 3.61977-03 6009 t8/HR 36 R32 ORFA 32 STEAMi Litt"" 9 <SPIN5) 3.61997-03 GOOD MR/HR 37 CVH V HYDRAE!< K4CEHTRATION .0 6009 / 38 TCV03 CV BASEMEt!T LEVE-'FT TEMP!t3 94.6 6009 DEGF 39 TCV07 CV It>>TERMEDIATE LYL oFT TEMP tt7 107.0 GQQD DEGF 40 TCV08 CV It}TERMEDIATE LVL 6FT TEMP tte 106.7 '4009 IFEF 41 CV ItiTERMEDIATE LVL 6FT TEMP Ng 107.0 6009 DEGF TCV}0 CV IttT~RM"DIAt" 'L 6 T TEM~ tt}0 106.7 6009 DEGF 43 TCV}7 CV OPERATIt!6 L-"Y" 6FT TEMP <<}7 119.0 GOOD DEGF
Time: ~134 Message: 68 GINNA STATION 199 EVALUATED EXERCl E MESSAGE FORM ~f:R C <<iii Simulated Plant Conditions: See Attached Sheets ~Massa e; "<< "THIS IS AN EXERCISE>>"" FOR CONTROLLER USE ONLY Controller Notes:
- 1) Accident evaluation and response continues.
Actions Ex ected:
- 1) RecoveryiRe-entry and declassification discussions should commence per the guidance provided in EPIP 3-4, "Emergency Declassification and Recovery".
Discussions should include but not be limited to the following: A) Preliminary discussions between the EOF and the TSC on the following:
'hort Term plant concerns such as:
- 1. Cool down of the plant
- 2. Repair and return to service of 480 volt Bus 14 transformer.
- 3. Repair and return to service of the "B" RHR pump.
- 4. Repair and return to service of the "B" Sl pump.
- 5. Repair and return to service of the "C" Sl pump.
- 6. Repair and return to service of the Bus 14-16 tie breaker.
'ntermediate term plant concerns such as:
- 1. Core damage assessment.
- 2. Clean-up of Auxiliary Building.
- 3. Clean-up of water in containment.
- 4. Long-term core cooling.
- 5. Radiological release calculations and evaluation.
B). Preliminary designation of the recovery organization. C). State and counties may also conduct parallel recovery/re-entry discussions.
- 2) Recovery/Re-entry interface between the EOF/TSC and offsite agencies should be demonstrated as time allows.
1993 EVALUATED EXERCISE PXDoe: IB~< MAZOR PARAMET ENGINEERED SAPEGUARDS Reactor Shutdown ES NO Hi h Head S.I. Pum s N-31 CPS FX-924 FI-925
~GPM
~>~ GPM N-32 CPS N-35 ~WAMPS 1A. ER STBY OOS N-36 AMPS 1B. INSERV STBY 0 Avg. Nuclear power Ql 1C. INS RV STBY 00 RCS Pressure ~PSXG BAST Level = /O PRZR Level C)
A RCP RUNNXNG TOPPED Low Head 8.I. Pum s B RCP RUNNING STOPPED FX-626 OO GPM 1A S/G Level 1A. SER STBY OOS RECIRC 1B S/G Level ~SS 1B. NSERV STBY 0 RECIRC 1A S/G Pressure 0 PSIG RWST Level = 1B S/G Pressure XX PSXG Turbine/Generator ONLINE/ FFLIN Containment 8 ra Pum s 4 KV Buses GIZ /DEENERGIZED FX-931A GPM 480V Buses ZE /DEENERGIZED FX-931B & GPM DC Batteries A79O VOLTS B~3D VOLTS 1A. NSE V 00 Cnmt Pressure Q~~ PSIG 1B. INSERV B OOS Cnmt Sump A Level B Level
~r~ FEET NaOH Tank Level =
Cnmt
" LoopSump gt INCHES Hot Leg I 0F Recirc Fans
~4'ontainment A Loop Cold Leg ~Zi O oF 1A. SER STBY OOS B Loop Hot Leg NQ=2 'F 1B NSER STBY OOS B Loop Cold Leg RVLIS
~(~~~DO
'F 4
1C. 1D. NSERV S BY OOS NSERV STBY OOS
- CET ~DXSoF, Post Aces ent Dampers PE CLOSED S/G A Total Aux FW Flow O GPM S/G B Total Aux FW Flow C'PM Service Water Pum s 1A. NSER STBY OOS DIESEL GENERATORS 1B. NSER STBY OOS A.
B. RUNNIN UNLOADED STBY OOS RUNNING UNLO DED TB OOS 1'ER 1C. ER STBY OOS STBY OOS A&B Header Pressure PSIG TSC RUNNING D OOS Security RUNN UNLOADED TB OOS Com onent Coolin Water Pum s 1A. NSERV OOS ENGINEERED S DS 1B. E STBY OOS Aux. Peedwater Pum s Surge Tank Level = ~O 1A. INSERV TB OOS Standb Aux. Feedwater Pum s 1B. INSERV TB OOS 1C. NSE V 00 Turb. Driven INSERV B OOS 1D. INSE V S OOS CST Level ~~~FEET
- CET = Average of Selected Core Exit Thermocouples
t(OV 17i 1993 13:4'. i.. GINNA Sit)ULATGR PAGE 1 TREND GROUP ASSIGNt(it<'T S<JN(ARY GR'<<JP'VE(P; PRQ(;ED<! -'P!P ]-5 PLANT POINT ID DEKRIPTIGtl VA'i QUAL E, U. AT% At(TICIPATED TRAllSIEt<< W/0 SCRAl( ATWS ALR)) 2 RXT REA-TOR TRIP BRFAKER STATUS RX TRIPPED ALR)< 3 N31 SOKE RAt(Gic 0="TECTGR N-31 1.2808&02 6009 CPS 4 tG2 SOURCE RAti<GE DcTECTOR K-32 1.33045+02 GQQD CPS 5 N35 It(TERt(EDIATE RAt(K Dc~TOR N-35 1.02801-11 6009 Al(P 6 N36 It(TER<"iciDIATE RANK DETc"TOR N"36 1,02330-11 GOOD At(P 7 NP AVcRAGE NUCLEAR POWiR .00 GOOD 8 PRCS l?cA"=TOR COOLA!(T SYSTB1 AVG PRESS 3. LENG PSIG 9 LPM PRESURIIER AVERAGE LEVEL ,0 LALt( / 10 FRCLA REA".TGR COOLANT LOOP A AVG FLOW 75.3 INH>> / 11 FRC' REACTOR CGGLNT LOOP 8 AVG FLCW 43.1 INHD 7,
!>>z ~ 4 RXT!6 RCPA BREAKER CAiJ:.E RX TRIP TRIPPED ALRt(
13 RXT17 RCPB BREAKER CAU:.i RX TRIP TRIPPED A<<( 14 TSUBTC iTC It<'CORc SUB"OQLcD t(felt( -785.6 LAL>> 9-"GF LSGA STtr CEN A t(ARROW RAhGE AVG LEVE 65.6 H)<$( 0/ 16 LSGB STN GEN 8 NAMOW RANci AVG LEE. 84.3 H(ui /
!7 PSGA Siti GB) A AVcRAGE PRESS<JRE 0. LALN PSI6 18 PSGB Tti Cit( 8 A%RAG: PRESSURE 0. LALt( PSIG 19 GENEKR! GitKRATGR Ot( 't(i BREAKER !61372 TRIPPED AL(I 20 GEt(BKR2 Git.-"RATOR GN 'NE BREAKER 9K137 TRIPPED ALNi 21 BUS11A BL'6 11A SL'PPLY BREAKER TRIPPED ALRtt BUS!18 BUS !'8 SUPPLY 8<<cAKER TRIPPED ALRt',
23 BUS!2A tiOT TEPJ(It(AT% 0)' PCS (7/19/91) tiOT TRIP DEL 24 BUS!28 t(OT TERt(lt!ATED Qti PFCS (7/'.9/91) NO! TRIP DEL 811A12A BUS 1!A TO 12A T!i BREAKER t>OT TRIP ALR)( 26 8!18128 8<J." !!8 TG 128 Tii BREAKER hO! TRIP ALRl', 27 PCV CONT<AIN.":ENT AVE!?AGE FRFSSURc 3. 17 HWRN PSIG 28 LSU:"lPA CGN AINt(ct<T SU<"<c' AViRA6c LEVcL 31.2 HENG FKT
')9 l.0942E SU~<- 8 LEViL 8 ItiCHES (TRAIN A) H!GHEP, INHD 30 L0943E SL<<~ 8 l cVEL 8 INCHES (TRAIN 8) LOITER HIGHER It(HD 31 L09429 SUtP 8 LE% 78 It(C<<CS (TRAIN A) HIGHER INHD 32 L09439 SL<~t' LiVEL 78 INCHES (TRAIN 8) HIGHER INHD 33 L0942C SUiP 8 LEVEL 113 iti~HcS(TRAIN A) HI6HEF. ALRt(
34 L0943C SU $ 8 LEVEL 113 IttCt S(TRAIt( 8) HIG)<=P, 'LRt( 35 L09428 SU~ 8 LEVFL 180 INCh"S(TRAIN A) LOWER 6009 36 L09438 5<JAP 8 LEVcL 180 it)DES(TRAIt( 8) LOWER 6009 37 L0942A S<Ji'P 8 LEVEL 214 It(CHES(TRAIN A) LO)(if? 6009 38 L0943A =Ut 8 LE<rcL ~14 IN'HicS(TRAIN 8) 6009 39 T0409A RCLA HQT LEG TENFERATU+= 210.4 6009 DEGF 40 T0410A RCLB hOT LEG TEtlPERATCmc 210.7 %009 DEGF T0450 RC< A COLD LEG TEt!PERATLRE 215.0 6009 DEGF 42 T0451 RCLB COLD LEG TctPERATLRE 204.5 6009 DEGF 43 TAVGAWIDi BC<LA TAVG (Ttr3T/TCO< 9 HILii RtK) 212.7 GXD DECF 44 TAVGBWID RCL". TAVG (THQT/!CO:9 WIDE RNG) 207.6 GQQD DcGF 45 LRV REACTOR VESSc: AVERAGE 'VEL 39.0 LALt( 46 TCCORE E' It(CO""= TC AVERAG>> Tit(P 802.3 HAL>> DEGc 47 FAUXFWA S/6 A:OTA" AUX FEEL~<AT='R FLGI( 0. G009 GPN 48 FAUXFMD S/6 8 TOTA'UX Fc>>DWATER FLOW 0. GOOD GPt( 49 BKR081 ."iTR AJXILIARY FEEDWATER PUt!P A GQOLi BKR082 tiTR AUXILIARYFEEDWATER PU)lP 8 OFF 6009 V3505 AUX Fh PUtF 6<cd( SUPPLY VALVi A CLOSED 6009 V3504 A!J) .=W PUii> STEA." SUPPLY VALVE 8 CLO "9 6009 E (, f>>/r
ttOV 17> 1993 13:4 E. 6ltctA SlttLtLATOP. TREt~i" GRGU~ ASSIGNidiT SU"ttAR) GROUP VEtaT 1 PROC DUR": EP I P 1 5 PLANT STATUS POIi"tl ID DESCRIPTIOi"'g.LE OVAL E. U. 53 FSIA SA."cT'i IN:ECTION LOOF A AVG FLOW 0. GOOD GPtt 54 FSIB SA.>> Y Itt'ECTIGtt LGGP B AVG FLOW 232. 600 D PN 55 P2fa0 SERVICE WAMe, PUtZS A k B lZABER 87. 6009 PSIG 55 P2161 SERVICE WATER PUttPS C <; D HEADER 86. 6000 PSI6 1 I 57 BKf$41 SERVICE WAMc PUlP A 0 6000 58 BKR042 SERVICE ttATER PUK B OV GOOD 59 BKR043 <"RVIC" WATER K<>~ " Gt'l GOOD 60 BKR044 SERVIC": WATER PUttP D Ott GOOD
tiGV 17> 1993 >i ~ mo Gite Sit!BLAT/8 PAGE 1 TREND> 690.'~ ASSIGNHihT StJt >>ARY PG> >y I Py ~RG"= "'>".E'PIP 1 "5 >" '9 STATUS POINT ! 0 DES"RIP 'ON VA'> ('UAL E. U. 1 F06!9 C05'Ot!Et!T CQO> IN" LGQ? TOTAL FLll 6493. 6009 GPH r LfNST RH'ELING WATcR STORAGE TANX LVL 19.7 LMRR / VS033 33 FGQT LEVEL Hit!D c~EB 3.0 6009 ttPH t>t9033 33 FOOT LEVE.* W!tiB DIRECTION 6QGD BEG. 41.'3,1 5 MT033 33 FOOT LE'F~> TEtL.ERATURE GOOD BFGF 6 t>T250 250 FOOT LEVE: TEt!PFRAT>JRE 38.8 GOOD BEGF 7 NT2 250 TG 33 FQGT LEV='= TA TE!lP -4.3 6009 DEGF 8 RO! AR="" I-CONTRO: RH;"> 9. 225?2-02 6009 t8/HR 9 RO" ARE-" -CONTAIIBll 3.05492+05 HALtl tS/HR
!0 R05 A?Z.'"6?Et!T FL~> PIT 5.72137+00 GOOD t-/HR 11 R09 A "'-LETDOWN) L't~ t"Gt>ITGR 2.93427+01 6009 HR/HR ~ r2 R34 A>>".4 34 - AUX DLBG CV SPRAv PLl>? 1.01742+00 6009 tS/ta 13 R35 AR:.~ Z-PASS ~At!?~ P@cL 1.09648>00 6009 %/HR R10A CP)RAINY>=ttT IODINE tlONITGR R10A 1.00432+07 HENS PN 15 R!1 CGt!TAII'l>~elhi AIP, PART ICV ATE 9.78647+06 HALtl CPtl R!2 CQtA!eENT C."8 r>QNITOR 1.04864+07 HEt/6 CPtt >7 R!08 PLyl? VEttT IODINE tl0!tITQR R!09 1.02772+06 HAM CPtl .'8 =
R!3 A>JX 9> 96 EXf'.>>""ST AIR PARTIC!F ATE 2.4I963+02 6009 CPtl 1'? R!4 AOX 8'G EXHAOST GAS tlGNITQR 5.59917+01 6009 CPtt R!S LIQJIID l>ASTE BISPOS>".'r3ttITOR 1.01012+03 GOOD CPtl ST":i>; 6""NERATOR 9ABER BRAIN 2.00678%3 GGQD CPtl ng C>> P~W AREA 29WATAltP ti HIP RAl>-""" 2.99398+02 HALH R/HR R30 AREA 30-CGNTA! t4lEt~i HIGH RANGE 2.99398+02 HAUf R/HR R!5 CGtP=:USER AIP. EZCTC>R EXHAUST !.46428~03 K09 CP>'l nc'6 CV VitiT Cl'>A!! 5~ Gil RAt>>or. GAS 4.20511-05 6009 XI/CC R12A6 >.V v"N CHAti "-A>,""A 6.-"."c">A 2.00000400 6009 N/HR 12A? CV VBi' CHAN> j-tl>B RAtà 6AS >>.205!1-05 6009 XI/CC 28 R! 2A9 CV V-"N: CNN "-H'GH RA%.""GAS 9.9998?M 6009 XI/CC
'P9 P,! 4A5 P'." V"NT CHAtl S-LG'A RAtlGE GA. 2.30991-06 GOOD XI/CC 30 F;14A7 . LAiT VEN>T M!?->>IB RANGE GAS 2.20996-03 K09 XI/CC 3! R!4A9 P A'> VER CHAt'H.'GH R4Jtii GAS .20996-03 6009 Xl/CC tl~
p$ 5>>c AIR E3ECTGR CHAN =' RANGE GAS <.22985-06 GOOD XI/CC 33 R!5A7 AIR E:ECTCR CHAt'->>IB RANGE GAS i. 809M105 6009 XI/CC ZJ R!SA9 AIR EZCTOR CH>>W 9-H! PARSE GAS 1 '2999-03 6009 XI/CC R3! -",. -'" 31 STD"> 'P .. l.. Itt~) 1997-03 G009 tg/HR
+30 "=;:~ "". STE@'i LIRE P. (-. Itt6) 3.61997-03 t8/HR
>CVH V -~~%6 P C"" "'>"'>>"'.9
~ 0 6009
- CV03 8S.3 KGD BEGF TV/07 >t!I-"RttiBIAT= '.-" 6. I TEl">" ti? 100.9 6009 DEGF 40 TCVOB CV 'N>TER~!ED!ATE LVL 6F: TEt'>P N 100 9 'QOGD DEGF 41 TCVO9
"" '"'T"<""DIAT- ><" FT TB'= 4~ 100.9 C009 D"-6F TCV'10 CV Iti'TERt>EBIA:E LV>. 6FT TET ll!0 100.9 KOD BEGF
;CV!7 CV G-.ERATli~i.-. :=V'?T EH? ~17 116.4 6009 BEGF
Time: 1415 Message: ~6 GINNA STATION 1993 EVALUATED EXERCISE MES AGE FORIVI 8 I C I R Simulated Plant Conditions: See Attached Sheets ~essacee: <<" ~THIS IS AN EXERCISE~" >> FOR CONTROLLER USE ONLY Controller Notes:
- 1) Accident evaluation and response continues.
Actions Ex ected:
- 1) Recovery/Re-entry and declassification discussions should commence per the guidance provided in EPIP 3-4, "Emergency Declassification and Recovery".
Discussions should include but not be limited to the following: A) Preliminary discussions between the EOF and the TSC on the following:
'hort Term plant concerns such as:
- 1. Cool down of the plant
- 2. Repair and return to service of 480 volt Bus 14 transformer.
- 3. Repair and return to service of the "B" RHR pump.
- 4. Repair and return to service of the "B" Sl pump.
- 5. Repair and return to service of the "C" Sl pump.
- 6. Repair and return to service of the Bus 14-16 tie breaker.
'ntermediate term plant concerns such as:
- 1. Core damage assessment.
- 2. Clean-up of Auxiliary Building.
- 3. Clean-up of water in containment.
- 4. Long-term core cooling.
- 5. Radiological release calculations and evaluation.
B) ~ Preliminary designation of the recovery organization. C). State and counties may also conduct parallel recovery/re-entry discussions.
- 2) Recovery/Re-entry interface between the EOF/TSC and offsite agencies should be demonstrated as time allows.
1993 EVALUATED EXERCISE Time: ~/ MAJOR PARAMET ENGINEERED SAFEGUARDS Reactor Shutdown E NO Hi h Head S.I. Pum s N-31 CPS FI-924 42 GPM N-32 CPS FI-929 GPM N-35 ~)AMP S 1A. NSER STBY OOS N-36 AMPS 1B. INSERV STBY 00 Avg. Nuclear Power 42 1C. INSERV STBY OOS RCS Pressure 0 PSIG BAST Level = ~0 PRZR Level A RCP B RCP 1A S/G Level RUNNING/ RUNNING OPP TOPP FI-626 'PM Low Head S. 1A. INSERV
. Pum s TB OOS ECIRC 1B.S/G Level 1B. INSE V B OOS RECIRC 1A S/G Pressure PSIG RWST Level ~ ~9~%
1B S/G Pressure 0 PSIG Turbine/Generator ONLINE FFLIN Containment S ra Pum s 4 KV Buses GIZE /DEE RGIZED Fl-933A~GPM 480V Buses ERGIZE /DEENERGIZED FI-93 1B~~GPM DC Batteries A~SO VOLTS B l3OVOLTS 1A. NSERV T OOS Cnmt Pressure ~Cr PSIG 1B. NSERV TB OOS Cnmt Sump A Level Cnmt Sump B Level
~R,~FEET D . INCHES NaOH Tank Level = ~% " Loop Hot Leg OF Containment Recirc Pans A Loop Cold Leg ~/~.'F 1A. NSER STBY OOS B Loop Hot Leg ~)~0F 1B. SER STBY OOS B Loop Cold Leg F 1C. NSERV STB OOS RVLIS Sk =% 1D. NSER STBY OOS
- CET ~/S2A 'F Post Accident Dampers OPE CLOSED S/G A Total Aux FW Flow GPM 9/G B Total Aux FW Flow ~GPM Service Water 1A. R Pum s S B OOS DIESEL GENERATORS 1B. STB OOS 1C>> STBY OOS A. RUNNIN UNLOADED STBY OOS 1D. SER STBY OOS B. RUNNING UNLOADED OOS A&B Header Pressure PSIG TSC RUNNING ED TB OOS Security RUNN UNLOADED T OOS Com onent Coolin Water Pum s 1A. INSERV TB OOS ENGINEERED SAP DS 1B. NSER STB OOS Surge Tank Level =
Aux. Feedwater Pum s 1A. INSERV 8 OOS Standh Aux. Peedwater Pum s 1B. INSERV TB OOS 1C. INSE V B 00 Turb. Driven INSERV T OOS 1D. NSERV TB OOS CST Level ~)~FEET
- CET = Average of Selected Core Exit Thermocouples
NOV 17~ 1993 14: 15 R. E. GIM(A Sit(ULATOR PAGE 1 TREND GROUP ASSIS)ST SUtft(ARY GRmlP: EVENT1 PfmCEDURE: EPIP I< PLANT STATUS POINT ID DESCRIPTION E. U. 1 ATMS ANTICIPATED TRANSIENT M/0 SCRAt( ATMS ALRtl 2 RXT REACTOR TRIP BREAXER STATUS RX TRIPPED ALR(( 3 N31 SSRCE RAN6E DETECTOR N-31 3.91741+01 6009 CPS N32 SSSCE RANGE DETECTOR N-32 3.63077%1 6009 CPS 5 N35 INTER)(H)IATE RANGE DETECTOR N-35 1.00925-11 Goon AtP 6 N36 INTERtKDIATE RANGE DETECTOR N-36 1.00461-11 6009 NP 7 AVERAGE NUCLEAR POMER .00 6009 X 8 PRCS REACTOR COOLANT SYSTEtl AVG PRESS 6. LALt( PSI6 9 LPlR PRESSURILER AVERAGE LEVEL .0 LALN X 10 FRCLA REACTOR COOLANT LOOP A AVG FLOM .0 IQS 11 FRCLB REACTOR COOLANT LOOP 8 AVG FLOM .0 1%9 X 12 RXT16 RCPA BS(ER CAUSE Rr TRiP TRIPPED ALRtf 13 RXT17 RCPB BRENER CAUSE RX TRIP TRIPPED ALRtf 14 TSUBTC INCORE TC SUBCm)LED t(ARGIN 69.6 Goo< DE6F 15 LS6A STN 6EN A NARROM RANGE AVG LEVEL 69.7 HALN X 16 LSGB ST)( GEN 8 NARROM RANGE AVG LEVEL 88.5 HALN X 17 PSGA STN 6EN A AVERAGE PRESSURE 0. LALtf PSIG
)8 PSGB STN GEN 8 AVERA6E PRESSURE 0. LAL)( PSIG 19 GENBKR1 6EKRATOR ON LINE BREA)(ER 161372 TRIPPED ALRtf 20 GENBXR2 GEGQTOR ON LINE BREAXER 9X1372 TRIPPED ALRt(
21 BUS 11A BUS 11A SUPPLY BRENER TRIPPED ALRtf 22 BUS118 BUS 118 SUPPLY BREAXER TRIPPED ALRtf 23 BUS12A NOT TERtfit(ATED Otf PPCS (7/19/91) NOT TRIP DEL 24 BUS 128 NOT TERHINATED ON PPCS (7/19/91) NOT TRIP DEL 25 Bi1A12A BUS 11A To 12A TIE BRENER NOT TRIP AU% 26 8118128 BUS 118 TO 128 TIE BRENER NOT TRIP ALRt( 27 CONTAINttENT AVERAGE PRESSlRE .64 6009 28 LSNPA CONTAItft(E)(T SUt(P A AVERAGE LEVEL 31.2 HE% 29 L0942E SU)P 8 LEVEL 8 INCHES (TRAIN A) HIGHER IQS 30 L0943E SU)P 8 LEVEL 8 INCHES (TRAIN 8) HIGHER INH)) 31 L09429 SU)P 8 LEVEL 78 INCHES (TRAIN A) HI6HER INHB 32 l.0943D SU)P 8 LEVEL 78 MHES (TRAIN 8) HIGHER I%6 33 L0942C SU(P 8 LEVEL i13 INCHES(TRAIN A) HI6HER ALRtf 34 L0943C SU)P 8 LEVEL 113 INCHES(TRAIN 8) HIGHER ALR)f 35 L09428 SU)P 8 LEVEL 180 INCHES(TRAIN A) Lof(ER 6009 36 L09438 SOP 8 LEVEL 180 INCHES(TRAIN 8) Lo))ER 6009 37 L0942A SQP 8 LEVEL 214 INCHES(TRAIN A) Lo))ER 6009 38 L0943A SUtP 8 LEVEL 214 INCHES(lRAIN 8) UNER 6009 39 T0409A R(XA HOT LEG TEt(PERATURE 141.7 6009 40 T0410A RCLB HOT LE6 TBiPERATURE 139.8 .. GOOD 41 T0450 RCLA COLD LEG THPHNTNE 152.6 6D09 42 T0451 RCLB COLD LEG TE)(PH(AT(SE 124.1 6009 43 TAWQID RCLA TAVG (THOT/TC(LD MIDE RNG) 147.2 GOOD 44 TAV6BMID RCLB TAVG (THOT/TCOLD MIDE RNS) 131.9 600D 45 LRV REACTOR VESSEL AVERAGE LEVEL 87.6 LALN 46 TCCORE Ei.i INCORE TC AVERAGE TE)P 150.1 6(me 47 FAUXFMA S/6 A TOTAL AUX FEHNATER FLO(( . 0. Goon 48 FAUXFMB 6/6 8 TOTAL AUX FEEINATER FLOM 0. GOM 49 S(R081 t(TR AUXILIARYFEH)MATER PU)P A OFF 6009 50 S(R082 NTR AUXILIARYFEEDMATER PU)P 8 OFF 6009 51 V3505 AU)( FM PUt(P STEAtf S(PPLY VALVE A cLosED Goon 52 V3504 AUX FW PU)P STEA)f SUPPLY VALVE 8 CLOSED 6009
NY 17'993 14:15 R. E. GINA SINULATN PA6E 2 TREND GROUP ASSIGNNENT RNMY 6ROUP: EVENTi PRXHIRE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION VALUE GUN. E. V. 53 FSIA SAFETY INACTION LOOP A AVG FLN 0. 6009 GPN 54 FSIB SAFETY IN3ECTION LOOP 8 AV6 FLOW 361. 600D GPN 55 P21<e SERVICE WATER PNPS A h 8 HEADER 81. 6009 PSIG 5b P2 161 SERVICE WATER PlIPS C h D HEADER 86. 6009 PSIG 57 NR041 SERVICE WATER PlIP A 6009 58 NR042 SERVICE WATER PNP. 8 6009 59 NR043 SERVICE WATER PNP C 6009 60 NR044 SERVICE WATER PNP D 600D
NOY 17~ 1993 14:16 L E. GIMO SINULATOR TREND Gfm'SSIBQKNT SUNNARY GROUPS EVENT2 PROCEDURE: EPIP 1% PLAt(T STATUS POINT ID DESCRIPTION E. U. 1 F0619 COMPONENT COOLING LOOP TOTAL FLM 6493. 6009 6PN 2 LSST REFUELING MATER STORAGE TANK LVL 17.1 LMRtf 3 MS033 33 FOOT LEVEL MIND SPEED 3.2 GOOD 5% 4 MD033 33 FOOT LEVEL MIND DIRECTION 71. 6009 OEG. 5 MT033 33 FOOT LEVEL TENPERATURE 46.9 6009 OEGF 6 MI250 250 FOOT LEVEL TB(PERATURE 47.9 6009 XGF 7 MDT2 250 TO 33 FOOT LEVEL DELTA TENP 1.0 6009 DEGF 8 R01 AREA IMNTRQ. MN 9.22572M %09 N/HR R02 AREA 2~AIN)K)fT 3.05492+05 HALN . NR/HR 10 R05 AREA 5-SPENT FUEL PIT 9.495IMI 6009 N/HR 11 R09 AREA 9~DOMN LINE NNITOR 2.73842+01 6009 NR/HR 12 R34 AREA 34 - AU)( fuG CY SPRAY PUNP 1.00577+00 6009 NR/HR 13 R35 AREA ZrPASS SANPLE PA)EL 1.0964888 6009 NR/HR 14 R10A CONTAlt(NENT IODIt(E NONITOR R10A 9.57744+06 HAU( CPN 15 R11 CONTAINNENT AIR PARTIC(uTE 1.02182+07 HENS CPtl 16 R12 CONTAINBfT 6AS t)ONITOR 1.00867+07 HENS CPtl 17 R10B PLANT VENT IODINE NONITOR R10B 1.04562Kb HALN CPN 18 R13 AUX BLDG EXHAUST AIR PARTIC(LATE 2.58151+02 6009 CPN 19 'R14 AUX BLDG EXHAUST 6AS te)ITOR 5.59917%1 6009 CPN 20 R18 LIQUID MASTE DISPOSAL NONITOR 1.01888+03 6009 CPN 21 R19 STEAN GENERATOR BLO@M DRAIN 1.938&SAG 6009 CPN 22 R29 AREA 29-CONTAINNENT HIS RANGE 2.9939&HQ HAUl R/HR 23 R30 AREA 3MONTAINNENT HI% RAN6E 2.993%H02 HALN R/HR 24 R15 CONDENSER AIR EJECTOR EXHAUST 1.420&9%3 6009 CPN 25 R12A5 CV VENT CHAN MN RANEE GAS 4.20511M 6009 XI/CC 26 27 R12A6 R12A7 CV VENT CHAN CV VENT CHN b~ 7+ID GANA RANK GAS 2.000NHOO 4.20511~ 6009 6009 NR/HR UCI/CC 28 R12A9 CV VENT C)N 9+IGH RA%iE GAS 9.99987M 6009 XI/CC R14A5 PLANT YENT CHAN MOM RANGE 6AS 2.30991M 6009 XI/CC 30 R14A7 PLANT VENT CHAN 7+ID RANGE 6AS 9.98974M 6009 UCI/CC 31 R14A9 PLANT VENT CHAN 9+IGH RANGE GAS 2.20996<3 6009 XI/CC 32 R15A5 AIR EJECTOR CHAN MOM RANGE 6AS 6.22985-06 6009 XI/CC 33 R15A7 AIR EJECTOR CHAN 7+ID RANGE GAS i. (O9~ 6009 XI/CC 34 R15A9 AIR EJECTOR CHAN 9+I RANK GAS 1.52999M 6009 Xl/CC 35 R31 AREA 31 STEAN LINE A (SPING) 3.61997<3 6009 N/HR 36 R32 AREA 32 STEAN LINE B (SPING) 3.61997M 6009 NR/HR 37 CVH CV HYHROGEN CONCENTRATION .0 6009 X 38 TCV03 CV BASENENT LEYEL &FT TENP $3 71.1 6009 DEGF 39 TCV07 CV INTERNEDIATE LVL &FT TB(P ()7 69.4 6009 DE6F 40 TCV08 CV INTERNEDIATE LVL &FT TENP f)8 &9.4 -.6009 DEGF 41 TCV09 CV INTEftNEDIATE LVL &FT TENP H 69.4 6009 DEGF 42 TCV10 CV INTERtKDIATE LVL &FT TENP 410 69.4 6009 DEGF 43 TCV17 CV OPERATING LEVL 6FT TENP ND 67.7 6009 DEGF
Time: 1430 Message: 70 GINNA STATI N 1993 EVALUATED EXERCISE MESSAGE FORM MMM f .: << I <<C << IR Simula ed Plant Conditions: See Attached Sheets ~Messe e: <<<<<<THIS IS AN EXERCISE<< FOR CONTROLLER USE ONLY Controller Notes:
- 1) Accident evaluation and response continues.
Actions Ex ected:
- 1) Recovery/Re-entry and declassification discussions should commence per the guidance provided in EPIP 3-4, "Emergency Declassification and Recovery".
Discussions should include but not be limited to the following: A) Preliminary discussions between the EOF and the TSC on the following:
'hort Term plant concerns such as:
- 1. Cool down of the plant
- 2. Repair and return to service of 480 volt Bus 14 transformer.
- 3. Repair and return to service of the "8" RHR pump.
- 4. Repair and return to service of the "8" Sl pump.
- 5. Repair and return to service of the "C" Sl pump.
- 6. Repair and re'turn to service of the Bus 14-16 tie breaker.
'ntermediate term plant concerns such as:
- 1. Core damage assessment.
- 2. Clean-up of Auxiliary Building.
- 3. Clean-up of water in containment.
- 4. Long-term core cooling.
- 5. Radiological release calculations and evaluation.
B). Preliminary designation of the recovery organization. C). State and counties may also conduct parallel recovery/re-entry discussions.
- 2) Recovery/Re-entry interface between the EOF/TSC and offsite agencies should be demonstrated as time allows.
3):::: L'ead.'ontrollers";.'should'nsure::;th t'e'.:shi ':::":ch n e.'demonstra ion":has..been a'de""u "tel'"'::co'm'e e'd::;
1993 EVALUATED EXERCISE Time: (83a MAJOR PARAMET ENGINEERED SAPEGUARDS Reactor Shutdown YE NO Hi h Head s. . Pum s N-3'1 CPS FI-924 GPM N-32 3 CPS FI-925 6% GPM N-35 F08 AMPS 1A. ER STBY OOS N-36 AMPS 1B. NSE V STBY 0 Avg. Nuclear Power RCS Pressure PRZR Level
'~PS IG 1C.
BAST NSERV STBY OS Level = A RCP RUNNING QPP Low Head S. . Pum s B RCP RUNNING OPPE FI-626 OO GPM 1A S/G Level ~II 9 1A. NSER STBY OOS C RC 1B S/G Level 1B. S V STBY REC C 1A S/G Pressure 0 PSIG RWST Level = 1B S/G Pressure PSIG Turbine/Generator ONLINE/ FFLINE Containment S ra Pum s 4 KV Buses NERGIZED DEE IZED FI-93 1A~GPM 480V Buses RG DEENERGIZED FI-93 1B~GPM DC Batteries A~VOLTS BQQVOLTS 1A NSERV TB 00 Cnmt Pressure Cnmt, Sump A Cnmt Sump B Level Level
~e 2- FEET PSIG INCHES 1B.
NaOH NSERV Tank Level = ~4 OOS
" Loop Hot Leg 2' Conta nm t Recirc Fa s A Loop Cold Leg OF 1A NS STBY OOS B Loop Hot Leg OF 1B. NSE STB OOS B Loop Cold Leg d7.ra DF 1C. NSE STBY OOS RVLIS Q, 1D. NSER STBY OOS
- CET OF Post Accident Dampers P CLOSED S/G A Total Aux FW Flow + GPM S/G B Total Aux FW Flow > GPM Service Water Pum s 1A. SER STBY OOS DIESEL GENERATORS 1B. NS R S BY OOS 1C. NSER STBY OOS A. RUNNIN UNLOADED STBY OOS 1D. NSE STBY OOS B. R ENG UNLOADED TB OOS A&B Header Pressure ~~~> PSIG TSC RUNNING D OOS Security RUNN LOADED STB OOS Com onent Coolincr Water Pum s 1A. IN V B OOS ENGINEERED SAP Aux. Feedwater Pum s DS 1B. SERV S BY OOS Surge Tank Level = ~
1A. NSERV T OOS Standb Aux. Peedwate 1B. INSERV TB OOS 1C. S V OO Turb. Driven NSERV OOS 1D. INSERV S B OOS CST Level ~i.~FEET
- CET = Average oi'elected Core Exit Thermocouples
HOV 17i 1993 14'29 R. E. GINA SINULATGR TRE)m 6ROUP ASSIS)ST SUNNY GROUP: EVEHTf PROCEDURE: EPIP f< PLANT STARS POINT 1D DESCRIPTION E. U. 1 Al% AHTICIPATED TRANSIENT W/0 SCRAN ATWS ALRtt 2 RXT REACTOR TRIP BREA)(ER STATUS RK TRIPPED ALRt( 3 H31 SO(SCE RA)(BE DETECTOR N-31 3.9039041 6009 N32 SSSCE RANGE DETECTOR N-32 3.95821+01 GOM 5 H35 INTERNEDIATE RANGE DETECTOR H-35 1.00925-11 6009 6 H36 INTERNEDIATE RANBE DETECTOR N-36 1.00461 "11 6009 7 NP AVERAGE NUCLEAR POWER .00 6009 8 PRCS REACTOR COOLANT SYSTEN AVG PRESS 5. LAUI LPIR PRESSURIIER AVERAGE LEVEL .0 LALN 10 FRCLA REACTOR COOLANT LOOP A AVG FLOW ~ 0 INHS 11 FRCLB 8',TOR COOLANT LOOP B AVB FLOW .0 INHS 12 R)(T16 RCPA BRENER CAUSE RK TRIP TRIPPED ALRt( 13 RG17 RCPB BRENER CAUSE R)( TRIP TRIPPED ALR)t 14 TSUBTC INCORE TC SUBCGOLED NARBIN 82.7 6(m~ DEGF 15 LS6A STN GEt( A HARROW RANGE AVG LEVEL 71.8 HAU( X lb LSGB STN 6EN B HARROW RANGE AVG LEVEL 90.7 HAUI X 17 PSGA STN GEN A AVERAGE PRESRRE 0. LALN PSIG 18 PSGB STN GEN B AVERAGE PRESRRE 0. LALN PSIB 19 6ENBKRt 6ElGQTGR GN LINE BREAKER 161372 TRIPPED ALRt( 20 GENS)(R2 GE)G(ATOR ON LINE BREAKER '51372 TRIPPED ALRt( 21 BUS 11A BUS iiA SUPPLY BRENER TRIPPED ALRN 22 BUSilB BUS iiB SUPPLY BREA)(ER TRIPPED ALRt( 23 Bt$ 12A NQT TERNINATED 0)t PPCS (7/19/91) NOT TRIP DEL 24 BUS12B NOT TERttl )(ATED N PPCS (7/19/91) NOT TRIP DEL 25 B11A12A BUS ilA TG 12A TIE BREA)(ER NGT TRIP ALRtt 26 B11B129 BUS ifB TO 12B TIE BRFNER NOT TRIP ALRtl 27 PCV CONTAINNEHT AVERAGE PRESSURE .66 GO09 28 LSQ(PA CONTAIN)(Et(T SUNP A AVERAGE LEVEL 31.2 HENG L0942E RlP B LEVEL 8 INCHES (TRAIN A) HIGHER IQS L0943E SSP B LEVEL 8 INCHES (TRAIN B) HI6HER INHS 31 L0942D RRP B LEVEL 78 INCHES (TRAIN A) HIGHER INHS 32 L0943D SNP B LEVEL 78 INCHES (TRAIN B) HIGHER INHS 33 L0942C RlP B LEVEL 113 INCHES(TRAIN A) HIGHER ALRtt 34 L0943C SUtP B LEVEL 113 INCHES(TRAIN B) HIGHER ALRtl 35 L0942B SIP B LEVEL 180 INCHES(TRAIN A) LOWER 6009 36 L0943B SW' LEVEL 180 INCHES(TRAIN B) LS)ER 6009 37 L0942A SUNP B LEVEL 214 INCHES(TRAIN A) Lo))ER 6009 38 L0943A SOP B LEVEL 214 INCHES(TRAIN B) L(WER GOOD 39 T0409A RCLA HOT LEG TENPERATURE 132.1 6009 40 T0410A RCLB HOT LEG TENPERATURE 132.1 -. 6009 41 T0450 RCLA COLD LE6 TENPE)(AllSE 137.4 6009 42 T0451 RCLB COLD LEG TE)IPE)(AT(SE 107.6 6009 43 TAVBAWID RCLA TAVG (THOT/TCGLD WIDE RNG) 134.7 6009 44 TAVGBMID RCLB TAVG (TNT/TC(LD WIDE RNG) 119.8 6009 45 REACTOR VESSEL AVERAGE LEVEL 90.4 LALt( 46 TCCQRE El. 1 INCGRE TC AVERAGE TENP 138.1 600~ 47 FAUXFWA S/6 A TOTAL AUX FEEDWATER FLS( 0. 6009 FAUXFWB S/6 B TDTAL AUX FEEDWATER FLO)( 0. 6009 49 Bt(ROBI Nm AU)(ILIARYFEEDWATER PU)(P A OFF 6009 50 Bt(R082 NTR AUXILIARYFEEDWATER PUNP 9 DFF GQO9 51 V3505 AUK FM PUNP STEAtt SUPPLY VALVE A CLOSED 6009 52 V3504 AUX FW PtNP STEA)t SUPPLY VALVE B CLOSED 6009
MN 17> 1993 14:29 R. E. GINA SINLATOR PA6E 2 TREND GROUP ASSIGNENT RNNSY 6ROUP: EVENT1 PRXEDUfK: EPIP I< PLANT STATUS POINT ID DESCRIPTION VALUE QUAL E. U. 53 FSIA SAFETY INACTION LOOP A AVS Flti 0. GOOD 6N 54 FSIB SAFETY INACTION LOOP B AVG FLN 458. 6009 GPN 55 'P2160 SERVICE NTER PNPS A 5 B HEADER 87. 6009 PSIG 56 P2161 SERVICE NTER PUNPS C h D HEADER 86. 600D PSIG 57 IIR041 SERVICE NIER RIP A 600D 58 IIR042 SERVICE NTER PNP B 6009 59 IWR043 SERVICE NTER PNP C GOOD 60 BKR044 SERVICE NTER PlIP D 6009
NOV 17> 1993 14:30 R. E. GINA SltmLATGR TREND GRIP ASSIGNNENT SUtlMY GROUP: EVENT2 PROCEDURES EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION E. U. 1 F0619 Co)PGMENT CI.ING LOOP TOTAL FLN 6493. 6009 6Ptl 2 LR)tST REFUELING NTER STORAGE TAN LVl. 15.4 LII X 3 NS033 33 FOOT LEVEL ttIND SPEED 2.8 6009 tPH N$33 33 FOOT LEVEL l)IND DIRECTION 71. GOOD IKG. 5 NT033 33 FOOT LEVEL TBPERATURE 47.0 6009 DEGF 6 NT250 250 FOOT LEVEL TB)PHQTURE 48.1 GOOD DEGF 7 NDT2 250 To 33 FOOT LEVEL DELTA TBP 1.1 6009 K6F 8 R01 AREA i<ONTRGL Root) 9. 17~ 6009 N/HR 9 R02 AREA 2~AIMNBIT 3. 12608%5 HALtl t8/HR 10 R05 AREA ~ENT FUEI. PIT 9.9425'M 6009 t8/HR li R09 AREA 9-LETDON LlNE t)GNITOR 2.69153+01 6009 N/HR 12 R34 AREA 34 - AUX BLDG CV SPRAY PU)P 9.~1 Goon N/HR 13 R35 AREA 35+ASS SANPLE PAhEL 1.09648+00 6009 t8/HR 14 R10A CONTAIN)lENT IODINE tloMITOR R10A 9. 91393+06 HALN CPN 15 Rii CGMTAINENT AIR PARTIMATE 1.0i74807 HENS CPtl 16 R12 CGNTAINt)EMT GAS t)GNITGR 1.02182+07 HENS CPtl 17 RiOB PLANT VENT IODINE NNITGR R10B 9.8005&5 HALtl CPtl 18 R13 AUI BLDG EXHAUST AIR PARTICULATE 2.55932+02 600D CPM 19 R14 AUK BLDG EXHAUST GAS tlONITOR 5.67216%1 6009 CPtl 20 R18 LIGUID WASTE DISPOSAL ti)MITOR 1.01012+03 Goon CPtl 21 R19 STEA)1 GENERATOR BLM)GN DRAIN 2.05057M 6009 CPM 22 R29 AREA 2HZNTAINtlENT HIGH RANGE 2.99398+02 HAL)l R/HR 23 R30 AREA 30-CGMTAINtlglT HI6H RANGE 2.99398+02 HALtl R/HR 24 R15 CONDENSER AIR EJECTOR EXHAUST 1.41457%3 GOOD CPtl 25 R12A5 CV VENT CHAN ~Sl RANK 6AS 4.20511M 6009 UCI/CC 26 R12A6 CV VENT CHAN b~ GAttN VENT GIN 7+ID RANK GAS 2.00000H)0 6009 N/HR 27 Ri2A7 CV 4.20511M 6009 XI/CC 28 R12A9 CV VENT CNN 9+IGH RAKE GAS 9.99987M Goon UCI/CC 29 R14A5 PLIT VENT CHAN MN RANGE GAS 2.30991M 6009 XI/CC 30 R14A7 PLANT VENT CHAN 7+ID RANGE 6AS 9.98974M 6009 XI/CC 31 R14A9 PLNT VENT CHAN 9+IGH RANGE 6AS 2.20996M 6009 Xl/CC 32 R15A5 AIR EJECTOR CHAM MOM RANGE GAS 6.2298~ GOM UCI/CC R15A7 AIR EJECTOR CHAN 7+ID RANGE GAS 1.809~ Gm XI/CC 34 R15A9 AIR EJECTOR CHAN 9+I RANGE 6AS 1.52999<3 Goon UCI/CC R31 AREA 31 STEA)l LINE A lSPING) 3.61997M 6009 t8/HR 36 R32 AREA 32 STEAtl LINE 8 (SPING) 3. 61997<3 6009 N/HR 37 CVH CV HYDROGEN CONCENTRATION .0 6009 X 38 TCV03 CV BASBlENT LEVEL 6FT TBP 13 71.6 Goon DEGF TCV07 CV INTERNEDIATE LVL 6FT TBP 47 69.7 6009 DEGF 40 TCV08 CV INTERHEDIATE LVL 6FT lBP IG 69.7 -.Gm K6F 41 TCV09 CV INTERHEDIATE LVL 6FT TBP I9 69.7 6009 DEGF 42 TCV10 CV INTERHEDIATE LVL 6FT TBP IIO 69.7 6009 DEGF 43 TCV17 CV OPERATING LEVL 6FT TEtP 117 67.7 6009 DEGF
Time: = 1500 Message: 71 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM Ei I <<C << I R ITSCIECRIJENCIESCISVRYEY CTR Simula ed Plant Conditions: See Attached Sheets Messacee: """THIS IS AN EXERCISE+"" THE EXERCISE IS TERMINATED FOR CONTROLLER USE ONLY Controller Notes:
- 1) Deliver when all exercise objectives have been demonstrated.
Actions Ex ected:
- 1) Close out by making an announcement to all facilities (including RECS) that the exercise is terminated.
NOV 17> 1993 14:59 R. E. GINA Sit((LATOR PA6E 1 TREND GROUP ASSIBHNENT SUNNARY GROUP: EVENT1 PROCEDURE: EPIP I< PLANT STATUS POINT ID DESCRIPTIOH E. U. 1 ATl6 ANTICIPATED TRANSIENT W/0 SCRAN ATHS ALRN 2 RXT REACTOR TRIP BREAKER STATUS RX TRIPPED ALRN 3 N31 SMICE RAH6E BETE(:TOR N-31 3.50752101 Gm CPS N32 SMICE RANGE DETECTOR N-32 3.91741+01 6009 CPS 5 N35 IH)ERNEDIATE RANGE DETECTOR N-35 1.00925-11 6009 At(P 6 N36 INTERNEDIATE RANBE DETECTOR N-36 1.00461-11 6009 AtP 7 NP AVERAGE NUCLEAR POMER .00 6009 X 8 PRCS REACTOR COOLA)(T SYSTEN AVG PRESS 5. LALN PSIG LPlR PRESSURIIER AVERAGE LEVEL .0 LALN X 10 FRCLA REACTOR COOLANT LOOP A AVB FLOH .0 INH8 X 11 FRCLB REACTOR COOLANT LOOP B AVB FLO)t .0 IN{8 X 12 RKT16 RCPA BREAKER CAUSE RX TRIP TRIPPED ALRN
!3 RXT17 RCPB BREAKER CAUSE RX TRIP TRIPPED ALRN 14 TSUBTC INCORE TC SUBCOOLED HARBIN 75.8 600< DEBF 15 L%A ST)t 6EN A NARRO)t RANGE AVG LEVEL 76.4 HALN 'X 16 LSBB STN GEN B HARRmt RANGE AVB LEVEL 95.6 HALN X 17 PS6A STN GEN A AVERAGE PRESSURE 0. LALN PSIB LG PSGB STt( 6EN B AVERAGE PRESSURE 0. LALN PSIG 19 'EHBKR1 BBGtATOR OH LINE BREAKER 161372 TRIPPED ALRN 20 GEHBKR2 BE%RATOR ON l.lHE BREAKER 9X1372 TRIPPED ALRN 21 BUS11A BUS 11A SUPPLY BREAKER TRIPPED ALRN 22 BUS11B BUS 11B SUPPLY BREAKER TRIPPED ALRN 23 BUS12A HOT TERNIHATED Ot( PPCS (7/19/91) NOT 'IHIP DEL 24 E812B NOT TERtlIHATED 0)t PPCS (7/19/91) NOT TRIP DEL 25 Biih12A BUS 11A TO 12A TIE BREA)(ER NOT TRIP ALRN 26 B11B128 BUS 11B TO 12B TIE NOT TRIP BREA)(ER'OHTAINNEHT 27 PCV AVERAGE Pt(ESSURE .64 GOOD 28 LSQ(PA CONTINENT SUNP A AVERAGE LEVEL 31.2 HEMi 29 L0942E SQP B LEVEL 8 INCHES (TRAIN A) HIGHER IHH8 30 L0943E SU)P B LEVEL 8 INCHES (TRAIN B) HIGHER INH8 31 L0942D SUtP B LEVEL 78 INCHES (TRAIN A) HI6HER INH8 32 L0943D SU)P B LEVEL 78 INCHES (TRAIN B) HI6HER 1%8 33 L0942C SU)P B LEVEL 113 INCHES(TRAIN A) HI6HER ALRN 34 L0943C SU)P B LEVEL 113 INCHES(TRAIN B) HIGHER ALRN 35 L09428 SU)P B LEVEL 180 INCHES(mAIN A) Lm 600D 36 L09438 SUtP B LEVEL 180 INCHES(TRAIN B) LNER 6009 37 L0942A SUIP B LEVEL 214 IHCHES(TRAIN A) LNER GOOD 38 L0943A SUtP B LEVEL 214 INCHES(TRAIN B) L(mER 6009 39 T0409A RCuI HOT LEG TEMPERATURE 136.9 6009 40 T0410A RCLB HOT LEG TENPE)tATUfK 136,9 - 60R 41 '0450 RCLA COLD LEG TENPERATNE 134.4 6009 42 T0451 RCLB COLD LEG TE)IPERATuIE 134.0 GOOD 43 TAVGAMID RCLA TAVG (TNT/TCOLD HIDE RNB) 135.7 GOOD 44 TAVBB)tlD RCLB TAVB (TNT/TC(U) HIDE RNB) 135.5 6009 45 LRV REACTOR VESSEL AVERAGE LEVEL 90.3 LALN 46 TCCORE E1.1 IHC(mE TC AVERA6E TEMP 139,0 600'.
47 FAUXFIN S/6 A TOTAL AUK FEEDNTER FUN 6009 48 FAUXF)IB S/6 B TOTAL AUX FEEDNTER FLN 0. 6009 49 BKR081 t(TR AUXILIARYFEEDNTER PUNP A OFF 6009 50 BKR082 t(TR AUXILIARYFEEDHATER PUNP B OFF 6009 51 V3505 AUX F)t PUNP STEAN SUPP).Y VALVE A CLOSED 6009 52 V3504 AUX F)t PUtP STEAN S(FPLY VALVE B CLOSED GOR
>z/
NOV 17~ 1993 14:59 R. E. GINA SIIILATOR PA6E 2 TREND 6ROUP ASSIGQKKT SLY GROUP! EVENT1 PRXEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION VALUE QUAL E. U. 53 FSIA SAFETY INJECTION LOOP A AVG FLN 0. 600D GPN 54 FSIB SAFETY IN ECTION LOOP B AVG FLN 0. 600D GPN 55 P2160 SERVICE NTER PNPS A h B HEADER 87. GOOD PSIG 56 P2161 SERVICE NTER PtIPS C h D fKAOER 86. 600D PSIG 57 NR041 SERVICE NTER PNP A GOM 58 IIR042 SERVICE @TER PNP B 600D 59 NR043 SERVICE NTER PUNP C 600D 60 IR044 SERVICE NTER PNP D GOOD
NOV O~ f993 15:00 R. E. GIWA SINLATOR
,TREND GROUP ASSIMENT RNMY GROUP: EVENT2 PROCEDURE: EPIP 1-5 PLA)fT STATUS POINT ID DESCRIPTION E. U.
1 F0619 Co)FONENT Cm.ING LOOP TOTAL FLM 6493. GOOD GPtl 2 LRMST REFUELIN6 MATER STORAGE TAN LVL 14.6 LMR)f X 3 MS033 33 FOOT LEVEL MIND SPEED 3.6 Gom )FH 4 MD033 33 FOOT LEVEL MIND DIRECTION 74. 6009 DEG. 5 MT033 33 FOOT LEVEL TEtlPERAIURE 48.5 GOOD DE6F 6 MT250 250 FOOT LEVEL TBfPERAIURE 48.6 6009 DE6F 7 MDT2 250 To 33 FOOT LEVEL DELTA TBF .1 6009 DEGF 8 R01 AREA 1M)ff89 Rootl 9.44062M 6009 N/HR 9 R02 AREA 2~AINNENT 3.07254%5 HALN NIN 10 R05 AREA 5-SPENT FUEL PIT 9.54~1 6009 N/HR 11 R09 AREA 9~f)MN LINE tfoNITOR 2.85101%1 Gm NIN 12 R34 AREA 34 - AUr BLDG CV SPRAY PU)F 1.0174240 6009 NIHR 13 R35 AREA ~ASS SA)FLE PQKL 1.09648+00 Gm N/% 14 R10A CONTAIt)NENT IODINE 5NITOR RiOA 1.02624+07 HENB CPtf 15 Rli CONTAINMENT AIR PARTICKATE 9.99992+06 HALN CPtf 16 R12 CONTAINBfT GAS tlONITOR 9.78647+06 HALtl CPN 17 R10B PLANT VENT IODINE t)ONITOR R10B 1.0144&5 HALN CPtl 18 R13 AUK BLDG EXHAUST AIR PARTIMATE 2,61516+02 6009 CPtf 19 R14 AUI BLI)6 E)(HAUST 6AS tloNITOR 5.69671+Of 6009 CPN 20 R18 LIQJID MASTE DISPOSAL KNITQR 1.09175I03 6009 CPN 21 R19 STEAtf GENERATOR BLO)fDMf DRAIN 1.8972&03 6009 CPtl 22 R29 AREA 29~AIQKNT HIGH RANGE 2.99398M HALtl R/HR 23 R30 AREA 3MONTAIN%NT HI% RANGE 2.99398+02 HAUI R/N
~
24 Ris CONDENSER AIR EJECTOR E)(HAUST 1.40241+03 6009 CPtl 25 R12A5 CV VENT CHAN ~QM RANK GAS 4.20511M 6009 XI/CC 26 R12A6 CV VENT CHAN GQtQ 2.00000+00 6009 N/HR 27 R12A7 CV VENT CHAN 7+ID RANK GAS 4.20511M 6009 UCI/CC 28 R12A9 CV VENT CHAN MfGH RA%K GAS 9.99987M 6009 UCI/CC
- 29. R14A5 PLANT VENT CHAN MQM RANGE GAS 2.30991M 600D UCI/CC 30 R14A7 PLANT VENT CHAN 7&ID RAN6E GAS 9.98974M 6009 UCI/CC 31 R14A9 PLANT VENT CHAN 9+IGH RANGE GAS 2.20996M 6009 XI/CC 32 R15A5 AIR EJECTOR CHAN MQM RANGE GAS 6.229~ 6009 XI/CC 33 R15A7 AIR EJECTOR CHAN 7+ID RANGE GAS 1.80~ 6009 XI/CC 34 R15A9 AIR EJECTOR CHAN 9+I RANGE GAS 1~ 52999M 6009 UCI/CC 35 R31 AREA 31 STEAtf LINE A lSPING) 3.61997-03 6009 N/HR 36 R32 AREA 32 STEAN LINE B lSPING) 3.61997M 6009 N/HR 37 CVH CV HYDROGEN CONCENTRATION .0 6009 X 38 TCV03 CV BASBKNT LEVEL 6FT TBF $3 71.2 6009 DE6F 39 TCV07 CV INTERtlEDIATE LVL bFT TBF N7 69.3 6009 OEGF 40 TCV08 CV INTERtfEDIATE LVL 6FT TBF f)8 69.3 - 6009 OE6F 41 TCVO9 CV INTERtfEDIATE LVL 6FT TBF H 69.3 859 DEGF 42 TCV10 CV INTERtlEDIATE LVL 6FT TBF 410 69.3 6009 BEGF
'3 TCV17 CV OPERATING LEVL 6FT TBF Ci7 67.3 6009 EEGF
NOV 17~ 1993 15:14 R. E. GIMI(A Sit(ULATOR PA6E 1 TRE)m GROUP ASSIGNNENT SUt(t(ARY GROUP: EVENT1 PROCEDURE! EPIP 1"5 PLANT STATUS POINT ID DESCRIPTION E. U. 1 ATMS ANTICIPATED TRANSIENT M/0 SCRI( ATMS ALRt( 2 RKT REACTOR TRIP BREAKER STATUS Rr TRIPPED ALR)f 3 N31 SIBCE RAN6E DETECTOR N-31 3,471 35tOf 6009 CPS N32 SIKE RANGE DETECTOR N-32 3.7454(HOI 6009 CPS 5 N35 INTERfKDIATE RANGE KlECTOR N-35 1.00461-11 6009 At(P 6 N36 INTERtEDIATE RANGE DETECTOR N-36 1.00461"li 6009 At(P 7 NP AVERAGE NUCLEAR POWER .00 6009 X 8 PRCS REACTOR COOLANT SYSTE)f AVG PRESS 6. LAU( PSIG 9 LPIR PRESSURIlER AVERAGE LEVEL .0 LAU( X 10 FRCLA REACTOR CO%ANT LOOP A AVG FLOW .0 INH8 X fi FRCLB RECTOR COOLANT LOOP B AVG FUN .0 INH8 X 12 RKT16 RCPA BREWER CAUSE Rr TRIP TRIPPED ALR(f 13 R)(T17 RCPB BREAKER CAUSE Rr TRIP TRIPPED ALRN f4 TSUBTC INCORE TC SUBCOOLED tIRGIN 88.6 600~ DE6F 15 LSGA STt( GEN A NARROW RANGE AVG LEVEL 78.7 HAU( 'X 16 LSGB STt( GEN B NARR(N RANGE AVG LEVEL 98.0 HAUf X 17 PS6A STN 6EN A AVERAGE PRESE)RE 0. LALN PSIG 18 PSGB STt( 6EN B AVERAGE PRESSURE 0. LAL)( PSIG 19 GENBKRl GBERATOR ON LINE BREAKER 161372 TRIPPED AUI 20 GENBKR2 696NTOR ON LINE BREAKER 9r1372 TRIPPED ALRf( 21 BUSilA BUS ilA SUPPLY BREAKER TRIPPED 'LRN 22 BUSliB BUS 1 lB SUPPLY BREAKER TRIPPED ALRt( 23 BUS12A NOT TERt(INATED ON PPCS (7/19/91) NOT TRIP DEL 24 BUS12B NOT TERNINATED Oti PPCS (7/19/91) NOT TRIP DEL 25 B11A12A BUS 11A TO 12A TIE BREAKER NOT TRIP ALRN 26 B11B128 BUS 11B TO 128 TIE BREAKER NOT TRIP ALRN 27 PCV CONTAIIENT AVERAGE PRESSURE .66 6009 28 LS(IPA CONTAIt(HENT SIP A AVERAGE LEVEL 31.2 HENS 29 L0942E SUtP B LEVEL 8 INCHES (TRAIN A) HI6HER W8 30 L0943E SQP B LEVEL 8 INCHES (TRAIN 8) HI6HER W8 31 L09429 SUtP B LEVEL 78 INQKS (TRAIN A) HIGHER INH8 32 L0943D SUtf' LEVEL 78 INCHES (TRAIN B) HIGHER INH8 33 L0942C SUtP B LEVEL 113 INCHES(TRAIN A) HI6HER ALRN 34 L0943C SOP B LEVEL 113 INCHES(TRAIN B) HI6HER ALR)f 35 L09429 SUtP B LEVEL 180 INCHES(TRAIN A) L(NER 6009 36 LO9438 SSP B LEVEL 180 INCHES(TRAIN B) LOWER 6009 37 L0942A SUtP B LEVEL 214 INCHES(TRAIN A) LOWER 6009 38 L0943A SUtP B LEVEL 214 INCHES(TRAIN B) L(NER 6009 39 T0409A RCLA HOT LEG TE)(PERATURE 125.8 6009 DEGF 40 T041OA RCLB HOT LEG TE)(PERATURE 125.8 ~ 6009 lKGF 41 T0450 RCU) COLD LE6 TE)(PERAT(BE 128.2 6009 OEGF 42 TO451 RCU) COLD LEG TEtIPERAT(mE 127.8 6009 OEGF 43 TAVGAMED RCLA TAVG (THOT/TCOLD WIDE RNG) 127.0 6009 OEGF 44 TAVGBMID RCLB TAVG (THOT/TCOLD WIDE RNG) 126.8 6009 DE6F 45 LRV REACTOR VESSEL AVERAGE LEVEL 90.4 6009 X 46 TCCORE El. 1 INCORE TC AVERAGE TEt(P 130,4 GX~ DEGF 47 FAUrFMA S/6 A TOTAL AU)( FEEINATER FUN 0. 6009 GPt( 48 FAUrFWB S/6 B TOTAL AUr FEEDMATER FL(W 0. 6009 GPt( 49 BKR081 t(TR AUrILIARYFEHNATER PU)(P A OFF. GX9 50 BKR082 tfTR AUKILIARYFEHNATER PU)(P 8 OFF 6009 51 V3505 AUr FM PU5'TEA)( SUPPLY VALVE A CLOSED 6009 52 V3504 AUr FM PI(P STEAt( SUPPLY VALVE B CLOSED 6009
NOV 17> 1993 15:14 R. E. GINA SINULATOR PAGE 2 TREND GROUP ASSIQNENT SUNQRY GROUP: EVENTI PROCEDURE: EPIP 1< PLANT STATUS POINT ID DESCRIPTION VALUE QUAL E, U. 53 FSIA SAFETY INJECTION LOOP A AVG FLOM 0. 600 D GPN 54 FSIB SAFETY INJECTION L00P B AVG FLOM 0. GOOD GPN 55 P21b0 SERVICE MATER PNPS A fc B HEADER 87. GOOD PSIG 5b P21bi SERVICE MATER PIIPS C h D HEADER Bb. 600D PSIG 57 NR041 SERVICE MATER RIP A 600D 58 NR042 SERVICE MATER PINP B 600D 59 NR043 SERVICE MATER PNP C GOOD b0 BKR044 SERVICE MATER PNP D 600D
NOV 17> 1993 15:15 R. E. 61%A SINULATOR TREND GROUP ASSIGNNENT SUNNARY 6ROUP: EVENT2 PROCEDURE( EPIP 1"5 PLANT STATUS POINT ID DESCRIPTION E. U. 1 F0619 CQR)NENT Cm.ING LOOP TOTAL FLM 6493. BOM 6Ptl 2 LSST REFUELING NTER STORA6E TAN LVL 14.6 L((RN 3 MS033 33 FOOT LEVEL NIND SPEED 4.3 GOM lFH 4 M9033 33 FOOT LEVEL WIND DIRECTION &8. 6009 DEG. 5 NT033 33 FOOT LEVEL TENPERATURE 48.9 6009 DE6F 6 NT250 250 FOOT LEVEL TENPERATURE 48.9 600D DEGF 7 MDT2 250 TO 33 FDOT LEVEL DELTA TBP .0 GOM DE6F 8 Roi AREA i~t(TROL R(mN 8.912RHQ 6009 NR/HR 9 R02 AREA 2-CONTAINNENT 3.07254M HALN N/HR 10 R05 AREA 5-SPENT FUEL PIT 9.828~i 6009 t8/HR 11 R09 AREA 9&.IImN LINE NONITOR 2.&&072+01 6009 NR/N 12 R34 AREA 34 - AUX DLD6 CV SPRAY PUNP 1.00577400 600D t8/HR 13 R35 AREA ZrPASS SANPLE PQKL 1 ~ 09648%0 6009 NR/HR 14 RloA CONTAINENT IODINE )SNITOR RiOA 9. &&051+06 HALN CPN 15 Rii CONTAINNENT AIR PARTIOlATE 9.57744+06 HALN CPtl 16 R12 CONTAI)mB(T 6AS NONITOR 1.02624+07 HENS CPN 17 R109 PLANT VENT IODINE N(NIT(R R109 1.01449%6 HALN CPtl 18 R13 AUX BLDG EXHAUST AIR PARTICULATE 2.55932+02 60M CPtl 19, R14 AUX BLDG EXHAUST GAS N(NITOR 5.38579+01 6001} CP)l 20 R18 LIQUID ((ASTE DISPOSAL NNITOR 1.059ZWa 6009 CPN 21 R19 STEAN 6ENERATOR DLO(m( DRAIN 1.91370%3 GOOD CPN 22 R29 AREA 29~AIN)(ENT HI% RANGE 2.99398+02 HALN R/HR 23 R30. AREA 3(HXNTAINNENT HI% RANGE 2.99398%2 HALN R/HR 24 R15 COt(DENSER AIR EJECTOR EXHAUST 1.46428+03 600D CPN 25 R12A5 CV VENT CHAN 5-LOj( RANGE BAS 4.20511~ 6009 UCI/CC 26 27 R12A& R12A7 CV CV VENT CHAN 6~ GAPA VENT CHAN 7+ID RANK 6AS 2.0000QHO 4.20511-05 6009 ta/HR 6009 UCI/CC 28 29 30 R12A9 R14A5 R14A7 CV VENT CHAN KA(T VENT CHAN PLANT VENT CHAN
~
9+IGH 7+ID RA%E GAS RANGE GAS RANGE GAS 9.99987-04 2.30991M
- 9. 98974M 6009 XI/CC BOM UCI/CC GOOD UCI/CC 31 R14A9 PLNT VENT CHAN 9+IGH RANGE BAS 2.20996<3 6009 UCI/CC 32 R15A5 AIR EJECTOR CHAN MN RAN6E BAS &.22985-06 6009 UCI/CC 33 R15A7 AIR EJECTOR CHAN 7-NID RANGE BAS 1.8097~ GOOD UCI/CC 34 R15A9 AIR EJECTOR CHAN H(I RANGE GAS 1.52999M GOOD UCI/CC 35 R31 AREA 31 STEAN LINE A (PING) 3. &1997M 6009 %/HR 36 R32 AREA 32 STEAN LINE B (SPINB) 3.61997M 6009 NR/HR 37 CVH CV HYDROGEN CONCENTRATION .0 Gm 38 TCV03 CV BASB(ENT LEVEL 6FT TB(P ()3 71.8 6009 KGF 39 TCV07 CV INTERNEDIATE LVL &FT TENP 47 69.8 6009 XBF 40 TCV08 CV INTERNEDIATE LVL 6FT TBF ()8 69.8 -. 6009 IHiF 41 TCV09 CV INTERNEDIATE LVL &FT TBF 49 69.8 'ma DE6F 42 TCV10 CV INTERNEDIATE LVL &FT TENP 410 69.8 600D 43 TCV17 CV OPERATlNG LEVL &FT TENP 417 67.8 GOOD DEGF
NOV 17~ 1993 15:29 R. E. GINA SII(ULATOR PAGE 1 TREND GROUP ASSIGNtKI(T SUt(t(ARY 6ROUP: EVENT1 PROCEDURES EPIP 1-5 PLA)IT STATUS POINT ID DESCRIPTION VALUE E. U. 1 ATMS ANTICIPATED TRANSIENT W/0 SCRAt) ATWS ALRt( 2 RXT REACTOR TRIP BRENER STATUS RX TRIPPED ALRt( 3 N31 SMICE RAN6E DETECTOR N-31 3.27340401 6009 CPS N32 SONCE RANGE DETECTOR N-32 3.36511%1 6009 CPS 5 N35 INIERIKDIATE RANGE DETETOR N-35 1.00461-11 6009 At(P 6 N36 INTERtKDIATE RANGE DETKTOR N-36 1 ~ 00461-11 6009 At(P 7 NP AVERAGE NUCLEAR POWER .00 GOOD X 8 PRCS REACTOR COOLANT SYSTB( AV6 PRESS 6. LAL)I PSIG 9 LPlR PRESSURI2ER AVERAGE LEVEL .0 LAUI X 10 FRCLA REACTOR COOLANT LOOP A AV6 FLOW .0 INHB X 11 FRCLB REACTOR COOLANT LOOP 8 AVG FLOW .0 INHD X 12 RXT16 RCPA BREAKER CAUSE R)( TRIP TRIPPED ALRt( 13 RXT17 RCPB BRENER CAUSE R)( TRIP TRIPPED ALR)( 14 TSUBTC INCORE TC SUBCOOLED t(ARGIN 92.6 600~ DEGF 15 LS6A STt( GEN A NARROW RAKE AV6 LEVEL 81.0 HALt( X 16 LSGB STN GEN 8 NARROW RANGE AVG LPiEL 100.0 HENS X 17 PSGA STN GEN A AVERAGE PRESSURE 0. LALII PSIG 18 PSGB STtl GEN 8 AVERAGE PRESSURE 0. LALt( PSI6 19 GENBKRl GBERATOR ON LINE BRENER 161372 TRIPPED ALR)I 20 GEMNR2 GE%RATOR ON LINE BRENER 9X1372 TRIPPED ALR)I 21 BUS11A BUS 11A SUPPLY BRENER TRIPPED ALR)I 22 BUS118 BUS 118 SUPPLY BRENER TRIPPED AUW 23 BUS 12A NOT TERt(INATED Oti PPCS (7/19/91) NOT TRIP DEL 24 BUS)28 NOT TERIIINATED ON PPCS (7/19/91) NOT TRIP DEL 25 811A12A BUS iiA TO 12A TIE BRENER NOT TRIP ALRt( 26 8118128 BUS 118 TQ 128 TIE BRENER NOT TRIP ALRI( 27 PCV CONTAIQKNT AVERAGE PRESSURE .66 6009 28 LSUI(PA CONTAI)WENT SUI(P A AVERAGE LEVEL 31.2 HENS 29 L0942E SUIP 8 LEVEL 8 INCHES (TRAIN A) HIGHER INHD 30 L0943E SUtP 8 LEVEL 8 INCHES (TRAIN 8) HI6HER Ita) 31 L0942D SOP 8 LEVEL 78 INC)KG (TRAIN A) HIGHER INHD 32 L0943D SUtP 8 LEVEL 78 INQKS (TRAIN 8) HIGHER INHD 33 L0942C SUtP 8 LEVEL 113 INCHES(TRAIN A) HI6HER ALRI( 34 L0943C SUIP 8 LEVEL 113 INCHES(TRAIN 8) HI6HER ALR)( 35 L09428 SmP 8 LEVEL 180 INCHES(TRAIN A) LOWER 600D 36 L09438 SUIP 8 LEVEL 180 INCHES(TRAIN 8) Gm 37 L0942A SUtP 8 LEVEL 214 INCHES(TRAIN A) LOWER 6009 38 L0943A SUNUP 8 LEVEL 214 INCHES(TRAIN 8) L(WER 6009 39 T0409A RCLA HOT LEG TB(PERATURE 124.2 6009 40 T0410A RCLB HOT LEG TB(PERATURE 124.2 - 6009 41 T0450 RCLA COLD LEG TE)PERATNE 124.4 6009 42 T0451 RCLB COLD LEG TBIPERATNE 124.1 6009 43 TAVGAWID RCLA TAVG (THOT/TCOLD WIDE RN6) 124.3 GOOD 44 TAVGBWID RCLB TAVG (TNT/TC(LD WIDE RNG) 124.2 6009 45 LRV REACTOR VESSEL AVERA6E LEVEL 90e4 GXD 46 TCCORE Ei.i INCORE TC AVERAGE TBP 128,2 600e 47 FAUXFWA 6/6 A tate. AUX FEEDWATER FLO(( 0. GOM 48 FAUXFWB S/6 8 TOTAL AUX FEEDWATER FLOW 0. 6009 49 BKR081 NTR AUXILIARYFEEDWATER PU)P A OFF 6009 50 BKR082 NTR AUXILIARYFEEDWATER PU)P 8 OFF GOOD 51 V3505 AUX FW P(WP STEAt( SUPPLY VALVE A CLOSED 6009 52 V3504 AUX FW PUt(P SIEA)I SUPPLY VALVE 8 CLOSED GOOD
NOV 17'993 15:29 R. E. GINA SIILATOR PA6E 2 TREND 6ROUP ASSIMENT SUNNRY 6ROUP: EVENTi PRXEDURE: EPIP 1-5 PUOT STATUS 0 53 POINT ID FSIA DESCRIPTION SAFETY INJECTION LOOP A AVG FLOM VALUE 0. QUAL 6009 E. U. GPN 54 FSIB SAFETY INJECTION LOOP B AV6 FLOM 0. 6009 GPN 55 P21b0 SERVICE MATER PtIPS A h B HEADER 87. 6009 PSIG Sb P21b1 SERVICE MATER PNPS C h D fEADER Bb. 600D PSIG 57 NR041 SERVICE MATER PNP A GOOD 58 NR042 SERVICE MATER PNP B 6009 59 NR043 SERVICE MATER PNP C 6009 b0 NR044 SERVICE MATER PNP D 6009
NOV 17~ 1993 15:30 R. E. GINA SINU)TOR TREND 6ROUP ASSIS)ST SUtmARY GROUP: EVENT2 PROCEDURES EPIP 1-5 PLANT STATUS P01NT ID DESCRIPTION E. U. 1 F0619 COtPONENT COOLING LOOP TOTAL FLN 6493. 600 D GPN 2 LR)ST REFUELINB NATER STORAGE TAN LVL 14.6 LNRtt 3 NS033 33 FOOT LEVEL NIND SPEED 5.2 600D AH 4 N$33 33 FOOT LEVEL ilIND DIRECTION 64. 6009 IKB. 5 NT033 33 FOOT LEVEL TE)tPERAIURE 49.1 6009 DE6F 6 NT250 250 FOOT LEVEL TE)lPERATURE 49.0 GOOD IHF 7 NDT2 250 TD 33 FOOT LEVEL DELTA TE)tP -.1 600D DE6F 8 Roi AREA HXNTROL ROOtl 9.22572M 6009 N/HR 9 R02 AREA 2~AINtK)tT 2.90067M HAUl N/HR 10 R05 AREA 5-SPENT FUEL PIT 1.00577+00 6009 N/HR 11 R09 AREA 9~0@ LINE ttONITOR 2.88402+01 6009 tS/HR 12 R34 AREA 34 AUX BLOB CV SPRAY PUtlP 9.8852@01 6009 N/N 13 R35 AREA ZrPASS SANPLE PA)KL 1.09648+00 6009 N/HR 14 R10A CONTAINtKNT IODINE NNITOR R10A 9.78647+06 HAUl CP)t 15 R11 CONTAIN)KNT AIR PARTIMATE 9.744ZHOb .HAUl CPN 16 R12 CONTAIN)KNT GAS t)ONITOR 1.01303%7 HENS CPN 17 RiOB PLANT VENT IODINE NNITDR R109 9.63272+05 HAUf CPN 18 R13 AUX BLDG EXHAUST AIR PARTIMATE 2.6039M2 GOM CPN 19 RI4 AUX BLDG EXHAUST BAS mlTOR 5.27077+01 600D CPtl 20 R18 LIQUID MASTE DISPOSAL NNITOR 1.0321&t03 6009 CPtl 21 R19 SIGN GENERATOR SLSiDOO DRAIN 2. 10438+03 GOOD CPtl 22 R29 AREA 29~AIN)KNT HI6H RANGE 2.99398+02 HALN R/HR 23 R30 AREA 30-COMTAINNENT HI6H RANGE 2,99398+02 HALN R/HR 24 R15 CONDENSER AIR EJECTOR EXHAUST 1.39035>03 600D CPtl 25 R12A5 CV VENT CHAN MN RAN6E GAS 4.2051H5 XI/CC 26 27 R12Ah R12A7 CV VENT CS)N CV VENT CHAN h~ 7+ID GAIN RAN6E GAS 2,00000k00 4.2051M5 GOOD GOOD 600D N/HR UCI/CC 28 R12A9 CV VENT CHAN 9+IGH RA%E BAS 9.99987-04 6009 XI/CC 29 R14A5 PLANT VENT CHAN MON RANGE GAS 2.30991M 600D UCI/CC 30 R14A7 PLANT VENT CHAN 7+ID RANGE 6AS 9.98974M 6009 Xl/CC 31 32 33 R14A9 R15A5 R15A7 PLANT VENT AIR EJECTOR CHAN ~ CHAN MIBH RANGE GAS 2.20996M RANGE GAS AIR EJECTOR CHAN 7+ID RAN6E BAS 6.2298~ 1.80975-05 6009 GOOD 6009 UCI/CC UCI/CC XI/CC 34 R15A9 AIR EJECTOR CHAN 9+I RAN6E 6AS 1.52999M GOOD UCI/CC 35 R31 AREA 31 STEA)t LINE A lSPING) 3.61997M 6009 tS/HR 36 R32 AREA 32 STEAtl LINE B lSPING) 3.61997-03 6009 N/HR 37 CVH CV HYDROGEN CONCENTRATION .0 6009 X 38 TCV03 CV BASE)KttT LEVEL 6FT TENP t)3 72.1 600D DEGF 39 TCV07 CV INTERNEDIATE LVL 6FT TBP t)7 70.0 6009 DEGF 40 TCV08 CV INTERtlEDIATE LVL hFT TE)tP t)8 7O.O-. 6009 IKGF 41 TCV09 CV INTE)MEDIATE LVL 6FT TEttP f9 70.0 600D DE6F 42 TCV10 CV INTERtKDIATE LVL 6FT TE)tP 010 70.0 6009 DE6F 43 TCV17 CV OPERATINB LEVL 6FT TEttP CI7 68.1 GOOD XGF
NGV 17~ 1993 15;44 R. E. GINA SIN(!LATOR TREND MUP ASSIBNNENT SUNDRY GROUP: iMNf PRXEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION VALUE I)AL E. U. 1 ATWS ANTICIPATED TRANSIENT W/0 SCRAN ATWS ALRN 2 RXT REACTOR TRIP BREAKER STATUS RX TRIPPED AUI 3 N31 SO(ICE RANGE DETECTOR N-31 3.56860101 6009 CPS N32 SG(ICE RA%E DETECTOR N-32 3.29609%1 6009 CPS 5 N35 INTERNEDIATE RANEE DETECTOR N-35 1.00461-11 GOM ANP 6 N36 INTERNEDIATE RANEE DETECTOR N"36 1.00461-11 6009 QP 7 NP AVERAGE NUCLEAR POWER .00 6009 8 PRCS REW:TGR COOLANT SYSTEN AVB PRESS 6. LALN PSIG 9 LPIR PRESSURILER AVERAGE LEVEL .0 LALN 10 FRCLA REACTOR COOlANT LOOP A AVG FLOW .0 INHS X li FRCLB REACTOR COOLANT LOOP 8 AVB FLOW .0 INH8 12 RXT16 RCPA BREAKER CAUSE RX 1RIP TRIPPED AUI f3 Rxjij RCPB BREAKER CAUSE RX TRIP TRIPPED ALRN 14 TSUBTC INCORE TC SUBCOOLED NARBIN 95.0 600> BEEF f5 LSBA STN BE)i A NARROW RA%E AV6 LEVEL 83.5 HALN 16 LSGB STN BEN 8 NARROW RANGE AVB LEVEL 100.0 HENS X 17 PSBA STN GEN A AVERAGE PRESSURE 0. LALN PSIG 18 PSEB STN 6EN 8 AVERAGE PRESSU!(E 0. LALN PSIG 19 BE)IKRl GEtHIATOR ON LINE BREAKER 161372 TRIPPED ALRN 20 GENBKR2 EE%RATOR ON LINE BREAKER 9X1372 TRIPPED ALRN 21 BUS11A BUS 11A SUPPLY BREAKER TRIPPED ALN 22 BUS118 BUS 118 SUPPLY BREAKER TRIPPED AUI 23 BUS 12A NGT TERNINATED ON PPCS (7/19/91) NOT TRIP DEL 24 BUS128 NOT TERNINATED Gt( PPCS (7/19/91) NOT TRIP DEL 25 811A12A BUS 11A TG 12A TIE BREAKER NOT TRIP ALRN 26 8118128 BUS 118 TG 128 TIE BRENER NOT TRIP ALN 27 PCV CONTAINNENT AVERAGE PRESSURE .66 6009 28 LSI(PA CONTAINNENT SUNP A AVERAGE LEVEL 31.2 HENS 29 L0942E SU)P 8 LEVEL 8 INCHES (TRAIN A) HIGHER IN)I 30 L0943E SUtP 8 LEVEL 8 INCHES (TRAIN 8) H16HER INHB 31 L09429 SU)P B LEVEL 78 INCHES (TRAIN A) HIGHER INHH 32 L0943D SU)P 8 LEVEL 78 INCHES (TRAIN 8) HIGHER INHB 33 L0942C SUtP 8 LEVEL if3 INCHES(TRAIN A) HIGHER ALRN 34 L0943C SUtP 8 i&EL 113 INCHES(TRAIN 8) HI6HER ALI 35 L09428 SUtP 8 LEVEL 180 INCHES(TRAIN A) L(IER 6009 36 L09438 SU)P 8 LEVEL 180 INCHES(TRAIN 8) LOWER 6009 37 L0942A SUtP 8 LEVEL 214 INCHES(TRAIN A) LG)(ER 6009 38 L0943A SUtP 8 LEVEL 214 INCHES(TRAIN 8) LOWER 6009 39 T0409A RCLA HOT LEG TENPERATURE 123.4 6009 40 T0410A RCLB HOT LEG TEt(PERAlUK 123.4 -. 6009 41 T0450 RCLA COLD LEB TENPERAT(IE 122.7 '-6(ID 42 T0451 RCLB COLD LE6 TENPERAT(IE 122.4 6009 43 TAVBAWID RCLA TAVE (THOT/TCOLD WIDE RNE) 123.1 60(m 44 TAVGBWID RCLB TAVE (THOT/TCOLD WIDE RN6) 122.9 6009 45 LRV REACTOR VESSEL AVERAGE LEVEL 90.5 6009 46 TCCGRE El.l INCGRE TC AVERAGE TENP 127.9 600~ 47 FAUXFWA S/6 A TOTAL AUX FEEDWATER FUN 0. 6009 48 FAUX RI S/6 8 TOTAL AUX FEEDWATER FLOW 0. 6009 49 BKR081 t(TR AUXILIARYFEEDWATER PUNP A OFF, 6009 50 BKRO82 NTR AUXILIARYFEEDWATER PUNP 8 OFF 6009 51 V3505 AUX FM PUtP STEAN SUPPLY VALVE A CLOSED 6009 52 V3504 AUX FW PU)F STEAN SUPPLY VALVE 8 CLOSED 6009
NOV 17~ 1993 15:44 R. E. GINA SINLATOR PAGE 2 TREND GROUP ASSIGNNENT SUNARY GROUP: EVENT1 PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION QN. E. U. 53 FSIA SAFETY INACTION LOOP A AVG FLN 0. GOOD GPN 54 FSIB SAFETY INECTION LOOP B AV6 FLON 0. 600D GPN 55 P2160 SERVICE NATER PlNPS A 5 B HEADER 87. 600D PSI6 56 P2161 SERVICE NATER PINPS C h D HHKR 86. 600D PSI6 57 NR041 SERVICE NATER PlNP A GOOD 58 NR042 SERVICE NATER PINP B 6009 59 iNR043 SERVICE NATER PtNP C GOOD 60 NR044 SERVICE NATER PINP D 600D
HOV 17~ 1993 15:45 R. E. GINA SINLATOR TREND 6ROUP ASSIMENT SUt(t(ARY GROUP: EVENT2 PROCEMKl EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION E. U. I F0619 C05%NENT COOLINB LOOP TOTAL FLM 6493. 6009 6PN 2 LRMST REFUELINB MATER STORAGE TANK LVL 14.6 LMRN X 3 MS033 33 FOOT LEVEL MIND SPEED 3.7 GOOD le 4 ¹9033 33 FOOT LEVEL MIND DIRECTION 67. 6009 DEG. 5 ¹T033 33 FOOT LEVEL TEISATURE 49.5 6009 DE6F 6 MT250 250 FOOT LEVEL TBPERATURE 49.6 6009 IKBF 7 MDT2 2SO TO 33 FOOT LEVEL DELTA TEIF .1 GOOD IKGF 8 ROI AREA I<Ot(TII(X ROOt( 9.22572M 6009 t8/HR 9 R02 AREA 2~AIQKNT 3. 14411+05 HALI( t8/HR 10 R05 AREA 5-SPENT FUEL PIT 1.0232960 BOX t8/HR 11 R09 AREA 9-LETDO¹N LIHE t(ONITOR 2.75423+01 6009 l8/HR 12 R34 AREA 34 - AUX BLDG CV SPRAY PUNP 9.44062<1 6009 t8/HR 13 R35 AREA ~ASS SNPLE PQ8. 1.09648M 6009 t8/HR 14 RIOA CONTAINNEhT IODINE NNITOR RIOA 1 ~ 00432+07 HEHB CPt( 15 Rl1 COHTAINI(ENT AIR PARTICIIATE 1.01741+07 %NB CPN 16 R12 CONTAIN((ENT BAS NNITOR 1.04864M fENB CPt( 17 RIOB PLANT VENT IODINE !SNITDR RIOB 9. 84289+05 HALII CPN 18 ,R13 AUX BLOB EXHAUST AIR PARTICULATE 2.55932+02 6009 CPtI 1'9 R14 AUX BLDG EXHAUST NS NNITOR 5.69671+01 6009 CPtl 20 R18 LIOUID MASTE DISPOSAL tSNITOR 1.05925+03 6009 CPtl 21 R19 STEAt( GENERATOR BLMSO DRAIN 2. 06835KK3 6009 CPt( 22 R29 AREA 29~AINI(ENT HIGH RAN6E 2. 99398+02 HALt( R/HR 23 R30 ARE'A 30<ONTAItST HI% RANGE 2.99398%2 HALI( R/HR 24 R15 CONDEHSER AIR EJECTOR E(HAUST 1.46428+03 6009 CPN 25 R12AS CV VENT CHAN MOM RANK GAS 4.2051 1M 6009 XI/CC 26 27 R12A6 R12A7 CV VENT CV VENT CHAN h~ 6ANA CHAN 7+ID RANK 6AS 2.000MOO 4.20511M 6009 6009 I8/HR UCI/CC 28 R12A9 CV VENT CSN 9+IBH RA%E BAS 9.99987M 6009 XI/CC R14AS PLANT VENT CHAN MOM RANGE NS 2.30991M 6009 XI/CC 30 R14A7 PLNT VENT CHAN 7+ID RANGE 6AS 9.98974M 6009 Xl/CC 31 R14A9 PLANT VENT CHAN MIGH RANGE NS 2.20996M 6009 Xl/CC 32 R15A5 AIR EJECTOR CHAN MO¹ RANGE NS 6.22985-06 6009 UCI/CC 33 RISA7 AIR EJECTOR CHAN 7+ID RANGE NS 1.80975-05 6009 UCI/CC 34 RISA9 AIR EJECTOR CHAN 9+I RANGE BAS 1.52999<3 6009 UCI/CC 35 R31 AREA 31 STEAtI LINE A (SPIHB) 3. 61997M 6009 t8/HR 36 R32 AREA 32 STEAN LINE 8 (SPINB) 3.61997M 6009 t8/HR 37 CVH CV HYDROGEN CONCENTRATION .0 6009 X 38 TCV03 CV BASEtIENT LB%1 6FT TEt(P <<3 72.4 6009 IK6F 39 TCV07 CV INTERI(EDIATE LVL 6FT TEI(P <<7 70.3 6009 DEGF 40 TCV08 CV INTERHEDIATE LVL 6FT TEt(P <<8 70.3 . 6009 IKGF 41 TCV09 CV INTHNEDIATE LVL 6FT TBP <<9 70.3 '6009 DEGF 42 TCV10 CV INTERt(EDIATE LVL 6FT TEMP <<10 70.3 6009 IKBF 43 TCV17 CV OPERATIHB LEVL 6FT TEt(P <<17 68.2 6009 IKGF
R E GINNA STATION Intermediate Buifding North - Basement Leve Technician: Date: Time: Inst. Type: Serial er'e: / Power: LLO Note: All readings are in mr/hr unless otherwise noted. rrerelrrraa eaP No. Opmr lQOamg C p 0 07:3049:10 All Areas (--N (Clean) Radiation Levels 0.01 mR/hr rOO( Smears
'i rO Containment 250(j pm Airborne Activi iodine=1 E-11 uCi/cc Part.=1E-10 uCl/cc
'rp inc Ip~
."riven
~ ~
~ ~
0 Su X FIN ~ ~
"A;9 w weCAhl u(Orn0 aux FW- ,~00 Pumo Qil IOrx 553r @0 0 0 Oa 0
"hrilerq 0
VOtO( 9riven Aux, r"W PurnpS OO
¹ = Smear Location -x-.x- = Rad/Cont. Barrier 4 Cont. Area Radiation Level ¹', = Neutron Radiation Level i ~
I High Cont Area .¹c = Contact Reading ;I
.I
+ Radiation Area Technician Remarks: ~ + High Rad. Area i' Locked High Rad.
R.E.GINNA STATION Intermediate Buifding North - Basement Level Technician: Date Time: Inst. Type: / Serial ¹'a: I Power: Ll 0: Note: All readings are in mr/hr unless otherwise noted.
~ ra(tart(as aep tr rQ ) B No. a pmr l Oocm2
~ r(
/
0 B A B 0 09:10-10:30 0 poor Radiation Levels 36 Containment A=3m R/hr L 8=0.6mR/hr
~
A Smears 250dpm
', t~MII Ip~ iodine=1 E-11 uCi/cc
.ro(nS pneen Part.=1E-10 uCi/cc
~ ~
Aux FW ~
~
tt
-ump 0
Oo 0 poor '7 ((Q A
,~gQ B Turbine Aux FW-
>urrtp Pil 5 5 3 @0 it 0o((
rS B 0 0 o S 0 0 r n((((t r et 0 0 0 MOIOr Onven AuxP((r Pumps 00
-x-.x- = Rad/Cont. Barrier l
Smear Location Cont. Area Radiation Level ¹', = Neutron Radiation Level ) ( (,e ir High Cont. Area ¹c = Contact Reading :I Il
+ Radiation Area Technician Remarks: ~+ High Rad. Area Locked High Rad.
R.E.GlNNA STATlON intermediate Building North - Basement Level Technician: Date: Time; Inst. Type: / Serial ¹'a: / Power: LLD: Note: All readings are in mr/hr unless otherwise noted. Irrrrartrss eap No. B 4pmr 1oocm2 g A 0 10:30-1 5:00 Radiation Levels A=37m R/hr Ooor B=17mR/hr eo I Q Containment Smears B 2504pttl 0 ~Aia a ti i iodine=1E-11 uCi/cc Part.=1 E-10 uCi/cc g )o
'roinS Lnr,von
~ ~
Aux rR ~ ~
~ ~
- mo Ooar Tur0tns
>ux FW-
?ump Qtl
,~OG B i:i r 0
Tang
'o8 0 O O B
.httlqrea 0
tAofor Driven Aug. FW Pumps OO
¹ = Smear Location -x-.x- = Rad/Cont. Barrier Cont Area Radiation Level ~¹' Neutron Radiation Level f r%l High Cont. Area
,i
¹c = Contact Reading .'I + Radiation Area Technician Remarks:
.~
- f "+
High Rad. Area Locked High Rad.
I%I.ONNA STATlON Technician: Dare: Time: IINSI $0gh - Tyy ~ lorn.~re: Mote: AN readl ate in wtlttf 4~140 o&orwiio not Jamt $ 7
~100orn j ter 07:3049:10 All Areas Containment (Clean)
Radiation Leve)s 0.01mR/hr . Smears 260dpm a~id a ~ i iodine=1E-11 uCi/cc Part=1E-10 uCi/cc refers 0
~
a Smsm Looedon .a-x. ~ nedlConL Sardsr e Cut. Atia
- Qt ~
~ Sereelon Level ~ Nernron Ihreeeon Level Qe ~ leon QNff. Area
'A! ~ Concecc AaicÃno ~ ~ geagon Aroi Wsohnlrdmr nsmenrs: Qi ~ lnyn use. Area
~ Leh& 'High Rad.
Atee
R.E.QINNA STATlON Technician: Date: 'Hme: Inst. Typo: I Seri ~ I <<'e: I Pevrer. Note: All readinQO are in mr/hr unleaa otgerwlee not
~ $7 Ne. 4Sml100crn2 I
I (A fq l 09:40-10:30 Containment Radiation Levels A=3m R/hr frat atn a B=0.5mR/hr Smears 250dpm
~ill h II ti I iodine=1E-11 uCi/cc B 0 Part.=1E-10 uCi/cc Ethetlst
, FDR Atla C
~ Smear Locathn -x-x- a Rad/Cont. Barrier Cont. Area
- QN
!g. ~ Radlatlen Level 'Ne ~ Contact Realng
~~ Meutran Sad!ation Level Qe Ngh Cont. Area Radladon Area Teehlllelen Rameftte: Qo Ngh Rad. Area
~
~ R L,ochod High Aad.
Area
R.e.elNNA ITATlON Technician: Data: lime: lnit.Ty: Ser/el g'e: / Power'. LLD: Note: All FeatHAOO ere ln mr/hr unleaa otherwlle nota!. Fdo. dnttt/100ont2 I r a Bl (A 10:30-10:50 lg Radiation Levels A=37m R/hr B=17mR/hr Containment Smears 250dpm Fe A arm Airborne Activi Iodine=1E-11 uCi/cc Part.=1E-10 uCi/cc B Fe I arm l a B 0 FCR At/I C Q+ 40 ~ dmem Looadon
~ Radladon Lar/al Corltaot Rainy
~ chnkQan Ramarkae
~
.a-a. Rad/Cont. earner
~ lr/atman Ra@aden Larrel
~
Qe Q~
~ Com. Area w Hdtl Cont. Area a gacga50tl Area
~ Nyn Rad. Area
~ ~ Locked High Rad.
Arae
8,8.0!NNA ITATlON Ittilg Ious) - Top Lewl Technician: Dace: Time: lnit.Type: I Serial s': I Power. LLD: Nato: All reecllnNN ere in fnrlhr unteee atherwiie nated. I Ho. dhrccs100errc1 I I (CAN C 10:50-12:50 Radiation Levels Containment A=6R/br B=1R/hr C=500mh/hr 0=37mR/hr Smears 5,000dpm Airborne Activi A iodine=3E-9 uCi/cc Part.=9E-9 uCi/cc D Kcleuct FCR ACS C e Smear Location -x-x- e Ihd/Cert. Barrier e
~
'A QN
~ Rsrhsdon Level e Contaot lteatlnl peahnlcden Rsmarhs:
+ a Mscnron Radiadon Level
~
Q~ e Cont. Area Q~~ Ngh Conc. Area a gNIation Aree
~ RhNc Rsd. Area Q~ Lashed High Rad.
Area
8,5.6WNA STATION Technician: Date: Yama: Inst. Type: Serial a': I Pawan Note: All res~ are in mr/hr unless otherwise noted. l.LD: 3aet $ 7 Ne. t! Rrrtl1OOarrt2 ! 12:50-15:00 Containment bhse Radiation Levels re ate A-37m R/hr B=50mR/hr
~ears A=3000dpm B B=5000dpm me Activi locI~2E-9 ulcc Part~2E-9 uCI/cc btaa re ats B
(,x~
~
ron Atra
~ Smas Laaattan .a-a. a WCant earrlar.
Qt .'.W ~ Ratiatlan Latrel 'W ~ Contaot Raasnl Pe:ltnlalan Ramartta:
~ ~ Matnran Raatattan Lawl Cont. Area Nyh Cont. Area Itsa5on Area Nyh Ral. Area Locetod High Rad.
. Araa
8, j.QNIA ITATlON Date: ttme: fnet. TV': Sar(el a': I Power: LLD: pote: All reedl~ eM in rnrlhr unieae otherwiee noted. 3oor d yrttr 1 OOarn2 Ooor I 45 a6 L(OOr Control Point / Sigh wrh Oestt 07:309 l0 Contoittmettt All Areas (Clean) Radiation Levels 0.01m R/hr Smeara 250(I pm Httcteor l Somttte l ~ale a ti I Room I iodine=1E-11 uGilcc. Part.=1 E-10 uCi/cc Possttoa ttuctettr Somttte Shed
<Pa r;tt~ .NJ ~ Smear Local -x<<x- a IbcUCorn. Iarriw ~ ~ Can. Area w nadtadon Level ~z w rtaotron ttadtadon La(rat Q~ w Nyh Cont. Area
,Ne ~ Contact Baaing ~ Satiation Area ,7eehnician ltemarhs: Q w Neh ttad. Area Locit& High Red. Area
ll.f.tINNA STATION +++meow- + am' Tachyon: tnat. Ty~: I Cats'rillo! OerISI a 'e Note: All reedll> ate ln Qf/Q Mggygg
~00r
)
toe. Setter tOOsnng,
~6 ioot
( 5f Cottttot Poet Sett-In
/
Oesh t A 09:10-10:30 Continment Radiation Levels A=3m R/hr B=0.5mR/hr
'nrears l4eleor t 2500PITI Satek t l~liH A*ti i toots I iodine=1E-11 Posseoa uCi/cc uCi/cc'art.=1E-10 A
tQ e em'ocation -x-x- e Had/Cona Senior a Ccet. AN
- g. ~ Wsihsnon Least +i
~ Nsntron hsrhsoon Lsvd O~ m Noh Cont. Ares 4e ~ Coetect AeaNni e ga5gion Area tWachnklln Itemarle:
Om Ngh SNL Ares
~m 4ggg4 High Red.
area
R.I.ON%A SYATlOH TecttlllcQfli limo: inane. Type: I OoaaI a': I aoww: Motl,'ll PIOOI~ ere ill nlr]ill Mggggg O~~
~ OOI
<d ioo<
(o COIItrOI Poet / Sign iII Oem
) A 10:30-15:00 ContainmM Radiation Levels A=37m R/hr B=17mR/hr
/meara 250dpm
~g Noes irborne Activi I iodine=1E-11 uGi/cc',
POSSOoo Part.=1E-10 uci/cc j
+gJ a w goISoooo
',4e ~ Contact hoedlnO ,WOehniC{an
~
eggs LOgg+0 -I a. a RSdlCNt Itemarha
~l hAt w NAIIIIoll OAIlolloo Lily
~ m Qo
~
Q+ w
~
~
CeeL A%a OOOI. Ataa RQSRSodl ArII w IOgII NNI. Afoa
~ed Hlgn Had sew
R.B.QINNA STATlON +'IQ Ioutft - Iasesnent Level Technicisn: pete: Time: inst. Type: Seri ~ I <<'e: r Power: pote; fA)( res4ing ere in mr/hr unless otherwise noted Nt. 4nmf100em1 Ooof 3b
'o -o{ Shoo <---
I IA I Hydfagtn f 4 {Teaamarntr I.a{fndfy oane{S an{is re i I i.ontginment 07:3049:10 CI{emrcaI All Areas Ofaln Tant (Clean) Radiation Levels 0.01mRlhr smears 250dpm Airborne Activi odine~1E-11 u ilcc. Part.-"1E-10 uCilcc Saent Ftft{ TfiI C-- traIItd Aaatss Fons Sirrmmtr Fii{tr --> 0 Smear I eeet{all -x x > Ilail/aollt. terr{el ~ Corlt. Area
~ RaHatkm Level ~ Neutron RaNstkn Level Qo w Nth aoot. Area c ~ Contact Reading ~ Ralathn Ares Techrldan Rlnsrlts: Q~ w Hit{1 gat. Arel
~ Lociteci High Rsd.
Area
R.K.QINNA STATIC~ Tochnfclan: Inst. Type: Seri ~ I <<'a: I sower: I I 1: Note: All reidlnge ere In mr/hr unites otherwlae noted. Ne. Ehrttr 100ortt1 p O "Ol ShOO <--- 4 I rrIraroqen I Coccmorner iaunarg oan etc CnsS I I I l Containment
~ ~ e f 09:10-10:30 1:homrcct Qrarn lane Radiation Levels A A=3m R/hr B=0.5mR/hr
/meara 250dpm Irbome Activi odine~1E-11 uQ/cc Part"-1E-10 uci/cc A
~ sar SOent Fuet >it
--)
Qw i c aA4 Aeeoes; Fons 5trrmmtr Filttr 0 ,Qo ~ Smear Loostlon .x-x. e ltert/Cont. center ~ m Cont. Area
~ I4dlatlon Level ~ Neutron Radiation Level Qa n Noh ContAree.
~ Contact Reading e ga¹atlon Area T~nidan Remarita: Q~ Ntth rtsrt. Ares 0 Ane Looted High Rad
h.5.0lNNA STATEN Technician: Inst.Ty pe: serrel a'e: I power: r.Ln: Note: All reedlngO ere fn mr/hr unleae othe~le noted. dyrsM100orn j o ol >rroD wy410gdn I QdCom0rndf
".aundty owners dna' I >8 l
)
1 COhtalhmeht o ~ ~ e f 10:I'-15:I Chdmrdcl OIOln fane Radiation Levels (A A=37m R/hr B=17mR/hr
/meara 250dpm irbame Activi odine<1E-11 uCi/cc Part~1E-10 uCi/cc A
S~t F.df Ot 5irrmmdf Filfyr Qres i-- roNN Access Fee Qt w S.maar LOaadsn
~ haclelon Level
-X-X. w nadiCOiir. larder
~ Neut en hacgalon ~ ~
Q>>
~ ConL Argo w Ngh COIIL ursa
~ Contact loa4ny 7whnicSen Ranee: Q m
~
~ Itsation Aru
~4 nsd. Area High Rid Atw
R.K.QINNA STATION Technician: Dsts! Tllll~: Inat. Type: Serial <<'s: r power: LLD: Note: All readings're in mr/hr unleaa otherwiso noted. SSSMIOOsnlg Oooc 38 O "Ol SIIOO (--- IA I IIrOcopen I oeoonISIner 1.OIIndnr Den eIS OnNS 18 I I 8 B Containment 10:30-15:00 t:hemrool DURING PA$ $ Qcoln Tonk OPERATION Radiation Levels A=3R/hr B B=500mR/hr C=50mR/hr Smears All Areas=250dpm ale'A t'R Iodine=1E-9 uCi/cc Part.=5E-9 uCi/cc So+i f.~ r t
--) C W kCcea 'FOIS filter S1IImmer 0
Qt ~ Sms,w Locaoon -x-x. ~ SadlOonI. Sarrlsc ~ m ConL Atee
~ Re~n Lewi ~ Meueon Radletlon Level Oe ~ ISSS OanI. Area
~ Contacc leedlno e Iticlatlon Arel TechWten Romaine: Q a IQSS l4S. Area a Looite4 High Rtd.
Arw
R.E.GINNA STATION ,":trautrr~"Hotehop . Technician: Date: Time: Inst. Type: I Power: LLD: Note: All readlnQI are ln mr/hr unless otherwise noted. tao xaHop M No. 4pm1100cm2 rrnae Ooor 41 I X I Laundry PASS FLOW Monitor I s 07:30-1 5:00 x 0 P X Radiation Levels I X X t t A=50mR/hr
'=25mr/hr .
Ooor B X X X X X Smears 40 I s 250dpm a~Ma iP x 0 I P ~ i Iodine=1 E-11 uCi/c I X Part=1E-10 uCi/cc Id/' ~R.35 Ch Oecon Table 3R/hr A *1*NOTE 111 I CALL X X X I TSC (506) P BEFORE A STARTING S SANIPLE S I 0 FLOW I 0 I 4 0 0 t 0 0 0 ate ~e Snk
~ Smear Location -x-x- a Rad/Cont. Barrier ~ ~ Cont. Area l
~'c Radlatlon Level
~ Contact Reading
+ ~ Neutron Radiation Level Qi m High Cont. Area
~ Radiation Area Technician Remarks: Qim High Rad. Area
~ Locked High Rad..
O Area
Technician: Date: Tints: inst. Typo: Serial S'a: I Power: LLD: Note: AII readlnge are ln mr/hr unleee otherwlae noted. 4Rttt1100etttg Ooar 4t 'a X>>>>X>> I I Laundry X NO PASS FLOW Monitor I1 07:30-1 5:00 t a ( P All Areas X (Clean) I x x t ~ Radiation Levels 0.01m R/hi Ooor Smears 40 I-5 0 250dpm A tt ttt X R Ai& iodine=1 E-11 uCi/cc I X Part.=1E-10 uCi/cc I ~t535 Ocean X Table I 0.01 mR/hr
***NOTE'""
I
'X CALL
'X X>>>>'a'>>>> X>> I TSC X X (506)
BEFORE STARTING SAMPLE FLOW
>> grocer l.ocadon -x-x- >> RadlCont 4'c
>> Radlsdon Level
~ Contact Reading
+>> Bards.r Neutron Radiation Level Cont. Area High Cont. Area Radiation Area Technician Remarka: High Rad. Area Locked High Rad..
Area
R.E.GINNA STAT10N ::,~Pf@+4,,, ..~~~~~Hotsho'p;:.:. n Technician: Date: Time: Inst. Type: Serial ¹'e: I Power: LLD: Note: AII reading are In mr/hr unless otherwise noted. No. 4pntl10acrng fritaer Ooor 41 I I I I Laundry I PASS FLOW Monitor I1 07:30-15:00 I I a Radiation Levels I I I A=50m R/hr B=25mrlhr Ooar 40 B I I X 'I 'I Smears I 5 a 250dpm P Airborne Activi I Iodine=1 E-11 uCi/c I I Part.=1E-10 uCI/cc Oecon g Id' ~ll-35 di Table 3R/hr A ***NOTE*** I I CALL I I I I TSC (506) P BEFORE A STARTING S SAMPLE lI S FLOW 0 0 I Shop A 0 0 0 Sink ~ Sink
~ Smear Location -x-x- ~ Rad/Cont. Barrier
¹c a Radiation Level
~ Contact Reading g Neutron Radiation Level Qo
+
Cont. Area High Cont. Area Radiation Area Technician Remarks: Qo High Rad. Area Locked High Rad. '. Area
R.E.GINNA STATlON Technician: Date: Time: RWP/SWP ¹: inst. Type: / Serial ¹'a: / Power: LLD: ote: All readings are in mr/hr unless otherwise noted. Ct(ST~1.P¹P No. dpm/100cm2 DDD 07:30-1 5:00 All Areas (Clean) Radiation Levels 0.01mR/hr Smears 250dpm Airborne Activi
-x ---x ---x I
iodine=1E-11 uCi/cc Part.=1E-10 uCi/cc l X I I I X l ¹ = O Smear Location -x-x- = Rad/Cont. Barrier Cont. Area Radiation Level Contact Reading
+ = Neutron Radiation Level
+
High Cont. Area Radiation Area
~
High Rad. Area
~
Technician Remarks: Q+
+ Locked High Rad.
Area
I.I.ONNA STAY<~ TechrKclan: DeN: Tllne: fnat. Type: Sar/el e'; / power: Nate: +> rieti I ~ 'n Cnr/hr unleaa OtgICWiII nOt<<. No. dhnt/10Oo/n4 I r R-I8 I Spent Fuel Pit I C 07t30-09:10 A ! Oecon ~it I I T I All Areas W I I I HEPA Radiation Levels t A g Filttn I
'r I 0.02mR/hr Oren t
r Smears I 250dpm I t Airborne Activi iodine=1E-11 uCi/cc Part.=1E-10 uCi/cc
'roetrr .~ I transfer Cgeg SOP (.
Nder <t/RI SI~ RrRO
~ Srnsa Looatlon .a-a. e Rad/Cont harder
~ a Cont. Atia Qo
~
~ ~ Ra/Radon Level ~ Neutron Radlatlon Level pe ~ Nyh ConL Area P Ne e Contact laatlnl.
Technician lhmaclta: P'RRh gatiatlon Acoa Rad. Area I ~ Local HIQh R<< Ana
R.I.OWSA STATNlti e Technl64n: Inst. Type: Note: Atl rea
/
Date! Senal 4 s: TlIll~: 4m in mr/hr unlasa otherwilo noted. I powet: Me. SSRII100ontg I I R- I8 I l 0 SPent F'Llel Pit I C I
'f Oecpn t'it I 09:10-10:30 c
I I W Radiation Levels B ', A B A=3 mR/hr I Oren I B=0.5mR/hr c f Smears l I 250dpm I B Airborne Activi iodine=1E-11 uCi/r, I c Part.=1E-10 uci/cc I I SOIS (--
"ontte ~ I frORtf>>r CONS A M IIScr MINI SlOr>>g>> Iree
~ Smsa Loostlon -x-s. a Ran/Cent. Satnar ~ e Cont. Aru
,Qt
- g. Sedation Level
~
Ne ~ Coeact leonl.
+~ Rsunon Ranlanon Level 0'~ NSh Cont. Ates a NaNadon Area 7echnicien Ranatka: Qi a NSh Ran. A(aa 0 ~ Locke4 High Red.
Ane
R.E.QINNA STATlaN Technician: Date: lime: fnat. Type: Serial d e' Note: All readiISa ere in mr/hr unleia otherwise noted. Po r'LD: lgn. 4 Rmr100omg R-18 B I
'5 10:30-10:50 Spent Fuel Pit I C Deco'it A I Radiation Levels t 't I I A=37m R/hr W HEPA B=17mR/hr 8 A I 2 Filtca Smears t
OrCrn I , 250dpm t CJ I
'I Ai& A tl IIX I
iodine=1 E-11 uCi/cc t B Bridge Part.=1E-10 uCi/cc
'rostra .onto I Trangfgt COnal SOP l.
A Hgtr <ugl Slot Argg
-x-x- e Rad/Cont. Barrier Qd L.
Ne
~ Smear Location
~ Retgadon Level
~ Contact Raalno.
Tochrtician Remarlta:
~ ~ Metrtron Radiation Level Qe Qi m
m CoAt. Area Hlgll Cont. Area
~ Radiation Area a High Rad. Area L,ocltad High Rad I
Q Area
e Tao hniclll: Inat. Typo: Data: Sarr ~ I e'al Nota: All raadfele are in mr]hr unlaaa otharlIlriaa noted. Time:
/ Pewar:
No. dhrrtr 1 COerrtg I It'- I8 I 2 0 Spent F'ueI Pit 10:50-12:50 I C I t 2 Oecpn ~it A t T I 2 All Areas I l I 2 HKPA Radiation Levels I I l A Rlten 62R/h I prdrn
'r C. Smears I
r l 200,000dpm I Airborne Activi I iodine=4E-1 uCi/cc Part.=3E+0 uCi/cc
"~e .~ I lrCIISIRP Q~
SOP I
~ <uel Slat090 AtRO Qt ~ Smam Laesden -a-x. ~ Rad/Cant. Ssrrter ~ ~ Cont. Ates W ~ Rsrdadan Lmrel '
s Neutron Radladen Lmrel Qe s Ndh Cent. Ares 4e ~ Contact SoaNnl. ~ a Is¹edon Area Veehnlrdsn Rsmarla: 0 Ndh Rad. Area
~ L~ed Nigh Rad Aces
R.f.QINNA STATION Technician: Oate: Time: Inst. Type: / Seri ~ i a'e: I Power: Note: All reec&% ere in mr/br unless otherwise noted. No. ddrrrr100crng e-I8 I 1
'l2:50-15:00 e o o Spent Fuel Pit I C Oecon Pit A I Radiation Levels I
e T I A=37mR/hr N HKPA B=17mR/hr 8 A I g Filters Smears. l Ordrn x A 000,000dpm a I I x i~lid II ti I iodine=SE-7 uCi/cc S 8 8ndqe Part=2ER uCi/cc c SOP l--
'rind<<
B
.~ I Trongfet Conal aIder p<RI Sin woo Qg Ne a Sme<< i.ooadon Rardadan ~ Contact ReaNng.
TechrNciin Nemarita garrai
~
-x-x-m w Rad/Cone. Rani<<
aiarnron Radladon Larval Qe 0-Cont. Area Ngh Cont. Area
~tion Ngh I4ci. Area Area L,~el Htgh Rad.
Area
~ ~ ~ '
~ ~
<<4
=
RR W
~ 1
~ ~
I s ~ e ~
~ ~
0 0 ~ S K%I
~ ~
~: ~ ~ ~
~ ~
0
~ ~
Qe I. 0 0 ~ I ~
~ ~ ~ I ~ ~ ~
R.E.QINNA STATION NhR: TechnlcIIn: Date: Time: Inst. Type: Nots: All res~ s ~ ln mr/hr oolsss otherwise noted. d~100deng New Fuel Sioroge 10 30-10:60 Radiation Levels A=37mRIhf B=10mR/hf Oocr Smears. 29 250dprn Aifbofne Activi iodine=1E-11 uCilcc Part.=1E-10 uGilcc Penebothn. F'm 0 RH5T y s 0 0 0
'~ Smear Locatke. -x-x- a Rad/Cont..Barrier ~ ~ Cont. Arel w Radlatlon Level
~ Contact Reading
+ w Natrtron Radiation Level Ps w tRgh Cont. Area a gaciatioll Area Technician Remarks: P~ w Rtgh Rad. Area a l.odored High Rad Area
~ ~
N
~ ~ ~
if Itt ~ ~
~ ~
'pW
~ ~
- Qa I ~
~ I I ~ I ~ ~ I ~
~ ~ ~ ~
Acmic'j cc <<e R.E.QINNA STATION ,>ccccnccncrc <<acne censce"a .Ac "c cnr ccc " w 'ccc" . ecn a'-cc c n f Ir c Technician: Date: Ttclcs: Inst. Type: I Seri sr 4's: I power: LLD: Note: All raadlnle are ln mrihr unleaa otherwise noted. dftml100ertta r.. S New Fuel Storage 5 f ~~a~a~~~ f I 0 OOCC 12:50-15:g 29 Radiation Levels 17mRlhr
~ ~
( aagf ~meara 500,000dpm
~ ~
Pffnetrotion Fr+ a~64 c I Og iodine=6E-7 uCMcc Part~2EA uCllcc 0 0 C C W s 0 0 oc5 a Smear Location -x-x- a Rad/Cont. Barrier Cont, Area
~ Radiation level ~ Neutron Radiation i.evei Oe ~ Hlffh Cont. Area
~ Contact Reading a Radiation Area echniclan Remarks: Q~ a HIIh Rarf. Area
~ Locked High Rad.
O Area
a ~
~ '
)0 e~
e 0
~I
~O
~ ~
I ~ ~
~ ~ ~
~ ~ ~
K>s
~ ~
.gl )r
~ '
~ ~ ~ 0
~ ~
0
~ ~
~ ~ ~
~
~ ~
s Q a
~
~t 0 I I I I ~ ~
~ ~
~ ~
~ ~ ~
K>I gag t~ %$
~ '
~; ~ ~ ~ ~
~ ~ I ~
s ~
~ ~ ~ ~
RR St~ ~ e~ ~O
~
~W
~e
~ 1 II fit ~ ~
~ ~
~ ~
e ~ 0 a K5s Sg~
~ ~
~ ~ ~ ~ ~
~ ~ ~ ~ ~
~ ~
~ ~
~ ~ ~ I ~ ' I ~ s
~>> s~
~k a~a
~ ~
~
~
~
smAN w
~
'I~
~
W~ RR W~ ~W
~
I I I I I III III '
~ ~
~ ~
~ ~ ~
E>I
~ ~
.gP, La: 5
~; ~ ~ ~
~, ~ ~ ~
~ ~
R.E.GINNA STATlON :"".:."Aoidltiiijgsr'rgdin'@l~0g+4~%" Technician: o te: Tiara. inst. Type: Serial ¹'a: I power, LLD ote: Ail readings are in mrIhr i Auttgtrg.~ dlrttt/100cittg RWST
- o. 8 It oo Bus 16 A
CDT
~e C 8 Charcoal/HEPA CDT Filler MCC 1M 07:30 gp 5p C
CDT All Areas (Clean) Radlatton Levels D CDT 0.1mRIhr Smears 250dpm l~liH il i;4 sar OOQ O iodine=< E-'1 0 Part 1E 10 uCt/cc uCilcc 4 RC Filter Dl Vault 0 Q VCT Co OOQO
~ Smear Location -x-x- ~ RadICont. Barrier ~ ~ Cont. Area Radiation Level
¹c ~ Contact Reading
¹ ~ Neutron Radiation Level 0 ~ High Cont
~ Radiation Area Area Technic/an Remarks: Q' High Rad; Area
~ Locked High Rad.
Ares,
R.E.GINNA STATION 0- Technician: Cate: 'Rme: Inst. Type: / Serial ¹'e: I Power: LLD Note: All readings are in mr/hr unle oth Autorr'.gyes tlptttl10Octttg RWST tt0 0'us 16 0 A GOT
~ ee G B Charcoal/HEpA GOT 10:50-12:go MCC Filter tM All Areas C Radiation Levels GOT 62R/h Smears 0 500,000dpm GOT ~Nd II ti I iodine=4E-1 uCi/cc Part.=3E+0 uCi/cc sar ooOo RC Ol Vault Filter VCT CHT po ooOo 0 I S mear Location -x'-x- a Rad/Cont. Barrier ~ ~ Cont. Area ¹c ~
Radiation Level Contact Reading Q¹ ~ Neutron Radiation Level 0 + w High Cont. Area Radiation Area Technician Remarks: Q~ w High Rad, Area
~ Locked High Rad.
R.E.GINNA STATION i!'Auxlllagfi;BVBdinQ';ql+er'meditet"'eevgr"'j E't'ttst'i~jpjjg'?'. Technician: Date: Time: Inst. Type: / Serial ¹'e: I Power: LLD: Note: All readings are in mr/hr unless otherwise noted. AUNTS.~ No. dpml100cm2 RtNST oo 0'us 16 A GDT G B Chorcool/HEPA GDT Filter 12'50-15:00 1M Radiation Levels C 17m R/hr GDT Smears 1,000,000d pm D Airborne Activi GDT iodine=6E-7 uCi/cc Part.=2EW uCi/cc ooOo Voice Hlcy sop RC Dt Vault Filter VCT CHT Qo ooOo
'tt I 0 I Smear Location -x-x- = Rad/Cont. Barrier Cont. Area
¹c = Radiation Level Contact Reading
¹ ~ Neutron Radiation Level 0-e High Cont. Area g Radiation Area Technician Remarks: 8- High Rad. Area Locked High Rad.
h y'nn
R.<.CIRCA STATION Technician: Date: Time: Inst. Type: / SerlU <<'s: I Power. lsote: All res<<loss sre In mrlhr unless otherwise noted. No. d Rtttt1QOomi I Containment Veisel 10:00-1 0:50 AII Areas Radiatiop Levels 1 R/hr Smears 50,000dpm Ai* A r IV Iodine=3E-9 uCi/cc f( K Part.=9E-9 uCi/cc
*nnNOTEe*nn AT THIS TIIIE PLAYERS IN THIS AREA r WILL I
g I 7 BE FORCED I TO LEAVE DUE TO HIGH Sump Q Sump Tank 4, DOSE RATES Pft Pumps
- g. e Ratdadon l.oval ga ~ Contact RoaNno TechnicIan Remarks:
~
e Smut LOCadnn -X-X- a Rad/Cnl>>. Sarrler
~ Neutron Radladon Level Pe 0
pe Cont. Area Ngh Cont. Area RacNation Area High Red. Area a Lockecl High Rid. Area
N,I.ORNA ITATlON AcmdINV ~ +4 %act secK ~ - yggNg Ind Technician: Dote: Tlee:- Inst. Type: / Serial S': rrowar: LI,C: Mote; All ree4 gI are in mrlhr unieae otherwiae noted, 4t8 "aFIa Cg~ 'yrnl1COorng 4 C ~ AQ RHQ SCREE
=vCS 07:309:10 9 All Areas CVCS (Clean)
Radiation Levels 0.8mR/hr x Qe Smears 250dpm Ale A ti itK C iodine=1 E-11 uCi/cc CVCS Part.=1E-10 uCilcc RWST R( Cv A JL w Smear Looadon llardadon losel da w Canraar Reading
~!Helen ltemaAa
~
x x w RadlConr. Senior w Iaautron Radladon I.assi O~ Q'w
~ Cont. Atom w Ngh Com. Area IlSQlSOtl Area NSh Rad. Ares baked High Rad.
Atw
e.i.a+ca ITATlo~ Techrdcian: Dere: Tlllle: inst. TyPe: Serial e': r power: Mott: All rIN~ ~ ln mr/hr gnlogg oNIFwjg4 A4C~ LLD: adc9 ltrIS op~ 4hettl SCOerng; 4 ( aa lg IIIIR deny
- PCS I e
~ ~
09:10-10:00 Qa Radiation Levels 9 CVCS A=3mR/hr. c B=O.SmR/hr E
, Smears 260 dpm x
Qe ~ill* a ~ i iodine=1E-11 uCi/cc Part.=1E-10 uCi/cc C CVCS RWQ A RE K v A L 0 o a Seem Loosens -e-x. ~ lied/Cont. Settler
~
~ ~ Cont. Atria
'~ QO
~ gargstmn Losel ~ Weotron hadlat4n Losel Qs ~ Ngh Cont. Area A ~ Contact ReeOny a QI+A Acii
,7eehnlo4n hemsraa Q~ s Ihgh had. Area
~yg 'Qgh Rid.
arw
IM.QNhfA ITATlON ~ ~~% ~anent LevN . ~~ ~ Tocllflic)ll: DIte; Time: . inst. Tyyo: I S4rlil 4" 0; Power: I.l.g,
" ~'/"<<nliaa otherwiso noted.
dh>>OO A RltR FCRS VCS I ~
~
sgw OS:10-10:00 CPS 9 8
~ 0 a Radiation Levels A=3mR/hr .
f 8=0.5mR/hr N Smeam 250dpm r Qr ~AW II Bi iodine=1E-11 uCi/cc Part.=1 E-10 uCi/cc C CVCS RWQ A R f Ev '~ w Smear I.deaden w Radladen I.mrel
~ Ccetact RoaNng
'~
-a-x- a RadlCont. Sant<<
w Ieetnren Radladen Larral
~
Qe
~
e Cont. Ataa w ISSh Com. Area
~ ftaNt5on Arei ~ chnkSan ltanaAa: Qw ISSh Rad. Area m Locked High Rid.
Arao
fflefrT~r'l ft.I.QINNA STATION TechrHclan:
/
ada "r SFP Oate: a e: Time: . I ur(II44 othirwiao noted. Dg~ rrower LLD 4Rcccl 1OOerccg 4 a +Q
- PCS RHR geng
~ ~e
( ~ 10:00-40:50 t'ai All Areas Radiation Levels 9 Qr 600mR/hr CVCS ~ Q Smears f 6,000dpm
~aw a x ledine=1E-9 uCi/cc.
Qc Part.=3E-9 uCi/cc n*nNQTE e*ee AT THIS C TIME CVCS PLAYERS IN THIS AREA WILL RWST BE FORCED TO LEAVE DUE TO RE HIGH g V A DOSE RATES
.x-a. Can.~
~
,Qt w Smear Loeaoon w RaUConc. Senior ~ ~
- g. w RarRaC(on Level w Mecnron Radlaoon Lerlel Qo w CenC. Area A ~ Contact looting CCCC(CC
~ gst540 ArII 7echrdclan lanate: Q~ w R(C(CC Rao. Area o ~ ~yd HIOh Rad.
Ane
Qelgg4 QC~Wl-~ I~ II I I I ~ ~
~ ~ ~
~ ~
4KZZEl ~ y I . ~
~ ~
t *
~ 4 ~ 0 ~ ~
I 0 P
~ ~
geiger-
~
QO~W- ~ I~ I I I III ~ ~ (o) ~ III I I I ~ ~
~ ~ o
~ ~
~ 0 Kill
~
~ l
~ ~ ~
~e ~ ~ ~ 4 I ~
I ~
r<<'r/tran'.r.'. <<cc;;, R.EsGINNA STATION Technician: Date: Time: Inst. Type: ger/al /r's: / Power: LLD: Note: All readings are in mr/hr unless otherwise noted. M AUXOPg.M No, dpnt/100ttrn2 I A ~a Monitor Tank 0 Bus 14 Ooor 26 B 07:30-10:50 Monitor All Areas Tank (Clean) A Aux. Bldg. Radiation Levels Supply A/H Unit 0.1mR/tir .
~ ~
Smears
~ ~
250dpm a< I Airborne Activi iodine=1 E-11 uCi/cc Part =1E-10 uCi/cc ooooo ~Prooeasing g a 0 I s X 0 0 ~ X 6 A Pogtharg
~O Ooor 28 Ooor 27
<<¹ ~ Smear Location -x-x- a Rad/Cont. Barrier ~ ~ Cont. Area W ~ Radiation Level
¹c ~ Contact Reading
+ I Neutron Radiation Level Qs
+
m High Cont. Area
~ Radiation Area Technician Remarks: Qc m High Rad-. Area Locked High Rad.
O Area
"" 'je84""
R.E.GINNA STATlON 8@ .."Wfaa3rSndti Technician: Date: Tlm e: tnst. Type: / Serial ¹'s: I Power: LLD: Note: All readlnge-are ln mr/hr unless otherwise noted. M AUxops~ No, dpm/100cm2 I A Monitor Tank Bus 14 Ooor 26 B Monitor 10:50-12:50 Tank A Aux. Bldg, All Areas Supply A/H Unit Radiation Levels 62R/h
~ ~
Smears 200,000dpm Airborne Activi iodine=4E-1 uCi/cc part.=3E+0 uC!/cc OOOOO O.
~
0 s x P B A Posahara Ooor 28
~ Smear Location -x-x- ~ Rad/Cont. Barrier Cont. Area OjF ~ Radiation Level
¹c ~ Contact Reading
+ ~ Neutron Radiation Level Qo
+
High Cont.Area Radiation Area Technician Remarks: Qi High Rad-. Area Locked High Rad. Area I
R.E.GINNA STATlON Technician: Date: Time: inst. Type: Sedal ¹'e: I power: LLD. Note: Ail readlnga are in mr/hr unless otherwise noted. M
+mott.se No. ttpml100oma I
A Monitor Tank 8us 14 Ooor 26 tat 8 Monitor 0 Tank 1:50-1: A AUx. B(4g SUPPiy A/H Unit Radiation Leyele
~ ~ 17m R/hr smears 500.000dpm Airborne Actin locNAOWE-7 tIQl/cc Part~2EA ulcc OOOOO ~itrooeaaina 0
I s x P 0 S
~ X 8 A
~ 0 Ooor 28 Door 27
~ Smear Location -x-x- a Rad/Cont. Barrier
¹c ~ Radiation Level Contact Reading
+ ~ Neutron Radiation Level 0- Cont. Area High Cont. Area Radiation Area Technician Remarks: 6- High Rad-. Area Locked High Red.
Area
SECTION 9.0 ONSITE RADIOCOGICAL AND CHEM/STRY DA TA
9.1 Radiolo ical Summar A. Source Term The radiological source term assumed for this scenario was selected to include appropriate quantities of noble gas and radioiodine resulting from the postulated 3% fuel melt accident scenario. Protective action recommendations i.e., sheltering or evacuation for certain Emergency Response Planning Areas (ERPAs)-will be required based upon the anticipated declaration of a General Emergency and plant conditions. As a result of accident release rates, the projected whole body and thyroid doses will exceed EPA Protective Action Guides beyond the Site Boundary. The assumed noble gas and radioiodine release quantities are shown in Figure 9.1 as a function of time. The scenario involves one release point which is from the Plant Vent. This occurs as follows: Time Release Poin Release Rate Ci sec 10:50- Plant Vent 3.21 E+2 (Noble Gas) 12:50 3.21 E-2 (Radioiodine) The noble gas-to-radioiodine ratio assumed is 10 000:1 during this period of release. Isotopic breakdowns of assumed noble gas, radioiodine and particulate release quantities are provided in Table 9.1. B. Inte rated Offsite Doses Due to Plume Ex osure The downwind integrated doses at 3.5 miles, based upon a 2.0 hour actual release duration are: Time Release Poin Inte ra ed Dose Rem 10:50- Plant Vent 1.50E+0 (Whole Body) 12:50 2.63E-1 (Child Thyroid) Princi al Plant Radiolo ical Indications Figures 9.1 through 9.5 provide trend plots for key plant radiological indications, including plant vent concentration, letdown monitor level, containment radiation level and reactor coolant concentration.
TABLE 9.1 The assumed release quantities for the Ginna Exercise Scenario are summarized as follows: Time: 10:50-12:50 hr Nuclide ~curie Sec Total Curies Released K Kr-85 1.6 E+01 1.2 E+05 Kr-85m 5.0 E-01 3.6 E+03 Kr-87 2.9 E+01 2.1 E+ 05 Kr-88 4.3 E+01 3.1 E+05 Xe-131m 4.6 E-01 3.3 E+03 Xe-133 1.5 E+02 1.1 E+06 Xe-133m 2.1 E+01 1.5 E+05 Xe-135 2.8 E+01 2.0 E+05 Xe-135m 7.1 E+00 5;1 E+04 Xe-138 2.8 E+01 2.0 E+05 Total Noble Gas 3.2 E+ 02 2.3 E+06 l-1 31 4.7 E-03 3.4 E+01 I-1 32 6.7 E-03 4.8 E+01 I-1 33 9.5 E-03 6.9 E+01 l-1 34 2.6 E-03 1.9 E+01 I-1 35 8.6 E-03 6.2 E+01 Total Radioiodine 3.2 E-02 2.3 E+02 Long-Lived Particulate 1.2 E-09 1.5 E-06
Figure 9.1 Assumed Source Terms CI/SEC 1.0E+03 .. i 5 ! i I- I
~ I I
1;OE+ 02 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 1.0E+ 01 ~ ~ f f f f f t 1 5 I 5 I I 5 I 5 5 ~ ~ 5 l f l l f l! I! l l l f! ! t 5 5 I f - l l 1! l l l f l l 1.0E+00:: 5 5 I 5 ~ ~ l l ! l
- f l l l l f l !!!i!!!!!!!!!if ~ ~
l l l f! ! l l l f! f f t I 5 5 1.0E-01 It!it I I I I I I I I I t I I I t I I I I I I I I I I I! I I I I I I 1.0E-02 l f l f f l l f l l l!!!I!! 5 ~ f ~ ~ f l I I I l l f l l l l l I! .! f l 1.0E-03 5 ~ f ~ l l l l l f l l f l!I f l l l! I! l f l l f l l l l l! l! ! ! l l t5 1
~
1.0E-04-,- I 5 I I I I I li I I I I I I I I I t I I I I I I I I I I I I I I I I I I I I 1.0E-05:5 5 5 5 I ~ ill!! f l l l !if l l l I l l l fill!fill!! !all! f I ! !! l l l! 1.0E-06 I l l l I l I f l l f!!! ! l I l l l 5 5 5 ~ 5 ~ 5 I 5 5 5 ~ 5 ~ 5 1 t 5 5 ~ 5 1 1 ~ 1.0E-07,- I I I I I I I I I t Ill I t I I I.k I! I I I I I I I I I I I I I I I I! I I I I I I I I I I I I I I I I I I I I 1.0E-08: I I! 11! I I I I I ! 11 t I! I!! I I! I!! I!I 1.0E-09~ 0 4 0 4 0 4 0 LO 09 4LO 0 r 0 LOOOQOLOOLOO09 0 ~ C9 0 0 ~ C9 LO 0 LO ~0 09 4 0 ~ C9'ct'0 ~
- 0) $ 00000~v v-
~ ~ ~
00 00 ~CVOl CVOl09 090909 rt N T T T T T T CLOCK TIME
~ NOBLE GAB Cl/SEC RADIOIODINE Cl/SEC
Figure 9.2 Plant Vent Concentrations uci/cc 1.0E+01 a ~ ~ a a a a a a a a a a ~ 1.0E+00:, I I I I I I I I I ) t ) I I I I I I I-I ) ~ I I I I I I I I I I 1.0E-01 ~ ~ a I ) a
~ ~ ~ ~ ~ ~ ~ ~ ~ I ~ ~ ~
a
~
a I =') I I I I 1.0E-02 . I I I ~ I I II I I I! II) I I I I I I I I I 5 I !! I I I I I I I I ~ ! } } I ! 1.0E-03 .
~
) ~ ~
)
~
I ~ a I ~ a
~ I ~ ~ ~
a
~
a
~
~ ~ ~ ~ ~ ~ ~ ~
I a})1 1.0E-04 a I I I I I I I ! !!! I I I) I I } I! I I I I I I I I I I ~ I I I I I ! I I I I 1.0E-05 = I ~ ~ ~ ~ ~ I I ~ I I I ~ I I I I I ~ I I I I I I t I I I I t I I I I I I I I I ~ ~ I t ~ I I . I I I I I I I I I I 1.0E-06-, I I I I I I I I I ~ ~
! I I I I I I I I I I
1.0 E-07-
~ I I I I I I I I I I I I I I I I I I I I I I I I I I ~ ~ I I I I I I I I ~ I I I I I I I I I I I I I I I I I I I I 1.0E-08: I I I I ~ I I I I~ fII ) II I ~ I I I I I ~ ~
I } I f I I I } I! I I ~ ! I I I I I I I I I I I 1.0E-09,: ~ I I ~ ~ ~ I ~ I I I I I I I I I I I ~ I ~ ~ I I I I I I I I I I I I I I I I I I I I I I I I I I I I ~ I I I I I 1 .OE-1 0& 4 rl 0 0 ~80r Q O O LO O LAO C9 cf Ov- COCO~C9 LO 040 0 LO LO OLOO 0 v- CO 404
%Or
- 0) %OOOO Owe v-~AC))l
~ ~ ~ ~ ~ ~
00 00 N Ol 09 09 09 09%% T CLOCK TIME NOBLE GAS ~ RADIOIODINE
Figure 9.3 Letdown (R-9) Readings MREM/HR 1.0E+ 05 1.0E+04 1.0E+03 1.0E+02 1.0E+01 1.0E+00 0 0 00900 N'cf'Or LO LO 0 8 0 0 rrrrr r LOOOOLOOLO 000rrr rf' r 4O OrQ OC940r0940r LO O Q O LO O LO rrr rOlOlOl
~ ~
09 09 rrrrr
~ ~
r r rCV09e9COC9%
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
00 CO W 1 CLOCK TIME
~ LETDOWN
Figure 9.4 Containment Radiation M REM/HR 1.0E+07 1.0E+06 1.0E+05 1.0E+04 I .OE+ 03::,-.- 1.0E+ 02-:-.: 1.0E+01 1.0E+ 00~ LOOOOOLOO 4 0 lO 0 4 0 ~LO 0 00 r4 009 LO 09 Ct'Ot- COOr 09 ct 0 ~ 09 'ct' 09 LO
'cf' 40 0 Lfl v-OOSSSOOO 0 v v N N Ol Ol 09C90909% N T V T T CLOCK TIME
~ CV RADIATION
Figu e 9.5 RCS Activity uci/cc 1.0E+06 1.DE+04 1.0E+03 1.0E+02 1.0E+01 1.0E+00 0 LO 0 LO 0 0 COVO~COO LO 0 400 09 'ct' 0404 w 09%0~ O LO cf' O Q O v- 09 LO 4 O LO O v-00 00 0) 0) 0) 0 000'-~ ~~AN OlOl09090949% T T T T
~ ~ ~ ~ ~ ~ ~ ~
C9 T
~
L l l T
~
W CLOCK TIME RCS Activity
9.2 IN-PLANTRADIOLOGICAL DA TA ROCHESTER GAS AND ELECTRZC GZNNA STATZOM SERVICE BUILDING NORTH DATE:! SURVEY YRSYRUREST'ERZAZs NUMbER:~
'! SURVEYED bY!
COUHTZNO ZNSTRUMENZ. SERZAZ NUMbER! REMARKS
'REA ~IPOWER!
SURVEYED! RNZ'/SMP NUMbER:
~
L?dKhXZ~~ I I I 07:30-15:00 All Areas (Clean) Radiation Levels 0.01mR/hr SU Smears z 250dpm Airborne Activi eJ ul iodine=1E-11 uCi/cc Sg I J Part.=1E-10 uCi/cc
~
J 2 CI CsI U fj I ~
'S1 I 0
~
Q (1 QU IQB
]
2 2
~ RELDZNlssd ZN MR/MR UlGL5d ~RRÃZSR llOTfD
R.E.GINNA STATION tact rtrxtrt.rht Technician: Date: Tlnte: Inst. Type: / Serial g'a: I Power: LLO: Note: All readinga are in mr/hr unless otherwise noted. No. dpm/100clrt2 Ooor 65 Ooor 0 46 Mens Oressing Area Room 07:30-1 5:00 All Areas (Clean) L Radiation Levels 0 0.01 mR/hr C K Smears S El E 250dpm 0 R Airborne Activi W Iodine=1E-11 uCi/c E R Part.=1E-10 uCi/cc LctNtty (--To Turbine Buddln Smear Location -x-x- = Rad/Cont. Barrier Cont. Area Radiation Level ¹c = Contact Reading
¹ = Neutron Radiation Level 0 ==
+
High Cont. Area Radiation Area Technician Remarks: Q = High Bad. Area Locked High Rad. O Area I
r<<'p" t,. R.E.GINNA STATION i<<petti
't<<ina Ql
<<it<<<<<<<<<<u<<. <<<<<t<<<<>>'A<<>><<ante>d>>>Q
- Technician: Date: Tlute:
Inst. Type: / Serial er'e: I Power: LLD: Note: All readings'are in mr/hr unless otherwise noted. Door 8 No. dpm/100cm2 Carpenters OA Stoiat3e Planners Pipe Shop 07:30-15:00 All Areas Stock (Glean) Room Radiation Levels Weld Shop 0.01mR/hr Smears Uens 250dpm Room Airborne Activi Mechanic Iodine=1E-11 uCi/cc Shop Part.=1 E-10 uCi/cc Kot Shop Bectrtc Shop O Smear Location -x-x- = Rad/Cont. Barrier Cont. Area Radiation Level ¹c = Contact Reading
+ = Neutron Radiation Level High Cont. Area Radiation Area Technician Remarks: High Rad. Area Locked Migh Red.
Area
R.E.GINNA STATION >>:'r: j~i50ff@A 50uth~~q-'.oufhm~'~',>i;R':<4:
!K~"iii%r!re'r,",,+N~KNifr:,z!!,4N!fH>fffr'r!44>>'eq~'jgf:;
Technician: Date: Time: Inst. Type: / Serial 0': I Power: LLD: Note: All readings'are in mr/hr unless otherwise noted. sVC44.Rrr No. dpm/100cm2 0 Qlj Q Xg~" L i)Cf
~ [] R>>r GOO
'lj 0 07:30-15:00 All-Areas 0 Pff 0 (Clean) 0
+O OO p Radiation Levels O~ HP/Chem. Qdf Offices 0.01m R/hr 0 Smears O~
Pa~ 0
>>~lid 0
0 p ~ aa 250dpIH ff Ij il Iodine=1E-11 uCi/cc ff.O Part.=1 E-10 uCi/cc g CDC3DC3 OO lj
~~
Q a ~np ll Rises Office C.R. C3 Door 74 O Smear Location
=. Radiation Level
-x-x- = Rad/Cont. Barrier
¹ = Neutron Radiation Level Cont. Area p>> High Cont. Area
¹c = Contact Reading + Radiation Area Technician Remarks: 0= High Rad. Area Locked High Rad. '; Area
R.E,GINNA STATION ::,"Ail"VolaNe Treatment Building. - Control Panel Area Technician: pate: Time: Inst. Type: Serial (('s: I Power: LLp: Note All readings are in mr/hr unless otherwise noted. AVTCP Fr(P No. dpm1100cm2 07:30-1 6:00 All Areas (Clean) Radiation Levels 0.01mR/hr H2S04 To AYT Smears NaOH Sample Sink Tank Tank Dl Room 250d pITI Airborne Activi Anotyter ) Iodine=1 E-11 uCi/cc Part.=1E-10 uCi/cc Ro(t Uonrior AVT Control Panel f H20 Door Heater Desk 28 I Door 67 Door I9 '(¹ ~
= Smear Location -x--x- = Rad/Cont. Barrier Cont. Area 0
~
~ ~
Radiation Level .<4, = Neutron Radiation Level = High Cont. Area , ¹c = Contact Reading + = Radiation Area Technician Remarks: High Rad. Area f Locked High Rad.
R,E.GINNA STATlON ::,."All"'.Vofatfte':":.::Treatment,:l,BuBdinQ:": - Oemtnerafizer Area Technician: Date: Time: inst. Type: I rieriat ¹'s: I Power: LLD: Note: At( readings are in mr/hr unless otherwise noted Door No. dpm1100em2 27 Low High Conductivity Conductivity Waste Waste Tank Tank 0 07:30-15:00 Oemin All Areas 0 (C)ean) Radtat>on Levels Dilute 0.01mR/hr NH40H Smears Mixed C 250dpm Demin ~air II r' iodine=1E-11 uCi/cc Part.=1E-10 uCl/cc Anion Dilute Regen NaOH B 0 Demin Cation ilute Regen H2S04 A Demin ¹ = Smear Location -x-x- = Rad/Cont. Barrier Cont. Area Radiation Level ¹ = Neutron Radiation Level High Cont. Area ¹c = Contact Reading Radiation Area Technician Remarks: High Rad. Area Locked High Rad. Area
're423gj~ fiji R.E.GlNNA STATlON Technician: Date: Time:
Inst. Type: I Serlel rr'e: I Power: LLD: Note: All readlnga are ln mrlhr unless otherwise noted. wo NRC Office Kitchen IZM Mens Room Womens Room )3~32 07:30-15:00 All Areas (Clean) Radiation Levels 0.01m Rlhr Smears dpm/toocm2 dpm/toocm2 rtc 260dpm oocm2 d pm/1 oocm2 No. d pm/100cn / Airborne Activi iodine=1E-11 uCilcc Part.=1E-10 uCilcc
~ w ee Smear Location g ee Radiation Level gg, m Contact Reading Qi ~
Cont. Aroo teett Cont. Ares m Neutron Radfatfon Level -x-x- ee Radlcont. Serrier + o Aocaotfon Ares Technician Aernarfta: + o fee/2 Aod. Aron
+ a LOCksd Heh Aed. Arse
R.E.GINNA STATiON tstteaII~A~~ I'RY>IR~m RB"RrrRuvernr-u<0' Nt Technician: Date: Time: Inst. Type: / Serial ¹'0: I Power: LLD: Note: All readings;-are in mr/hr unless otherwise noted. 26 tI pret/100crts2 8 Iheset-GerL Svc. Air Comp. 0000 0000 Air lonks k 0 eset-Gen. Condensote Borrtter Pumps 32 I I Heoter Bran fk I i Condensate See. l Oil Pumps System
~ 0 ~ 0 ~ ~ OO ~ ~ ~ 0 0 ~
~0 ~0 ~ ~ ~0 ~ ~ ~0 ~0
~0 ~0 ~ ~ ~0 ~ ~ ~0 ~0 Bottle Storooe LR 07:30-1 5:00 All Areas (Clean)
~0~
000000 Bottle Radiation Levels Q~0~
~0~
St9 0.01mR/hr
'mears Condenser s Door 8
250dpm Airborne Activi Chem. Add iodine=1E-11 uCi/cc Ptanps part.=1 E-10 uCi/cc r r Btoedoen lank
~ ~RO 01RRR, rrre water rLRl A'r train feed Pumpt Onrer
¹ O = Smear Location -x-x- = Rad/Cont. Barrier ¹c = Radiation Level Contact Reading
+ = Neutron Radiation Level Cont. Area High Cont. Area Radiation Area Technician Remarks: High Rad. Area Locked High Rad. tI Area
R.E.GINNA STATION Technician: Date: Time: Inst. Type: / Serial ttr'a: / 'ower: LLD: Note: All readings are in mr/hr unless otherwise noted. TVIWHCZL~ se No. dpm/100cm2 Reloy Room feed Wirier 07:30-1 5:00 All Areas (Clean) Radiation Levels Crane Bgtr 22 0.01mR/hr Smears 250dpm Condenser A~Nb II ti I iodine=1E-11 uCi/cc Part.=1E-10 uCi/cc 0 aSfs lube QQn Qm Oig Res, 0 C ta,
~ Chem.
tanhs 0 Mon feed
~ C=-~ See CN.
¹ = O Smear Location -x-x- = Rad/Cont. Barrier Cont. Area ¹c = Radiation Level Contact Reading Neutron Radiation Level 0
+
= High Cont. Area
= 'adiation Area Technician Remarks: O = High Rad. Area c Lockeu high Red.
Area
P tt(tIIIPtttt,ItttthttttttttttItN R.g.GINNA STATlON Technician: Date: Time: inst. Type: . / Serial ¹'s: I Power: LLD: Note: All readings are ln mr/hr unless otherwise noted. dpm1100cm2 Control Room I I I I L J I I I I I I I I L 07:30-15:00 All Areas (Clean) RadIatIon Levels 0.01mR/hr Smears 250dpm Airborne Activi iodine=1 E-11 uCi/cc K=V Part.=l E-10 uCi/cc I I 8=k CV ¹ = O Smear Location -x-x- = Rad/Cont. Barrier Cont. Area Radiation Level = Neutron Radiation Level Qs High Cont. Area ¹c = Contact Reading Radiation Area Technician Remarks: High Rad. Area Locked High Rad. l Area
~<>,'gcK.><~~>Kj <>?)wtpQp'F<, "~ A<+Pt.<rt~N<'+;,c'<+ $%<. tp~+>'~'>wq++pz>w'>;<p<
R Q.GiNNA STATiON .'.~ is+ w>r<,y v'; ~<>'Ster< ",~" ", ' S:>>"e'j;3;
',-'Li>iggh,
>34;..<a L>".h>>'3r<,j<:.iv a+>a'.;:< <.>
Technician: Date: Time inst. Type: / Serial ¹'e: I Power: LLD: Npte: All readings are ln mr/hr unless otherwise noted.
'iet,i' No. dpm1100cm2 3 " 5$ >i, 0
0 3; ~ 0 0 CV Purge --->
'---N Containment 07:309'10 All Areas (Clean) 0 Radiation'eve(8 0.01m R/hr smears R10A,11,12 250dpm
~<l< < ~ I CV Vent --> iodine=1E-11 uCi/cc Plant Part=1 E-10 uCi/cc Vent ---> - - -R108 13 14 0
0 0 0 A Purge 0 Exhaust il::<>> Fan 3[i I
- tr;,
~
8 Purge fxhoust fon O -x-x- ~ Rad/Cont. Barrier Smear Location Radiation Level 4'c = Contact Reading Technician Remarks:
~ ~ Neutron Radiation Level Q~
+
~ ~ Cont, Area
~ High Cont. Area
~ Radiation Area Q' High Rad. Area Locked High Rad Q Area
~c4k+N~Mc+apNjc(', RYc r 'tres +4& g s.
~ a'Ã~a q%c<gcrv r'wNQM e cw~'g R f.GINNA STATION ;<r 'piary rj"+ %i'j"x'"+~l,.'71 r,i'np t j;c, ',:e ~'<' rw Technician:
Inst. Type: N p pe; AII rea ding I
/'erial Date:
¹'e:
Time: I are in mr/hr unless otherwise noted. Power: LLD: No. dpm/100cm2
~ r ll tl 0 ;r ~
0 r 0 09:10-10:30 0 CV Radiation Levels Purge ---> Containment A=3m R/hr B=0.5mR/hr Smears 250dpITI R IOA,11,12
~ale ii ii i Iodine=1 E-11 uCI/cc CV Vent --> Part=1 E-10 uCI/cc A
Plant Vent ---> -R10B 13 14 U 0 0 0 0 A Purge 0 Exhaust Fan Cl B Purge Exhaust Fun
= Smear Location -x-x- ~ Rad/Cont. Barrier ~ Cont. Area
~ Radiation Level ' Neutron Radiation Level Q+ m High Cont. Area
¹c = Contact Reading + ~ Radiation Area Technician Remarks: Q' High Rad. Area
~ Locked High Rad O Area
C
~ ~ ~ -I wr wary ao.iv h~; a'v ~ 'vi~ mQ a
~ ~ ~
~
~ ~
I I I
~ ~
Qo I ~ ~
~ ~
~ ~
~ > ~
~
~ ~
~ . I ~
~ I
~
~
~
~ ', ~
~ ~
~ ~
~ ~
R.E.GINNA STATION Technician: Date: Time: Inst. Type: / Serial rrr'e: I Power: LLD: Note: All readings are ln mr/hr unless otherwise noted. dpm/100ctn2 0 0 0 0 10:50-12:50 CV Purge ---> Containment All Areas Radiation Levels A=6 R/hr c 8=1 000mR/hr R10A,11,12 C =500m R/hr 0=37mR/hr CV Vent --> Smears As 8=600dpm Plant C&0=2000dpm Vent ---> -
-R10B,13,14 Ai~ A ti itK lod<ne=1EW uC>/cc 0 B Part=1E-7 uCi/cc CL 0 A Purge 0 Exhaust Fan c 8 Purge Exhaust fan O ~~ Smear Location Radiation Level
-x-x- ~ Rad/Cont. Barrier
~ Neutron Radiation Level Q'
~ Cont. Area
. High Cont. Area
¹c = Contact Reading + = Radiation'Area Technician Remarks: Q High Rad. Area
~ Locked High Rad.
O Area
R.E.GINNA STATION Technician: Date: Time: Inst. Type: / Serial <<'a: I Power: LLD: gate: All readings are ln mr/hr unless otherwise noted. No. dpm/100cm2
~ \
0 0 ~ I 0 CV Purge ---> 0
~ 8 . Q Containment 12:50-1 5:00 Radiation Levels
[] A-37m R/hr B=50mR/hr R10A,11,12 smears A=3000dpm B=5000dpm Plant Airborne Activl Vent ---> - -R10B,13,14 Iodine=2E-9 uCl/cc Part.=2E-S uCI/cc 0 0 0 0 lint Purge 0 Exhaust Fan B Purge Exhoust Fan ¹ = O Smear Location -x-x- ~ Rad/Cont. Barrier Cont. Area
~ Radiation Level ~ Neutron Radiation Level Oe ~ High Cont. Area
¹c = Contact Reading + ~ Radiation Area Technician Remarks: Q+ ~ High Bad. Area
~ Locked High Rad.
O Area
R.E.GINNA STATION Intermediate'uilding North - Operad Technician: Date: Time: Inst. Type: / Serial ¹'e: I Power: Note: All readings are in mr/hr unless otherwise noted. Wert THOP aetP N4. dpm(1aacm2 0 (---N 07:3049:10
~ R-i/A Containment All Areas (Clean)
Radtat>on Levels 0.01mR/hr Smears 260dpm A~id Il r
. iodine=1 E-11 uCi/cc Part.=1 E-10 uCi/cc 8
L a Purge Exhaust Fan W 0 R Cl a Uon 8 4 Steexn purqe Oaae ettoust fNt 57 Chateau Leer O.l. etoter-Stortxye lank
'¹ ) = Smear Location -x-x- = Rad/Cont. Barrier Cont. Area Radiation Level +i = Neutron Radiation Level High Cont. Area
.'¹c = Contact Reading Radiation Area , Technician Remarks: High Rad. Area t Locked High Rad. A I'ne
R.E.GlNNA STATlON Intermediate Building North - Operating Leve Technician: Date: Time: Inst. Type: / Serial ¹'e: I Power: Note: All readings are in mr/hr unless otherwise noted. WtrrIHO¹ frrrp I N4. dpmr1000mg t
<---N 09:10-1 0:30
~ R- l2A Containment Radiation Levels A=3m R/hr B=0.5mR/hr Smears 250dpm I~IN 4 ri iodine=1E-11 uCi/cc Part.=1 E-10 uCi/cc I
A I t Urge Exhaust fan W 0 R 0 A taon 8 4 St¹4 pr¹rta Oaor rrxaxrt F4e 57 Chemistry l(Xt 0J. Weter-Sloreta fantr
'¹; = Smear Location -x-x- ~ Rad/Cont. Barrier Cont. Area Radiation Level Neutron Radiation Level High Cont. Area
,'¹c = Contact Reading Radiation Area
- Technician Remarks
- High Rad. Area Locked High Rad, Area
R.E.GINNA STATION intermediate Building North - Operating Level Technician: Date: Time: Inst. Type: / Serial ¹'e: / Power: Note: All readings are in mr/hr unless otherwise noted. No. d pmi t Oacm2 0 y A
/
I (---N
'I 0:30-1 0:50 t
Radiation Levels R-irk I Containment A=37m R/hr B=17mR/hr R 1%A Smears 250dpm o
~ee Il el iodine=1E-11 uCi/cc Part=1 E-10 uCi/cc 8
A a Purqe Exhaust Fan W 0 t R 0 Auon 8 4 Stars piece Ooor aiaaarl fa¹r 57
.B Cieenestry t OJ. Wder-Skarote tank I¹ } = Smear Location -x-x- = Rad/Cont. Barrier 4 Cont. Area Radiation Level
',.¹c = Contact Reading
/ = Neutron Radiation Level 0= High Cont. Area
+ Radiation Area
, Technician Remarks: 0= High Rad. Area Locked High Rad. Area ~
R.E.GINNA STATION intermediate Building North Operating Le Technician: Date: Time: Inst. Type: / Serial ¹'a: I Power: LLD; Note: All readings are in mr/hr unless otherwise noted. trrartTttop atttr N4, dpm/100Cm2 D D 10:50-12:50 All Areas Radtation Levels Containment A=6R/hr C B=1000mR/hr C=500mR/hr D=37mR/hr B Smears A&B=600dpm C&D=2000dpm QA IBt c >>~ik>> iodine=1 EW uCi/cc 8 A L Part=1 E-7 uCi/cc Purqe ExhtJusl Fan - 0 W 0 R 0 Alon 4 Stet¹n C PttrtJ¹ OOor t F4t D 57 Ckrrvatry Lett OJ. Wotar-Storoga fry
'¹ ) = Smear Location -x-x- = Rad/Cont. Barrier 0
, ¹c = Radiation Level Contact Reading
+ = Neutron Radiation Level Q>>
+
Cont. Area High Cont. Area Radiation Area , Technician Remarks: High Rad. Area Locked High Rad. Area
R.EeGINNA STATION Intermediate Building North - Operating Level Technician: Date: Time: Inst. Type: / Serial ¹'s: I Power: LL4: Note: All readings are in mr/hr unless otherwise noted. WTrrTstaa Sat¹ Na. dpmlloocm2 8 it4n c (---N 12:50-15:00
~ R i/A Containment Radiation Levels A = 50mR/hr B = 37mR/hr C = 2mR/hr smears A = 5000dpm B = 3000dpm C = 3000dpm Airborne Activi Iodine = 2E-9 uCi/cc A
8 Part. = 2E-9 uCi/cc 0 Purqe Exhoust Foll w 0 C R 0 A@On e 4 irlcssn Pt¹qe Ooor shauai Fan 57 C Chamrslry ltgt Ol, SASer tllaaqe lank
¹) = Smear Location -x-x- = Rad/Cont. Barrier Cont. Area=
Radiation Level,'I = Neutron Radiation Level High Cont. Area
¹c = Contact Reading Radiation Area
,. Technician Remarks: High Rad. Area Locked High Rad.
R.E.GlNNA STATlON intermediate Building North - Mezzanine Level Technician: Oate: Time: Inst. Type: / Serial ¹'a: I power: LLD; Note: All readings are in mr/hr unless otherwise noted. wTtt Ttteeg earp No., dPml1OOr.trial
,0 S;carr.
0 07:30%9:10 All Areas (Clean) Containment Radiation Levels 0.01mR/hr Smears 250dpm Airborne Activi iodine=1 E-11 uCi/cc Part.~1E-10 uCi/cc 0 4 Mein 0 S)earn --) I I I I I I Door I I I 45 IIIte Rcetortt r~ '¹ = Smear Location -x-;x- = Rad/Cont. Barrier Cont. Area
~
Radiation Level '4"; = Neutron Radiation Level High Cont. Area
¹c = Contact Reading
~
Radiat>on Area Technician Remarks: ~ High Rad. Area Locked High Rad. Area
~ i ~ ~
~ .
~ ~ ~ ~
I
='='=-'"'-IIL!Pdi)till
- =llllll5i~aaHMFll o~~
~
I ' I I
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~ ~
~ ~
a I 0 ~ ~
~ ~
~ ~
ygO o~~
~ I+~
I~ ~
~0 t ' ~
)4 ~
~ ~ ~ ~
~ ~ ~ I
~ ~ ~ ~ ~
~ ~
R.E.GINNA STATION Intermediate Building North - Mezzanine Level Technician, Date: Time: Inst. Type: / Serial ¹'a: I power: Note: All readings are in mr/hr unless otherwise noted. WTrerrree2 pap No. dpm(100cm2 pica& ) 0 (--N 10:30-15:00 Radiation Levels I A=37mR/hr Containment B=17mR/hr Smears 260dpm B a~le ari iodine=1E-11 uCi/cc Part.=1E-10 uCi/cc A Main Steam --) 1 I I I I I I I Door I I I 45 HHS Raced '¹ = Smear Location -x-.-x- = Rad/Cont. Barrier 0 Cont. Area
~ ~
Radiation Level
¹c = Contact Reading
'¹~~ = Neutron Radiation Level 0=
+
High Cont. Area Radiation Area Technician Remarks: ~ High Rad. Area
+ I
~
Locked High Rad. Area
9.3 POST-ACClOENT SAMPL!NG RESULTS TABLE 9-2A Chemistry Data Equilbrium Activity Reactor Coolant System "B" Loop Sample Sample time: November 17, 1993 O 04:30 Nuclide Activit Ci/cc Ar-41= 3.25E-02 Kr-85m= 4.02E-02 Kr-87= 5.41E-02 Kr-88= 6.59E-02 Xe-133= 2.13E-01 Xe-135= 2.03E-01 Xe-135m= 9.19E-02 Xe-138= 3.06E-01 Total Gas Activity= 1.01E+00 Total Degassed Activity= 1.55E+00 Total Activity= 2.56E+00 Boron = 345ppm pH =7.0 For more detailed chemistry information see HP/Chemistry turnover sheet.
TABLE 9-3A Chemistry Data Post-Accident Samples Reactor Coolant System "B" Loop Sample Sample time: November 17, 1993 O 09:30-1 0:29 Nuclide Activi
- Ci/cc Ar-41= 2.27E-02 Kr-85m= 2.81E-02 Kr-87= 3.78E-02 Kr-88= 4.61E-02 Xe-1 33= 1.49E-01 Xe-135= 1.42E-01 Xe-135m= 6.42E-02 Xe-138= 2.14E-01 Total Gas Activity= 7.04E-01 Total Degassed Activity= 1.08E+00 Total Activity= 1.79E+00 I-1 31= 1.11E-02 l-1 32= 2.14E-01 l-1 33= 1.09E-01 l-134= 4.60E-01 1-135= 2.25E-01
* = Activity Corrected to Time of Shutdown Boron = 2150ppm pH = 5.0 Sam le Dose Rates:
Gas Undiluted 35cc gas bulb = 2.9 mR/hr on contact, Liquid
- Undiluted sample = 1.62 mR/hr on contact,
TABLE 9-3B Chemistry Data Post-Accident Samples Reactor Coolant System "B" Loop Sample Sample time: November 17, 1993 O 10:30-15:00 Nuclide. Activi
- Ci/cc Kr-85= 1.34E+01 Kr-85m= 4.36E+02 Kr-87= 7.94E+02 Kr-88= 1.17E+03 Xe-131m= 1.24E+01 Xe-133= 3.97E+03 Xe-135= 7.61E+02 Xe-135m= 1.93E+02 Total Gas Activity= 7.93E+03 Nuclide Activit
- Ci/cc I-1 31= 4.51E+03 l-1 32= 6.50E+03 l-1 33= 9.17E+03 I-134= 2.52E+03 I-135= 8.28E+03 Total Radioiodine Activity= 3.10E+04 Ba-140= 8.09E+03 La-140= 8.43E+03 Cs-134= 1.10E+03 Cs-137= 5.00E+02
* = Activity Corrected to Time of Shutdown Boron = 2150ppm pH =5.0 Sam le Dose Rates:
Gas - Undiluted 35cc gas bulb = 19.5 R/hr on contact, 111 mR/hr at 1 meter. - Diluted 35cc gas bulb = 107 mR/hr on contact, 0.07 mR/hr at 1 meter. Liquid - Undiluted sample = 804 R/hr on contact, 1.3 R/hr at 1 meter. - Diluted sample = 804 mR/hr on contact, 1.3 mR/hr at 1 meter.
TABLE 94A Chemistry Data Equilibrium Activity Containment Atmosphere Sample time: November 17, 1993 O 04:30 N Iid acti ittCi/ *I Ar-41= 1.42E-06 Xe-133= '.83E-05 Xe-133m= 1.99E-07 Xe-135= 3.39E-07
TABLE 9MB Chemistry Data Post-Accident Samples Containment Atmosphere Sample time: November 17, 1993 I 09:30-10:29 Nuclide Activit
- Ci/cc Ar-41= 1.09E-04 Kr-85m= 1.35E-04 Kr-87= 1.82E-04 Kr-88= 2.21E-04 Xe-133= 7.17E-04 Xe-135= 6.82E-04 Xe-135m= 3.09E-04 Xe-138= 1.03E-03 Total Gas Activity= 3.38E-03 I-131= 3.30E-08 I-132= 6.34E-07 I-133= 3.24E-07 I-134= 1.36E-06 1-1 35= 6.67E-7
* = Activity Corrected to Time of Shutdown Sam le Dose Rates:
Gas - Undiluted 3500cc marinelli = 0.58 mR/hr on contact 0.01 R/hr at 1 meter - Undiluted 35cc gas bulb = 0.01 mR/hr on contact, 0.01 mR/hr at 1 meter. - Diluted 35cc gas bulb = 0.01 mR/hr on contact, 0.01 mR/hr at 1 meter.
TABLE 94C Chemistry Data Post-Accident Samples Containment Atmosphere Sample time: November 17, 1993 O 10:30-15:00 Nuclide Activi
- Ci/cc Kr-85= 2.09E-01 Kr-85m= 6.78E+00 Kr-87= 1.24E+01 Kr-88= 1.82E+01 Xe-131m= 1.94E-01 Xe-133= 6.19E+01 Xe-135= 1.19E+01 Xe-135m= 3.01E+00 Total Gas Activity= 1.24E+02 Nuclide Activit
- Ci/cc 1-1 31= 4.33E-02 1-1 32= 6.23E-02 I-1 33= 8.82E-02 l-1 34= 2.42E-02 l-1 35= 7.96E-02 Total Radioiodine Activity= 2.98E-01 Ba-1 40= 7.61E-02 La-140= 7.96E-02 Cs-1 34= 1.04E-02 Cs-1 37= 4.71E-03
* = Activity Corrected to Time of Shutdown Sam le Dose Rates:
Gas - Undiluted 3500cc marinelli = 12.9 R/hr on contact 137 mR/hr at 1 meter - Undiluted 35cc gas bulb = 306 mR/hr on contact, 1.75 mR/hr at 1 meter. - Diluted 35cc gas bulb = 0.18 mR/hr on contact, 0.01 mR/hr at 1 meter.
TABLE 9-5A Chemistry Data
. Equilibrium Activity Containment Sump Sample time: November 17, 1993 I 04:30 Nuclide Activi Ci/cc Cr-51= 6.52E-05 Mn-54= 1.22E-05 Co-58= 1.78E-04 Co-60= 3.25E-05 Nb-95= 1.60E-05 Mo-99= 1.64E-05 Sb-124= 1.66E-05 I-1 31= 6.43E-04 1-1 33= 1.95E-04 Xe-133= 1.21E-04 Cs-134= 1.01E-04 Cs-137= 2.49E-04 Boron = 210ppm pH = 6.8
TABLE 9-5B Chemistry Data Post-Accident Samples Containment Sump Sample time: November 17, 1993 O 09:30-10:29 Nuclide Activi
- Ci/cc Ar-41= 1.13E-03 Kr-85m= 1.40E-03 Kr-87= 1.89E-03 Kr-88= 2.30E-03 Xe-133= 7.44E-03 Xe-135= 7.07E-03 Xe-135m= 3.21E-03 Xe-138= 1.07E-02 Total Gas Activity= 3.51E-02 Total Degassed Activity= 5.42E-02 Total Activity= 8.93E-02 I-1 31= 4.19E-03 l-132= 8.06E-02 I-1 33= 4.13E-02 I-1 34= 1.73E-01 l-135= 8.48E-02
* = Activity Corrected to Time of Shutdown Boron = 2150ppm pH =8.8 Sam le Dose Rates:
Liquid - Undiluted sample = 11.8 mR/hr on contact, 0.02 mR/hr at 1 meter. - Diluted sample = 0.01 mR/hr on contact, 0.01 mR/hr at 1 meter.
TABLE 9-SC Chemistry Data Post-Accident Samples Containment Sump Sample time: November 17, 1993 O 10:30-15:00 Nuclide Activi
- Ci/cc Kr-85= 1.72E+00 Kr-85m= 5.60E+01 Kr-87= 1.02E+02 Kr-88= 1.50E+02 Xe-131m= 1.60E+00 Xe-133= 5.10E+02 Xe-133m= 7.40E+01 Xe-1 35= 9.80E+01 Xe-135m= 1.96E+02 Total Gas Activity= 1.19E+03 1-1 31= 4.38E+03 I-1 32= 6.30E+03 I-1 33= 8.93E+03 I-1 34= 2.45E+03 1-1 35= 8.05E+03 Ba-140= 7.70E+03 La-140= 8.05E+03 Cs-134= 1.05E+03 Cs-137= 4.76E+02
* = Activity Corrected to Time of Shutdown Boron = 2150ppm pH = 8.8 Sam le Dose Rates:
Liquid - Undiluted sample = 781 R/hr on contact, 1.28 R/hr at 1 meter. - Diluted sample = 781 mR/hr on contact, 1.28 mR/hr at 1 meter.
TABLE 9-6 Continuous Air Monitors (CAMS) (Auxiliary Bldg & TSC) Auxiliary Building Top Floor Time Noble Gas Radioiodine Particulate Alarmin ? 07:00 - 09:10 50 50 50 No 09:10 - 10:00 50 50 50 No 10:00 - 10:50 100 50 50 No 10:50 - 12:50 To ofScale To ofScale To of Scale Yes 12:50 - 15:00 50 To ofScale 100 Yes Auxiliary Building Intermediate Floor TIIYle Noble Gas Radioiodine Particulate Alarmin ? 07:00 - 09:10 50 50 50 No 09:10 - 10:00 50 50 50 10:00 - 10:50 150 50 50 No 10:50-12:50 To of Scale To of Scale To of Scale Yes 12:50 - 15:00 50 To of Scale 100 Yes Auxiliary Building Basement Floor Time Noble Gas Radioiodine Particulate Alarmin ? 07:00 - 09:10 50 50 50 09:10 - 10:00 50 50 50 No 10:00 - 10:50 300 125 70 Yes 10:50-12:50 To of Scale To ofScale To ofScale Yes 12:50 - 15:00 50 To ofScale 100 Yes Technical Support Center Time Noble Gas Radioiodine Particulate Alarmin ? 07:00 - 09:10 50 50. 50 No 09:10 - 10:00 50 50 50 No 10:00 - 10:50 50 50 50 No 10:50 - 12:50 50 50 50 No 12:50 - 15:00 50 50 50 No
TABLE 9-7 Air Sample Results in TSC and Control Room 07:30 - 15:00 Particulate Filter = 60 cpm iodine cartridge = 60 cpm
SECTION 10. 0 METEOROLOGICAL AND OFFSITE RADIOLOGICAL DA TA
N.I.QIANA STATlON TechrHcfan: Date: maaiaV Time: Iii ice aetna
~ - sr~ ~
fnto Tfp. I a': Note: 4ll 'ee~ a ~ in aerial r mr/br unleie otherwise notect. power: LLQ: A88 SrO Oq~ dRnM1OOeng ', 4 ( aa
- VCS RHR Fond 10:50-12:50 All Areas 9
CVCS Radiation Levels 62R/h Smears 1,000,000dpm x Qa Airborne Activi iodine=4E-1 uCi/cc Part.=3E+0 uCi/cc C CVCS RWST R f fV A 4 0
.x-a.
~ MConr.
,Qt w Smear Looadon w Banier ~ ~ Can. Area 'W w RerNaden LeVel w Nemine Radladan LeVel Qe inSR Corn. Area A ~ Contlct Holing .. ~ gggt15on Area Technician ltemuha: Q~ w Ngn Rad Area
~ ~gd High Rad.
R.R.QtNNA STATlON Technician: Date: Time: . lnat. Typo: / Seri ~ I <<'e: / Power LLQ
/tote: An reed/nRa are in mr/hr un/eee otnerwiea noted Rett/1000/tent A@a SrO CuM~S 0
A ( ww Ag PCS RHR FCnS 0 te 4
~
J
~
12:50-1 5:00 S CVCS Radiation Levels A A=37mR/br B=17mR/hr x Qe Smears l 2,000,000dpm Airborne Activi C iodine=6E-7 uCi/cc CVCS Part.=2EA uCi/cc RWSTi RE K tI A cled
-x-x-
~
w Smear Loosdon w Rad/Cont Ra/der ~ a Cont. Area '~ .Qd i w Ra/Radon LN/et w Net/tron Red/aden LN/al Qe w NRh Cont. Area lc ~ Contact ReaNng e Raglan Area Tochnhhn Romarkl: Qw NSh Rad. Ares l.o:lied High Rad. Area
R.E.QfNNA STATfos
~ <<k Technician: Ca<<: 'Itrne:
po<<er Mote: All readlno ~ Setlel 0'a: ln Tnr/hr unlace othiWs
/
noted. demr100ttm2 Sl Pumps CS Pum lo 07:30-10:50
~ ace ~
"0 Non-reqen All Areas WcNe Holdup Hs (Clean},
Tonk Radiation Levels 0.8mR/hr Aks Smears Charging 250dpm e Pump Airborne Activi Cootinq 0 Fons iodine=1E-11 uCi/cc 0 Part.=1 E-1 0 uCi/cc Oo Spent Resin Tonk Room Sur Tank
~ ~
~ Le EO o
~a HO
~ 4 E
I I CtHt ~i'ump Room
~ Smear Locatfon -x-x- e Rad/Cont. Barrfer ~ ~ Cont. Area
~ Radfatfon Level Nc ~ Contact Readfng
~ Neutron Radlatlon Level 0 ~
~
High Cont. Area Radfatfon Area Technfcfan Remarka: Q~ ~ High Rad. Area 0 ~ Locked High Rad, Area
10.1 METEOROLOGICAl DATA
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Meteorolo ical Conditions A. Basis The meteorological conditions for this scenario were based upon historical meteorological data recorded by the Ginna primary weather tower and the N tt I IN th 9 I ~97 1993. Ilt dtd 9 9 I d the data to provide the wind direction and atmospheric stability conditions required by the scenario during the period of release. National Weather Service and other Exercise controllers will provide Exercise participants weather forecast summaries based on the meteorological data and other supporting information available from the historical record. The goal of this approach is to provide participants with more realistic forecast information. B. Scenario Assum tions The scenario begins with light, southerly winds which shift and become northeasterly by mid-morning. During the period of release (10:50-12:50 hr), the average meteorological conditions are as follows: Wind Speed = 3mph(at33ft) Wind Direction = 45 degrees (at 33 ft; wind from) Pasquill Stability = E
TABLE 10.1 WEATHER FORECAST INFORMATION NOVEMBER 17, 1993 07:30 AM - 3:00 PM LAKE ONTARIO FORECAST'ODAY:,SOUTHERLY WINDS WILL BE SHIFTING NORTHEASTERLY BY MID-MORNING. TEMPERATURES ARE EXPECTED IN THE MID 40'S. WINDS WILL REMAIN FROIVI THE NORTHEAST AT 5 MPH THROUGHOUT THE REMAINDER OF THE AFTERNOON. NOTE: SUPPLEMENTAL FORECAST INFORMATION TO BE PROVIDED BY NATIONALWEATHER SERVICE CONTROLLER AT THE FOLLOWING TELEPHONE NUMBER. (716) 328-7633 OR BY DESIGNATED NYS CONTROLLER IN ALBANY
11/17/93 07:00 RECORD NUMBER 1336 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A ~ 3.5 MPH 0.9 6.1 SPD 33B 2.9 MPH 1.3 0.5 6.0 SPD150A 4.4 MPH 1.2 0.8 6.8 SPD150B 4.8 MPH 1.2 3.4 8.0 SPD250 5.6 MPH 0.9 4,4 8.5 DIR 33A 321 DEG 122 264 40 DIR 33B 321 ~ DEG 122 278 55 DIR150A 323 DEG 61 300 DIR150B 325 DEG 85 308 25 DIR250 322 DEG 96 320 TER 33A 44.4 F ~ TER 33B 44.3 F TER150A 44.0 F TER150B 43.8 F TER250A 43.8 F TER250B 43.7 F DT150-33A -0.6 F/ DT150-33B -0.8 F/ DT250-33A -0. 6 F/ DT250-33B -0. 6 F/ DEWPOINT 49.7 F RAIN 0.00 INCH 0 1.02 1.02 0.00
11/17/93 07:15 RECORD NUMBER 1337 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A 5. 0 MPH 0.8 3.5 6.8 SPD 33B 4. 8 MPH 0.9 2.8 6.7 SPD150A 6. 3 MPH 0.6 4.0 7.4 SPD150B 7. 8 MPH 0.6 6.3 10.2 SPD250 7. 4 MPH 0.4 6.4 8.0 DIR 33A 320 DEG 287 328 DIR 33B 313 DEG 8 284 335 DIR150A 311 DEG 5 300 328 DIR150B 312 DEG 4 306 325 DIR250 322 DEG 4 315 333 TER 33A 44.2 F TER 33B 44.2 F .0 TER150A 43.6 F TER150B 43.6 F TER250A 43.4 F 0 TER250B 43.3 F DT150-33A -0.8 F/ DT150-33B F/ DT250-33A -0. 8 F/ DT250-33B -1.2 F/ DEWPOINT 49.7 F RAIN 0.00 INCH 0 1.02 1.02 0.00
11/17/93 07:30 RECORD NUMBER 1338 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A 5.1 MPH 0.9 3.2 7.1 SPD 33B 4.7 MPH 2.5 7.3 SPD150A 6.2 MPH 0.4 4.9 7.0 SPD150B 7.6 MPH 0.3 7.0 - 8.3 SPD250 7.1 MPH 0.4 6.1 8.2 DIR 33A 317 DEG 6 280 324 DIR 33B 309 DEG 7 293 328 DIR150A 305 DEG 4 293 314 DIR150B 306 DEG 3 299 313 DIR250 322 DEG 3 314 329 TER 33A 43.8 F TER 33B 43.9 F TER150A 43.4 F TER150B 43.0 F TER250A 43.1 F TER250B 42.9 F DT150-33A -0.8 F/ DT150-33B F/ DT250-33A -0.7 F/ DT250-33B -1.2 F/ DEWPOINT 49.6 F RAIN 0.00 INCH 0 1.02 1.02 0.00
11/17/93 07:45 RECORD NUMBER 1339 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A 5.0 MPH 0.9 3.3 7.2 SPD 33B 4.7 MPH 1.0 2.5 6.9 SPD150A 6.1 MPH 0.6 4.8 7.3 SPD150B 7.3 MPH 0.6 5.9 ~ 9.2 SPD250 7.6 MPH 0.5 6.1 8.5 DIR 33A 322 DEG 9 281 326 DIR 33B 321 DEG 9 282 331 DIR150A 312 DEG 297 333 DIR150B 312 DEG 6 299 331 DIR250 330 DEG 5 319 341 TER 33A 44.0 F TER 33B 43.9 F TER150A 43.2 F TER150B 42.8 F TER250A 43.0 F TER250B 42.9 F DT150-33A -1.2 F/ 0 DT150-33B -1. 4 F/ DT250-33A -1.0 F/ DT250-33B -1.4 F/ DEWPOINT 49.4 F RAIN 0.00 INCH 0 1.02 1.02 0.00
11/17/93 08:00 RECORD NUMBER 1340 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A 5.7 MPH 1.0 2.8 7.7 SPD 33B 5.3 MPH 1.2 2.4 7.4 SPD150A 6.9 MPH 1.0 4.4 9.7 SPD150B 8.1 MPH 0.9 5.9 10.3 SPD250 8.8 MPH 6.8 11.1 DIR 33A 339 DEG 14 286 356 DIR 33B 320 DEG 67 290 10 DIR150A 320 DEG 8 299 339 DIR150B 320 DEG 302 334 DIR250 333 DEG 309 354 TER 33A 43.5 F TER 33B 43.6 F 0 TER150A 42.6 F TER150B 42.3 F 0 TER250A 42.4 F TER250B 42.4 F DT150-33A -1.2 F/ DT150-33B -1.5 F/ DT250-33A F/ DT250-33B -1. 6 F/ DEWPOINT 49.2 F RAIN 0.00 INCH 0 1.02 1.02 0.00
11/17/93 08:15 RECORD NUMBER 1341 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A 7.1 MPH 1.4 3.1 9.5 SPD 33B 6.7 MPH 0 1.5 2.0 9.3 SPD150A 8.4 MPH 0 1.2 5.7 11.3 SPD150B 9.8 MPH 1.2 6.9 12.9 SPD250 9.5 MPH 0 1.0 7.2 11.8 DIR 33A 321 DEG 0 25 93 344 DIR 33B 320 DEG. 47 288 18 DIR150A 315 DEG 293 346 DIR150B 315 DEG 0 295 349 DIR250 327 DEG 0 13 298 358 TER 33A 42.9 F
.l""'ER 33B, 42.9 F -"0 " " 41.8
. ~4 Y ERl5'OA':--'-'-. F 0
, "..-;,.'TER'150B 42. 0 0 F'2.0 TER250A F TER250B 41.9 F 0 DT150-33A F/
DT150-33B -1. 4 F/ DT250-33A -0.9 F/ 0 DT250-33B -1.4 F/ 0 DEWPOINT 48.9 F RAIN 0.00 INCH 0 1.02 1.02 0.00
11/17/93 08:30 RECORD NUMBER 1342 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A 6.4 MPH 3.5 8.9 SPD 33B 6.1 MPH 1.2 2.0 8.7 SPD150A 7.3 MPH 1.2 4.7 10.7 SPD150B 8.5 MPH 1.3 6.0 12.6 SPD250 10.1 MPH 1.0 7.7 12.1 DIR 33A 343 DEG 13 285 346 DIR 33B 342 DEG 12 291 347 DIR150A 321 DEG 13 293 348 DIR150B 320 DEG 12 300 346 DIR250 342 DEG 9 320 358 TER 33A 42.6 F TER 33B 42.7 F TER150A 42.2 F TER150B 41.9 F TER250A 42.7 F TER250B 42.6 F DT150-33A -0.8 F/ DT150-33B -1.1 F/ DT250-33A 0.1 F/ DT250-33B -0.5 F/ DEWPOINT 48.6 F RAIN 0.00 INCH 0 1.02 1.02 0.00
11/17/93 08:45 RECORD NUMBER 1343 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A 5. 7 MPH 1.2 2.3 9.0 SPD 33B 5. 0 MPH 1.6 0.9 8.0 SPD150A 8. 1 MPH 1.5 4.4 11.4 SPD150B 9.1 MPH 1.3 6.1 12.3 SPD250 11.5 MPH 1.3 8.7 13.6 DIR 33A 342 DEG 77 288 17 DIR 33B 336 DEG 98 303 DIR150A 341 DEG 10 308 358 DIR150B 340 DEG 37 311 DIR250 355 DEG 184 330 TER 33A 42.6 F TER 33B 42.7 F TER150A 42.3 F TER150B 41.9 F TER250A 42.9 F TER250B 42.7 F DT150-33A -0.8 F/ DT150-33B F/ DT250-33A 0.3 F/ DT250-33B -0. 4 F/ DEWPOINT 48.4 F RAIN 0.00 INCH 0 1.02 1.02 0.00
11/17/93 09:00 RECORD NUMBER 1344 , GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A 4. 2 MPH 1.2 1.4 7.0 SPD 33B 3.9 MPH 1.4 7.4 SPD150A 8.8 MPH 1.2 5.7 10.7 SPD150B 9.9 MPH 1.2 6.6 12.0 SPD250 14.2 MPH 0.8 11.5 15.4 DIR 33A 346 DEG 68 289, 36'48 DIR 33B 338 DEG 284 47 DIR150A 345 DEG 6 330 356 DIR150B 343 DEG 5 323 351 DIR250 1 DEG 192 352 TER 33A 43.1 F TER 33B 43.1 F TER150A 42.4 F TER150B 42.1 F TER250A 44.0 F TER250B 44.0 F DT150-33A -1.0 F/ DT150-33B F/ DT250-33A 0.9 F/ DT250-33B 0.5 F/ DEWPOINT 48.9 F RAIN 0.00 INCH 0 1.02 1.02 0.00
11/17/93 09:15 RECORD NUMBER 1345 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A SPD 33B 4.2 4.0 MPH MPH 1.3 1.5 3.5 2.1 '.29.2 SPD150A 9.2 MPH 1.3 6.2 12.4 SPD150B 10.1 MPH 1.3 7.4 13.6 SPD250 5.3 MPH 1.7 2.1 10.0 DIR 33A 356 DEG 49 288 6 DIR 33B 344 DEG 69 296 8 DIR150A 340 DEG 8 321 359 DIR150B 338 DEG 37 322 0 DIR250 357 DEG 241 333 6 TER 33A 43.3 F TER 33B 43.4 F TER150A 43.5 F TER150B 42.3 F TER250A 43.9 F TER250B 43.9 F DT150-33A F/ 0 DT150-33B -1. 4 F/ DT250-33A 0.6 F/ DT250-33B 0.1 F/ DEWPOINT 48.9 F RAIN 0.00 INCH 0 1.02 1.02 0.00
11/17/93 09:30 RECORD NUMBER 1346 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A 4.2 MPH 1.5 2.8 11.3 SPD 33B 4.3 MPH 1.7 2.1 10.0 SPD150A 9.5 MPH 1.3 6.7 11.9 SPD150B 10.5 MPH 1.3 7.3 12.8 SPD250 11.5 MPH 1.2 8.1 13.4 DIR 33A 357 DEG 100 305 DIR 33B 358 DEG 144 313 20 DIR150A 347 DEG 37 323 DIR150B 345 DEG 37 325 DIR250 359 DEG 280 332 TER 33A 43.3 F TER 33B 43.4 F TER150A 43.6 F TER150B 42.5 F TER250A 43.7 F TER250B 43.6 F DT150-33A -0.9 F/ DT150-33B -1.2 F/ DT250-33A 0.4 F/ DT250-33B 0.1 F/ DEWPOINT 49.3 F RAIN 0.00 INCH 0 1.02 1.02 0.00
11/17/93 09:45 RECORD NUMBER 1347 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A 3.7 MPH 1.2 2.8 9.0 SPD 33B 4. 3 MPH 1.4 2.2 8.9 SPD150A 10. 4 MPH 1.2 7.0 12.7 SPD150B 11.2 MPH 7.8 12.9 SPD250 12.4 MPH 8 10.5 14.4 DIR 33A 8 DEG 173 311 33 DIR 33B 4 DEG 202 328 41 DIR150A 356 DEG 187 338 DIR150B 354 DEG 163 344 DIR250 9 DEG TER 33A 43.5 F TER 33B 43.6 F TER150A 43.9 F TER150B 42.7 F TER250A 44.0 F =- TER250B 44.0 F DT150-33A -1.2 F/ DT150-33B -0.9 F/ DT250-33A 0.5 F/ DT250-33B 0.9 F/ DEWPOINT 49.6 F RAIN 0.00 INCH 0 1.02 1.02 0.00 I
11/17/93 10:00 RECORD NUMBER 1348 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A 3.5 MPH 1.3 2.5 9.6 SPD 33B 3.6 MPH 1.4 3.2 9.4 SPD150A 6.2 MPH 0.9 4.8 7.1 SPD150B 6.4 MPH 0.8 4.8 7.1 SPD250 5.9 MPH 0.6 5.2 6.6 DIR 33A 17 DEG 257 303 32 DIR 33B 7 DEG 166 292 30 DIR150A ll DEG 356 21 DIR150B 10 DEG 0 ~ 74 357 19 DIR250 19 DEG 13 27 TER 33A 43.5 F TER 33B 43.3 F TER150A 43.9 F TER150B 43.6 F TER250A 44.7 F TER250B 45.0 F DT150-33A 0.2 F/ 0 DT150-33B 0.0 F/ DT250-33A 1.2 F/ DT250-33B 1.7 F/ DEWPOINT 50.1 F RAIN 0.00 INCH 0 1.02 1.02 0.00
11/17/93 10:15 RECORD NUMBER 1349 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A 3.3 MPH 1.2 2.4 4.8 SPD 33B 3.5 MPH 0 0.9 2.7 4.5 SPD150A 3.5 MPH 1.0 3.0 6.4 SPD150B 3.7 MPH 1.0 3.3 6.6 SPD250 3.6 MPH 0.5 3.3 6.2 DIR 33A 24 DEG 257 303 32 DIR 33B 27 DEG 166 292 30 DIR150A 31 DEG 64 356 41 DIR150B 30 DEG 74 357 39 DIR250 29 DEG 4 13 37 TER 33A 43.1 F TER 33B 42.9 F TER150A 43.2 F TER150B 43.7 F TER250A 45.0 F TER250B 45.0 F DT150-33A 0.8 F/ DT150-33B 0.5 F/ DT250-33A F/ DT250-33B 1.6 F/ DEWPOINT 50.2 F RAIN 0.00 INCH 0 1.02 1.02 0.00
11/17/93 10:30 RECORD NUMBER 1350 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A 3.0 MPH 1.2 2.7 5.2 SPD 33B 3.0 MPH 2.5 4.7 SPD150A 3-. 0 MPH 0.6 2.7 6.6 SPD150B 3. 2 MPH 0.4 2.7 6.8 SPD250 3.2 MPH 0.6 2.7 7.0 DIR 33A 41 DEG 90 355 51 DIR 33B 42 DEG 36 358 52 DIR150A 40 DEG 15 51 DIR150B 42 DEG 23 51 DIR250 40 DEG 31 50 TER 33A 42.8 F TER 33B 42.6 F TER150A 43.2 F TER150B 43.8 F TER250A 43.3 F TER250B 43.1 F DT150-33A 0.3 F/ DT150-33B 0.3 F/ DT250-33A 0.5 F/ 0 DT250-33B 0.5 F/ DEWPOINT 50.4 F RAIN 0.00 INCH 0 1.02 1.02 0.00
11/17/93 10:45 RECORD NUMBER 1351 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A 3.0 MPH 0.7 2.7 4.7 SPD 33B 3.0 MPH 0.7 2.7 SPD150A 3.5 MPH 0.7 3.0 6.1 SPD150B 3.6 MPH 0.7 2.7 6.3 SPD250 3.9 MPH 0.4 3.1 6.0 DIR 33A 39 DEG 10 27 50 DIR 33B 40 DEG 19 48 DIR150A 41 DEG 22 52 DIR150B 42 DEG 26 51 DIR250 43 DEG 37 49 TER 33A 42.6 F TER 33B 42.6 F TER150A 42.8 F TER150B 42.7 F TER250A 43.1 F TER250B 43.0 F DT150-33A 0.3 F/ DT150-33B 0.3 F/ DT250-33A 0.5 F/ DT250-33B 0.5 F/ DEWPOINT 50.3 F RAIN 0.00 INCH 0 1.02 1.02 0.00
11/17/93 11:00 RECORD NUMBER 1352 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN SPD 33A 3.0 MPH 0.5 2.3 4.5 SPD 33B 3.0 MPH 0.4 2.2 4.6 SPD150A 3.0 MPH 0.6 2.0 6.1 SPD150B 3.1 MPH 0.4 2.8 6.2 SPD250 3.3 MPH 0.3 2.9 5.6 DIR 33A 38 DEG 47 DIR 33B 39 DEG 23 49 DIR150A 39 DEG 20 53 DIR150B 41 DEG 27 54 . DIR250 38 DEG 33 41 TER 33A 42.9 F TER 33B 42.8 F TER150A 42.8 F TER150B 42.5 F TER250A 44.0 F TER250B 43.8 F DT150-33A 0.7 F/ DT150-33B 0.7 F/ DT250-33A F/ DT250-33B 1.1 F/ DEWPOINT 50.3 F RAIN 0.00 INCH 0 1.02 1.02 0.00
11/17/93 11:15 RECORD NUMBER 1353 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A 3.1 MPH 1.0 2.5 4.7 SPD 33B 2.9 MPH 0.7 2.6 4.3 SPD150A 3.1 MPH 0.4 2.6 5.7 SPD150B 3.2 MPH 0.5 2.7 5.7 SPD250 3. 1 MPH 0.4 2.7 4.7 DIR 33A 44 DEG 37 359 52 DIR 33B 45 DEG 12 51 DIR150A 42 DEG 12 31 46 DIR150B 38 DEG 30 48 DIR250 43 DEG 31 53 TER 33A 43.2 F TER 33B 42.8 F TER150A 43.1 F TER150B 43.2 F TER250A 44.0 F TER250B 43.8 F DT150-33A 0.4 F/ DT150-33B 0.4 F/ DT250-33A 0.8 F/ 0 DT250-33B 0.8 F/ DEWPOINT 50.3 F RAIN 0.00 INCH 1.02 1.02 0.00
11/17/93 11:30 RECORD NUMBER 1354 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A 3.0 MPH 1.0 1.7 4.0 SPD 33B 2.9 MPH 1.0 1.8 3.6 SPD150A 3.5 MPH 0.8 2.6 5.2 SPD150B 3.6 MPH 0.7 2.0 5.2 SPD250 3.4 MPH 1.5 3.2 5.5 DIR 33A 38 DEG 356 49 DIR 33B 39 DEG 48 DIR150A 39 DEG 37 58 DIR150B 42 DEG 34 58 DIR250 38 DEG 28 66 TER 33A 43.1 F .0 TER 33B 43.2 F TER150A 42.9 F TER150B 42.8 F TER250A 43.8 F TER250B 43.8 F 0 DT150-33A 0.3 F/ 0 DT150-33B 0.3 F/ DT250-33A 0.7 F/ DT250-33B 0.7 F/ DEWPOINT 50.5 F RAIN 0.00 INCH 1.02 1.02 0.00
11/17/93 11:45 RECORD NUMBER 1355 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A 3.1 MPH 0.6 2.3 5.5 SPD 33B 2.8 MPH 0.5 1.5 4.9 SPD150A 2.7 MPH 0.6 1.5 8.1 SPD150B 3.0 MPH 0.6 2.8 8.3 SPD250 2.6 MPH 0.5 1.6 8.0 DIR 33A 37 DEG 71 341 46 DIR 33B 38 DEG 36 358 DIR150A 51 DEG 5 39 63 DIR150B 53 DEG 4 44 60 DIR250 65 DEG 2 59 69 TER 33A 43.6 F TER 33B 43.4 F TER150A 44.0 F TER150B 44.1 F TER250A 44.9 F TER250B 44.9 F DT150-33A 0.6 F/ DT150-33B 0.6 F/ DT250-33A F/ DT250-33B 1.2 F/ DEWPOINT 50.9 F RAIN 0.00 INCH 1.02 1.02 0.00
11/17/93 12:00 RECORD NUMBER 1356 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A 3.1 MPH 0.5 2.2 4.7 SPD 33B 3.1 MPH 0.5 1.7 4.0 SPD150A 3.2 MPH 0.5 2.0 6.4 SPD150B 3.4 MPH 0.5 2.1 6.8 SPD250 3.3 MPH 0.6 2.1 6.5 DIR 33A 35 DEG 101 324 DIR 33B 35 DEG 36 353 46 DIR150A 54 DEG 42 DIR150B 54 DEG 45 61 DIR250 67 DEG 62 71 TER 33A 43.9 F TER 33B 43.6 F TER150A 44.3 F TER150B 43.9 F TER250A 45.2 F TER250B 45.8 F DT150-33A 0.8 F/ DT150-33B 0.7 F/ DT250-33A F/ 0 DT250-33B 1.4 F/ DEWPOINT 51.6 F RAIN 0.00 INCH 0 1.02 1.02 0.00
11/17/93 12:15 RECORD NUMBER 1357 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A 3.3 MPH 0.6 1.9 4.5 SPD 33B 2.9 MPH 0.6 1.5 3.9 SPD150A 2.7 MPH 0.9 2.3 6.4 SPD150B 3.0 MPH 0.6 2.. 6 6.5 SPD250 3.3 MPH 0.5 2.0 5.7 DIR 33A 43 DEG 51 DIR 33B 42 DEG 10, 13 57 DIR150A 64 DEG 45 78 DIR150B 64 DEG 43 77 DIR250 67 DEG 75 TER 33A 44.2 F 0 TER 33B 44.0 F TER150A 44.9 F TER150B 44.4 F TER250A 45.2 F TER250B 45.7 F DT150-33A 0.6 F/ DT150-33B 0.7 F/ DT250-33A 1.0 F/ DT250-33B F/ DEWPOINT 51.8 F RAIN 0.00 INCH 0 1.02 1.02 0.00
11/17/93 12:30 RECORD NUMBER 1358 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN SPD 33A 3.3 MPH 0.6 1.5 4.5 SPD 33B 2. 9 MPH 0 0.6 1.3 4.0 SPD150A 3. 8 MPH 0.8 1.6 '.1 SPD150B 3. 4 MPH 0.3 3.9 7.0 SPD250 2. 8 MPH 0.5 1.7 4.5 DIR 33A 43 DEG 14 85 DIR 33B 48 DEG 12 72 DIR150A 45 DEG 33 79 DIR150B 44 DEG 35 77 . DIR250 45 DEG 39 81 TER 33A 44.6 F TER 33B 44.6 F TER150A 45.3 F TER150B 45.7 F TER250A 45.5 F TER250B 45.5 F DT150-33A 0.5 F/ DT150-33B 0.6 F/ DT250-33A 0.9 F/ 0 DT250-33B 1.0 F/ DEWPOINT 52.3 F RAIN 0.00 INCH 0 1.02 1.02 0.00
11/17/93 12:45 RECORD NUMBER 1359 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A 3. 2 MPH 0. 6 -2.2 5.5 SPD 33B 3.0 MPH 0.6 2.7 5.0 SPD150A 3.1 MPH 2.3 7.1 SPD150B 4.7 MPH 0.5 3.6 '7.8 SPD250 4.0 MPH 0.5 2.9 5.0 DIR 33A 39 DEG 0 DIR 33B 37 DEG 22 68 DIR150A 40 DEG 34 81 DIR150B 38 DEG 32 76 DIR250 44 DEG 36 82 TER 33A 44.1 F TER 33B 44.2 F TER150A 44.4 F TER150B 44.4 F TER250A 45.3 F TER250B 45.2 F DT150-33A 0.6 F/ DT150-33B 0.6 F/ DT250-33A F/ 0 DT250-33B F/ DEWPOINT 51.9 F RAIN 0.00 INCH 1.02 1.02 0.00
11/17/93 13:00 RECORD NUMBER 1360 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A SPD 33B 3.2 2.7 MPH MPH 0.4 0.4 1.9 1.7 '.0 4.0 SPD150A 3.6 MPH 0.8 1.7 5.7 SPD150B 3.7 MPH 0.6 2.9 6.8 SPD250 3.0 MPH 1.2 2.7 6.5 DIR 33A 40 DEG 51 357 65 DIR 33B 37 DEG 12 DIR150A 78 DEG 0 60 92 DIR150B 78 DEG 0 61 91 DIR250 81 DEG 71 90 TER 33A 44.8 F TER 33B 44.9 F TER150A 45.5 F TER150B 45.5 F TER250A 45.7 F TER250B 45.7 F DT150-33A 0.6 F/ 0 DT150-33B 0.5 F/ DT250-33A 0.9 F/ DT250-33B 1.0 F/ DEWPOINT 52.3 F RAIN 0.00 INCH 0 1.02 1.02 0.00
11/17/93 13:15 RECORD NUMBER 1361 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A 3.3 MPH 0.5 2.0 6.4 SPD 33B 3.0 MPH 0.5 1.3 6.2 SPD150A 3.1 MPH 0.7 1.9 5.6 SPD150B 3.2 MPH 0.8 2.1 7.3 SPD250 3.8 MPH 0.5 1.6 6.2 DIR 33A 35 DEG 0 51" 359 DIR 33B 32 DEG
II q 1 s h 4 K' '\ l 1 C. )I TABLE 10.2 Plume Arrival & Departure Times Distance miles Arrival ~De arture 0.5 11:00 13:00 1.0 11:20 13:20 2.0 11:40 13:40 3.0 12:00 14:00 12:20 14:20 5.0 12:40 14:40 6.0 13:00 15:00 7.0 13:20 15:20 8.0 13:40 15:40 9.0 14:00 16:00 10.0 14:20 16:20 11.0 14:40 16:40 12.0 15:00 17:00 NOTES: " After indicated arrival time, refer to offsite radiological data shown on Table 10.3 as appropriate for zone of interest. '" After indicated departure time, all dose rates (mR/hr) will be background. For ground deposition readings, refer to post-plume radiological data shown on Tables 10.4 and 10.5 ~ 1 TABLE 10.3 RADIOLOGICALSURVEY DATA (RG&E SURVEY TEAMS) CLOSED OPEN DOSIMETRY CLOSED WINDOW ON OPEN WINDOW ON INCREMENT IODINE PARTICULATE WINDOW,AT CONTACT WINDOW AT CONTACT EXPOSURE CARTRIDGE FILTER ZONE 3 FEET mR/hr mR/hr 3 FEET mR/hr mR/hr mREM CPM CPM A 4.8E+03 4.8E+03 7.1E+03 7.1E+03 1.2E+03 6.1E+03 7.6E+02 2.2E+03 2.2E+03 3.3E+03 3.3E+03 5.6E+02 2.6E+03 3.6E+02 1.0E+03 1.0E+03 1.5E+03 1.5E+03 2.5E+02 1.2E+03 1.8E+02 4.7E+02 4.7E+02 6.9E+02 6.9E+02 1.2E+02 5.8E+02 1.1E+02 2.9E+02 2.9E+02 4.3E+02 4.3E+02 7.2E+01 3.7E+02 8.1E+01 1.9E+02 1.9E+02 2.8E+02 2.8E+02 4.7E+01 2.6E+02 6.7E+01 G 1.2E+02 1.2E+02. 1.8E+02 1.8E+02 3.0E+01 1.8E+02 5.7E+01 8.6E+01 8.6E+01 1.3E+02 1.3E+02 2.2E+01 1.4E+02 5.2E+01 6.8E+01 6.8E+01 1.0E+02 1.0E+02 1.7E+01 1.2E+02 5.0E+01 NOTES:
- 1) Dose rate readings apply to Victoreen 450 dose rate instrument or equivalent.
- 2) Dosimeter incremental exposure assumes a 15-minute stay-time in the particular zone of interest.
- 3) Air samples assume use of RADECO H-809C air sampler or equivalent. Volume assumed is approximately 180 liters (30 Ipm for 6 minutes), and field reading is with HP-260.
4 I4 4 ~ hW h 4 I 4 h 4 1 4 4 I 4 4 4 4 TABLE 10.3 RADIOLOGICALSURVEY DATA (COUNTY SURVEY TEAMS) CLOSED OPEN DOSIMETRY CLOSED WINDOW ON OPEN WINDOW ON INCREMENT IODINE PARTICULATE WINDOW AT CONTACT WINDOW AT CONTACT EXPOSURE CARTRIDGE FILTER ZONE 3 FEET mR/hr mR/hr 3 FEET mR/hr mR/hr mREM CPM CPM 4.8E+03 4.8E+03 7.1E+03 7.1E+03 1.2E+03 9.6E+03 1.2E+03 2.2E+03 2.2E+03 3.3E+03 3.3E+03 5.6E+02 4.1E+03 5.5E+02 1.0E+03 1.0E+03 1.5E+03 1.5E+03 2.5E+02 1.9E+03 2.7E+02 4.7E+02 4.7E+02 6.9E+02 6.9E+02 1.2E+02 8.9E+02 1.5E+02 2.9E+02 2.9E+02 4.3E+02 4.3E+02 7.2E+01 5.6E+02 1.1E+02 1.9E+02 1.9E+02 2.8E+02 2.8E+02 4.7E+01 3.8E+02 8.3E+01 G 1.2E+02 1.2E+02 1.8E+02 1.8E+02 3.0E+01 2.6E+02 6.7E+01 8.6E+01 8.6E+01 1.3E+02 1.3E+02 2.2E+01 2.0E+02 6.0E+01 6.8E+01 6.8E+01 1.0E+02 1.0E+02 1.7E+01 1.6E+02 5.6E+01 NOTES:
- 1) Dose rate readings apply to Victoreen 450 dose rate instrument or equivalent.
- 2) Dosimeter incremental exposure assumes a 15-minute stay-time in the particular zone of interest.
- 3) Air samples assume use of RADECO H-809C air sampler or equivalent. Volume assumed is approximately 10 cubic feet and field reading is with HP-260.
"'7 ~ 1 Il '4 i@7 'V 'I 9) 4 1 ( 'I TABLE 10.4 POST-PLUME RADIOLOGICALSURVEY/SAMPLING DATA ( FOR END WINDOW AND PANCAKE PROBES) POST-PLUME DECAY TIME = 1.0 HOURS END WINDOW PANCAKE PROBE (CPM) PROBE (CPM) ZONE 1 METER 1 CM 1 METER 1 CM A 2.3E+ 03 3.3E+04 3.BE+ 03 5.0E+04 B 1.1E+03 1.5E+ 04 1.BE+03 3.9E+04 C 4.9E+ 02 6.9E+ 03 8.0E+02 1.7E+04 D 2.3E+ 02 3.2E+ 03 3.7E+ 02 8.1E+ 03 E 1.4E+ 02 2.0E+ 03 2.3E+ 02 5.0E+03 F 9.2E+ 01 1.3E+ 03 1.5E+02 3.3E+03 G 5.9E+ 01 8.3E+02 9.6E+ 01 2.1E+03 H 4.2E+ 01 6.0E+ 02 6.9E+ 01 1.5E+03 I 3.3E+ 01 4.7E+ 02 5.5E+ 01 1.2E+03 t 1 g I r I 4' 1 'h l n A ~w 1 t TABLE 10.5 GAMMA MICRO-R/HR READINGS DUE TO GROUND DEPOSITION POST-PLUME DECAY TIME = 1.0 HOURS @1 METER @1 CM ZONE MICRO-R/HR MICRO-R/HR A 1.1E+03 1.8E+03 B 5.0E+ 02 8.5E+ 02 C 2.2E+ 02 3.8E+ 02 D 1.0E+02 1.8E+02 E 6.4E+ 01 1.1E+02 F 4.2E+ 01 7.1E+ 01 G 2.7E+ 01 4.6E+ 01 H 1.9E+ 01 3.3E+ 01 I 1.5E+ 01 2.6E+ 01 t 'la gI / 44 s< M P 'k '4~ I 0 "k I ~~, q ~)pe ~l f I jJ ~ 4 4&< mW" gi p VGV>> f/) j l ;i <<") / sl I. V t " :.- ) b bi l V z k ) e 1, 5 a $ = ~~ t C Ot'l..k \ i i~ Q l~ 4 sg I. "" r-~ .fl f~W, aj g 4" (K~ Ir k ' FlGURE 10.2 PLUME MAP. (0-0'll E) pffft t t,CI~ t~ ~ ted@ ~ ~ ~ ~ t~lTT FDCt r-- I ~a LAat aoA tttt l suss TATIOH 104 .S Slip. Cl 0 R ~I I R W Ct O R I a 0 I' ~ R I ~ t II I I +t I ~ g;.gcjt;:. =""s N I E I I / I r l Je J ;I' .J I II ~ tt I ~ .~ I>> 'I 'I t It t IN I ~ I 2fj /iE r I E / t r I J r r - 'I 'I r I II ' 'I I I Figure 10.3 15 MII ~c. ~ N Rlyctee 8hrN Plume Map 0-10 Mile I ~cccrteppeKcrc I ic cc utah mrc 1 0 .lVII III rcrc iec Sttch I <P .'C ~c 'I h ~ ) Vee berth I .. /c Ccc /I 'r hnl hticli p'Llehcecc ~ 8etch Feet re / Le+et P'Ki wt .c Pc I n I ee nn 8ren t.j;:,. + ~ per let ~ tel ~ cce Ctnn /
- /I': I cclcclt ev U ro
~ I We Web( IKK ~ tl ~ (P reA cf I /4. g I I P / ~ Well / ~ I~ ~ ~ WII ~ ~ I AI ljce, ~ <<I'//'QO Wlfcerct IF%I Ice ~ I r " '-'//'.I . Ihhhc I I ~ I Jl'v r'/ hv R h recto rF c'eer rwr M ~ Pnthh htKO Qi( ct I I \ ICP / J 0 Ceccn C ( COIPIPh /I 'V / ~ 0 II r K OIPI 0 5 heir I CI 0 IJ ~ ~ IQQ / I;MPP fi r Wl 'CI 'Ih ~ P, 1 P i P.C. F)~'9,.x'-"A fik'AR S.'Q'~ 10.3 A/R SAMPLING DATA t p hh ~ r~ Pt,I O'I ~(s Q'J' )fi3c I ~ I ." f-3'- o > 0 'a8 J(A" f h .) 0( Of->> '-'.> f.r -3R:.5 ff 3~t C i. ->>-'IG ~ Ir i 'l'IC! 'r '!Bi (h f 3Gt" '..'" ~&'. t! Ih f A/I"i Al 'di t h\ ht r r".Jti t PIC ' >>fi) ,h..'~ ~ '.340.: 6 d Or 'l 3.!GA'">GIRT%A) 5 l Ivt I -!<() "'! Al 3rUQ3>> if3V.IIH ~ GOfi 'IGAR C' I Q j~.>>i J~ lhri i h "P'r '<~ 36t> '- ')0- tIC""~~ .0. ~'C I i(<, "r'l>Q P I>>
- I) 8
-'n.3.".P ~i uJ 3V -';l.i >hfdf> '.. i*"..."6:: r' I zhhl~i, y '6(!-3f t"..Z ~I,)'3 I Q .o. 0 'V>>t .'.'(!-3 VO h-30',C 69, .if ~ 3vO,~; CV 3r3o.'C P.O '"(4 2 K' 3C0.O '.>Q 3 g{' TABLE 10.6-A AIR PARTICULATE FILTER ISOTOPIC ACTIVITY SAMPLE COLLECTION DURING PLUME PHAS COUNTY TEAMS - 10 CUBIC FT SAMPLE l-131 I-133 " I-135 CS-134 CS-137 BA-140 LA-140 ZONE UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC A 2.23E-09 4.45E-09 4.03E-09 5.34E-10 - 2.45E-10 1.25E-11 1.25E-11 B 9.90E-10 1.98E-09 1.79E-09 2.38E-10 1.09E-10 5.54E- 'I 2 5.54E-12 C 4.43E-10 8.85E-10 8.01E-10 1;06E-10 4.87E-11 2.48E-12 2.48E-12 D 2.07E-10 4.13E-10 3.74E-10 4.96E- 1 1 2.27E-1 1 1. 1 6E-'1 2 1.16E-12 E 1.27E-10 2.54E-10 2.30E-10 3.05E-11 1AOE-11 7. 12E-13 7.12E-13 F 8.35E-1 1 1.67E-10 1.51E-10 2.00E-11 9.18E-12 4.68E-13 4.68E-13 G 5.33E-11 1.07E-10 9.65E-11 1.28E-11 5.86E-12 2.98E-13 2.98E-13 H 3.83E-11 7.66E-11 6.93E-11 9.19E-12 4.21E-12 2.14E-13 2.14E-13 I 3.02E-11 6.04E-11 5.47E-11 7.25E-12 3.32E-12 1.69E-13 1.69E-13 TABLE 10.6-8 SILVER ZEOLITE CARTRIDGE RADIOIODINE ISOTOPIC ACTIVITY SAMPLE COLLECTION DURING PLUME PHAS COUNTY TEAMS - 10 CUBIC FT SAMPLE
- I-131 I-132 I-133 I-134 I-135 ZONE UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC A 2.23E-07 3.21E-07 4.45E-07 O.OOE+ 00 4.03E-07 B 9.90E-08 1.43E-07 1.98E.07 O.OOE+ 00 1.79E-07 C 4.43E-OS 6.37E-OS 8.85E-08 O.OOE + 00 8.01E-OS D 2.07E-08 2.98E-OS 4.13E-OS O.OOE+ 00 3.74E-OS E 1.27E-OS 1.83E-OS 2.54E-OS O.OOE+ 00 2.30E-OS F 8.35E-09 1.20E-OS 1.67E-OS O.OOE+ 00 1.51E-OS 5.33E-09 7.67E-09 1.07E-OS O.OOE+ 00 9.65E-09 H 3.83E-09 5.51E-09 7.66E-09 O.OOE+ 00 6.93E-09 S
I 3.02E-09 4.35E-09 6.04E-09 O.OOE+ 00 5.47E-09 i}}