ML20127G305
| ML20127G305 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 03/25/1985 |
| From: | CONSOLIDATED EDISON CO. OF NEW YORK, INC. |
| To: | |
| Shared Package | |
| ML20127G295 | List: |
| References | |
| PROC-850325, NUDOCS 8506250411 | |
| Download: ML20127G305 (103) | |
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CONSOLIDATED EDISON COMPANY OF NEW YORK f INDIAN POINT UNIT NO. 2 i DRILL SCENARIO NO. 1985 i
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O CONSOLIDATED EDISON COMPANY OF NEW YORK INDIAN POINT UNIT NO. 2 DRILL SCENARIO NO. 1985 TABLE OF CONTENTS Section I. Introduction II. Objectives III. Drill Scenario IV. Messages & Controller Field Reports V. Observer / Controller Instructions VI. Plant Status Log VII. Radiological / Meteorological Log VIII. Radiological Information IX. Logistics O
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i 4 -~ CONSOLIDATED EDISON COMPANY OF NEW YORK
,/ I INDIAN POINT UNIT NO. 2' DRILL SCENARIO NO. 1985, i
I. INTRODUCTION The purpose of this drill is to demonstrate Con Edison's capa-bility to effectively implement the Indian Point Unit No. 2 Site Emergency Plan and Procedures.
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This document has been prepared to assist the drill Observer / Con-trollers in the conduct and evaluation of the drill. It contains all the information and data necessary to properly conduct the I d
drill in an efficient and coordinated manner and is broken down !
i as follows: l Section II Objectives - this section defines the drill objectives. !
Section III Drill Scenario - this section describes the Indian Point Unit No. 2 postulated sequence of events occurring which will require the onsite emergency response organizations to respond. For each event described, the anticipated results of the participants are also detailed. These results should be used as a guide in evaluating the drill. However, it should be O noted that the results observed may vary from those stated and should be evaluated on a case-by-case basis with respect to applicable procedures.
Section IV Messages - this section contains copies of the drill messages which will be utilized to control the progress of the drill scenario.
Section V Observer / Controller Instructions - this section provides general instructions to the drill Observers and Control-1ers in the conduct of the drill. Also included is evaluation criteria for evaluating the responses of the drill participants.
Section VI Plant Status Log - this section contains time-related information (non-radiological) concerning plant conditions, which corresponds to the development of the drill scenario.
! -Section VII Radiological / Meteorological Log - this section contains time-related plant radiological and meteorological data which corresponds to the development of-the drill scenario.
Section VIII Radiological Information - this section contains time-related radiological information in the following categories as required by the scenario:
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o Primary Coolant Activity Containment Activity Release Path Activity I-I I
SCENARIO NO. 1985 o Plant Radiation Levels Facility Radiation Levels
( ) o o Reuter-Stokes Readings o Plume Monitoring Data & Figures o Offsite TLD Readings o Post Accident Samples o Post Accident Offsite Contamination Levels o Medical Emergency Data Section IX Logistics -
this section contains information and direction for the handling of peripheral items related to the day of the drill, o Food for participants o Access lists o Methods of identification of players, controllers, observers, visitors, etc.
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gg CONSOLIDATED EDISON COMPANY OF NEW YORK
' INDIAN POINT UNIT NO. 2 DRILL SCENARIO NO. 1985 II. OBJECTIVES A. Emergency Operations Facilities
- 1. Demonstrate the activation and staffing of emergency response facilities.
o Control Room (CR)*
o Technical Support Center (TSC) o Operational Support Center (OSC) o Emergency Operations Facility (EOF) o Corporate Response Center (CRC)
- A separate non-operating watch organization will be identified and instructed as to the time to report to the control room. This will ensure their availability to respond when the Chief Controller starts the drill.
(" 2. Demonstrate Indian Point Unit No. 2's communication
\ capabilities among the Control Room (CR), Technical Support Center (TSC), Emergency Operations Facility
- 3. Demonstrate the ability of Indian Point to coordinate, control and deploy radiological monitoring teams via the respective field communications system.
B. Alerting and Mobilization of Officials and Staff
- 1. Demonstrate the ability of Indian Point Unit No. 2 staff to classify actual or potential emergencies in accordance with Indian Point Emergency Plan Implamenta-tion Procedures as to:
o Alert o Site Area Emergency
- 2. Demonstrate the capability of Indian Point Unit No. 2 to notify the State, local and Federal levels of government in accordance with Federal and established protocols.
- 3. Demonstrate the capability to communicate technicsl information between Indian Point Unit No. 2 emergency facilities. Indian Point Unit No. 2 will also demonst-rate communicating with the NRC via the NRC Hot Line.
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4 SCENARIO NO. 1985 O C. Emergency Operations Management
- 1. Evaluate the adequacy and capability of implementation of the Indian Point Unit No. 2 radiological emergency plan.
- 2. Demonstrate the emergency respense capabilities of Indian Point Unit No. 2.
- 3. Demonstrate the capability of Indian Point Unit No. 2 to implement its radiological emergency preparedness plan in a manner satisfying NRC acceptance criteria.
- 4. Demonstrate the ability of key emergency personnel at Indian Point Unit No. 2 to initiate and coordinate timely and effective decisions with espect to a radiological emergency, and clearly demonstrate command and control functions at the station.
- 5. -Demonstrate that there is effective organizational control (direction and control) and integrated onsite radiological emergency response including deployment of field monitors, and receipt and analysis of field data.
D. Accident Assessmeg
- 1. Demonstrate the ability of Indian Point Unit No. 2 to receive and assess radiological data from field teams in accordance with the emergency plan implementation procedures.
- 2. Demonstrate the ability of Indian Point Unit No. 2 to calculate dose proj ections , compare the projections to the Protective Action Guides (PAGs) and determine appropriate protective actions.
- 3. Demonstrate the activation, operations and reporting procedures of Indian Point Unit No. 2 field monitoring teams dispatched beyond the site boundary.
E. Actions to Protect the Public
- 1. Demonstrate the capability of Indian Point Unit No. 2 personnel to assess the actual or potential exposure to radiation of the offsite population and to recommend appropriate Protective Actions.
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i SCENARIO NO. 1985 F. Health, Medical and Exposure Control Measures i
- 1. Demonstrate exposure control practices for repair and field teams in accordance with the provisions of the Indian Point Unit No. 2 onsite Emergency Plan Implement-ation Procedures. Accountability practices and exposure control measures will be limited to the Operational Support Center.
- 2. Demonstrate the decision process for limiting exposure of emergency workers.
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CONSOLIDATED EDISON COMPANY OF NEW YORK INDIAN POINT UNIT NO. 2 DRILL SCENARIO NO. 1985 III. DRILL SCENARIO Initial Conditions Con Edison Indian Point Unit No.2 has been shutdown for a refuel-ing outage for 10 days and the first spent fuel elements have been placed in the fuel storage building. Spent fuel is in the process of being unloaded from the reactor vessel.
Narrative Summary The fuel handling crew in the fuel storage building is moving a spent fuel cask from the south end of the building to the storage pool via the crane. As the cask travels over the area of the spent fuel removed from the reactor during this outage, the cables break and the cask falls into the pool and breaks several fuel elements.
The fuel storage building ARM alarms in the Control Room and all the local monitors in the fuel storage building alarm warning the crew to evacuate. After evacuating the building the fuel O- handling crew notifies the Senior Watch Supervisor of the accident.
After analyzing the ARMS and PRMs, the Senior Watch Supervisor declares an ALERT. Notification is made to the offsite authorities.
The site emergency assembly alarm is sounded. No assembly of non-players will be made. Accountability Officers will be appointed to simulate accountability interface with the Chief Accountability Officer.
Mobilization will be handled by the individual facility directors as per procedure.
After the cask accident, the spent fuel cooling pump shuts down.
The Control Room is alerted to the pump shut down by the spent fuel pit water temperature alarm annunication. In addition; because of failure of the reactor vessel press ray cavity seal and subsequent leakage into the reactor vessel cavity, the reactor cavity sump level increases and the containment sump pumps start operating continuously at a steady rate of discharge and the containment radiogas monitor alarms show a rise in containment activity. Isolation of the containment ventilation will not take place because the radiogas monitor contact is defective.
s Entry to the containment will show water running down the inside area of the biological shield wall. t will be found that the nitrogen bottles for the " press ray" cavity seal are all empty and no spare bottles are available in containment.
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SCENARIO NO. 1985 Prior to the cask accident the refueling crew left a spent fuel assembly in storage in the rod control cluster change fixture station. This presents an additional concern because of the ON decreasing refueling cavity level.
Later the release rate increases to a level requiring the declaration of a Site Area Emergency. While the time lapse between the release levels necessitating the declaration of an Alert and a Site Area Emergency ie not realistic, it will allow for the original dose assessment to be performed by the Senior Watch Supervisar and the subsequent assessment by the Emergency Operations Facility personnel.
The release will continue for approximately two and one half hours to allow offsite air concentrations and field measurements to be performed and to allow the TSC/OSC repair teams to repair the failed equipment.
No post accident offsite sampling will be required and a recovery phase will not be demonstrated. It is expected that the drill will be terminated at approximately 1215 hours0.0141 days <br />0.338 hours <br />0.00201 weeks <br />4.623075e-4 months <br />.
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SCENARIO NO. 1985 DETAILED SCENARIO TIME LINE INITIATING
-z MESSAGE t
\ #l TIME NUMBER EVENT
SUMMARY
T = 08:30 1 Initial Conditions established.
T = 08:40 A Fuel Handling Reactor Operator (FHRO) &
Controller leave the Control Room and go to the Fuel Storage Building (FSB).
FHR0 will not be told his job until they reach the FSB.
T = 08:55 2 FHR0 is told that the spent fuel cask he has been moving across the storage pool drops on top of fuel elements that have been among the first removed from the core. Violent bubbling is seen in the pool water. FSB air monitoring and ARM alarms.
ANTICIPATED RESULTS Fuel Handling Reactor Operator (FHRO)
- Immediately evacuates FSB.
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- Goes to the nearest phone to call the
( ,) Control Room.
T= 08:57 3 Control Room category alarms initiated.
o ARM /PRM high radiation.
ANTICIPATED RESULTS Control Room Operator (CRO) l l
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- Inspects instruments on ARM /PRM panel.
- Reviews Abnormal Operating Instructions A.12.2 and A.13.B.
- Reviews Abnormal Operating Instruction A.17.2 T= 08:59 3-C-1 The FHR0 should call the Control Room and report the accident.
T = 09:00 4 Alarmed radiation monitor values.
R-5 2.5 R/hr -
kAL'A T R-13 l
' Offscale g3
- R-14 Offscale 4
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' R-27 2.0 x 10 Ci/sec III-3
SCENARIO NO. 1985 DETAILED SCENARIO TIME LINE INITIATING
( MESSAGE TIME- NUMBER EVENT
SUMMARY
ANTICIPATED RESULTS Control Room Operator (CRO)
- Notifies Senior Watch Supervisor.
Senior Watch Supervisor (SWS)
- Declares an ALERT because of Initiating Condition No. 6.
- Fills out " Radiological Emergency Data Form, Part I."
- Directs the " Communicator" to make the appropriate notifications in accordance with IP-1002.
Starts offsite dose assessment IP-1007.
B - Dispatches Watch Rad Prot Tech to survey the Fan Bldg. and the PAB.
( C - Dispatches the Watch Chem Tech to sample the Plant Vent.
- Obtains Reuter-Stokes readings IP-1037.
- Determines whether any protective actions are required. A no protective action recommendation would be con-sidered correct.
Operations Control Center (OCC)
D - Follows directions in IP-1002 section 4.4.
T = 09:05 5 Controller gives OCC duty person the message to be used for the pager initia-tion.
Controller specifies individuals to be notified under 4.4.5 and 4.4.6.
Controller deletes requirements of 4.4.3.
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SCENARIO NO. 1985 DETAILED SCENARIO TIME LINE INITIATING O
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TIME MESSAGE NUMBER EVENT
SUMMARY
T.= 09:10 3-C-2 The SWS should declare an ALERT at this time and initiate appropriate actions and notifications if not already done.
T = 09:10 E OSC staffing limitations set by Controller.
T = 09:30 The Watch Rad Prot Tech reports the results of the Fan Bldg /PAB field survey to the SWS.
T = 09:30 6 Spent Fuel Pit Cooling Pump Trips.
Annunciator Spent Fuel Pit Hi-Temp.
T = 09:40 F Controller directions to CRC personnel.
T = 09:45 The Watch Chem Tech reports the results of the Plant Vent sample to the SWS.
T = 09:50 7 Spent Fuel Pit Cooling Pump overload is blown.
T= 10:00 8 Controller gives CR0 message that the Plant Vent curie per second discharge O has jumped up by a factor of 100.
ANTICIPATED RESULTS Control Room Operator (CRO)
- Notifies Senior Watch Supervisor and Plant Operation Manager.
Plant Operations Manager (POM)
- Notifies the Emergency. Director and recommends the emergency classifica-tion be changed to a SAE because of initiating condition No. 8.
G - Directs the OSC Coordinators to send a Rad Protection Tech to perform a fiald survey at the Fan Building and the Primary Auxiliary Building 80' el. l
- Directs the OSC Coordinators to have the Chem Tech sample the plant vent and determine the radioactive concentrations.
Emergency Director (ED)
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- Declares a SITE AREA EMERGENCY because of initiating Condition No. 8.
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e SCENARIO No. 1985 DETAILED SCENARIO TIME LINE INITIATING O TIME MESSAGE NUMBER EVENT
SUMMARY
- Determines whether any protective actions are required. A recommendation for sheltering within a 5 mile radius would be considered correct.
- Has " Radiological Emergency Data Forms, Parts I, II & III" filled out.
- Directs the EOF " Communicator" to make appropriate notification to the offsite authorities and Con Edison facilities.
- Directs ORAD to initiate further offsite sampling to evaluate radiation levels.
- Obtain status of accountability.
- Directs evacuation of relocation of all non-essential personnel.
Offsite Radiological Assessment Director
(~N y) (ORAD)
- Check information obtained from TSC.
- Perform necessary dose projections.
Determine recommended protective actions using IP-1013. Review with ED.
- Confers with Dose Assessment H.P. and dispatch offsite monitoring teams to specified environmental sampling survey points.
- Continues to mobilize the EOF staff if full activation has not been completed as yet.
- Directs Survey Team H.P. to monitor the radiological condition at the EOF.
- Directs Survey Team H.P. to have site boundary surveys performed as called for.
TSC Manager
- Continues to have full mobilization of
\ TSC staff implemented.
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SCENARIO NO. 1985 DETAILED SCENARIO TIME LINE INITIATING O TIME MESSAGE NUMBER EVENT
SUMMARY
- Transmits plant data to EOF.
- Investigates the isotopic makeup of the spent fuel radioactivity related to full power days and time after shutdown.
- Checks the balance of ventilation system to preclude spread of activity in plant.
- Supports Control Room and maintenance activities.
Chief Accountability Officer (CAO)
- Expected to complete accountability within 30 minutes of the declaration of an SAE.
Continues to mobilize the OSC minimum staffing requirements as per IP-1023.
- Supplies repair and corrective action team members as requested by OSC O Coordinators.
Radiation Protection Technician (RPT)
- Provides radiological control for the Control Room, including set up of Step-Off Pad and "frisker" at entrance from turbine floor to SWS office; or as directed by the SWS.
- Performs surveys requested by SWS or POM.
- Evaluates PRM-ARM instrumentation; l - Determines status of controlled area i evacuation, and reports to SWS.
Survey Team Health Physicist (STHP)
- Checks equipment availability.
- Performs field survey at EOF; including set-up of TRITON in accordance with IP-1041, and set-up of SAM-2/RD-22 and RM-14/HP-210 Counter and Air Sampler O- in accordance with IP-1020.
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SCENARIO NO. 1985 DETAILED SCENARIO TIME LINE INITIATING
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MESSAGE ,
TIME NUMBER EVENT
SUMMARY
- Obtains two (2) Handi-Talkies from Security.
- Assigns film badges and dosimeters.
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- Sets-up FRISKER and Step-off Pad at upper and lower entrance of EOF.
- Performs appropriate surveys approxi-mately every 30 minutes.
- 'ollows and maintains personnel xposure and contamination control for all personnel.
- Confers with ORAD and dispatches onsite field survey teams and receives data. Places field survey readings on Site Map.
T= 10:10 H, I & J Controller field reports regarding water levels.
( T= 10:15 8-C The Emergency Director should declare a SITE AREA EMERGENCY and initiate appro-priate actions and notifications if it has not already been done.
T= 10:25 K CRC notification requirements set by Controller.
T= 10:30 The Rad Protection Tech reports the results of the Fan Building / Primary Auxiliary Building 80' el, to the OSC Rad Protection Coordinator.
T= 10:45 The Chem Tech reports the results of the Plant Vent sample to the Rad Protection Coordinator and Chemistry Supervisor.
T= 10:45 9 Control Room annunciators; f
l o High Water Reactor Cavity o Hi-Hi Water Reactor Cavity o VC sump pumps start T= 10:45 L Controller Field Report to explain 10, 10-C-1 & 10-C-2.
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SCENARIO No. 1985 DETAILED SCENARIO TIME LINE INITIATING
(' ) TIME MESSAGE NUMBER EVENT
SUMMARY
T= 10:50 10 Control Room PRM Annunciated. R-12 containment radiogas monitor recorder shows increasing activity.
T= 11:00 11 Spent fuel cooling pump thermal overload was found defective and was replaced.
The pump is now operating.
T= 11:15 10-C-1 R-12 did not activate containment isolation.
T= 11:20 12 Inspection in containment results in discovery of water running down reactor biological shield wall. N bottles used 2
for pressray seal are empty.
T= 11:23 13 The release has terminated.
T= 11:45 10-C-2 R-12 recorder contact defective.
T= 12:15 14 The drill is terminated.
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CONSOLIDATED EDISON COMPANY OF NEW YORK INDIAN POINT UNIT-NO. 2 DRILL SCENARIO NO. 1985 l l
IV. MESSAGES !
l TO: ALL EXERCISE PARTICIPANTS FROM: ALL LOCATIONS TIME: When the players report to the facility MESSAGE: EXERCISE GROUND RULES All Exercise participants are required to observe the following Exercise Ground Rules for the entire duration of the Exercisc.
If you have any questions, ask your Facility Controller for clarification at this time.
- 1. Ensure that all communications indicate that this is only an exercise. Make a positive statement that this is an exercise-related message at the beginning and and of all messages or conversations. If communication lines are kept open for extended periods, periodically repeat the caution. This is especially critical when
( transmitting messages over communication facilities that are monitored by non-Consolidated Edison personnel.
- 2. Take no actions that affect unit or non-exercise related operations.
- 3. Take immediate action (s) to restore safe operation, if an unsafe condition exists. Ignore exercise situation if actual safety becomes a concern.
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- 4. Use only the information provided in accordance with the exercise ground rules or derived from approved procedures. Do not improvise information. Provide the actual outside temperature and precipitation conditions, when applicable.
- a. Controllers will provide appropriate information at the location where that information would normally I be available (e.g., Reactor status at the Control Room, dose rate readings with field teams, meteoro-logical information at Control Room or EOF).
- b. Only selected parameters and readings will be provided. The selected information will be suffi-cient to make decisions in accordance with Con
() Edison plans and procedures.
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- c. DO NOT llECOME OVERLY CONCERNED W I T il Tile MECil AN ICS "p 0F Til E HEACTOR OR Tile CAliSE OF Til E ACCIDENT. Til l S EXERCISE IS DESIGNED TO TEST CON EDISON PLANS AND PROCEDURES AND IS NOT CONCERNED W I Til BRAINSTORMING Tile P R0ll A H I L ITY , FEASIBILITY OR DETAlLED MEC}lANICS OF Tile SIMI! LATED ACCIDENT.
- d. There will be a con Edison Observer / Controller at each important location. Controllers will provide information and clarification on which actions are to be simulated or are outside the scope of this exercise in order to keep the exercise progressing in accordance with the scenario. Observer / Control-1ers will also observe all aspects of the exercise to prepare an in-house evaluation of plans, proced-ures and training.
- 5. Be sure that the Con Edison Observer / Controller is aware of your actions (actual or simulated).
- 6. Make all procedurally required notifications unless directed not to by the Controller.
- 7. If samples inside or outside the site are deemed necessary, they will actually be collected if possible, and their analysis conducted or simulated if directed by a Controller. Observer / Controllers will accompany a# the survey teams, both onsite and offsite.
- 8. This exercise is conducted to evaluate our plans and pro cedures. The exercise is also a training vehicle for members of the Con Ed Emergency Response Organization to practice working together and with outside organiza-tions. Please make note of any improvements in.any arel that you observe as a participant and submit them to the Observer / Controller at the conclusion of the exercise.
- 9. If, during any part of the exercise, you are having trouble accomplishing your required duties, confusion arises, or clarification is necessary, ask your Controll Controller assistance or clarification does not neces-sarily imply failure on your part. Your Controller will know the limitations of information he can provide you.
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- 10. The Radiation Work Permit number for the emergency drill is 5633. This number will be used by all participants and observer / controllers entering the radiation area.
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SCENARIO NO. 1985 O
TO: SENIOR WATCH SUPERVISOR LOCATION: CONTROL ROOM TIME: T = 08:30 MESSAGE: NO. 1 i
This is a Drill Con Edison Indian Point Unit No. 2 has been shutdown for a refueling outage for 10 days and the first spent fuel elements have been placed in the fuel storage building. Spent fuel is in the process of being O unloaded from the reactor vessel.
storage in the rod control cluster change fixture.
There is a spent fuel assembly in This is a Drill
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SCENARIO No. 1985 CONTROLLER FIELD REPORT A TIME: 08:40 LOCATION: FAN BUILDING - OUTSIDE DOOR TO FUEL STORAGE BLDG.
Inform the Fuel Handling Reactor Operator (FHRO) that a refueling outage is in progress and he is at the present time inside the Fuel Storage Building. Some spent fuel has been removed from the reactor core to the FSB.
Give the FHR0 message no. 2.
Request the FHR0 explain what his actions would be for the conditions indicated on the message.
If the FHR0 does not notify the control room within 5 minutes give him message no. 4.
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SCENARIO No. 1985 O
V TO: FUEL HANDLING REACTOR OPERATOR LOCATION: FUEL STORAGE BUILDING TIME: TIME = 08:55 MESSAGE: No. 2 This is a Drill You have been moving a spent fuel cask, via the overhead crane, from the south end of the building toward the north end. When the cask reached the pool area where the just recently removed fuel elements are located, the apparatus breaks and the cask falls into the pool on
-s top of the spent fuel elements.
Violent bubbling in the water occurs and the Fuel Storage Building air monitoring and ARM instruments alarm.
This is a Drill i
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I~ SCENARIO NO. 1985 i
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TO: CONTROL ROOM OPERATOR 4 -LOCATION: CENTRAL CONTROL ROOM '
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! MESSAGE: No. 3 i
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- This is a Drill 4
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I 4 Control Room category alarms initiated.
! o ARM /PRM high radiation. L I
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I This is a Drill i
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SCENARIO NO. 1985 O
TO: FUEL HANDLING REACTOR OPERATOR LOCATION: FAN BUILDING / PRIMARY AUXILIARY BUILDING TIME: T = 08:59 if FHR0 has not notified CCR I
MESSAGE: NO. 3-C-1 i
This is a Drill You should notify the Central Control Room of the accident.
3 This is a Drill I
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. - _ . . _ _ . _ . _ . . _ _ _ . _ _ _ _ . . _ _ _ _ . _ - _ . _ _ . . _ _ . _ _ _ _ _ _ , _ . . _ . . . _ _ _ _ . _ . _ _ ~ _ _ _ , , _ , _ . _ . . . _ _ _ _ , . ~ .
l SCENARIO NO. 1985 O
4 TO: CONTROL ROOM OPERATOR / SENIOR WATCH SUPERVISOR LOCATION: CENTRAL CONTROL ROOM TIME: T = 09:00 after instrumentation is monitored 4
MESSAGE: NO. 4 i i
This is a Drill 4
i R-5 2.5 R/hr R-13 Offscale high R-14 Offscale_gigh O R-27 2.0 X 10 Ci/sec 4
This is a Drill 4
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SCENARIO NO. 1985 CONTROLLER FIELD REPORT B TIME: 09:00 plus 1
LOCATION: FAN BUILDING & PRIMARY AUXILIARY BUILDING 4
You may expect the Senior Watch Supervisor to dispatch the Watch Rad Protection Tech to perform a field survey at the Fan Building, el 80' of the Primary Auxiliary Building and possibly the 98' el of the PAB.
As tF ; field survey is performed, give the mR/hr values for the survey point as obtained from Section 8, TAB D.
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SCENARIO NO. 1985 CONTROLLER FIELD REPORT C O
j TIME: 09:00 plus LOCATION: PRIMARY AUXILIARY BUILDING 98' el.
You may expect the Senior Watch Supervisor to dispatch the Watch Chemistry Tech to sample the plant vent. You may also expect the SWS to direct the Watch Rad Prot Tech to perform a field survey in the plant vent sample area before the dispatch of the Chem Tech or to accompany the Chem Tech to provide radiological protection.
It is not necessary for the Chem Tech to take a sample when he arrives at the 98' el vent sample point but you should have him explain the procedure and the time necessary to obtain the sample.
After arriving back at the radiochem laboratory, you should wait approximately 30 minutes before supplying the sample values obtained O from Section 8, TAB C.
sample.
It is not necessary for the Tech to count a l
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SCENARIO No. 1985
- CONTROLLER FIELD REPORT D TIME: 09:05 (Approx.)
LOCATION: OPERATIONS CONTROL CENTER The OCC ity person has been called by the control room communicator and infor ed that an ALERT has been declared. After the OCC duty person ha s called the control room to verify the ALERT, he will proceed ta follow the notification requirements in IP-1002. Because this is a limited participation drill certain requirements of IP-1002 must be deleted.
Give the OCC Duty Person the specific parts of message no. 5 as he requires them. Do not give the Duty Person the complete message at the start.
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4 SCENARIO No. 1985
!O TO: OPERATIONS CONTROL CENTER DUTY PERSON LOCATION: OPERATIONS CONTROL CENTER TIME: T = 09:05 after notification by CCR MESSAGE: NO. 5 This is a Drill
- Utilize the notification drill signal of 34-34 only.
- The names of the players for section 4.4.5 & 4.4.6 of IP-1002 are
. Controller may obtain them from section 5 of the scenario.
- The notification requirements of section 4.4.3 of IP-1002 are deleted.
This is a Drill 1
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SCENARIO No. 1985 O
To: SENIOR WATCH SUPERVISOR 1
LOCATION: CENTRAL CONTROL ROOM TIME: T = 09:10 if SWS has not declared an ALERT MESSAGE: 3-C-2 This is a Drill t
- You should declare an ALERT at this time because Initiating Condition No. 6 has been satisfied and initiate appropriate actions and notifications.
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This is a Drill O 4 IV-13
SCENARIO No. 1985 CONTROLLER FIELD REPORT E TIME: 09:10 Approximately i '
LOCATION: OPERATIONAL SUPPORT CENTER I
After the Chief Accountability Officer arrives at the Operational Support Center, the CAO will proceed to activate the minimum personnel requirements as per IP-1023.
You should notify the CAO that the Material Control Storekeeper need not be activated for this drill.
If the CAO realizes that he does not meet the METCON crew requirements as delineated 'in IP-1023, notify the CAO that it should be simulated.
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' SCENARIO No. 1985 t
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i TO: SWS/POM 1
LOCATION: CENTRAL CONTROL ROOM J
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I MESSAGE: NO. 6 i
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This is a Drill CCR Annunciation: " Spent Fuel Pit Temperature Alarm".
J This is a Drill i
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1 SCENARIO NO. 1985 CONTROLLER FIELD REPORT F TIME: 09:40 Approximately LOCATION: CORPORATE RESPONSE CENTER After the CRC personnel have set up the CRC, they will start the notification of appropriate directors, managers and chief engineers.
Advise CRC personnel that there is no need for the directors, managers and chief engineers to come to the CRC, only to be contacted by telephone.
If the CRC personnel did not initiate contacting the appropriate directors, managers and chief engineers on their own, and you were required to give them the field report in a timely manner in order to O
\ keep the scenario on time, note in your critique notes.
Advise CRC personnel to state the following when contacting the appropriate directors, managers and chief engineers, "This is a notification drill being performed in conjunction with an Indian Point Site Drill. Thank you."
NOTE: If CRC personnel arrive after the declaration of a Site Area Emergency, then proceed to Controller Field Report K.
i I
IV-16
SCENARIO No. 1985 f
1 4
1 4
I l'
i l
} TO: NP0/POM I LOCATION: CENTRAL CONTROL ROOM i
i TIME: T= 09:50 i
MESSAGE: NO. 7 ;
i i
I i l
- t I' This is a Drill i
The spent fuel cooling pump power contactor overload is blown.
This is a Drill IV-17
i SCENARIO No. 1985
- O TO: CONTROL ROOM OPERATOR LOCATION: CENTRAL CONTROL ROOM .
TIME: T= 10:00
-MESSAGE: NO. 8 a This is a Drtil 1
() R - 27 discharge rate has jumped to 20 Ci/sec. l This is a Drill s
i i
9
)
i t
I i
I i
i IV-18 i
SCENARIO NO. 1985
_. CONTROLLER FIELD REPORT G
%J TIME: 10:00 plus LOCATION: TSC/OSC & FAN BLDG /PAB You may expect the OSC Rad Protection Coordinator to dispatch a Rad Protection Tech (1,or 2) and a Chem- Tech to survey the Fan Bldg., PAB 80' el and PAB 98' el and to obtain a plant vent sample.
It is not necessary for eke Chem Tech to take a sample when he arrives at the 98' el vent sample point but you should have him explain the procedure and the time necessary to obtain the sample. If for some reason this is the same Tech who sampled the plant vent before, he
("N need not go through the discription again.
As the Rad Prot Tech performs the field surveys, give him the mR/hr values for the survey points as obtained from Section 8. TAB D.
After arriving back at the radiochem laboratory, you should wait approximately 30 minutes before supplying the sample values obtained from Section 8 TAB C. It is not necessary for the Tech to count a sample.
O IV-19
jL SCENARIO No. 1985
{.
- CONTROLLER FIELD REPORT H i i t J
1-f i
1 l TIME: AS INDICATED BELOW j i
- LOCATION
- CENTRAL CONTROL ROOM i
4 Give SWS/POM the appropriate reading below as he asks for it.
l
' l REACTOR CAVITY l
1 I
! TIME LEVEL 10:00 4 19' j 10:15 4 19' i
, 10:30 4 19' I
t
, 10:45 19'8" 11:00 20'8" i 11:15 20'9" j l
i l
i ,
l l r i
I i l
i t
\
l IV-20 l e-,.
- .w--me,,,-_ _-
SCENARIO NO. 1985 CONTROLLER FIELD REPORT I O
TIME: AS INDICATED BELOW LOCATION: CENTRAL CONTROL ROOM Give SWS/POM the appropriate reading below as he asks for it.
(shut down maintenance instrument)
CORRESPONDING TO FUEL CAVITY LEVEL TIME LEVEL 10:00 93'9" 10:15 93'9" 10:30 93'7" 10:45 93' 11:00 92'8" 11:15 92'7" NOTE: Refueling water sotrage tank level is indicating 5'.
O IV-21
SCENARIO No. 1985 CONTROLLER FIELD REPORT J O
TIME: AS INDICATED BELOW LOCATION: CENTRAL CONTROL ROOM Give SWS/POM the appropriate reading below as he asks for it.
WIDE RANGE PRESSURIZER LEVEL (corresponding to fuel cavity level)
TIME LEVEL 10:00 33%
10:15 33%
10:30 33%
10:45 32.5%
11:00 30%
11:15 29%
NOTE: Refueling water sotrage tank level is indicating 5'.
O IV-22
SCENARIO No. 1985 lO
}
+ TO: EMERGENCY DIRECTOR 4
l LOCATION: EMERGENCY OPERATIONS FACILITY
! TIME: T= 10:15 if ED has not declared a SAE i MESSAGE: NO. 8-C i.
f This is a Drill 1
I i
I f You should acciare a SITE AREA EMERGENCY at this time because
- Initiating Condition No. 8 has bsen satisfied and initiate appropriate 1 actions and notifications.
1 i
l This is a Drill i
i 1-O i
i IV-23
SCENARIO No. 1985 CONTROLLER FIELD REPORT K TIME: 10:25 Approximately LOCATION: CORPORATE RESPONSE CENTER After the declaration of a Site Atea Emergency, you should expect that CRC personnel will start the notification of appropriate directors, managers and chief engineers.
If the CRC personnel did not initiate contacting the appropriate directors, managers and chief engineers on their own, and you were required to give them this field report in a timely manner in order to keep the scenario on time, note in your critique notes.
() Advise CRC personnel to state the following when contacing the approp-riste directors, managers and chief engineers, "This is a notification drill beina performed in con: unction with an Indian Point Site Drill.
You are not required to parttcipate. This is a drill. Thank you."
O IV-24
. - - - . . . - _ - _ _ . . . . _ _ - . - . .._ - _ - _. - ... . ... ~ ~ .. . .__.- .. .. ..
SCENARIO No. 1985 l
4 O
4
. TO: POM LOCATION: CENTRAL CONTR01 ROOM ,
l TIME: T= 10:45 MESSAGES. NO. 9 i
i This is a Drill l o Panel SB1 Alarm Annunciation
() "Hi-Water Reactor Cavity"
(> 19'7h")
Followed by:
"Hi-H1 Water Reactor Cavity"
() 20'5")
o VC Susp Pumps Start.
This is a Drill O
IV-25
SCENARIO No. 1985 CONTROLLER FIELD REPORT L TIME: 10:45 LOCATION: CON'f?CL ROOM / FIELD LOCATION
- a. Upon presentation (10:45) of Message No. 10 to the SWS/POM, he should check the pump power log to see if V.C. ventilation was completed. If he does, skip to c. below. (He will see that it was not completed).
- b. If he does not check the pump power log, give him Message No.
10-C-1 (approx. 11:15) and mark it in your critique.
- c. If an NPO or Repair Team is sent to check out why the PRM R-12 O did not activate the V.C. ventilation isolation, give Massage No.
10-C-2 to the NP0/ Repair Team when they arrive at the field location. If the POM simulates that or if there is no controller to go with the team, give the POM Message No. 10-C-2.
O IV-26
SCENARIO No. 1985 O
TO: POM LOCATION: CENTRAL CONTROL ROOM TIME: T= 10:50 MESSAGES. NO. 10 This is a Drill' Control Room Annunciatorst o Process Radiation Monitor (PRM) R-12 High Alarm.
o R-12 recorder shows increasing activity.
This is a Drill _
O IV-27
SCENARIO NO. 1985 O
TO: REPAIR TEAM /NPO LOCATION: FIELD LOCATION / CONTROL ROOM TIME: T= 11:00 MESSAGE: NO. 11 This is a Drill O The Spent Fuel Cooling Pump thermal overload was found defective and was replaced. The Pump is now operating.
This'is a Drill O
IV-28
SCENARIO No. 1985 O
TO: SWS/POM LOCATIOR: CENTRAL CONTROL ROOM TIME: T= 11:15 MESSAGE: NO. 10-C-1 This is a Drill O
PRM R-12 did not activate the V.C. Ventilation Isolation.
This is a Drill O
IV-29
SCENARIO NO. 1985 O
TO: NP0/SWS LOCATION: CENTRAL CONTROL ROOM TIME: T= 11:20 (approx.)
MESSAGE: No. 12 This is a Drill o Water has been observed ranning down the inside area of the reactor biological shield wall.
o The N 2 bottles supplying the press ray. seal are all empty and there are no spares at 95 ft. level of the containment.
This is a Drill O
IV-30
SCENARIO No. 1985 i O ;
I t
TO: CONTROL ROOM OPERATOR i
LOCATION: CENTRAL CONTROL ROOM !
TIME: T= 11:25 l MESSAGE: NO. 13 - d,,,
i This is a Drill !
l I
I The release has terminated.
i t
This is a Drill
{
f i
l O
IV-31
- l 1
SCENARIO No. 1985 O
TO: NP0/SWS/POM LOCATION: CENTRAL CONTROL ROOM TIME: T= 11:45 MESSAGE: NO. 10-C-2 1
1 i
- This is a Drill i
i The Radiogas Monitor contacts for activation of the ventilation j isolation valve are defective.
i l
1 l This in a Drill l
i l' .
O
! IV-32 i
SCENARIO No. 1985 O
TO: EMERGENCY DIRECTOR LOCATION: EMERGENCY OPERATIONS FACILITY TIME: T= 12:15 MESSACE: NO. 14 This is a Drill The drill is terminated. There is no need to activate the recovery O center or to perform post accident offsite environmental surveys.
This is a Drill 9
O IV-33
CONSOLIDATED EDISON COMPANY OF NEW YORK INDIAN POINT UNIT NO. 2 DRILL SCENARIO No. 1985 V. OBSERVER / CONTROLLER INSTRUCTIONS A. Exercise Control Organisation Exercise Observer / Controllers shall be appointed in order to control, observe, and later critique exercise activities.
The title " Observer / Controller" is used to designate either a single, or dual function during the exercise. Observers will be assigned to watch exercise activities as they occur.
They will provide no input or active involvement or direction to any participants during the exercise. Their only function is to quietly observe in order to later help develop a representative critique of exercise participants' actions.
Controllers will be assigned to various " key" locations in order to actively control the progress of the exercise.
They will input Control and Contingency Messages at the appropriate times and provide any necessary interpretation to exercise participants. Controllers will be the only ones who can answer participants' questions. They will also function as Observers to help evaluate performance: thus Observer / Controllers. The designation below of Observer /
Controller will mean either Observer, Controller, or Observer and Controller. The " Chief Controller" is the lead exercise manager (or controller) and will be located in O the Control Room. prior to the exercise, Observer / Controller instructions will be provided in order to familiarise all Observer / Controllers with the entire scope of the exercise, and answer any specific questions. Attachment A provides a listing of all exercise observers and Controllers, as well as their locations. Attachment B provides a listing of all exercise players.
B. Exercise Control Instructions
- 1. All Controllers shall be pre-positioned at least one half hour prior to the first message time.
- 2. prior to exercise commencement, all Controller communica-tions will be tested to ensure satisfactory exercise control.
- 3. All controllers will comply with instructions from the Chief Controller. .
- 4. Each Controller will have copies of the messages con-trolling the progress of the exercise scenario. Messages shall be delivered by the Controller at the appropriate times, to the designated individual (s). In the case of energency declarations, if the response of exercise O parwicipants necessitates the use of a contingency message, the situation should be discussed with the Chief controller prior to issuance of the message.
V-1
SCENARIO No. 1985 Controllers will use the following techniques to control the exercise in accordance with the scenario.
(v~') a. Control Messages - Control messages provide information to the participants and/or cause the participants to take action needed to keep the exercise moving smoothly. The Controller will give a hard copy of the control message to the designated participant at the specified tina.
Simultaneously. the Controller will provide the essential information verbally. The Controller will follow through and clarify the message by answering questions to ensure that the participants do not read extraneous meaning into the message.
The Controller will not tell participants what action they are expected to take,
- b. Contingency Mescages - Contingency messages will be used only if participants fail to take the major actions expected from the control messages by the time designated. Controllers will give the contingency message to the designated participant and explain in as much detail as necessary what actions the participant is expected te perform.
Contingency sensages are used to keep the exereise on schedule, though their use may indicate g-'s inadequate plan implementation.
b c. Control Information - Controllers for Health Physics and Environs Field Teams will provide instrument readings and other information to team members verbally when they request it by performing the measurements, etc. Controllers will refer to their current location and the applicable time period to obtain requested data from the approp-riate tables in Section 8.
- d. Control cuidance - Controllers will provide verbal guidance to participants to keep the exercise oriented to the pre-arranged scope and scenario.
Controllers will direct participants to simulate certain actions that are outside the immediate scope of the exercise at the time participants announce their intention to perform the action.
Observer / Controllers will note that the participants slaulated the action. Participants must request information that is not autcastically provided from participants at other locations. Controllers will steer participants away from types of informa-tion that are outside the exercise scope to avoid bogging the exercise down in a quest for informa-tion that Controllers do not possess and have no intention of providing,
(J) u_
V-2
SCENARIO NO. 1985 NOTE: All messages controlling the progress of the
() 5.
exercise scenario are noted with a number.
All Controllers shall synchronize their watches to ensure that messages are delivered at the proper time.
Times on sessages are real time.
- 6. Each Controller will have copies of time-related plant and radiological parameters (data) corresponding to the development of the exercise scenario. This information should be issued, only upon request or when required, to the appropriate exercise participants by either the Control Room Drill Controller, or Controllers accompany-
. ing the radiological monitoring or inplant health physics personnel.
- 7. Controllers shall not provide information to the exercise participants regarding scenario development or resolution of problem areas encountered. The exercise participants are expected to obtain information through their own organizations and exercise their own judgements in determining response actions and resolving problems.
- 8. Any inquiries originating from the general public, as a result of exercise activities, will be referred to a Controller. An explanation will consist only of stating that a practica drill is underway at the plant O and all events are simuisted (i.e., not real).
- 9. Some exercise participants may insist that certain parts of the scenario are unrealistic. The Drill Controller has the sole authority to clarify any questions regarding scenario content.
l 10. Each Observer / Controller should use the Los Sheet l contained at the end of this section to take detailed notes regarding the progress of the exercise and the responses of the exercise participants at their respec-tive assigned locations. Each Observer / Controller should carefully note the arrival and departure times j
for exercise participante, the times at which major activities or milestones occur, and problem areas encountered. Observer /Contro11ers' comments should
- consider the evaluation elements set forth in Section
! C " Exercise Evaluation Criteria." All notes taken
- should be retained for the purposes of reconstructing the exercise chronology and preparing a written aritique j of the exercise.
I 1 11. The exercise is tentatively scheduled to end as indicated in~the last message. Instructions for reassembly of i
j the Observer / Controller team will be given at that time.
V-3 I
i
[
SCENARIO No. 1985
,_s NOTE: In the event of a real emergency during the
(
exercise, the exercise may be immediately terminated
\ by the Drill Controller, if deemed appropriate.
C. Exercise Evaluation Criteria -
Observer / Controllers shall familiarize themselves with the duties and action requirements of the personnel they are monitoring.
Certain generic evaluation points are to be considered for all locations / participants, as appropriate. These includes o Notification, alerting and mobilization of emergency response personnel.
o Adequate communications capabilities among onsite and offsite emergency response facilities and personnel.
o Timely activation of energency facilities and teams.
o Clear and appropriate direction and control of all exercise activities.
o Emergency procedures are followed. In some cases they should be referred to during accomplishment of specific duties; e.g., dose assessment.
o Overall adequacy of the scenario to test the various emergency preparedness plans and procedures.
o Benefit of the exercise to its participants.
The following guidelines provide basic evaluation criteria which must be addressed by the Observer / Controller in order to effectively critique the exercise. Evaluation criteria are grouped according to exercise activity location and individual (or team) functions.
NOTE: Specific exercise performance must be compared directly with company energency procedures.
Therefore, individuals assigned as observer / Con-tro11ers shall be cognizant of the respective procedures and all actions that shall be carried out by the participants they observe.
After completion of the drill, and before the and of the next normal working day, the Chief Controller shall hold a verbal critique, where all Observer / Controllers shall discuss their observations and any noted shortcoming, and present their reconsendations to taprove performance and energency preparedness. Critique comments will be requested
() from all participants at the conclusion of the exercise.
V-4
SCENARIO No. 1985
- 1. Control Room Prior to initiating the exercise, the Drill Controller will confer with the Senior Watch Supervisor (gWS) in order to identify any ongoing operational or maintensuce activities that should not be interrupted. Those personnel engaged in these activities will be notified that they are to disregard any exercise-related announce-ments or activities. Emphasis should be made, however, that in the event of a real emergency the exercise may be terminated and station announcements will specify "THIS IS NOT A DRILL" and that instructions should be followed by all personnel.
The Observer / Controller shall observe the action of all personnel assigned to the Control Room and all personnel who report to the Control Room for assignment. In addition, he will pay special attention to the followings o Use of map and overlays.
o Placement of calls to NRC, NYS and Counties.
o Notification, alerting and mob 111:stion of emergency response personnel, including calling in off-duty p,ersonnel.
() o Operations handling of accident conditions if appropriate.
o Instructions given to Search and Rescue teams, Repair and Corrective Action teams, and Rad Protection and Chem. Techs by the Senior Watch Supervisor (SWS).
o Does the SWS handle the emergency by directing his people or trying to do the work himself.
o Is the time frame of actions by the SW8 reasonable enough.
o Department of all personnel in the Control Room.
The following procedures are to be used in the evaluation:
IP-1001 Mob 111:stion of onsite Emergency Organisation IP-1002 Energency Notification and Consunication IP-1003 Planned Discharge of Containment Atmosphere During Accident Conditions IP-1007 Determination of the Magnitude of Release and Exposure Rate IP-1010 Search and Rescue Teams IP-1011 Repair and Corrective Action
\ IP-1013 Recommendation of Protective Actions for Offsite Population V-5
SCENARIO No. 1985 IP-1016 Obtaining Meteorological Data
/ 'N IP-1020 Airborne Iodine - 131 Determination
\-- IP-1021 Manual Update and Readout of Proteus Plant Parameter Data IP-1026 Operation of the NAWAS Communication System IP-1037 Obtaining Offsite Reuter-Stokes Monitor Data IP-1038 Emergency Personnel Exposure IP-1043 Operation of the NYS Radiological Emergency Consunications System (RECS)
IP-1047 Obtaining Offsite Exposure Rates from MIDAS Via Control Room ASCII Terminal.
Plus Immediate Action Procedures for SWS, CRO, WATCH HP, POM
- 2. Technical Support Center The Observer / Controller should observe the followings o Timely activation o A mintaus of four qualified persons manning the center.
o Field survey performed.
o Noble gas monitor set up.
l o "Frisker" set up.
l o Work performed in professional manner.
o Phor.es are plugged in and direct lines to control Room, NRC, and EOF are checked out.
The following procedures are to be used in the evaluation:
IP-1020 Airborne Iodine - 131 Determination IP-1021 Manual Update and Readout of Proteus Plant Parameter Data IP-1035 Technical support Center IP-1041 Use of the Triton to Monitor Noblegas l
l 3. Operations Control Center (OCC)
The Observer / Controller should observe che followings o Timely initiation of a call to the paging service company.
o Adequate communications, including how problems with the radio and telephones are handled.
l Message handling and communication logging proced-l\ ures.
I V-6
SCENARIO NO. 1985 o Verification call to Indian Point Unit No. 2
() o Control Room for authenticity of emergency.
Preparation of records of personnel who have called in.
The following procedure is to be used it the evaluation:
IP-1002 Emergency Notification and Communication
- 4. Assembly Area The Observer / Controller should observe the followingt o Do they seek out their section or department accountability officer, generally stay together as a group and remain orderly?
o Were Assembly Area radiation surveys performed and results recorded? This will depend on whether there is an SAE or GE classification and releases to the environment.
o Is there documentation of accountability and is it understandable to others.
("'s The following procedure is to be used in the evaluation:
V IP-1027 Site Personnel Accountability and Evacuation
- 5. Operational Support center The Observer / Controller should observe the followings o Is there documentation of accountability and is it understandable to others?
o Do the personnel awaiting assignment remain orderly?
o Were radiation surveys performed and recorded?
o Receipt of request to form teams.
o Handling the assignment of team members.
The following procedures are to be used in the evaluation.
IP-1020 Airborne lodine - 131 Determination IP-1023 Operational Support Center
() IP-1027 IP-1041 Site Personnel Accountability and Evacuation Use of the Triton to Monitor Noblegas.
V-7
f SCENARIO NO. 1985
- 6. Emergency Operations Facility This is the command post for the interface with offsite authorities and it should seen so to the Observer / Control-1er. Look for the following thingst o The Energency Director in in command of the EOF.
o The ORAD is in control of the radiological assess-ment activities, and reports results and recommenda-tions to the Emergency Director in a timely and efficient manner.
o Any extra personnel. spectators and those awaiting orders are quietly standing out of the way.
o The H.P. or support personnel are performing duties in a timely and efficient manner and reporting results to either the Emergency Director or ORAD.
o Instrumentation deployed in the EOF is placed in a non-interfering position.
o Adequate communications, including how problems with the radio and telephone are handled. Message handling and communications logging procedures.
( o Radioactive release rates, whole body and thyroid exposures to the offsite population are calculated quickly after the receipt of data from the Control Room or the offsite monitoring teas (s).
o Prompt notification to the NRC, NYS and Counties of exposure data and changes to site seteorological conditions.
o The Emergency Director assigns, where possible, his routine calls to someone else thereby leaving himself free to command the action.
o Data forms filled out and turned in to the ORAD /
Health Physicist.
o Timely deployment of teams.
o A central point for receipt of radiological monitoring data is desisusted and adequate' communications with field teams demonstrated.
o Demonstrate ability to assess plant conditions, reclassify the incident (if appropriate), develop timely protective action recommendations, or O' communicate with offsite authorities in an accurate and timely manner.
V-8
SCENARIO No. 1985 o Demonstrate ability to control radiological (7- ) monitoring field teams for " plume-tracking." and
\# ingestion pathway monitoring.
o Demonstrate ability to develop recommendations for recovery and re-entry activities.
o Demonstrate ability to provide radiation exposure control for emergency workers.
The following procedures are to be used in the evaluation:
IP-1002 Emergency Notification and Consunication IP-1003 Planned Discharge of Containment Atmosphere During Accident Conditions IP-1004 Post Accident Offsite Environmental Surveys.
Sampling and Counting IP-1005 Use of SAM-2/RD-22 to Determine Thyroid Burdens IP-1006 Site Perimeter Surveys IP-1007 Determination of the Magnitude of Release and Exposure Rate IP-1013 Recommendation of Protective Actions for Offsite Population IP-1016 Obtaining Meteorological Data IP-1020 Airborne Iodine - 131 Determination g
IP-1021 Manual Update and Readout of Proteus Plant Parameter Data IP-1029 Emergency Closecut/ Class Reduction Written Summary to Authorities IP-1036 Estimation of Population Dose Within the 10 Mile Emergency Planning Zone IP-1037 Obtaining Offsite Reuter-Stokes Monitor Data IP-1038 Energency Personnel Exposure IP-1041 Use of Triton to Monitor Noblegas IP-1043 Operation of the NYS Radiological Energency Consunications System (RECS)
IP-1048 Deescalation of Emergency and Initiation of Recovery Plus Immediate Action Procedures for ED, TA, ORAD, DAHP, STHP, MIDAS. EOF COMM, EOF CLERK
- 7. Security Buildina(s) or Security Control Points It is to be noted that all normal practices, such as sign-out and use of the hand and foot monitor and the portal monitor, are to be accomplished unless the Rad Prot Technician gives other directions because of radiological conditions. The Observer / Controller will pay special attention to the above along with the following:
O' o Timely activation or establishment of control points.
V-9
SCENARIO NO. 1985 ,
l o No one is wearing Anti-C clothing when leaving the site.
o All alarms from monitoring equipment or computer card terminals are acknowledged.
The following procedures are to be used in the evaluction: ,
IP-1017 Issuance and Use of Radiological Equipment Stored in the Command Guard House
- 8. Onsite Monitoring Teams l
Onsite monitoring teams will normally be assigned field survey work onsite, outside of the protected area fence, and at the Service Center building complex.
Check on the following items:
o Received KI done (simulated) from ORAD if required.
NOTE: Do not actually take the KI Dose.
o They have a dosimeter and film badge.
o They have i charcoal filter s respirator when Isaving the building complex to perform a survey.
('s
~.
V -o Radio check performed before leaving the EOF parking lot. "
~
"4 ,
o Field feadings taken slong the route to,the
- designated area. Siguidted field data will only
, be available-at designEterhmonitoring p31nts.
i . , ;
,' o- Work performad in a professional manner.
o
'u =
} ,
Data': forms filled out asiappropriate'and turned in to'the ORAD /Sealth P.hysicist..
y -
s .
The following, procedures are to be used in the evaluation: ,
.- w IP-1006 Site PerGeter Surveys IP-1008 Personnel Radiolo'gic.al Check and . Decontamination
~
IP-1009 Kadi.ological Check and Decoticawinatien of Vehicles .3, _
w IP-1014 Radi61ogical Chhick.of Equipment bisfore it '
Leaves the Site
~s
.. IP-1028 Oasiti (otit of plant) -
s Field Surveys c, . .. .
T
~
- 9. Of f sit'e Monitorir.g Teams. Y ~
~ -
~
~
,y, .
- The' Observer / Controller should observe the following:
m t
l O o.
s s
' Received II1 dose (simulated) from ORAD if required.
^
y.10 ' ~
4 . ,
% j _
~
o ., l, % .;' s ,
e y ' -
p: u
SCENARIO NO. 1985 NOTE! Do not actually take the KI dose.
o Operational check performed on survey instruments, sample counter and sample pump before leaving the EOF parking lot.
o Equipment check-off performed.
o Assignment of badges and dosimeters before leaving ;
the EOF parking lot.
o Charcoal cartridge raspirator made available before leaving EOF parking lot.
o Survey _ instrument made ready to take field readings.
o Radio check-out by communication to EOF before leaving.
i o Beta and gamma field surveys performed on the way to sample point.
o Sampling and field surveys performed at sample location.
o Instrument calibration performed and samples counted.
o Air snmpling started.
The following procedures are to be used in the evaluation:
IP-1004 Post Accident Offsite Environmental Surveys, Sampling and Counting IP-1006 Site Perimeter Surveys IP-1008 Personnel Radiological Check and Decontamination IP-1009 Radiological Check and Decontamination of
! Vehicles IP-1015 Mobilization and Operational Procedure for Offsite Monitoring Teams - Immediate Response.
IP-1020 Airborne Iodine - 131 Determination IP-1034 Mobilizatien and Operational Procedure for off-site Monitoring Teams - Supplemental Response IP-1039 Offsite Contamination Checks
- 10. Radiation Protection Technician (RPT)
The Observer / Controller should observe the following:
o RPT follows his instructions indicated in immediate action procedures.
o RPT follows instructions from SWS or OSC coordinator.
O o RPT performs survey as indicated using appropriate instrumentation.
V-11
,,p-, ,_-------,.-m,, - - - - - . , , -,,,--..,,---,-.-,..,,,---,,,_w.- --
SCENARIO NO. 1985 o RPT performs duties during medical emergency as es indicated in IP-1012.
'/ The following procedures are to be used in the evaluation:
, IP-1010 Search and Rescue Teams IP-1011 Repair and Corrective Action IP-1012 Onsite Medical Emergency IP-1020 Airborne Iodine - 131 Determination IP-1042 In-Plant Radiological Surveys and Sampling Plus Immediate Action Procedure WATCH H.P.
- 11. Chemistry Technician 4
The Observer / Controller should observe the following:
o Chemistry Technician follows Chemistry Procedures as appropriate.
o Samples are actually collected and counted, as indicated by the scenario.
o Results of sample counting (simulated and real) are trat.smitted to the SWS or OSC Coordinator as appropriate.
The following procedures are to be used in the evaluation:
IPC-E-001 Post Accident Sampling and Analysis of Reactor Coolant IPC-E-002 Post Accident Sampling and Analysis of the Vapor Containment Atmosphere IPC-E-003 Post Accident Sampling and Analysis of Plant Discharges for Noblegas, Radio-iodines and Particulates.
- 12. Maintenance Repair Team The Observer / Controller should observe the following:
o Response and repair time.
o Proper equipment brought to perform the work.
o Maintenance Repair Team members follow Rad Prot Technician's instructions.
o Radiological precautions taken.
The following procedures are to be used in the evaluation.
IP-1010 Search and Rescue Teams O IP-1011 IP-1023 Repair and Corrective Action Operational Support Center V-12
SCENARIO NO. 1985 CONSOLIDATED EDISON COMPANY OF NEW YORK INDIAN POINT UNIT NO. 2 EMERGENCY PREPAREDNESS EXERCISE
)
OBSERVER / CONTROLLER LOG SHEET Name: Date:
Location:
TIME OBSERVATION / COMMENT O
,I I
i O .
l V-13
ATTACHMENT A Page 1 of 2 O/
ss EMERGENCY DRILL ASSIGNMENT SHEET CONTROLLERS-0BSERVERS June 1985 Drill Date LOCATION POSITION NAME CCR Chief Controller Miele/ Cotter Controller A. Nespoli i
i Observer - SWS Dose Assm't S. Sadlon i
Observer - Communicators (2) B. Raskovic 4
Controller - Watch Rad Prot Tech G. Rumold Controller - Watch Chem Tech J. Higgins Controller - Medical --------
Controller - Fire Brigade --------
Controller - GPO Designated by NPG TSC Controller A. Wynne Observer - Data Processing N. Altomare Observer - Communicator J. Ellwanger l
Observer - TSC Personnel @ CR Impell - J. Gilbert OSC Controller - 72' elevation W. Ryan Observer - 72' elevation V. Nutter I
observer - 53' Conference Rm Impe}l - R. Weber _
Controller - OSC Team E. Everett Controller - OSC Team R. Platt Controller - OSC Team J. White Controller - OSC Team W. Grassie Controller - OSC Team R. Eifler EOF Controller G.H. Liebler i Observer - Communicators (2) J. Spivak I Observer - Dose Assm't A. Ferraro
( ,
Observer - Emergency Director Liebler & Ferraro V-14
ATTACHMENT A Page 2 of 2 EMERGENCY DRILL ASSIGNMENT SHEET CONTROLLERS-0BSERVERS June 1985 Drill Date f LOCATION POSITION NAME EOF Controller - Offsite Team M. Byster Controller - Offsite Team E. Goetchius Controller - Onsite Team M. DiGenova ASSEMBLY Observer - Area A-B --------
Observer - Simulator --------
Observer - Constr. Office --------
Observer - M.O. Bldg. --------
Observer - 72' TS/ Admin --------
- Observer - Unit No 1 Admin Bldg --------
Observer - Service Center --------
SECURITY Command Guard House M. Sanchez River Front Gate --------
Main Gate --------
Service Center --------
ENC Controller Designated by Publ. Info.
Observer --------
Observer --------
Observer --------
OCC Observer M. Ross CRC Observer M. Smith ASTORIA-ECC Observer ----
RC Observer --------
AEOF Observer --- -
V-15
ATTACHMENT B Page 1 of 4 I 4
EMERGENCY DRILL PLAYER ASSIGNMENT SHEET JUNE 1985 DRILL Date l
JOB FUNCTION NAME l
Emergency Director (ED) J. Basile Technical Advisor to ED J. Makepeace $/
Offsite Radiological Assm't Director T. Teague d-i Dose Assessment H.P. D. Smith Survey Team H.P. D. Miller
. !!IDAS Operator R. Hewitt i
Communicators M. Shannon J. Bahr S. Mathieson Clerical P. Allan E. O'Shaughnessy l () Onsite Team J. Zendek M. Ma gee i P. Madigan R. Sciacklinscky
?
Offsite Team V. Lander L. Mettey Astoria ECC Coordinator - --
Astoria Backup Team --------
i EOF Information Liaison B. Lindgren i
l Tech Advisor to EOF Information Liaison J. Goodale D. Gaynor l
I l Meteorologist --
l TSC Manager J. Quirk Schedule & Planning Coordinator N. Prezioso System Analysis Coordinator D. Rush j Core Physics Engineer J. Trapp I
l I & C Support Coordinator H. Somers lO V-16
J ATTACHMENT B t
i Page 2 of 4
- 6 EMERGENCY DRILL PLAYER ASSIGNMENT SHEET JUNE 1985 DRILL l
Date
- JOB FUNCTION ! NAME 1
! Test & Performance Engineer J. Barlok Consnunicator at TSC SRO or R0 Designated by NPG*
TSC Consnunicator at CCR SRO or RO Designated by NPG*
Data Facility Supervisor P. Santini Data Courier E. Schlechting Data Processor at CCR SRO or R0 Designated by NPG*
Data Processor at TSC L. Volpe Document Controller R. LoBue 4 Core Physics Coordinator --------
l Licensing Support Coordinator --------
Procedure Support Coordinator N. Lizzo Plant Operations Manager J. Curry l Senior Watch Supervisor SWS Designated by NPG*
1 Shift Technical Advisor V. Mullin Senior Reactor Operator SRO Designated by NPG*
Reactor Operator RO Designated by NPG*
Operations Communicator at CCR SRO or RO Designated by NPG*
Support Facility Supervisor SFS Designated by NPG*
i Nuclear Plant Operators NP0s Designated by NPG*
Watch Chemistry Technician As Scheduled Watch Radiation Protection Technician As Scheduled Security J. Boylan
- Watch schedule will influence who is designated.
1 V-17
I I
Attachmint B l l
Page 3 of 4 EMERGENCY DRILL PLAYER ASSIGNMENT SHEET JUNE 1985 DRILL Date JOB FUNCTION NAME Radiation Protection Coordinator - OSC J. Cullen Maintenance Coordinator - OSC J. Sullivan I & C Coordinator - OSC J. Odendahl Q.A. Supervisor - OSC R. Landwaard Project Management Specialist A. Longano Material Control Storekeeper --------
Chief Accountability Officer C. Irwin Accountability Staff W. Breckel Communicator at OSC J. Sullivan T. McKenna J. Buljeta R. Bunch J. Nigro Os OSC Individual Team Member - Maintenance W. Dodd D. Downing F. Jerrich D. Baumgarte J. Ifkovitz R. Karasinski OSC Individual Team Member - I & C E. Baisel G. Durkee J. Glickman P. Keyes F. Visosky M. Williams J. Porrazo OSC Individual Team Member - Rad Prot T. Kunkel A. Jennings D. Andersson 1
OSC Individual Team Member - Operations Supv and 3 NP0s Designated by NPG*
i 1
OSC Individual Team Member - Chemistry J. Kohnken J. Connolly D. Gabriel l
OSC Individual Team Member - QA C. Hacker l
Facility Rad Prot Tech - TSC, OSC, CR Obtained from OSC members Medical Representative i
Administrative and Logistics Manager C. Biersack j
Engineer & Construction Support Manager M. Silberstein S OCC Watch Person As scheduled 1
j Emergency News Center Director Designated by L. Kleinman Emergency News Center Office Manager
- Watch schedule will influence who is designated.
(
V-18 i..
a Attachment B Page 4 cf 4 O EMERGENCY DRILL PLAYER ASSIGNMENT SHEET i JUNE 1985 DRILL Date JOB FUNCTION NAME Corporate Spokesperson Designated by L. Kleinman Information Coordinator Information Gatherer Writer f Government Liaison Media Liaison Technical Expert
! Health Physics Expert i
Documenter Status Board Person l
Rumor Control Staff Inquiry Response Staff Au'io/ d Visual Coordinator Registration Coordinator l Telecopier Operator l Photocopier Operator l Typist !
l Messenger i f l
l l Recovery Manager --------
l l V-19 l
O CONTROLLER PHONE LIST CCR '447-8021 Next-to-Map-Table-739-1126 Next to-Map-Table-526-5379 CR Conununicator Position TSC 737-2952 TSC Mgr's Desk 526-5390 TSC Mgr's Desk OSC 526-5555,6,7 OSC Coordinator's Desk @ TSC 526-5558,70,73 OSC 72' Elev. CAO area 526-5695,96 OSC 72' Elev. HP area EOF 526-5263 All Consoles 737-7235 Upper Level O
i I
O V-20 ~
1 i
O O O PLANT STATUS LOG SCENARIO No. 1985 PARAMETER TIME 08:30 09:00 09:30 10:00 10:30 10:50 11:00 Reactor Shutdown (Y/N) Y Y Y Y Y Y Y NIS Power Range (%) 0 0 0 0 0 0 0 NIS Interim. Range -10 -10 -10 -10 -10 -10 -10 1
- 35 (Amps) 10 10 10 10 10 10 10 NIS Interim. Range -10 -0 -0 -10 -0 10-
- 36 (Amps) 10 10 10 10 10 10 NIS Source Range
- #31 (CPM) 200 200 200 200 200 200 200 NIS Source Range 150 150 150
- 32 (CPM) 150 150 150 150 RCS Incor T/C l (Center) (*F) 120 120 120 120 120 120 120 RCS Incore T/C (Highest) (*F) 140 140 140 140 140 140 140 RCS Pressure (PSIG) 0 0 0 0 0 0 0 RCS Avg. Temp. (*F) 120 120 120 120 120 120 120 RCS Cold Leg Temp. (*F) 120 120 ,
120 120 120 120 120 SAT Meter Margin (*F) 130 130 130 130 130 130 130
- RCP in Service (Y/N) N N N N N N N Pressurizer Level (%) 40 40 40 40 40 40 40
, Reactor Vessel Level (%) 100 100 100 100 100 100 100 4
S/G Levels #21 (%) 100 100 100 100 100 100 100 1 #22 100 100 100 100 100 100 100
- 23 100 100 100 100 100 100 100 i #24' 100 100 100 100 100 100 100 0 0 0 0 0 0 i S/G Press #21 (PSIG) 0 0
- 22 0 0 0 0 0 0
- 23 0 0 0 0 0 0 0
. VC Sump Level (ft.) 30 30 30 30 42 43 44 VC Hydrogen (%) 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Aux FW Flow SG21 (GPM) 0 0 0 0 0 0 0 SG22 (GPM) 0 0 0 0 0 0 0 SG23 (CPM) 0 0 0 0 0 0 0 SC24 (GPM) 5 5 5 5 RWST Level (ft.) 5 5 5 30 30 30 Cond Stor Tk Level (ft) 30 30 30 30
' VI-l
O O O PLANT STATUS LOG SCENARIO NO. 1985 PARAMETER TIME 11:10 11:15 11:25 11:30 12:00 13:00 Roactor Shutdown (Y/N) Y Y Y Y Y Y NIS Power Range (%) 0 0 0 0 0 0 NIS Interim. Range -10 -10 -10 -10 -10 -10
- 35 (Amps) 10 10 10 10 10 10 NIS Interim. Range -10 -10 -10 -10 -10
-10 10 10
- 36 (Amps) 10 10 10 10 NIS Source Range
- 31 (CPM) 200 200 200 200 200 200 NIS Source Range
- 32 (CPM) 150 150 150 150 150 150 RCS Incor T/C (Center) (*F) 120 120 120 120 120 120 RCS Incore T/C (Highest) (*F) 140 140 140 140 140 140 RCS Pressure (PSIC) 0 0 0 0 0 0 RCS Avg. Temp. (*F) 120 120 120 120 120 120 RCS Cold Leg Temp. (*F) 120 120 120 120 120 120 SAT Meter Margin (*F) 130 130 130 130 130 130 RCP in Service (Y/N) N N N N N N Pressurizer Level (%) 40 40 40 40 40 40 Roactor Vessel Level (%) 100 100 100 100 100 100 S/G Levels #21 (%) 100 100 100 100 100 100
- 22 100 100 100 100 100 100
- 23 100 100 100 100 100 100
- 24 100 100 100 100 100 100 S/G Press #21 (PSIC) 0 0 0 0 0 0
- 22 0 0 0 0 0 0
- 23 0 0 0 0 0 0
- 24 0 0 0 0 0 0 VC Pressure (PSIG) 0 0 0 0 0 0 VC Temperature (*F) 92 90 90 94 98 98 VC Sump Level (ft.) 44 45 45 45 45 45 VC Hydrogen (%) 0 0 0 0 0 0 Aux FW Flow SG21 (GPM) 0 0 0 0 0 0 SG22 (GPM) 0 0 0 0 0 0 SG23 (GPM) 0 0 0 0 0 0 SG24 (GPM) 0 0 0 0 0 0 RWST Level (ft.) 5 5 5 5 5 5 cond Stor Tk Level (ft) 30 30 30 30 30 30 VI-2
O (
PLANT STATUS LOG SENARIO No. 1985 PARAMETER TIME PARAMETER TIME 08: 30 08:30 Offsite Power Available 138KV 0 Service Water Pumps #21 0 13.8KV O (Essential Header) #22 0 Emergency D/Cs #21 S #23 S
- 22 S #24 0
- 23 S #25 S Gas Turbines GT-1 S #26 S GT-2 S Component Cool Heat Exchf21 0 GT-3 S #22 0 SIS Pumps #21 S RHR Heat Exchanger #21 0
- 22 S #22 0
- 22 S Charging Pumps #21 S VC Isol. Phase A Complete (Y/N) N
- 22 0 VC Isol. Phase B Complete (Y/N) N
- 23 S VC Isol. Vent. Complete (Y/N) N Containment Spray Pumps #21 S
- 22 S Exceptions Recirculation Pumps #21 S
- 22 S High Head SIS Flow #21 (GPM) S Component Cooling Pumps #21 S #22 (GPM) S
- 22 0 #23 (GPM) S
- 23 S #24 (GPM) S Aux Component Cooling Pumps #21 S Low Head SIS Flow #21 (GPM) 300
- 22 S #22 (GPM) 300 Aux Boiler Feed Pumps #21 S #23 (GPM) 300
- 22 O/S #24 (GPM) 300
- 23 S Accumulator Level #21 (%) 0/S Fan Cooler Units #21 0 #22 (%) 0/S
- 22 0 #23 (%) 0/S
- 23 O/S #24 (%) 0/S
- 24 0/S BIT Level (%) 0/S
- 25 0/S BIT Pressure (PSIG) O/S Legend: 0 =' Operating O/S =
Out of Service S = Standby
- = Change on status from previous log VI-3
O O PLANT STATUS LOG SENARIS NO. 1985 O
PARAMETER TIME PARAMETER TIME 10:00 10:00 Offsite Power Available 138KV 0 Service Water Pumps #21 0 13.8KV O (Essential Header) #22 0 Ecergency D/Cs #21 S #23 S
- 22 S #24 0
- 23 S #25 S Gas Turbines GT-1 S #26 S GT-2 S Component Cool Heat Exchf21 0 GT-3 S #22 0 SIS Pumps #21 S RHR Heat Exchanger #21 0
- 22 S #22 0
- 22 S Charging Pumps #21 S VC Isol. Phase A Complete (Y/N) N
- 22 0 VC Isol. Phase B Complete (Y/N) N
- 23 S VC Isol. Vent. Complete (Y/N) N Containment Spray Pumps #21 S
- 22 S Exceptions Recirculation Pumps #21 S
- 22 S High Head SIS Flow #21 (GPM) S Ccaponent Cooling Pumps #21 S #22 (GPM) S
- 22 0 #23 (GPM) S
- 23 S #24 (GPM) S Aux Component Cooling Pumps #21 S Low Head SIS Flow #21 (GPM) 300
- 22 S #22 (GPM) 300 Aux Boiler Feed Pumps #21 S #23 (GPM) 300
- 22 O/S #24 (GPM) 300
- 23 S Accumulator Level #21 (%) 0/S Fan Cooler Units #21 0 #22 (%) 0/S
- 22 0 #23 (%) O/S
- 23 0/S #24 (%) O/S
- 24 0/S BIT Level (%) 0/S
- 25 O/S BIT Pressure (PSIG) O/S Logend: 0 = Operating O/S = Out of Service S = Standby
- = Change on status from previous log VI-4 .
O O O PLANT STATUS LOG SENARIO NO. 1985 PARAMETER TIME PARAMETER TIME 10:45 10:45 offsite Power Available 138KV O Service Water Pumps #21 0 13.8KV O (Essential Hesder) #22 0 Energency D/Gs #21 S #23 S
- 22 S #24 0
- 23 S #25 S Gas Turbines GT-1 S #26 S GT-2 S Component Cool Heat Exchi21 0 GT-3 S #22 0 SIS Pumps #21 S RHR Heat Exchanger #21 0
- 22 S #22 0
- 22 S Charging Pumps #21 S VC Isol. Phase A Complete (Y/N) N
- 22 0 VC Isol. Phase B Complete (Y/N) N
- 23 S VC Isol. Vent. Complete (Y/N) N Containment Spray Pumps #21 S
- 22 S Exceptions Recirculation Pumps #21 S
- 22 S High Head SIS Flow #21 (GPM) S Ccaponent Cooling Pumps #21 S #22 (GPM) S
- 22 0 #23 (GPM) S
- 22 S #22 (GPM) 300 Aux Boiler Feed Pumps #21 S #23 (GPM) . 300
- 22 0/S #24 (GPM) 300
- 23 S Accumulator Level #21 (%) O/S Fan Cooler Units #21 0 #22 (%) O/S
- 22 0 #23 (%) O/S
- 23 0/S #24 (%) O/S
- 24 O/S BIT Level- (%) O/S
- 25 O/S BIT Pressure (PSIG) O/S Legend: - 0 = Operating O/S = Out of Service S = Standby
- = Change on status from previous log VI-5
O O O PLANT STATUS LOG SENARIO NO. 1985 PARAMETER TIME PARAMETER TIME 11:30 11:30 ,_
Offsite Power Available 138KV 0 Service Water Pumps #21 0 13.8KV O (Essential Header) #22 0 Energency D/Gs #21 S
- 23 S
- 22 S #24 0
- 23 5 #25 S Cos Turbines GT-1 S #26 S GT-2 S Component Cool Heat Exchf21 0 GT-3 S #22 0 SIS Pumps -*
- 21 S RHR Heat Exchanger #21 0
- 22 S #22 0
- 22 S Charging Pumps #21 S VC Isol. Phase A Complete (Y/N) N
- 22 0 VC Isol. Phase B Complete (Y/N) N
- 23 S VC Isol. Vent. Complete (Y/N) N Containment Spray Pumps #21 S
- 22 S Exceptions Recirculation Pumps #21 S
- 22 S High Head SIS Flow #21 (GPM) S Component Cooling Pumps #21 S #22 (GPM) S
- 22 0 #23 (CPM) S
- 22 S #22 (GPM) 300 Aux Boiler Feed Pumps #21 S #23 (GPM) 300
- 22 O/S #24 (CPM) 300
- 23 S Accumulator Level #21 (%) O/S Fan Cooler Units #21 0 #22 (%) O/S
- 22 0 #23 (%) O/S
- 23 0/S #24 (%) O/S
- 24 O/S BIT Level (%) O/S
- 25 0/S BIT Pressure (PSIG) O/S Legend: 0 = 5 Operating u/S = Out of Service S = Standby
- = Change on status from previous log VI-6
m, f^s
( )
%J PLANT STATUS LGG SENARIO NO. 1985 PARAMETER TIME 09:00 09:30 10:00 10:45 '
11:00 v.C. Purge Supply Fan 0 0 0 0 0 0 0 0 0 0 V.C. Purge Exhaust Fan #21 v.C. Purge Exhaust Fan #22 0 0 0 0 0 S S S S S V.C. Iodine Fan #21 S S S S S V.C. Iodine Fan #22 V.C. Sump Pump #29 S S S 0 0 V.C. Sump Pump #210 S S S O O FCV 1170 v.C. Ventilation Purge Supply Isolation Valve OPEN OPEN OPEN OPEN OPEN FCV 1171 V.C. Ventilation Purge Supply Isolation Valve OPEN OPEN OPEN OPEN OPEN FCV 1172 V.C. Ventilation Purge Exhaust Isolation Valve OPEN OPEN OPEN OPEN OPEN FCV 1173 V.C. Ventilation Purge Exhaust Isolation Valve OPEN OPEN OPEN OPEN OPEN Spent Fuel Pit Cooling Pump #21 0 0/S 0/S 0/S 0 S S S S S Spent Fuel Pit Cooling Pump #22 VI-7
O O O RADIOLOGICAL / METEOROLOGICAL LOG SCENARIO NO. 1985 PARAMETER TIME 08:30 09:00 09:30 10:00 10:30 10:50 11:00 R-1 CCR mR/hr / I 4 1 4 1 2 2 2 2 R-2 VC 80' mR/hr 2 2 2 4 12 3 3 R-4 Chrg. Pump mR/hr 1 1 1 2 2 2 2 R-5 F.S.B. mR/hr 2 2,500 2,500 0FFSCALE OFFSCALE OFFSCALE 5,000 R-6 Sample Ra mR/hr 2 2 2 3 3 3 3 R-7 VC Seal Table mR/hr 2 2 2 4 12 3 3 R-8 Drum Sta. mR/hr 2 2 2 4 4 4 4 R-10 Sta Line Penet mR/hr 10 10 10 10 10 10 10 R-II VC Part CPM 2,000 2,000 2,000 2,000 2,000 2,000 2,000 R-12 VC Cas CPM 800 800 800 10,000 30,000 2,000 1,000 R-13 Vent Part CPM 1,700 0FFSCALE OFFSCALE OFFSCALE OFFSCALE OFFSCALE OFFSCALE R-14 Vent Gas CPM 3,700 0FFSCALE OFFSCALE OFFSCALE OFFSCALE OFFSCALE OFFSCALE R-15 Air Ejector CPM 500 500 500 500 500 500 SOG R-16 F.C. Water CPM 15,000 15,000 15,000 15,000 15,000 15,000 15,000 R-17 Comp. Cool CPM 10,000 10,000 10,000 10,000 10,000 10,000 10,000 R-18 Liquid Waste CPM 850 850 850 850 850 850 850 R-19 S/G B.D. CPM 750 750 750 750 750 750 750 R-23 F.C. Water CPM 650 650 650 650 650 650 650 R-25 VC Hi-Rge R/hr 4 1 4 1 4 1 4 1 4 1 4 1 4 1 R-26 VC Hi-Rge R/hr < 1 4 1 ' 1 ' 11 11 12 12 3 3 R-27 Vent Monitor uCi/cc 0 5x10 5x10 5x10 5x10 5x10 1x10 R-27 Vent Flow Rate CFM 90,000 90,000 000 0.000 7 90,000 90,000 90,000 5 5 7 6 5 R-27 Vent Dis Rate uCi/sec 0 2x10 2x10 2x10 2x10 2x10 4x10 Main Steam #21 Rad Mon CPM 300 300 300 300 300 300 300
- 22 300 300 300 300 300 300 300
- 23 300 300 300 300 300 300 300
- 24 350 350 350 350 350 350 350 Vent Flow Rate CFM 90,000 90,000 90,000 90,000 90,000 90,000 90,000 Main Steam Exh Lbs/Hr 0 0 0 0 0 0 0 Air Ejector CFH 0 0 0 0 0 0 0 (measured value)
METEOROLOGICAL Wind Speed (meters /sec) 3.5 4.0 4.5 4.0 4.5 4.5 4.5 Wind Direction (degrees) 248 240 235 240 245 245 245 Pasquill Stability Category D D D D D D D VII-l
_ __ - -- - = _ = _ - . _ . - _- - - - - _ - _
-~ ,m O
RADIOLOGICAL / METEOROLOGICAL LOG SCENARIO No. 1985 PARAMETER TIME 11:10 11:15 11:25 11:30 12:00 12:30 R-1 CCR mR/hr 4 1 4 I 4 1 4 1 4 1 4 1 R-2 VC 80' mR/hr 2 2 2 2 2 2 R-4 Chrg. Pump mR/hr 1 1 1 1 1 1 R-5 F.S.B. mR/hr 15 8 2 2 2 2 3-6 Sample Ra mR/hr 2 2 2 2 2 2 R-7 VC Seal Table mR/hr 2 2 2 2 2 2 R-8 Drum Sta. mR/hr 2 2 2 2 2 2 l R-lO Sta Line Penet mR/hr 10 10 10 10 10 10
)) R-Il VC Part CPM 2,000 2,000 2,000 2,000 2,000 2,000 R-12 VC Gas CPM 900 350 800 800 800 800 R-13 Vent Part CPM 8,000 3,000 1,700 1,700 1,700 1,700 R-14 Vent Cas CPM 10,000 5,000 3,700 3,700 3,700 3,700 R-15 Air Ejector CPM 500 500 500 500 500 500 R-16 F.C. Water CPM 15,000 15,000 15,000 15,000 15,000 15,000
, R-17 Comp. Cool CPM 10,000 10,000 10,000 10,000 10,000 10,000 R-18 Liquid Waste CPM 850 850 850 850 850 850 R-19 S/C B.D. CPM 750 750 750 750 750 750 R-23 F.C. Water CPM 650 650 650 650 650 650 R-25 VC Hi-Rge R/hr < 1 < 1 < 1 < 1 4 1 < 1 3
R-26 VC Hi-Rge R/hr < 16 < l 7
< l < l < l < l R-27 Vent Monitor uCi/cc 5x10 lx10 0 0 0 0 R-27 Vent Flow Rate CFM 90,000 90,000 90,000 90,000 90,000 90,000 2
R-27 Vent Dis Rate uCi/sec 2x10 4 0 0 0 0 Main Steam #21 Rad Mon CPM 300 3G0 300 300 300 300
- 22 300 300 300 300 300 300
- 23 300 300 300 300 300 300
- 24 350 350 350 350 350 350 Vent Flow Rate CFM 90,000 90,000 90,000- 90,000 90,000 90,000 Main Steam Exh Lbs/Hr 0 0 0 0 0 0 Air Ejector CFM 0 0 0 0 0 0 (measured value)
METEOROLOGICAL Wind Speed (meters /sec) 4.5 .
4.5 4.5 4.5 4.5 4.5 Cind Direction (degrees) 245 245 245 245 245 245
- Pasquill Stability Category D D D D D D VII-2
v CONSOLIDATED EDISON COMPANY OF NEW YORK O INDIAN POINT UNIT NO. 2 DRILL SCENARIO 1985 VIII. RADIOLOGICAL INFORMATION TAB A TABLE 1: Primary Coolant Activity TAB B TABLE 2: Containment Activity TAB C TABLE 3: Release Path Activity TAB D TABLE 4: Plant Radiation Levels & Equipment Statua For Controllers TAB E TABLE 5: Facility Radiation Levels TAB F TABLE 6: Reuter-Stokes Readings TAB G TABLE 7: Plume Monitoring Data & Figures TAB H TABLE 8: Offsite TLD Readings TAB I TABLE 9: Post Accident Samples TAB J TABLE 10: Post Accident Offaite Contami-nation Levels TAB K TABLE 11: Medical Emergency Data i
i 4
l VIII
SCENARIO NO. 1985 l
I TABLE 1 O PRIMARY COOLANT ACTIVITY hrs. hrs. hrs. hrs.
! Nuclide uC1/al uCi/ml uCi/ml uCi/a1
! 132 l 133
- ~
134 135
{ Xe-133 j 133m 135 i 135m i 138 Kr-85
- 85a j 87 j 88 i Te-132
{ Cs-134 J 137 l 138
! Co-144 Le-140 l
O Ba-140 1
i NOT REQUIRED FOR THIS SCENARIO i
I k
l 4
i I
6 O
VIII-A
SCENARIO No. 1985 TABLE 2 CONTAINMENT ACTIVITY 1000 hrs 1030 hrs 1050 hrs 1100 hrs 1115 hrs Nuclide uC1/cc uC1/cc uCi/cc uC1/cc uCi/cc I-131 132 133 134 135 -
Xe-133 7.2x10 ' 2.3x10~3 9.0x10-5 1.6x10-5 4x10-6 133m 135 135m 138 Kr-85 85m 87 88 Te-132 Cs-134 137 138 Co-144 La-140 Ba-140 Only Isotopes Identified O
VIII-B
SCENARIO No. 1985 TABLE 3 RELEASE PATH ACTIVITY RELEASE PATH MEASUREMENT METHOD TIME RADIATION LEVELS PLANT VENT VENT CONTACT METHOD 09:00 BACKGROUND 10:00 6 mR/hr 10:50 6 mR/hr 11:00 BACKGROUND PLANT VENT CHEMISTRY SAMPLE 09:00 Noble Gas 6x10~3 uCi/cc I-131 uC1/cc I-132 NOT uC1/cc I-133 DETECT- uCi/cc I-134 ABLE uCi/cc I-135 uct/cc 10:00 Noble Gas 6x10~I uCi/cc I-131 uCi/cc I-132 NOT uCi/cc I-133 DETECT- uCi/cc I-134 ABLE uCi/cc uC1/cc O
i 10:50 I-135 Noble Gas 6x10~I uC1/cc j
I-131 uci/cc l 1-132 NOT uCi/cc i
I-133 DETECT- uCi/cc I-134 ABLE uCi/cc
' I-135 uC1/cc 11:00 Noble Gas 6x10~0 uC1/cc
' I-131 uC1/cc I-132 NOT uC1/cc 4
I-133 DETECT- uCi/cc I-134 ABLE uC1/cc I-135 uC1/cc NOTE: Vent contact reading provided to Rad Prot Tech. Chemistry data available 30 minutes after the sample is taken.
.O VIII-C
SCENARIO No. 1985 TABLE 4
() LOCATION PLANT RADIATION LEVELS TIME RADIATION LEVELS Fan Bldg. - Point 1 08:30 1 mR/hr 09:00 250 mR/hr 10:00 3500 mR/hr 11:00 300 mR/hr 11:15 10 mR/hr Point 2 08:30 1 mR/hr 09:00 10 mR/hr 10:00 350 mR/hr 11:00 15 mR/hr 11:15 5 mR/hr Point 3 08:30 1 mR'/hr 09:00 3 mR/hr 10:00 80 mR/hr 11:00 5 mR/hr 11:15 2 mR/hr Point 4 08:30 1 mR/hr 09:00 2 mR/hr 10:00 25 mR/hr 11:00 2 mR/hr 11:15 1 mR/hr Point 5 08:30 1 mR/hr 09:00 1 mR/hr 10:00 10 mR/hr O 11:00 11:15 2
1 mR/hr mR/hr Point 6 08:30 1 mR/hr 09:00 1 mR/hr 10:00 5 mR/hr 11:00 2 mR/hr 11:15 1 mR/hr NOTE 1: All loose contamination and airborne concentrations are actual levels detected.
NOTE 2: Data to be supplied to Rad Prot Tech at the locations after the survey is performed.
VIII-D-1
INDIAN PolNT NUCt. EAR POWEll 31 AlluN UNIT N3. E_ r-
- R ADI ATION SURVEY FGAM PJO. _L._)__ .
AtACTOR POWER LEVEL % Serial b.
Sect Type pdw by:
Tlaio: sway by:, ,
paw .sminews t . . -
. ,/
.e it,i.,6 p
/(D 4 FEB up j ,
..A__-3 -
, to 11/l'l mess.
Smear Results j ,-
- 4-imo # /
3 , g ,
_ r-
- 80 PAB l
-- <+>l111lllll lll -
I I
l l
k -
Vlli-D-2 l
SCENARIO NO. 1985 ;
)
TABLE 4
() LOCATION PLANT RADIATION LEVELS TIME RADIATION LEVELS Alley By - Point 1 08:30 1 mR/hr Plant Vent 09:00 7 mR/hr 10:00 690 mR/hr 11:00 8 mR/hr 11:15 1 mR/hr mR/hr l
Point 2 08:30 1 09:00 1 mR/hr 10:00 10 mR/hr 11:00 1 mR/hr 11:15 1 mR/hr 98' PAB - Point 1 08:30 4 1 mR/hr
. 09:00 2 mR/hr I 10:00 100 mR/hr 11:00 4 mR/hr 11:15 4 1 mR/hr Point 2 08:30 4 1 mR/hr 09:00 2 mR/hr 10:00 150 mR/hr i 11:00 6 mR/hr 11:15 4 1 mR/hr Point 3 08:30 4 1 mR/hr 09:00 1 mR/hr l 10:00 50 mR/hr
( 11:00 2 mR/hr l 11:15 4 1 mR/hr !
Point 4 08:30 4 1 mR/hr 09:00 4 1 mR/hr 10:00 15 mR/hr
' 11:00 1 mR/hr 11:15 4 1 mR/hr ,
Point 5 08:30 < 1 mR/hr
' 09:00 1 mR/hr 10:00 3 mR/hr 11:00 1 mR/hr 11:15 41 mR/hr t
I l
l NOTE 1: All loose contamination and airborne concentrations are l
actual levels detected.
l 30TE 2: Data to be supplied to Rad Prot Tech at the locations after !
I the survey is performed.
l VI!!-D-3 i
t
~
INDIAN PolNT NUCLEAR POWER STATION UNIT NO. Z RADIATION SURVEY FORMvU NO. xta
- Isetrument Type % Serial Me.'
, REACTOR QR LEVEL Dow: Time: suney W: - Revimmed W:
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- 3.
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I
- 3. Centesmanecien seewee are reeensed in Opes /100Cu2, and,sei, and s,,cto loses.on en our wy s>.orem
- 4. flecord reactor poseer % if todetton outwy et beeg porfoetwd V1i! -D -4
. ~
, IN01AN FOlhf' f 4UCLhAR POWER STATION
" I
~'. . I! NIT NO.c._2 __
RAOiATibN SURVEY F.G. i.M NO. .
atrumpat Type afACTOR POWER LEVEt. _% Serial Me, -
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SCENARIO NO. 1985 TABLE 4 l\ PLANT RADIATION LEVELS O
LOCATION TIME RADIATION LEVELS Plant Vent Chem Sample-Contact 09:00 1 mR/hr 10:00 25 mR/hr 11:00 2 mR/hr 11:15 4 1 mR/hr 80' PAB - Point 1 08:30 4 1 mR/hr 09:00 2 mR/hr 10:00 130 mR/hr 11:00 6 mR/hr 11:15 4 1 mR/hr Point 2 08:30 < 1 mR/hr i 09:00 3 mR/hr 10:00 150 mR/hr 11:00 7 mR/hr l
11:15 4 1 mR/hr Point Q,3 08:30 4 1 mR/hr 09:00 1 mR/hr 10:00 75 mR/hr 11:00 3 mR/hr 11:15 4 1 mR/hr 08:30 4 1 mR/hr Point Q)] 09:00 4 1 mR/hr 10:00 15 mR/hr gg 11:00 1 mR/hr
( ,/ 11:15 4 1 mR/hr 95' VC 10:00 21 mR/hr 10:30 67 mR/hr 10:50 5 mR/hr 11:00 2 mR/hr 11:15 2 mR/hr 46' VC - By Reactor Biological ALL TIMES 1250 mR/hr Shield Wall NOTE 1: All loose contamination and airborne concentrations are actual levels detected.
NOTE 2: Data to be supplied to Rad Prot Tech at the locations after the survey is performed except for the VC which will be O- supplied at the outer door of the air lock. No entry to VC will be permitted with the unit operating.
VIII-D-6
l
. 80' PAB l
I
--:- x
$meer Results
~~-
(- '
. 7 no. dpm /100 cm2 -D '
1
[ Q -
j Boron Tanks
@ C C Hx Air Rewivers ,
i i
23 '
\
~
/ :
5 f' 22- Charg. Pumps _
W ette f ( .. Cond. Tanks 21 ,
I i --
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3 21 WG5 Saling Station l NC5C l _ _
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7 l B l fens I
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1 SCENARIO NO. 1985 l l
}
TABLE 5 FACILITY RADIATION LEVELS 1 METER HEIGHT READING 10 ft. AIR SAMPLE LOCATION TIME B +( Y BKGD IODINE PART mR/hr mR/hr CPM CPM CPM Emergency All 4 1.0 4 1.0 200 200 200 Operation Times Facility (EOF)
Operational All 4 1.0 < 1.0 200 200 200 Support Times Center (OSC)
Technical All 4 1.0 4 1.0 200 200 200 Support Times Center (TSC)
Control Room All 4 1.0 4 1.0 200 200 200 (CR) Times O
P NOTE: Data to be supplied to Rad Protection Technician after the survey is completed.
U 1
VIII-E
- . _ - _ _ ~ _ . -
1
- O O O l
SCENARIO 100. 1985 TABLE 6 REUTER-STOKES READINGS mR/hr TIME 1 2 3 4 5 6 7 8 9 10 11 1
08:30 8E-3 8E-3 7E-3 7E-3 7E-3 7E-3 7E-3 7E-3 7E-3 7E-3 7E-3 09:00 8E-3 8E-3 8E-3 SE-2 7E-3 7E-3 7E-3 7E-3 7E-3 7E-3 7E-3 I
09:30 8E-3 8E-3 9E-3 4E-2 7E-3 7E-3 7E-3 7E-3 7E-3 7E-3 7E-3 10:05 8E-3 8E-3 2E-1 SE+0 7E-3 7E-3 7E-3 7E-3 7E-3 7E-3 7E-3 10:30 8E-3 8E-3 1E-1 4E+0 7E-3 7E-3 7E-3 7E-3 7E-3 7E-3 7E-3 10:55 8E-3 8E-3 1E-1 4E+0 7E-3 7E-3 7E-3 7E-3 7E-3 7E-3 7E-3 11:05 8E-3 8E-3 1E-2 9E-2 7E-3 7E-3 7E-3 7E-3 7E-3 7E-3 7E-3 11:15 8E-3 8E-3 8E-3 7E-3 7E-3 7E-3 7E-3 7E-3 7E-3 7E-3 7E-3 11:30 8E-3 8E-3 7E-3 6E-3 7E-3 7E-3 7E-3 7E-3 7E-3 7E-3 7E-3 11:45 8E-3 8E-3 7E-3 7E-3 7E-3 7E-3 7E-3 7E-3 7E-3 7E-3 7E-3 12:15 8E-3 8E-3 7E-3 7E-3 7E-3 7E-3 7E-3 7E-3 7E-3 7E-3 7E-3 VIII-F-1
O O O SCENARIO NO. 1985 TABLE 6(Continued)
RUETER-STOKES READINGS i
i TIME 12 13 14 15 16 08:30 8E-3 8E-3 8E-3 8E-3 8E-3 09:00 8E-3 8E-3 8E-3 8E-3 8E-3 09:30 8E-3 8E-3 8E-3 8E-3 8E-3 10:05 8E-3 8E-3 8E-3 8E-3 8E-3 10:30 8E-3 8E-3 8E-3 8E-3 8E-3 10:55 8E-3 8E-3 8E-3 8E-3 8E-3 11:05 8E-3 8E-3 8E-3 8E-3 8E-3 11:15 8E-3 8E-3 8E-3 8E-3 8E-3 11:30 8E-3 8E-3 8E-3 8E-3 8E-3 11:45 8E-3 8E-3 8E-3 8E-3 8E-3 12:15 8E-3 8E-3 8E-3 8E-3 8E-3 VIII-F-2
O O O SCENARIO NO. 1985 TABLE 7
~
PLUME MONITORING DATA-SECTORS 2 THRU 5 EMERGENCY / FIXED 3
SAMPLE SITE NO. OR 1 METER HEIGHT READING 10 FT AIR SAMPLE DATA CENTERING DIRECTION B + Y Y BKGD IODINE PART TIME NO. DEG MILES mR/hr mR/hr CPM CPM CPM All TIMES 2 1-10 < 1 < 1 200 200 200 08:42 60 2 < 1 < 1 200 200 200 09:12 60 2 ( 1 < 1 200 200 200 10:12 60 2 5 3 200 200 200 11:12 60 2 < 1 < 1 200 200 200 11:22 60 2 < 1 < 1 200 200 200 11:37 60 2 < 1 < 1 200 200 200 11:47 60 2 4 1 4 1 200 200 200 09:00 60 5 < 1 < 1 200 200 200 09:30 60 5 4 1 < 1 200 200 200 10:30 60 5 2 1 200 200 200 11:30 60 5 < 1 < 1 200 200 200 11:42 60 5 < 1 < 1 200 200 200 11:57 60 5 < 1 < 1 200 200 200 12:07 60 5 < 1 < 1 200 200 200 09:30 60 10 < 1 < 1 200 200 200 10:00 60 10 < 1 < 1 200 200 200 11:00 60 10 < 1 < 1 200 200 200 12:00 60 10 < 1 < 1 200 200 200 12:10 60 10 4 1 < 1 200 200 200 12:25 60 10 < 1 < 1 200 200 200 12:35 60 10 < 1 <1 200 200 200 NOTE: Plume Center Line Direction Is Given In Degrees. The Emergency Or Fixed Sample Sites Are Indicated By Sector No. And Mile Distance.
VIII-G-1
m SCENARIO No. 1985 TABLE 7 PLUME MONITORING DATA-SECTORS 2 THRU S (Continued)
EMERGENCY / FIXED SAMPLE SITE NO. OR 1 METER HEIGHT READING 10 FT AIR SAMPLE DATA CENTERING DIRECTION B + y y BKGD LODINE PART TIME NO. DEG MILES mR/hr mR/hr CPM CPM CPM 08:36 3 1 < 1 < 1 200 ' 200 200 09:06 3 1 2 1 200 200 200 10:06 3 1 9 5 200 200 200 11:06 3 1 2 1 200 200 200 11:16 3 1 < 1 < 1 200 200 200 11:31 3 1 < 1 < 1 200 200 200 11:41 3 1 <1 < 1 200 200 200 08:48 3 3 4 1 < 1 200 200 200 09:18 3 3 < 1 < 1 200 200 200 10:18 3 3 < 1 <1 200 200 200 11:18 3 3 < 1 <1 200 200 200 11:28 3 3 < 1 < 1 200 200 200 11:43 3 3 < 1 < 1 200 200 200 11:52 3 3 < 1 < 1 200 200 200 09:06 3 6 <1 < 1 200 200 200 09:36 3 6 4 1 < 1 200 200 200 10:36 3 6 < 1 < 1 200 200 200 11:36 3 6 < 1 < 1 200 200 200 11:46 3 6 41 < 1 200 200 200 12:01 3 6 < 1 4 1 200 200 200 12:11 3 6 < 1 < 1 200 200 200 NOTE: Plume Center Line Direction Is Given In Degrees. The Emergency Or Fixed Sample Sites Are Indicated By Sector No. And Mile Distance.
VIII-G-2
O O O SCENAPIO No. 1985 TABLE 7 PLUME MONITORING DATA-SECTORS 2 THRU 5 (Continued)
EMERGENCY / FIXED SAMPLE SITE No. OR 1 METER HEIGHT READING 10 FT 3 AIR SAMPLE DATA CENTERING DIRECTION B + y y BKGD IODINE PART TIME NO. DEG MILES mR/hr mR/hr CPM CPM CPM 09:30 3 10 < 1 < 1 200 200 200 10:00 3 10 4 1 < 1 200 200 200 11:00 3 10 < 1 .
< 1 200 200 200 12:00 3 10 < 1 < 1 200 200 200 12:10 3 10 < 1 < 1 200 200 200 12:25 3 10 < 1 4 1 200 200 200 12:35 3 10 4 1 < 1 200 200 200 08:36 4 1 < 1 4 1 200 200 200 09:06 4 1 < 1 < 1 200 200 200 10:06 4 1 < 1 < 1 200 200 200 11:06 4 1 < 1 < 1 200 200 200 I 11:16 4 1 < 1 < 1 200 200 200 11:31 4 1 < 1 < 1 200 200 200 11:41 4 1 < 1 < 1 200 200 200 i 08:48 4 3 ( 1 < 1 200 200 200
- 09:18 4 3 4 1 < 1 200 200 200 I 10:18 4 3 < 1 < 1 200 200 200 11:18 4 3 4 1 < 1 200 200 200 l
11:28 4 3 ( l < 1 200 200 200 i 11:43 4 3 < 1 4 1 200 200 200 11:53 4 3 < 1 41 200 200 200 I
l NOTE: Plume Center Line Direction Is Given In Degrees. The Emergency Or Fixed Sample Sites Are i Indicated By Sector No. And Mile Distance.
VIII-G-3
.. _ _ _-- _ _ - m_ _ . - .
O O O SCENARIO NO. 1985 TABLE 7 PLUME MONITORING DATA-SECTORS 2 THRU S (Continued)
EMERGENCT/ FIXED SAMPLE SITE NO. OR 1 METER HEIGHT READING 10 FT AIR SAMPLE DATA CENTERING DIRECTION B + y 7 BKGD IODINE PART TIME NO. DEG MILES mR/hr mR/hr CPM CPM CPM 09:06 4 6 ( l < 1 200 200 200 09:36 4 6 < 1 < 1 200 200 200 10:36 4 6 < 1 4 1 200 200 200 11:36 4 6 4 1 4 1 200 200 200 11:46 4 6 < 1 4 1 200 200 200 12:01 4 6 4 1 4 1 200 200 200 12:11 4 6 4 1 iC 1 200 200 200 09:30 4 10 4 1 < 1 200 200 200 10:00 4 10 4 1 < 1 200 200 200 11:00 4 10 < 1 4 1 200 200 200 12:00 4 10 < 1 4 1 200 200 200 12:10 4 10 < 1 < 1 200 200 200 12:25 4 10 < 1 < 1 200 200 200 12:35 4 10 < 1 < 1 200 200 200 ALL TIMES 5 1-10 ( l < 1 200 200 200 NOTE: Plume Ce ter Line Direction Is Given In Degrees. The Emergency Or Fixed Sample Sites Are Indicated By Sector No. And Mile Distance.
VIII-G-4
O O O SCENARIO NO. 1985 TABLE 7 (Continued)
PLUME MONITORING DATA-SITE BOUNDARY SECTORS (mR/hr)
WIND 1 2 3 4 5 6 TIME DIR B+ 7 Y B+ Y Y B+ y y B+ 7 Y B+ y y B+ 7 Y 08:30 248 4 1 < 1 4 1 < 1 4 1 4 1 09:00 240 4 1 < 1 2 < 1 < 1 4 1 10:00 240 5 3 180 100 7 4 11:00 245 < 1 < 1 4 2 < 1 4 1 11:15 245 < 1 < 1 4 1 < 1 < 1 < 1 11:25 245 4 1 < 1 4 1 < 1 <1 4 1
> 11:35 245 4 1 <1 < 1 < 1 < 1 <1 All other sectors I mR/hr at ALL TIMES PLUME MONITORING DATA-SITE BOUNDARY SECTORS AIR SAMPLES (CPM)
WIND 1 2 3 4 5 6 TIME DIR IODINE PART IODINE PART IODINE PART IODINE PART IODINE PART IODINE PART 08:30 248 200 200 200 200 200 200 09:00 240 200 200 200 200 200 200 10:00 240 . 200 200 200 200 200 200 11:00 245 200 200 200 200 200 200 11:15 245 200 200 200 200 200 200 11:25 245 200 200 200 200 200 200
> 11:35 245 200 200 200 200 200 200 Counter BKGD and other sectors 200 CPM st ALL TIMES VIII-C-5
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SCENARIO NO. 1985 TABLE 8 O-0FFSITE TLD READINGS MILE MILE SECTOR RING MREM SECTOR RING MRIM 1 1 9 1 5 5 10 10 2 1 10 1 5 5 10 10 3 1 11 1 5 5 10 10 4 1 12 1 5 5 10 10 5 1 13 1 5 5 10 10 6 1 14 1 5 5 10 10 7 1 15 1 5 5 10 10 8 1 16 1 5 5 10 10 l
l NOTE: Data to be supplied to Offsite Radiological
! Assessment Director.
l i
! NOT REQUIRED FOR THIS CCENARIO l
i iO VIII-H t
SCENARIO No. 1985 TABLE 9 POST ACCIDENT SAMPLES SAMPLE SECTOR TIME TIME ISOTOPES RADI0 ACTIVE MEDIUM MILE TAKEN COUNT IDENTIFIED CONCENTRATION
- NOT REQUIRED FOR THIS SCENARIO O
- SOIL = uC1/kg Water = uCi/ liter Vegetation = uCi/g dry weight NOTE 1 one day later NOTE 2 two days later NOTE 3: Data to be provided to Offsite Radiological Assessment Director after samples have been collected and processed.
VIII-I
SCENARIO No. 1985 TABLE 10 POST ACCIDENT OFFSITE CONTAMINATION LEVELS SECTOR SMEAR CHECK RESULTS-CPM MILE HRS HR5 (1) ER5 (2)
NOT REQUIRED FOR THIS SCENARIO O
NOTE 1: Time represents one (1) day later 2: Time represents two (2) days later 3: Data to be provided to offsite Radiological Assessment Director after checks are simulated.
O VIII-J
1 l
- SCENARIO No. 1985 i
E j TABLE 11 i
} MEDICAL EMERGENCY DATA i
! NOT REQUIRED FOR TMIS SCENARIO 3
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i 1
e VIII-K
CONSOLIDATED EDISON COMPANY OF NEW YORK
) INDIAN POINT UNIT NO. 2 DRILL SCENARIO No. 1985 IX. LOGISTICS A. Drill Size There will be a full scale activation of the following facilities.
Control Room Technical Support Center
- Operational Support Center Emergency Operations Facility Corporate Response Center B. Participation Assembly and accountability will be as follows:
Accountability Officers (AO) will be assigned for each of the following groups:
NPG TS
- EH&S AS Construction and they will await the call from the Chief Accounta ability Officer's staff at which time each A0 will report that all personnel are accounted for.
Operational Support Center (OSC) team members wearing white are bands will report to their respective section office when the " site assembly alarm" sounds. When each section's group of OSC team members is complete, they will report in person to the Chief Accountability Officer at the OSC.
C. Art Band Use The following arm band color coding will be used during the drill.
Green - Controller Red - Observer O White -
Blue -
Player NRC (available if they desire them)
IX-1
SCENARIO NO. 1985 D. Access O Access lists will only be prepared for the EOF for
'\m /
use by the Security Guard assigned to that post.
All other Nuclear Power personnel not partici-pating will be directed by their Department Managers to refrain from entering the TSC and OSC areas. Non drill participants requiring entry to the Control Room will be directed to contact the SWS assigned to the watch.
Security restrictions on entry through the Main Gate and Command Guard House will be lifted by the Chief Controller, through the Senior Watch Super-visor, one hour after the declaration of ALERT.
E. Lunch Lunch will not be provided to drill participants and the normal lunch break will be held at the and of the drill. The drill is expected to be tern-insted at approximately 1215 hours0.0141 days <br />0.338 hours <br />0.00201 weeks <br />4.623075e-4 months <br />.
F. Critique A aseting of all observers and controllers, with fs the exception of Irving Place, will be held in the
(
Simulator Cafeteria at 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br /> on June 5, 1985 where critique comments will be discussed, categor-ized and prepared for the formal critique to be held at 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> on June 6, 1985 at the Simulator Auditorium. The critique presentations will be made by the facility lead controllers. All players are welcome to attend.
l l
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(U i IX-2 f
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