ML20148T564
| ML20148T564 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 06/05/1997 |
| From: | Hughey W ENTERGY OPERATIONS, INC. |
| To: | Good G NRC |
| References | |
| GNRO-97-00052, GNRO-97-52, NUDOCS 9707090211 | |
| Download: ML20148T564 (28) | |
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Entergy Operations. inc.
h PO. Box 756 Port Gibson. MS 39150
, Tel 601437-6470 W.K.Hughey Daector NJclear Safety & Regda:Ory June 5, 1997 Senior Emergency Preparedness Analyst U.S. Nuclear Regulatory Commission 611 Ryan Drive, Suite 400 Arlington, TX 76011-8064 Attentiva: Ms. Gail Good
Subject:
Grand Gulf Nuclear Station Docket No. 50-416 License No. NPF-29 Emergency Preparedness Core Inspection GNRO-97/00052
Dear Ms. Good:
As we've discussed with you, Grand Gulf Nuclear Station will use a dynamic simulator for the emergency preparedness core inspection to be conducted at Grand Gulf on June 25, 1997.
The material you requested is enclosed.
Due to the short time between Grand Gulf's decision to utilize a dynamic simulator setting and the time for submitting the crew participants, scheduling of shift personnel during their relief shift has been difficult. A crew will be called in during their off time to participate.
If you need more information concerning the scenario, please /
contact Lloyd Calvery, SRO, Emergency Planning at (601) 437-6355.
/)/
Yours truly, ]t# } g-Ne[
WKH/WBA/ams enclosure: Core Inspection Material cc: (See Next Page) 9707090211 970625 PDR ADOCK 05000416 fffffffffffff.
'" ff G9706051
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, June 5,.1997 GNRO-97/00052 Page 2 of 2
)
lI cc: NRC Senior Resident Inspector (w/a)
Mr. N. S. Reynolds (w/o)
Mr. L. J. Smith (w/o)
Mr. H. L. Thomas-(w/o)
Mr. J. W. Yelverton (w/o).
4 Mr. E. W. Merschoff (w/2)
Regional Administrator
- U.S. Nuclear Regulatory Commission Region IV .
611 Ryan Plaza Drive, Suite 400 Arlington, TX- 76011 Mr. J. N. Donohew, Project Manager (w/a)
~
Office of Nuclear Reactor Regulation U.S.' Nuclear Regulatory Commission. --
Mail Stop 13H3 1 Washington, D.C. 20555 l
Document Control Desk (w/a)
U.S. Nuclear Regulatory Commission Mail Station P1-37.
Washington,.D.C. 20555 i
l i
i 1
080115 G9706051
4 Table of Contents 1
- 1. Schedule for the week of June 23,1997
- 2. Scope and Objectives
- 3. Scheduled Participants
- 4. Drill Scenario
- 5. Detailed Narrative of Scenario
- 6. Source Term and Meteorological Data l
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. Grand G lf N= lear Statica 1997 EP Core Inspection 82701 Drill :
SCHEDULE FOR WEEK OF JUNE 23 Monday, June 23 ; Entrance - General Manager's Conference Room at 1300 (1:00 P.M.) l Tuesday, June 24 ! 07:30 - Verification and validation of scenario with Inspection Team , j Wednesday, June 25 1 07:30 - Exercise for drill utilizing relief shift crew. (When drill is complete, crew 1 will remain under the cognizant of the EP OPS Coordinator untd :Jeased) 12:00 - Second exercise for drill utilizing training shift. l 1 Thursday, June 26 i ! ! Friday, June 27 - Exit- General Manager's Conference Room at 0900 (9:00 A.M.) 1
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fg SCOPE: j The purpose of this drill is to demonstrate by actual performance in a dynamic simulator setting the primary emergency preparedness functions that will be performed by the : j , operating crew prior to augmentation of other emergency facilities. " !- At no time will the drill be permitted to interfere with the normal safe operation of the l plant. 7 i The drill will include the appropriate offsite dose calculations and simulated notifications j to Federal, State, Local, and plant emergency personnel. L Using the applicable procedures and instructions, the operating crew will respond to the following: j? e ControlRodDrift b e Fuel Failure j e Loss ofOffsite Power !.
- RCIC Steam Leak with Failure to Isolate
! .. Emergency Depressurization Due to High Offsite Release Rate j e Implement the Emergency Plan as necessary
- Drill Objectives
i. } The primary otjective of the Emergency Ly--d,ses Core Inspection drill is to L ~' demonstrate the adequacy of the operating shift and other required emergency response personnel during a simulated accident. The simulated accident will be represented only to
- the point of augmentation for the shift by the activation of the other emergency facilities. In j general, the scenario will incluh the following objectives for the operating crew
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- 1. Provide plant os eniew dunng nutial Emergency Procedure i implementation.
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l 2. Classifies the emergency as an Unusual Event in accordance with 10-S i [ 1, Activation of the Emergency Plan,3.1.1 or 3.1.2 if required.
- 3. Assume the role of Emergency Director upon initial classification rig t emergency and makes announcement to the operstmg crew in accot&ce with 10-S-01-1, Activation of the Emergency Plan. I
. 4. Performs nuessment actions and directs actions from other departments to l ensure safe operation of the plant and protection of plant personnel, the general public, and plant equipment. ) ,
- 5. Completes a Notification form in accordance with 10-S-01-6, Notification of Offsite Agencies and Plant On-Call Emergency Personnel.
- 6. Designates communicators to make initial notifications to the state and local agencies within fifteen minutes of declarath i and the NRC ,
Operations Center immediately'after but within one hour of dectnation. .l
- 7. Activates the VIP 2000 in accordance with 10-S-01-6, Notification of Offsite Agencies and Plant On-Call Emergency Personnel.
- 8. . Announces the nature and classification cf the event over the plant paging system and the Administration Building paging system. l I
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- 9. Classifies the cmerg:ncy as an Alert in acc:rdance with 10-S-01-1, Activati:n cf the Emergency Plan,3.2.1,3.2.2. or 3.2.3 if required.
- 10. Activates ERDS (Emergency Response Display System) within one hour
. of the declaration of an Alert or higher classification.
I 1. Ensures an Offsite Dose Calculation is performed following the , declaration of an Alert of higher.
- 12. Performance of an Offsite Dose Calculation by the on-shift Chemist.
- 13. Implements Emergency Plan procedures as necessary.
- 14. Upgrades the emergency to a Site Area Emergency in accordance with 10-S-01-1, Activation of the Emergency Plan, if required.
- 15. Upgrades the emergency to an General Emergency in accordance with 10-S-01-1, Activation of the Emergency Plan, if required.
- 16. Issues Protective Action Recommendations when a General Emergency is .
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~ o 1 Drill Participants ) Morning Scenario: I
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"E" Shift ;
Shift Superintendent McIntyre, Thomas ; Shift Supervisor Weaver, Frank Plant Supervisor Roberts, Charlie i Reactor Operator Keesee, Sandra
' Reactor Operator Griffith, Walter i Reactor Operator Elliott, Steve ,
Primary Communicator Broome, Bryan Seconde:y Communicator McGuffee, Barry Offsite Dose Calculator Brad Philpott , l Afternoon Scenario op,, SM ' Shift Superintendent Sparks, Oreg Shift Supervisor Miller, Chris l Plant Supervisor Powell, Tony Reactor Operator Hall, Errol Killingsworth, David Reactor Operator Reactor Operator Hogue, Ronnie Primary Communicator Thomas, Barry ! Secondary Communicator Weeks, J. D. Offsite Dose Calculator Eric James i l l 1
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...u_-=.._...- * ** 1 m. GRAND GULF EMERGENCY PLANNING , NUCLEAR STATION DEPARTMENT w ENTERGY i 1 I I i i i k June 25,1997 Emergency Preparedness Assessment (82701) Drill CONTROL ROD DRIFTS / ATWS/ FUEL FAILURE / MSL STEAM LEAK IN TURBINE BUILDING / FAILURE TO ISOLATE OF B MSL/ OFFSITE DOSE RATES > GENERAL ! EMERGENCY LEVEL (EP-2 and EP-4) l l l I i ccNS Emirgency Plam Scea2rio Page 2 ef15 t . APPROXIMATE TIME: 1.25 HOURS , l
REFERENCES:
- 1. 05-S-01-EP-2, RPV Control i
- 2. 05-S-01-EP-21, RPV Control - ATWS i
- 3. 05-S-01-EP-3, Primary Containment Control l 4. 05-S-01-EP-4, Auxiliary Building and Radioactive Release Control I
- 5. 05-1-02-I-1, Reactor Scram
- 6. 05-1-02-I-4, Loss of AC Power
- 7. 05-1-02-IV-1, Control Rod / Drive Malfunctions
- 8. 05-1-02-II-2, Offgas Activity High
- 9. 10-S-01-1, Activation of the Emergency Plan
- 10. 10-S-01-19, Personnel Injury
- 11. 10-S-01, Notification of Offsite Agencies and Plant On-Call Emergency Personnel. '
- 12. GGNS Technical Specifications l 13. 01-S-06-2, Conduct of Operations ,
l 14. SOER 94-1, Nonconservative Decisions and Equipment Performance Problems Result in a l Reactor Scram, Two Safety Injections, and Water-Solid Conditions
- 15. SOER 96-1, Control Room Supervision, Operational Decision-Making, and Teamwork .
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- GGNS Emergency Plaa Scenario p ge3 gf15 ,
4 I TERMINAL OBJECTIVE: Given the applicable procedures and instructions, respond to the following:
- Aircraft Crash into Non-Vital Onsite Structure e 'CRD Pump Trip i
e Drift ofTwo Control Rods ! e' ATWS l .* ' Fuel Failure e Main Steam Line Break Outside Containment e Failure of a Main Steam Line to Isolate e Emergency Depressurization Due to High Offsite Release Rate (or to stop steam leak) j e Implement the Emergency Plan as -ry- . i *
- ENABLING OBJECTIVES: !
k Upon completion of this simulator scenario, the operating crew will complete the following objectives in
. accordance with simulator performance standards.
f ' A. CREW
- l. Perform the immediate and subsequent actions associated with the Control Rod / Drive -
Malfunctions ONEP for a control rod pump trip. ,
- 2. Perform the immediate and subsequent actions associated with the Control Rod / Drive Malfunctions ONEP for a control rod drifts.
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- 3. Perform the immediate and subsequent actions associated with the Reactor Scram ONEP. l
- 4. Perform the immediate and subsequent actions associated with the Loss of AC Power ONEP. l
- 5. Perform the immediate and subsequent actions associated with the Offgas Activity High - ;
ONEP. j i
- 6. Recognize and respond to entry conditions of EP2.
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-7. Recognize and respond to entry conditions of EP3.
- 8. Recognize and respond to entry conditions of EP4.
B. RO
- 1. Perform the immediate and subsequent actions associated with the Control Rod / Drive Malfunctions ONEP for a control rod pump trip. l
- 2. . Perform the immediate and subsequent actions associated with the Control Rod / Drive i Malfunctions ONEP for control rod drifts.
- 3. Perform the immediate and subsequent actions associated with the Reactor Scram ONEP.
- 4. Perform the immediate and subsequent actions associated with the Loss of AC Power ONEP.
- 5. Perform the immediate and subsequent actions associated with the Offgas Activity High ONEP.
L GGNS Emerge:cy Plas Scea:rio Pcte 4 cf15
- 6. Recognize and respond to entry conditions of EP2.
- 7. Recognize and respond to entry conditions of EP3.
- 8. Recognize and respond to entry conditions of EP4.
C. Plant Supervisor , i
- 1. Direct the activities associated with the Control Rod / Drive Malfunctions ONEP for a control rod pump trip.
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- 2. Direct the activities associated with the Control Rod / Drive Malfunctions ONEP for two control rod drifts.
- 3. Direct the activities associated with the Reactor Scram ONEP. ]
- 4. Direct the activities associated with the Loss of AC Power ONEP.
- 5. Direct the activities associated with the Offgas Activity High ONEP.
- 6. Direct the activities associated with EP-2.
- 7. Direct the activities associated with EP-3.
- 8. Direct the activities associated with EP-4.
D. Shift Supervisor /STA
- 1. Recommend actions to ensure that core cooling is maintained.
- 2. Independently verify the operating shift's identification of an event.
- 3. Evaluate the incids to determine that events are following the expected sequence.
- 4. Assist in evaluating the point-of-operation of the Emergency Procedure (EP) curves.
- 5. Recommend actions to mitigate or terminate the event.
- 6. Determine ifindications of core damage are present.
- 7. Provide recommendations on classification of event in terms oflevels of the Emergency Plan.
- 8. Analyze indications to determine the cause of the event.
- 9. Check systems governed by Tech Specs to ensure operability requirements are met.
- 10. Clarify Tech Specs and apply action statement requirements to an event.
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- D. Shift Superintendent .
- 1. Provide plant overview during initial Emergency Procedure implementation.
- 2. Classify the emergency as an Alert in accordance with 10-S-01-1, Activation of the -
' Emergency Plan,15.2,1.
s GGNS Esmergency Plan Scea:rio Pcgi5 cf15
- 3. Assume the role of Emergency Director upon initial classification of an emergency and makes announcement to the operating crew in accordance with 10-S-01-1, Activation of the Emergency Plan.
- 4. Performs assessment actions and directs actions from other departments to ensure safe _
. operation of the plant and protection of plant personnel, the general public, and plant ;
- equipment.
- 5. Completes a Notification form in accordance with 10-S-01-6, Notification of Offsite Agencies l and Plant On-Call Emergency Personnel. !
- 6. Designates communicators to make initial notifications to the state and local agencies within fifteen minutes of declaration and the NRC Operations Center immediately after but within :
one hour ofdeclaration. ,
- 7. Activates the VIP 2000 in accordance with 10-S-01-6, Notification of Offsite Agencies and i Plant On-Call Emergency Personnel.
- 8. Announces the nature and classification of the event over the plant paging system and the Administration Building paging system.
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- 9. Simulate activating ERDS (Emergency Response Display System) within one hour of the ., l declaration of an Alert or higher classification.
- 10. Ensures an Offsite Dose Calculation is performed following the declaration of an Alert of higher.
I 1. . Imph ments Emergency Plan procedures as necessary. ! i
- 12. Upgrad:s the emergency to a Site Area Emergency in accordance with 10-S-01-1, Activation of the Emergency Plan,ifrequired.
- 13. Upgrade . 2.c emergency to an General Emergency in accordance with 10-S-01-1, Activation of the Emergency Plan,ifrequired.
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- 14. Issues Protective Action Recommendations when a General Emergency is declared.
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GGNS Em:rgency Plan Scerrio P gi6 ef15 I.
SUMMARY
The plant is' operating at 100% power four months into the cycle. This is an off Friday and scheduled work is at a minimum today. The Chief Operating Officer is scheduled to bring some junior members of Congress down to the plant site for a tour today so housekeeping is a priority today. At time 10: The Director of PP&S calls the Control Room and infomis them that hejust witnessed the company's Selicopter crash into the Unit II warehousejust across from the SSW basins. There is no fire at this time. He is not sure if anyone was at work in the warehouse or how many persons was on the helicopter. He will be going over to the scene as soon as he hangs up.
. Fire Brigade Dispatched to the scene.
- Shift Superintendent assumes the role of Emergency Director.
- Declares an Alert.
- Emergency Director implements Emergency Plan.
At time 40: ; Plant Supervisor will report that the pilot is conscious and is being readied to be transport to the Parkview 1 Regional Medical Center. No fire has erupted and the fuel that has leaked has been foamed down. He ' reports that he will be returning to the Control Room leaving two fire brigade members standing by while l waiting on.E.4A officials. l At time 45: (After Plant Supervisor has returned to Control Room) i Health Physics personnel will contact the Control Room and inform them that a turbine building roof hatch i is open and Operations personnel need to take actions to close it.
- Condition Report may be initiated j e Plant Sepervisor will contact a Non-licensed Operator to close hatch At time 46:
The running CRD pump will receive a spurious trip. The standby pump will be started. When the standby pump is started, two control rods will start drifting in. Upon recognition of the two rods, a manual scram will be inserted. All rods will not insert due to a hydraulic block in the Scram Discharge Volume and an ; ATWS will exist.
- EP-2A will be entered.
- Since the turbine is still on line, reactor water level and reactor pressure may be maintained in its normal band as allowed by the EP-2A. The power leg of the EP will direct the shift to call for l attachments 18,19, and 20.
At time 52: A overcurrent lockout will occur on Load Control Center 16BB4. Breaker 52-16401 will have a ground. The LCC can be repaired by replacing the breaker. Power to the motor operated steam supply shutoff valves will be lost rendering the valves unable to be closed. i
GCNS Em:rgency Plam Scen:rio Pag) 7 cf 15 4 At time 55: Report of possible steam in the Turbine Building. Small Main Steam Line break will occur. Break will be accompanied by Turbine Bldg Ventilation High-High Radiation alarms and various area radiation monitors. The severity of the fuel failure malfunction will be increased to the point where MSL HI radiation alarm will annunciate. This will be an entry condition for EP-4. Offgas Pretreatment HI and HI-HI alarms will also illuminate requiring response per the Offgas Activity High ONEP.
. Crew will attempt to isolate steam leak by closing MSIVs.
. "B"MSL will not isolate.
At time 57: 1 1 The security shift supervisor will call the Control Room and inform them that door IT302 stills indicates open from where the operator exited it. He will request a Condition Report be initiated for the exit of the
- emergency door. Fuel failure has began due to flux tilts and rod tip crossing.
I NOTE: Crew may decide to emergency depressurize the RPV to stop the uncontrolled steam leak. At time 70: Offsite Dose Calculator will report that analyses indicates a TEDE at the site boundary of 1140 mr/hr. The ~ Shift Superintendent / Emergency Director will reclassify the event as a General Emergency and inform the Plant Supervisor that offsite release rates are above the General Emergency level. In accordance with EP-4, the Plant Supervisor will direct an Emergency Depressurization. The Shift Superintendent / Emergency Director will recommend to the state and local agencies to evacuate for a two mile radius,5 miles in downwind sectors and to seek shelter for the remainder in a ten mile Emergency Planning Zone (EPZ). At time 90: The repair team will repon to the Control Room that they have replaced the breaker for 52-16401 and that the Control Room may attempt to close it if desired. Once the breaker is closed, B21-F098A-D may be closed terminating the un-monitored release. The drill may be terminated after this if the Superintendent / Emergency Director has made the Protective Action Recommendation for the General Emergency. i l l
CGNS Em;rgrey Plam Scen:rio Page 8 ef15 II. SIMULATOR INITIALIZATION AND PLANT CONDITIONS
. A. Simulator Initialization
- 1. Reset the simulator, clear or verify clear all the counters at the top of the screen and kill or verify killed all cases.
- 2. Enter the following command and press enter:
case simsc EXD88
- 3. Take the simulator out of freeze
- 4. Startup all PDS/SPDS screens. Clear any graphs and trends off of SPDS.
- 5. Ensure the correct shutdown sequence is available at the, P680 for the present IC.
NOTE: Cases can take several minutes to execute. Use " Case Summary" to determine when the case is done.
- 6. Verify or perform the following IC: 15 Power level: 100 %
- 7. Run through any alarras and ensure alarms are on. Put the simulator in freeze if desired.
- 8. Refer to the following tables to e isure all simulator functions are inserted. _
Caution: You may have to click on the item on the summary to see the full status. Click CANCEL when you are done to avoid altering the item.
- 9. Install turnover guide.
- 10. Advance all chart recorders and ensure all pens inking properly.
I1. Enter the following meteorological conditions:
- 1935 hours e wind speed of 4 mph e wind direction of189 e stability class D e Delta temperature 0.1 degree F The Simulator Instructor will need a copy of an Emergency Notification form to assist in the roll ca_Il once the communicator calls on the OHL.
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Page 9 of15 ", D Simulator Function Summary t Malfunctions - Event Malfunction Severity Trigger Delay Ramp Title - N/A Cl1164 .05 N/A N/A CRD Scram Discharge Volume Hydraulic Block
- N/A C41263 1.0 .N/A N/A N/A SLC Piping Rupture N/A MSI83B N/A N/A N/A N/A "B" Inboard MSIV fails as is ,
MSI84B N/A N/A N/A N/A "B" Outboard MSIV fails as is ; 1 021021_20_37 7 Control Rod 20-37 Drift 1 - 021021_20_17 7 Control Rod 20-17 Drift - 2 RR071 .2 8 05 min Fuel Cladding Leak (display shows 0.00) (to be ramped to 1.0 after MSIVs are closed) 2 R21142AA .8 480 Volt bus 16BB4 Overcurrent Trip 2 MS%7B .05 8 N/A N/A Small break of Main Steam Line "B" Component Malfunctions . Event Component Severity Trigger Delay Ramp T_itle Malfunction Overrides Event Time OVRD # Severity Trigger Delay Title j I
l [* P;g310 cfl5 C. TurnoverInformation: .
'l.' Place the simulator back in freeze for turnover with the following conditions: .
Power 100 % Pressure 1020 psig Pull sheet step At target rod pattern , BOC ! !- Inform the crew during tumover of the following: l
- 1 l The plant is operating at 100% power four' months into the cycle. This is an off Friday and ;
- scheduled work is at a minimum today. The Chief Operating Officer is scheduled to bring i
! somejunior members of Congress down to the plant site for a tour today so housekeeping is a
- priority today.
! 2. . Assign positions and direct the crew to walk down the panels. Ensure the planned evolutions of the day are understood. After the crew has assumed the shift, the plant supervisor should conduct a pre-shift briefing.
- 3. All activities shall be done in accordance with approved procedures. !
- 4. The simulator " console" instructor will simulate performing the duties of the building operators. He should ensure proper communication is practiced.
- 5. Refer to the tables at the end for this scenario for a detailed listing of expected operator actions. .;
- 6. The following instructions contain the minimum required actions of the crew. More notifications or actions may be performed in each event than expected.
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P:3211 cf15
,l SCENARIO GUIDE III. SCENARIO ACTIVITIES A. Aircraft crash into unit II warehouse.
- 1. Ten minutes after the drill has commenced, the rimulator instructor (SI) will call the Control Room as the Director of PP&S. The SI will state that he was just coming in on his off day and observed the company's helicopter veer sharply after taking off from the EOF and crash into the southwest comer of the Unit II warehouse. There is no sign of a fire at this time but you did not investigate the wreckage prior to calling to repon the .
occurrence. You are not sure if anyone was at work but there were very few cars in the parking lot since it is an off Friday. You don't know how many people was on the helicopter. Inform the Control Room that you will assemble everyone you can find in the Site Services Building to help.
- 2. The Fire Brigade may be dispatched. If so, have the Plant Supervisor, acting as the Fire Brigade Leader, come into the Instructor's booth so that he can simulate talking to the Control Room and keep the Control Room informed.
- 3. The Control Room will contact Health Physics (for medical assistance) and provide them with what details of the crash they have. As HP, respond that you will dispatch a first aid team to the site.
- 4. The Shift Superintendent will declare an ALERT and call for communicators. The SI should allow the shift's communicator to answer either the radio or the telephone and respond accordingly.
- 5. Ten minutes after the initial call, have the Fire Brigade Leader (Plant Supervisor) contact the Control Room that the pilot was the only occupant of the helicopter. All MP&C personnel are accounted for and none have received injuries. The pilot has head and chest lacerations and will require transportation to an emergency medical facility. Fuel is leaking but has been foamed down and is being contained at the moment.
- 6. At drill time 30 minutes, have the Fire Brigade Leader contact the Control Room and inform them that the on-site ambulance is on its way to the scene. Inform the Control Room that the pilot's name is John Doe and that the EMT's do not think his injuries are life threatening.
- 7. At drill time 40 minutes, have the Fire Brigade Leader contact the Control Room end inform them that the on-site ambulance has left with the pilot in route to the Parkview Regional Medical Center. Actions have been taken to mitigate the possibility of a fire and that you are retuming to the Control Room. (If the Shift Superintendent /ED contacts the offsite agencies to terminate the event, as a MEMA representative, ask that he allow you some time to consult with other officials)
B. CRD pump trip and subsequent control rod drifts.
- 1. At drill time 45 minutes, the SI will contact the Control Room as a Health Physics person and inform them that a turbine building roofhatch is open on the nonh end above areas 3/6. Ask if they could get someone to close it. (The shift may simulate writing a condition report for the operational event.)
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'l SCENARIO GUIDE
- 2. After the call to the Control Room has been completed, trigger event #7. The running CRD pump, pump "A", will trip. The crew will respond per the ONEP to start the standby pump. Thirty (30) seconds after the trip, two control rods will begin drifting in (20-17 and 20-37). When the two control rods are identified, a manual scram will be inserted.
- 3. All control rods will not insert due to a hydraulic lock on the Scram Discharge Volume.
Power will decrease to less than twenty percent and the main turbine will stay on line. (The main turbine may trip on high water level depending on operator actions. Even if the main turbine trips, the bypass valves will be adequate to handle the steam flow.)
- 4. EP-2A will be entered via EP-2. The actions of EP-2A will lead the Plant / Shift Supervisor
. to request attachments 18,19, and 20 he performed. The SI will enter the Control Area and obtain the attachments. Once the attachments are in hand, the SI will hit F1 to access the EP Attachment page. Once on the attachment page, click on the buttons for attachments 18,19, and 20. After the attachment are active, retum the paperwork (attachments) back to the Control Room to signify that they are complete.
- 5. An ATWS will be classified as a Site Area Emergency.
- 6. The crew should observe the loss of power to Load Control Center 16BB4. As initial actions of the ATWS are completed, the Shift Superintendent /ED may call the Electrical Shop to have electricians investigate the loss of power. (The plent supervisor will direct the operator response.) Respond as the Electrical Supervisor that you will get an electrician to the LCC as soon as possible. If the Auxiliary Building operator is dispatched to check on the LCC, wait five minutes and then inform the Control Room that breaker 52-16401 is open and the white reset (86 device reset) button is sticking out further than normal.
- 7. At drill time 55 minutes, the SI, acting as the Turbine Building Operator will contact the Control Room with a sense of urgency. Report that you have violated radiological policies by exiting the en.ergency exit door in the stairway on 133 of the Turbine Building. Explain that when you exited the Main Turbine Lube Oil Reservoir room, you encountered what you think was steam filling the building. It was very warm and blinded you momentarily. (The SI conversation should be such that is becomes obvior s there is a steam leak in the Turbine Building that is of personnel safety sign 8ficance.)
- 8. As the fuel failure malfunction increases in severity, the Main Steam Line (MSL)
Radiation High annunciator will alarm. This will be an entry condition to EP-4. Directions from EP-4 will direct the crew to attempt to isolate the leak. When the MSIVs are closed, the "B"line will remain open.
- 9. When the three Main Steam Lines are closed, increase the severity of RR071, Fuel Failure, to 1.0 over two minutes. The one remaining steam line will not provide the same magnitude of readings as the four lines had been supplying. Increasing the malfunction will enable the MSL Radiation High alarm to stay in.
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, Pcge 13 of15 i i
i SCENARIO GUIDE l 1
- 10. SI will return the EP attachments to the Control Room when they become active. !
- 11. At drill time 57, SI will call the Control Room as Security Shift Supervisor and inform !
them that it appears the operator did not close door IT302, emergency exit door on the 133 : elevation in the turbine since it is still in alarm. (If the shift requested a non-licensed operator to close the turbine building roof hatch found open by the HP, contact the Control Room and ask them how you are suppose to close the hatch. Tell them you don't see how l to get up on the roof.) , C. Offsite Dose Calculations Exceed General Emergency Levels
- 1. At drill time 70 minutes, allow the Offsite Dose Calculator to inform the Shift ,
Superintender.t/ED that their calculations indicate a TEDE of 1140 mr/hr at the site '
' boundary.
- 2. After referring to the EALs, the Sidh 2uperintendent/ED will upgrade the event to a !
General Emergency.
- 3. The Plant Supervisor will direct an Emergency Depressurization in accordance with EP-4.
- 4. Protective Action Recommendations will be included in the new notification to State and Local Agencies. ;
D. Recovery Actions
- 1. If Electricians were dispatched to the LCC, at drill time 90 minutes inform the Control l
Room that breaker 52-16401 has been repaired and that you would like the Control Room l to energize the LCC. l
- 2. Once the motor operated main steam line shutoff valves, B21-F098A-D have been closed and protective action recommendations communicated to the offsite agencies, place the simulator in freeze and inform the crew that the drill is terminated.
IV.~ REVIEW A. Compare the crew's actions to those required by applicable procedures (see References). Critique any differences. ' B. Review the scenario's activities against scenario objectives. ! i C. Provide drill critique and feedoack to the Crew.
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. Pag 214 cf15 EXPECTED ACTIONS FOR EVENT #1 Crew Task
Description:
AIRCRAFT CRASH INTO UNIT II WAREHOUSE Complete Position Expected Actions / Behavior SST DECLARES AN ALERT { PSV MUSTERS THE FIRE BRIGADE AND ACTS AS LEADER SST ASSUMES THE ROLE OF EMERGENCY DIRECTOR AND MAKES ANNOUNCEMENT SST COMPLETES A NOTIFICATION FORM SST DESIONATES COMMUNICATORS SST ACTIVATES THE VIP 2000 . SST ANNOUNCES THE EVENT OVER THE PAGING SYSTEM SST ACTIVATES ERDS (simulated since not on Simulator) SST REQUESTS AN OFFSITE DOSE CALCULATION SST IMPLEMENTS PERSONNEL INJURY PROCEDURE EXPECTED ACTIONS FOR EVENT #2 - CREW TASK DESCRIPTION: CRD PUMP TRIP AND CONTROL ROD DRIFTS Complete Position Expected Actions / Behavior CRO RESPOND TO AND REPORTS CRD TRIP ALARM PSV DIRECT ACTION OF CRD MALFUNCTION ONEP ACRO DIRECTS TWO CONTROL ROD DRIFTS PSV DIRECT A MANUAL SCRAM ~ ACRO INSERTS MANUAL SCRAM, REPORTS ATWS < PSV ENTERS EP-2A PSV REQUESTS ATTACHMENTS 18,19,20 CRO ANNOUNCES LOSS OF POWER Td 16BB4 SST CLASSIFIES THE EVENT AS SITE AREA EMERGENCY,--
-PSV DIRECTS MSIVS CLOSED TO STOP STEAM LEAK CRO ANNOUNCES FAILURE OF MSL B TOISOLATE CRO ANNOUNCES THAT B21-F098B DOES NOT HAVE POWER SST DIRECTS REPAIR TEAM TO LCC 16BB4 l
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EXPECTED ACTIONS FOR EVENT #3' l CREW TASK DESCRIPTION: OFFSITE DOSE LEVEL EXCEED GE LEVELS ! l l . Complete Position Expected Actions / Behavior i ST GENERAL EMERGENCY ON TEDE ; ! ST- V OF GE LEVELS FOR EP-4 , SV RGENCY DEPRESSURIZATION PER EP-4 RO EAST FIVE ADS /SRVs AS DIRECTED l SV ACING SUPPRESSION POOL COOLING IN SERVICE , RO PRESSION POOL COOLING IN SERVICE (A LOOP ONLY) i ST TECTIVE ACTION RECOMMENDATIONS TO PUBLIC L i EXPECTED ACTIONS FOR EVENT #4 ; CREW TASK DESCRIPTION: OFFSITE DOSE LEVEL EXCEED GE LEVELS ! Complete Position Expected Actions / Behavior PSV DIRECTS CRO TO CLOSE FEEDER BREAKER TO 16BB4 > PSV DIRECTS B21-F098A-D CLOSED WHEN POWER IS RESTORED
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4 .< , GRAND GULF NUCLEAR STATION
, EMERGENCY DOSE PROJECTION FOR 06/25/0830 Line Number ! tem Data 7 Rx Shutdown 06/25/97,0846 8.A Wind Direction From 189 at 4.0 mph l 8.B. Affected Sectors RAB 8 C. Stability Class D ,
l9 Release Info Duration 2 hrs I Started 06/25/97 t 10 Type ofRelease Radioactive Gases 11 A. Release Rate Noble Gases ; I 11.B Release Rate Iodine . 12.A. Dose Commitment 2 hr. I i 12.B. TEDE Dose TEDE Dose in mrem SB 1.14 +E3 2 Mile 1.95 +E2 5 Mile 6.11 +El 10 Mile 2.38 +El 1
. l 12.C CDE Dose Thyroid Dose in mrem SB 1.12 +E4 2 Mile 2.02 +E3 5 Mile 6.93 +E2 10 Mile 2.99 +E2 I
1 l s
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a
.' NUCLIDE MIX DATA Kr-85 . 0000 I-131 2.1815 Kr.-85m ' 0000 I-132 20.07 Kr-87 .4451 I-133 13.9617 Kr-88 .4538 I-134 38.3948 Sr-89 0000 I-l35 21.8153 i
Sr-90 0000 Xe-131m .0004 Sr-91 0000 Xe-133 .1833 Y-91 0000 Xe-133m .0067 { Mo-99 0000 Xe-135 .5148 Ru-103 0000 Xe-138 1.8325 l 3 Ru-106 0000 Cs-134 0000 4 Sb-127 0000 Cs-136 0000 l Sb-129 0000 Cs-137 0000
- Te-129m 0000 Ba-140 0000
) Te-131m 0000 La-140 0000 ~ Te-132 0000 Ce-144 0000 1 Np-239 0000 4
- 4 4
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