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Revision as of 03:31, 27 February 2020
| ML20006F773 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 11/19/1986 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| References | |
| NUDOCS 9003010134 | |
| Download: ML20006F773 (468) | |
Text
{{#Wiki_filter:y. i/\ This is a copy of the 1986 Sequoyah Nuclear Plant Exercise Controllers Package. All information contained in the package is to be treated as confidential until after the exercise. Please ensure that your copy is kept in a secure place when you are not using it. Do not discuss details of the exercise with anyone other than another controller. An Y ,lu Thomas E. Adkins Exercise Director v Copy No. 0487E .
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Q NRC/ FEMA-EVALUATED EXERCISE INPLANT SCENARIO O w 9 O s
N . INTRODUCTION f 5 f
) Annual ~ exercises are required by regulation for each licensed commercial '
nuclear power plant in the United States. The purpose of these exercises . are to test Radiological Emergency plans (REPS) to ensure that the health and safety of TVA employees and the general public is protected in the event of a radiological accident. These exercises also serve to train emergency response personnel for the duties under rep and to observe-the - rep in action so that areap in need of improvement can be identified. t
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The TVA actions during the exercise will be evaluated by NRC and the "[ State and local actions will be evaluated by the Federsl Emergency i Management Agency (FEMA). NRC will issue a formal inspection report ! concerning the exercise and FEMA will issue a formal evaluation report detailing their findings. , This exercise will be initiated from the SQN control room on November 19, t 1986, at approximately 0800 CDT. The exercise will have a duration of ' eight to nine hours. The exercise will initially involve the onsite and l offsite TVA emergency organizations. This will be a full-scale exercise so the State of Tennessee and the risk counties will fully participate. Those participating in the exercise may include, but are not limited to, the following. A. Sequoyah Nuclear plant ( B. Tennessee Valley Authority Central Emergency Control Center (CECC), i Chattanooga, Tennessee C. Tennessee Emergency Management Agency (TEMA) Nashville, Tennessee { D.- Tennessee Department of-Health and Environment, Nashville, Tennessee P E. Hamilton CJunty Emergency Management Agency ', F. Cleveland /Bradley County Emergency Management Agency G. Tennessee Department of Agriculture i H. Tennessee Wildlife Resources Agency I. Tennessee Department of Conservation J. Covernor, State of Tennessee K. American Red Cross L. National Weather Servico M. Federal Emergency Management hgency g N. U.S. Coast Cuard l V i
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- 0. Risk Counties Civil Defense (Hamilton and Bradley) (
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P.- Host Counties (Rhea. Meigs, Sequatchie) Q. Emergency Broadcast System i R. ~ Nuclear Regulatory Commission and Other Federal Agencies S. Local Support Agencies in Risk Counties l T. Tennessee Department of Safety (Highway Patrol) , U. Tennessee Public Service Commission I V. Tennessee Department of Tourist Development W. Tennessee Department of ' Transportation K. Tennessee Department of Human Services j Y. Department of Energy ' 4 0440E
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I ( SEQ 00 VAN pucLEAR PLANT RADICLOGICAL EngRCENCY PLAN (atp) tagRctst i The 1986 SQW rep exercise will be a full-scale exercise requiring full j (~') participation by TVA, state, and local energency response agencies, i
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Exercise C0111 The TVA goals for the 1986 SQW exercise are as follows:
- 1. To allow plant and offsite personnel to test and practice their response espability in accordance with the SQN rep and rep implementing procedures to protect plant personnel and the general I
public as appropriate.
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- 2. To ensure that deficiencies observed in previous exercises have been corrected.
- 3. To identify emergency response capabilities that are in need of i improvement or revision.
I Exercise ob3ectives ; General Objectives i
- 1. Demonstrate the ability to alert and mobilize TVA emergency response personnel in a timely manner.
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- 2. Demonstrate the ability to activate TVA emergency centers in a timely manner. (
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- 3. Demonstrate the adequacy, operability, and effective use of emergency communications equipment and the adequacy of the communications system &. ?
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- 4. Demonstrate the ability of each emergency response facility manager
- to maintain command and control over all emergency response activities conducted from his facility throughout the exercise.
- 5. Demonstrate the primary functional responsibilities and/or problem -
. solving capabilities of emergency response personnel.
- 6. Demonstrate that timely and accurate information can be supplied to the State on a frequent basis.
- 7. Demonstrate the ability to effectively generate protective action recommendations. '
[ Specific Objectives A. Control Room objectives
- 1. Demonstrate the ability of the Site Emergency Director (Shift Engineer) to classify an emergency condition in a timely manner.
- 2. Demonstrate the ability to formulate and implement protective action measures in a timely manner.
__ _._ -_. .__________._________________.__________J
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- 3. Demonstrate the precise and clear transfer of responsibilities 0- from the Control Room staff to the TSC staff.
- 4. Demonstrate the ability of the Shift Engineer to periodically inform Control Room personnel of the status of the emergency situation and the plant conditions.
- 5. Demonstrate the ability of the Control Room staff to make a timely determination of the cause of an incident and perform mitigating actions to place the unit in a safe, stable condition.
B. Technical Support Center (TSC) Objectives
- 1. Demonstrate the ability to alert and mobilire the TSC emergency response personnel in a timely manner.
- 2. Demonstrate the ability to activate the TSC in a timely manner.
- 3. Demonstrate that effective command and centrol occurs in the TSC.
- 4. Demonstrate the precise and clear transter of responsibilities from the Control Room staff to the TSC staff.
- 5. Demonstrate the primary functional responsibilities and problem solving capabilities of the TSC staff.
- 6. Demonstrate the ability of the TSC staff to support the Control Room staff's effort to identify the cause of the incident, mitigate the consequences of the incident and place the unit in a safe, stable condition.
- 7. Demonstrate the proficiency of the Site Emergency Director in '
the TSC to classify an emergency condition.
- 8. Demonstrate the ability to account for site personnel in a timel) manner.
- 9. Demonstrate the ability to formulate and implement onsite protective ' actions in a timely manner.
- 10. Demonstrate the ability to perform timely assessments of onsite radiological conditions to support the formulation of protective ,
action recommendations.
) 11. Demonstrate the ability to assess information available from the containment and effluent high-level radiation monitoring systems and respond accordingly.
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- 12. Demonstrate the timely updating of TSC status boards.
C. Operations Support Centers (OSC) Objectives
- 1. Demonstrate the ability to alert and mobilire the OSC emergency response personnel in a timely manner.
- 2. Demonstrate the sbility to activate the OSC in a timely manner..
- 3. Demonstrate the ebility of the OSC staff to initiate and coordinate activities in an efficient and timely manner.
- 4. Demonstrate that OSC teams are thoroughly briefed on plant conditions before being dispatched.
- 5. Demonstrate that adequate health physics support is provided to OSC teams.
- 6. Demonstrate that OSC team leaders provide effective command and control.
- 7. Demonstrate that adequate communications are maintained between OSC teams and the OSC.
- 8. Demonstrate that there is a timely and efficient transfer of information between the OSC and the TSC.
O 9. Demonstrate the ability to obtain and to analyze samples drawn from the inplant normal or post-accident sampling systems.
- 10. Demonstrate the ability to direct and coordinate inplant health physics surveys in a timely manner. '
- 11. Demonstrate the ability to control the exposure of onsite emergency workers.
- 12. Demonstrate that a plant environmental monitoring team can be dispatched in a timely and efficient manner.
- 13. Demonstrate the timely updating of OSC status boards.
D. Central Emergency Control Center (CECC) Objectives
- 1. Demonstrate that the Operations Duty Specialist makes the '
g initial notification to the State in a timely manner.
- 2. Demonstrate the ability to alert and mobilize the CECC emergency response personnel in a timely manner.
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I e w 3. Demonstrate the ability to activate the CECC in a timely manner. k:<]
- 4. i Demonstrate that the CECC Director makes a clear announcement l When he determines the CECC operational.
- 5. Demonstrate that ef fective command and control occurs in the CECC.
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- 6. Demonstrate the ability to effectively call upon and utilize TVA corporate or outside support organizations when required. l i
- 7. Demonstrate the precise and clear transfer of responsibilities from the TSC staff to the CECC staff.
- 8. Demonstrate the ability to obtain vendor and other outside resources as required. l'
- 9. Demonstrate the ability of the CECC staff to direct and coordinate the deployment of Radiological Monitoring Teams in'a ;
timely manner, i 1
- 10. Demonstrate the ability to perform dose assessment activities in I a timely manner. '
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- 11. Demonstrate the ability to coordinate TVA dose assessment activities with those conducted by the State, l
'O 12. Demonstrate the ability of the dose assessment team to obtain, '
analyze, and use plant radiological condition information to produce dose assessments and to formulate timely protective action recommendations.
- 13. Demonstrate the ability to inform, update, and coordinate with State Radiological Health personnel regarding meteorological and dose assessment information in a timely manner.
- 14. '
Demonstrate the ability to inform and update RMCC emergency response personnel regarding the status of an emergency condition in a timely manner.
- 15. Demonstrate the ability of the CECC plant assessment team to analyze current plant conditions, identify projected trends rand
, potential consequences.
- 16. Demonstrate a timely and accurate flow of information from the TSC staff t o the CECC assessment teams.
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, a 17. Demonstrate the ability of the Core Damage Assessment Team to '
generate source tem infomation in a timely manner. i
- 18. Demonstrate a timely and ef fective flow of infot1 nation between -!
CECC radiological and plant assessment teams. I
- 19. Dsmonstrate that protective action recommendations are made by use of the Protective Action Guide (PAG) logic diagram.
- 20. Demonstrate the timely updating of CECC status boards, i
- 21. Demonstrate that protective action recommendations are provided .
to the State in a timely and clear manner. !
- 22. Demonstrate that proper security is established for the CECC. i I
- 23. Demonstrate the ability to perform timely assessments of offsite and/or onsite conditions to support the formulation of prot.ective action recommendations. .
- 24. Demonstrate the ability to effectively function in the new CECC.
- 25. Demonstrate the ability to alert Federal and industrial !
emergency contacts in a timely manner. ; E. Environs Assessment Activities O 1. Demonstrate the ability to coordinate Radiological Monitoring i Teams in conjunction with the State at the Radiological ; Monitoring Control Center (RMCC).
- 2. Demonstrate the ability of the Radiological Monitoring Teams to efficiently and effectively utilize their procedures to perform '
dose rate surveys, collection and analysis of radiological samples, and other prescribed radiological monitoring activities. ;
- 3. Demonstrate the ability of the monitoring teams to follow.
contamination control procedures.
- 4. Demonstrate the ability to control the exposure of offsite emergency workers.
- 5. Demonstrate ef fective comand and control of radiological monitoring activities from the plant, RMCC, and/or CECC as '
appropriate.
- 6. Demonstrate the ability to mobilize Division of Field Operations response teams to obtain river water samples and transfer them to a suitable location for analysis.
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- 7. Demonstrate the ability of Field Team members to use effective l
h' dress-out techniques using C-zone clothing under field conditions.
. . , . _ . . - . . _ ~ - - - _.__._s_ __.___._ _ _ ___.____ .____m -___ _.
p l h 6 I l i s A F. Public Information objectives Y~]
- 1. Demonstrate the ability to effectively function in the new Joint l Information Center (J3C) facility, l
2.. Demonstrate the ability to establish and operate a rumor control , center with the citisen's Action Line, J
- 3. Demonstrate the ability to produce a news release from the CECC every two hours.
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- 4. Determine the tine required to functionally staf f- the Public Information component of the CECC. )
g C. Connunications Objectives
- 1. Demonstrate the REP notification procedure throughout the S notification chain, beginning at the SQN Control Room and extending to State and local authorities. J o
- 2. Demonstrate the adequacy of communications links between the plant and the CECC.
- 3. Demonstrate the adequacy of communications links between the CECC and the State EOC.
() 4. Demonstrate the adequacy of communications links between the CECC and the J1C.
- 5. Demonstrate the adequacy of communication links between the CECC and the RMCC.
- 6. Demonstrate the adequacy of radios in the monitoring vans, at Lovell Field (RMCC), at the CECC, and at the SQN TSC.
- 7. Demonstrate the adequacy of Field Operations radio communicetions.
H. Exercise Operation objectives
- 1. Provide specific and measurable objectives for the exercise.
- 2. Improve controller and evaluator performance through an-increased level of training.
- 3. Provide additional information in the scenario package, i.e.,
Public Information messages, meteorological data, and evaluation forms.
- 4. Demonstrate the ability to adequately perform post-exercise critiques to determine any areas requiring additional capability
() improvement.
- 5. All participating personnel will know the date of the exercise but not its starting time or duration.
7 6 .' participating personnel and radiological monitoring vans from
%) Muscle Shoals will be prestaged in Chattanooga.
- 7. participating personnel from Knoxville and equipment will.be prestaged for the JIC.
- 8. Provide training for new CECC personnel
- 1. Drills That Will Be Conducted
- 1. One annual plant radiological monitoring drill.
- 2. One semiannual plant health physics drill.
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- 3. One annual radiochemistry drill.
- 4. One quarterly communications drill.
- 5. One annual plant communications drill.
- 6. One annual offsite environs monitoring drill.
- 7. One semiannual CECC dose assessment drill. .
J. Areas Not to be Demonstrated
; 1. Ingestion pathway activities.
- 2. Onsite and offsite recovery and reentry.
- 3. Fire drill activities.
- 4. Medical drill activities.
0202E C)
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, Rovisisn 5. N3v. 17, 1986-F SEQUOYAH RADIOLOGICAL EMERGENCY PPEPAREDNESS ' (REP) EKERC18E SCENARIO TIMELINE Initial Conditions: Unit 1 in Mode 1-at 100 percent power. (EOL; steady state power for last 60.
L days) Reactor coolant system activity is 0.38 uci/gm Dose Equivalent 1-131. Auxiliary feedwater pump 1A-A-tagged out for i motor bearing replacement. m Steam Generator #3 has a small tube leak of less: 0 than 0.2 spm.
- PZR p0RV block valve FCV-68-332 in closed due to excessive leakage through PCV-68-340.
C2 waterbox is being drained to inspect the tube sheet. Maintenance power supply to the annunciator ! equipment is tagged out to reroute the cables. ! (Panel M-7, A Rack, Breaker 1). ' Unit 2 in Mode 5 for a turbine outage. 0800 High vibrati'on annunciator alarms and loose parts T = + 00:00 hrs mor* tor alarms for reactor coolant pump #3 and. vibration is due to part of the impeller: f breaking off. ASE or STA sent to auxiliary
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instrument room to investigate. 0805 central. Annunciation power to'the main control room is T = + 00:05 hrs lost. An Assistant Shift Engineer-is sent to investigate. ll 0810 The Assistant Shift Engineer reports the T = + 00:10 hrs annunciator inverter output breaker has tripped and will not reset; it appears to be'a problem internal to the breaker. Assistance of Electrical maintenance is requested, i 4 0816 The Shift Engineer should declare an AtERT based
,T = + 00:16 hrs. on the annunciators being out for greater than .l 15 minutes. l l
t: 0845- The electricians confirm the breaker has internal T = 00:45 hrs damage an will have to be replaced. A replacement breaker is not available onsite, but , one is available at Watts Bar. Repair time will be approximately 2 - 3 hours.
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- 0910. .
Operators notice the count rate increasing on
. Te+ 01:10 hrs gross' failed fuel monitor and letdown monitor i
1-RE-90-104. Increase in the reactor coolant system activity.is due to fuel damage from'the - loose part in the reactor coolant system. 0955 Increasing radiation level indicated on the.
- T = 01:55-hrs condenser air exhaust monitor.-' Shift Engineer requests Health Physics to surveyLthe' main steam -
lines in the turbine building and the Chem lab'to. l take samples from the steam generators. _ 1
,= 1000 ~
The turbine building Assistant Unit Operator 5 T = + 02:00 hrs reports a large water leak in the vicinity of the' steam generator: blowdown heat exchanger. Investigation reveals the blowdown line has , broken just down stream of the second stage heat exchanger. Radioactive water is spilled on to-the turbine building floor. 1005 Operators terminate the turbine building leak by i T = + O2:05 hrs closing the steam generator blowdown valves. t However, an undetermined amount of liquid release has taken place via the' turbine building Q drains.
. 1015 .
Health Physics informs the Shift Engineer that T = + O2:15 hrs they can't determine which steam generator has the leak by monitoring the steam lines. 1030 Reactor coolant pump #3. seal #1, fails T = + 02:30 hrs catastrophically. The instrument line=to PI-62-65 ruptures. The auxiliary building Assistant Unit Operator notifies the control room he sees water leaking from the area of the seal return filter. A radiological release to the environs now occurs via the auxiliary building vent. Operators start a power reduction in order to
- remove reactor coolant pump #3 from service.
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- y. Site Emergency Director should declare a SITE AREA EMERGENCY based on a plant transient in progress with the annunciators out of service.
1100 Unit 1 is offline (hot stand by). Reactor T = + 03:00 hrs coolant pump #3 secured. Operators isolate leak g and terminate the release to the aux building.
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~3-11150 It is determined to cool down the reactor coolant
; ,, T.=-+ 03:50 hrs: system to Mode 5 in order to repair the seal on VV reactor coolant pump #3. When the steam dump-control switches are placed to " BYPASS.
INTERLOCK", malfunction occurs in the control circuit'which makes the dumps inoperable. 1200- Operators block the steam dump system and start a T = + 04:00 hrs cooldown using the steam generator power operated relief valves. Annunciator power is restored. Annunciators are: back in service. [* 1218 Chem Lab informs the Shift Engineer that they L T = + 04:18 hrs have determined that the #3 steam generator has the leak. 1222 Shift Engineer orders the operators to isolate IF T = + 04:22 hrs steam generator #3 following procedure. sc 1225 A massive tube rupture occurs in steam generator _ T = + 04: 25 hrs #3. pressure and level rise rapidly as the 7 : reactor coolant system inventory flows into the { ; steam generator. The powerfoperated relief valve opens and sticks in that position resulting in a radiological release to the environs. 1226 Safety injection occurs on' pressurizer low T = + 04:26 hrs pressure. Charging pump flow via the boron injection tank is very low due to blockage by boric acid accumulation at-the boric acid accumulation injection tank discharge. Safety injection pump 1A-A fails to start (electrical
- - fault). Safety injection pump 1B-B shows no flow (stuck check valve).
[5 Turbine driven auxiliary feedwater pump fails to come up to speed due to binding linkage on trip and throttle valve. Auxiliary feedwater pump 1B-B starts and supplies water to steam generator #4. t l l
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s 1230 Site Emergency Director should declare a'CENERAL- I T = + 04: 30 hrs EMERGENCY based on a known loss of coolant accident with failure of emergency core cooling-system to perform leading to' severe core damage. 1235 1 B-B Motor driven auxiliary feedwater pump trips T = + 04:35 hrs (electrical fault).
'1245 Attempts to manually isolate.the steam generator T = + 04:45 hrs power operated relief-valve are unsuccessful.
4 1300' Inadequate core cooling. is experienced' resulting T = + 05:00 hrs in clad damage and increased. radiological releases. Any attempts to' start RCps fail. .. Pressurizer power operated relief' valve 68-334'is "4 opened:to increase depressurization in an attempt .l to reduce the release'and start RHR. injection. g pressurizer power operated relief valve opens only 25 percent and sticks open.- Block. valve ; FCV 68-333'will not close due to a broken wire at ! the fuse block. ; t 1330- Reactor coolant system pressure is reduced to the
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T = + 05:30 hrs point at which residual heat removal begins-to inject and the core is reflooded. However, extensive core damage had occurred due to voiding resulting in the release of large amounts of , radioactivity. ; 1400 The pressurizer power operated relief valve-block-T = + 06:00 hrs valve is repaired and closed. 1545 The pressure within S/G #3 has reduced and the T = + 07i45 hrs power operated relief valve reseats and the release is terminated. -, 1600 Exercise is terminated. T = + 08:00 hrs TCB
- 11-03-86 1482EL i
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,~ J AtL7:45'a.m. (Central Time), initial exercise conditions are established )
as follows: Unit 1 is at 100 percent power with a small~ tube leak'(less ) 2 (,J ' -than Technical' Specification limit) in Steam Generator #3. Auxiliary 1 NE !Feedwater Pump 1A-A is tagged out for motor bearing replacement but it is ) expected that the pump will be restored to operable status within'the ~ . l action statement time requirement. Also, pressurizer PORV Block Valve i FCV-68-332 is isolated due to excessive p0RV seat leakage. The alternate - L power supply.to the annunciator inverter is tagged out for rerouting of j p cables. Unit 2 is in Mode 5. ' At 8:00 a.m., the alarm printer indicates high vibration for Reactor
- Coolant Pump #3. Increased vibration is the result of impeller l o breakage. The debris from the broken impeller'also causes fuel damage which leads to increasing RCS activity.
l l. The nomal supply breaker for annunciator power trips automatically due to internal breaker defects resulti.ng in the loss of all main control r room annunciators. Follow-up investigation indicates that a replacement breaker will have to be obtained from Watts Bar and total out-of-service. time'for the annunciators will be 2 to 3 hours. 1 An , ALERT is declared within 15 minutes of tho detemination that MCR annunciator loss will be for greater than 15 minutes. ALERT declaration l' L is expected to take place between 8:16 and 8:45 a.m. l At 1000 a.m., a rupture.in the steam generator blowdown line upstream of 'i 1-FCV-15-43 causes the spill of radioactive water (due to tube leak) onto Er~ - the turbine building floor. A liquid release to the environs takes place L ;i . : via the. turbine building cump to the discharge canal between approximately 10:00 a.m. and 10:15 a.m. At 10:30 a.m., Reactor Coolant Pump #3 experiences a catastrophic failure ! of its #1 seal. High pressure reactor coolant flows with little j resistance to the seal water return line of the CVCS system. As-the j
. return line is pressurized Relief Valve 62-636 fails to open to relieve the' pressure. As a result, the instrument line to PI-62-65 (located in ;
the Auxiliary Building) becomes overpressurized and ruptures. This event leads to the release of radioactivity to the environs via the Auxiliary j Building Emergency Cas Treatment System and the Stack. A Site Area Emert.ency is declared at approximately 10: 45 a.m. based on a plant transient in progress with the annunciators out'of service. After the RCp seal failure event is diagnosed, a rapid reactor shutdown is initiated. At 11:00 a.m. Unit 1 is taken offline. RCp #3 is secured. Operator actions have also isolated the release pathway from the Reactor Coolant system thus terminating the release averages to the environs. This release is below minimum detectible limits for the environmental monitoring teams.
t. After 11:00 a.m.,-the tube-leak in steam Cenerator #3 worsens. RCS i
-cooldown is initiated. At 12:25 p.m., the tube leak within steam Generator #3 deteriorates into a massive multiple tube rupture. Rapid RCS depressurization is experienced as RCS inventory flows into the steam generator. The power operated relief valve-(PORV) for the steam generator opens in response to the pressure increase to relieve steam to the atmosphere. However, the PORV fails to close when pressure falls below its setpoint (i.e., valve fails in the "open" position). The i pathway for radiological release is now established, As the tube rupture occurs, a safety injection signal is generated. - l.
However, a combination of equipment failures (blockage at the Boron Injection Tank, SI Pump IA-A electrical failure, and 81 Pump IB-B check . valve (failure) prevents the injection of needed SI flow into the core. l The turbine-driven Auxiliary Feedwater Pump also does not come up to speed. Only the motor-driven Auxiliary Feedwater Pump starts up to supply water to Steam Generator #4. i A CENERAL EMERGENCY is declared based on a known loss of coolant accident with- f ailure of emergency core cooling system. With the loss of RCS inventory and reduced heat removal capacity of the steam generators, inadequate core cooling conditions are experienced at . 1:00 p.m. Fuel damage occurs leading to the release of large amounts of radioactivity to the environs. i At 1:30 p.m...RCS pressure has been reduced to the point at which the Residual Heat Removal pumps begin to inject sufficient water for core cooling. Core cooling is established shortly thereafter. However, the release to the environs continues. At 3:45 p.m., the p0RV for Steam Generator #3 reseats and the release in terminated. 1782E TEA:JME 11/12/86 l e. O l
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- FROMt. Control Room Controller LOCATION:~ Main' Control-Room *
-TIME:-
0745' Central- Time (T = + 00:00 hrs) 1 l o ,. , Message: I
,. +
THIS IS A DRILL - DO NOT initiate actions affecting normal plant operations.
- f Initial' Conditions: Unit 1 ..
+
Unit 1.is in Mode-1 at 100% power. (EOL; steady state power for
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,.' last'60 days) l
.*- -RCS activity is'0'38,uci/gm DE I-131 ^
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-AFW Pump 1A-A is tagged'out for motor bearing replacement (It.is -
expected that-the' pump.will be-rest.ored-to operable status 1
-within the LCO action statement period).
S/C #3:has a small tube leak of less than 0.2 spm.-- ' PZR PORV block . valve FCV.-68-332 is closed due to excessive i leakage through PCV-68-340, s C-2 waterbox.is.-being' drained to inspect'the tube sheet.
.- Maintenance power supply to the annunciators is tagged out to
~ reroute the cables (Panel-H-7, A Rack, Breaker 1). ,
i ., -Initial Conditions: Unit 2 , Unit 2 is in Mode 5 for a turbine outage. 8
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LOCATION: Main-Control Room TIME:, LO800 Central Time (T = +-00:00 hrs)~ Message: THIS IS A DRILL DO NOT initiate a:tions affecting normal plant _ operations. 1
- p Loose parts-monitor annunciator alarms on panel 1-M-5.
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?hWv rooms with' portable IRDs.
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- Inst. Dept. should be notified'to perform PMI-52-1 on ige loose partsluonitoring system. 1 --
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- Provide the following data for RCP #3 vibration:
4 ' Pump Vibration = 2.7 mils Motor Vibration = 2.3 mils
- ;' e,7 Check 0064 < 3 milo.
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- Loose parts monitor lit for.S/G #3farea, but no. -
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~ TO : - ShifL Engineer
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' LOCATION: Main Control Room 4- ' TIME: ~0805, Central Time (T = + 00iO5 hrs)
- Message:-
-THIS IS A DRILL DO'NOT initiate actions affecting normal plant operations.
Annunciator power to'the main' control room is lost. O E i
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LOSS'0F CONTROL ROOM ANNUN6IATORS L,. M@F N IMMEDIATE ACTION Fin 4
'.if 1. Operations personnel shall immediately be stationed for increased surveillance of main control board.and common panels instrumentation $@x and indicators as appropriate.
[ 2. An individual will be stationed at the plant computer console to 4 monitor any alarms received on the alarm typewriter.
- D 3. Any plant transients will be stationed at the plant computer console l' to monitor any alarms received on the alarm typewriter.
- 4. Refer to IP-1 for classification of the event and implementation of 4
the REP. 7o s SUBSEOUENT ACTION 1. 69
@l:
Switch the control room annunciator inverter to its alternate power supply (unit 1 panel 1-L-236 and unit 2 panel 2-L-237). If the annunciator system is not restored proceed with step 2. (Ref Dws 45N655-1)
- 2. The shift engineer shall~ evaluate the plant condition and decide upon a prudent course of action using the following guidelines.
- a. The plant should be maintained as is if a stable condition exists - that is, the plant is shutdown or operating at power with no transients in progress.
< b. Any transient such as a plant cooldown, plant heatup, reactor startup, or, power level change should be terminated unless the 4
SRO determines that the completion of the evolution will result in a significantly more stable condition, a T b O C004/1651E
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?S .L ~ MESSAGE NO. 3-Jmj
. TO: . ASE Investigating Annunciator-Power Supply Problem :
,x FROM: Control: Room Controller / LOCATION:1 Annunciator Breaker Panel (Inverter Cabinet, Panel 1-L-236)' TIME:' =0810 Central Time (T - + 00:10 hrs) l L, Message: .- .THIS IS A DRILL : p DO NOT initiate' actions affecting normal plant operations. The inverter output breaker has tripped and will not reset. -It;-appears to be a problem internal to the breaker. (; ;
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[ I _i l: .. l; 5 . - THIS IS A DRILL i C0C4/1651E
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,;SE may;' declare"an EEELwithinL 15 minutes. :
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P;; jh . CONTINGENCY- : f Uxs/ MESSAGE N0; A ] l TO: . Shift Engineer l FROM:- Control Room Controller ) LOCATION: Main Control Room TIME: 0830 Central Time (T - + 00:30 hrs)
~
' Controller Note: Provide this message only-if it.ls apparent the SE-will
' l not declare'an ALERT. J I
THIS IS A DRILL. DO NOT~ initiate actions affecting normal plant operations.. .; The Shift Engineer-should declare an ALERT based on'the loss of all y annunciators for more than 15 minutes and complete: requirements of IP-3 ALERT. g
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MESSAGE NO. 4 n
.[A TO: Electrical Foreman FROM: Local. Controller . . , . . . . .
!, LOCATION:- Main Control Room
-TIME: 0845 Central Time (T - +~00:45 hrs)
Message: m
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.THIS IS A DRILL' DO NOT initiate: actions affecting normal plant operations.
J'
' Inverter, output breaker has internal damage and will require
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ta k^ s 4 THIS IS A ORILL 9-C0C4/1651E
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the maintenance team at'the appropriate times. %! ' u N W $s 0845- ' Electrical Maintenance checks with storeroom for' ' gn replacement breaker. (Drawings and parts list
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g a, ,,, 'L, 4 % t i j ll L ' MESSAGE'NO. 51
' ' 2 TO: AUO'/UO at. Panel 0-M-12.
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,.[ . ' FROM: Control Room Controller.- , ,
y' ' ' LOCATION: Main Control' Room r -.
' TIME:s .0910 Central Time (T --+.01:10 hrs)
. Message:~-
m
'.z's.-
THIS IS A DRILL'
~
-DO NOT-initiate actions affecting. normal plant operations..
The count rate indicated on 1-RE-90-104 is 1 x 105 cpm and is,in Lalarm. n s 4 es .
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.se 3
8 / THIS IS A DRILL o C0C4/1651E
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% j *' LOCATION - Sain Control Room' k.p1h o g
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' TINE:.. .go f(lyk
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. 0910 Central Time,;(T m + 01:10. hrs) 4 M' ;
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'THIS IS A'DRILI,.
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- D0 107 ibitlate" actions affecting normaliplant. operations. '",
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, * ;The-count >rateinNeated-onEl-RE-90-104'is:1x'105 cpm and is_in 4 .Ee i, n ., ' In tats - , , '
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. 1o ,- 4 3 , t S. 6 / y, C w. 4
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sed.by ,j rQw [. - p {F{ LThe: s
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count rate previous on the Gross. Failed. Fuel detector has_increa.
~ reading. .
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- i. .' Expected Actionst , ,.
1 4 o .- + s e i iConsult'AOI'28. J ,1 , m, , _. , L.. 5 g e.,4 G - 'l )' ,
+'
Request!to chemistry for.RCS. sample'and analysiw. a
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Q/ y' ,a ,;. 0 7 - Controller Notet- d
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ijhy" _RCS sample analysis results'are.available from the RCS chemistry data
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section of this manual. ' ,e #e>i i a [ V'alues.for 1-RE-90-104'are provided on the following page. [ t M,f f %.;M~ ~. ' )
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yl { f b( a > t 44 p , m. m' THIS IS A DRILL i
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':" LOCAT10Nii Main ~ Control: Room +
T .I.' of" f _ p i ,, , a f y i; s ; TINE:t 20910 Central Time'(T = + 01:10 hrs),, ^^ 4: ,..s, : . , Ib' _i.,E : k, . i
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THIS IS!A. DRILLi t'
- e
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. 4 a L( I 6 . 1 DD_NOT'iniitiate actions affecting nbraal plant" operations, '
'% -f
- t. , m& : -
t, . V j f ( 3 g L m < s;, y _aw a. m.
.1-RE-90+104 readings's "
L1.[w a u, 1,133_ Count Rate a. . s
- +
{. ' W/p \( ' f. 0910t ,10d,000- y r Dj ( f ^<"y, i '
<< 4 09301 ' 200,0005' <
0 Yd6 7 % L ; 0945' 400,000 ;q FFV 1000
- 10:15
.800,000'
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+a ; y. 1-10:30 - 1,000;000' f: l,y ; r ; 1 ,
lit 00^ 1,000,000 ' e'-
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11:30' 1,000,000.,. 'i G.W M o 1
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MESSAGE NO. 5A ,
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+ . y* jT0: AUO/UO at Panel .0-M-10 :.i
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s
, L lFRON:$ Control Room Controller ,. ,. x v-e .c t r. r ,
, , . i.
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o.&( . . .LLOCATION:1 Mai,n Control Room -
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A
< ; TIME:L.
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. '0910. Central Jime li1 (01:10 hrs) 1 l
. /. 9. ..
[3 ; . .._ ,
/c _ Message:i m '
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, 4 4 - THIS IS A. DRILL '
s t ,o j, : *- p . ,7 J 00'NOTinitiate.actibnsaffectingnormalplantopirations.p* j m i] 4 nx,. .n . ~. w , :q n
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. n a. n C ;The" count' , rate on-the Gross' Failed Fuel" detector has increased ab'ove itss a
g, ., f !
' previous reading. '
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\. MESSAGE NO. 6 ,
's_- ?
?
To: Unit Operator- l FRON: Control Room Controller , LOCATION: Main Control Room ' i TIME: 095$ Centr 41 Time (T = + 01:55 hrs) i Message [ t t THIS IS A DRILL , DO NOT initiate actions affecting normal plant operations, f Condenser air exhaust monitor (RM-90-99 and RM-90-119) reads li3E+3 cpm . and 3,3E+$ epm. [ r
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. TIME: 0955 Central Time (T = + 01:55 hrs) t m) Q :2 , L' f *4i,m w Messaget
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- THIS IS A DRILL
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mM e Condenser air exhaust-monitor trending upscale and has reached the alarm QC . condition. RM-90-99 and RM-90-119 read 3.3t+3 cpm and 3.3E+5 V ' f ,w respectively. A Expected Action: 0 th.1
- Follow requirements of A01-24.
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- SE to notify _TSC ag ,
TSC to request Radcon to survey the main steam lines l' f , and the chem lab to take samples from the S/Gs to ,
^D (C identify the faulted S/C.
s , vn., , , O, Controller Not'et W ' Hp survey results are contained in the "Inplant 4,t Radiation" Section of this manual. (See El. 714 and associated table).
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S/G chemistry results are contained in the " Chemistry" f, > section of this manual.
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l l (/^' \ i MESSACE NO. 7 j T ~
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FROM: AUO in Turbine Bldg. , , LOCATION: Turbine Building TIME: 1000 Central Time (T = + 02:00 hrs) Message l THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. j i There is a large water leak in the area of the second stage steam generator blowdown heat exchanger. There is water everywhere on the .j floor.
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~ !/\ THIS IS A DRILL l
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iLOCATION: Main controllRoom ' O v - - ', ' e. ,
.,ETIMEt! 1000 Central'TimeL(T = + 02:00 hrs)
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5 - e . P " ,, I r%;p .Messaget' ' Controller willl call unit 1 operator,to report this event.- ,
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i < DO NOT'initi:tte hilons affecting' normal plant operations. . '.! 1J t* , 1 u in . . m ,u
.i f' ' Maintenance
; repairing : leak,in. sump discharge line, outlide of turbine; ?I
($:',('M building.- Sust dishcarsing directly into unit 1 discherse canal: ' j Nn o ,, (conduit) .E . There is a~ 1arge water leak in the area of: the second stage N ( t i @d g,' s ateam generator' blowdown heatiexchanger. There'is water everywhere on' the floor.- , N j , y- e
.Egggeted Actions:- ' ' /, ?- ..
S.'% y . AUO notify control room.' ~, -
-* . Take steps to isolate S/G blowdown.
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- Consult Tech. Specs. and-IP-1 to determine J[
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- Control room to notify TSC of this abnormal plant '
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Notify Chemistry /Radeon of liquid releases via turbine
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building sump.
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+ Secure turbine floor sump pumps. !
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,[ + Confirm that radiation monitor reading 0-RE-90-212 is f ' A, elviated and indicates release to environment. !
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Chemistry sample results'for discharge to river are available=in
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1 Survey readings and contamination levels are provided in the; 4 Inplant' Contamination Levels section.:
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i THIS 18 A DRILL- ~i
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T0: Chemistry Technician performing Analysis of Discharge Canal Sample. J FROM: Chem Lab Controller j 1 LOCATION: Chem Lab TIME: l Message I l
.THIS IS A DRILL i
DO NOT initiate actions affecting normal plant operations. ; I l Results of analysis from sample points on attached map are ' Sample point A Sample point B Sample point C (Sampling Time (Sampling Time (Sampling Time j'j - 11:00 - 12:00) 11:30 - 12:30) 11:30 - 12:30) q Isotopgg Concentration Isotopes Concentration Isoto231 . Concentration (pci/1) (pCi/1) (pCi/1)
^
Cs-137 2.3E3 Cs-137 4.12E2 Cs-137 4E+1 . Cs-134 3.5E3 Cs-134 6E2 Cs-134 3.0 E+2~EE+1 Zr-95 1.3E3 Mn-54 2E4 Mn-54 2E3 Cr-51 3.5E4 Co-58 MDA , Mn-54 8.6E4 Co-58 6.6E-2 Co-60 MDA 2n-65
.l 1.3E1 Co-60 2.6E-2 I-131 7E2 *~
Cr-51 7E3 I-133 3E2 Co-58 3.3E-1 1-131 6E3 Xe-133 IE3 Co-60 1.3E-1 I-133 3E3 X-135 1E2 Ke-133 IE4 Kr-88 1El ' I131 3E4 Xe135 IE3 1133 1.5E4 Kr88 2E2 l Xe133 6E4 Xe135 6E3 Kr88 2E3 Cross Cross 4.8 2E4 Gross 4.0E2 Activity 2.4E5 Activity Activity 4.21E3
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THIS IS A DRILL
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L0 CATION: Chemistry Lab TIME: 10:00 to 10:30 Central .'; Controller Note: Provide the following analysis results from turbine I building sump if performed by Chemistry. I t t f
-t THIS IS A DRILL .
DO NOT initiate actions affecting normal plant operctions. i Results of analysis from turbine building sumpt . Samplins time 10:00 - 10:30 D i ( Isotypeg Concentration ()Jci[cc) Cs-137 9.7E-4 Cs-134 1.5E-3 i Zr-95 5.6E-6 ' Co-58 1.4E-7 ', Co-60 5.5E-8 Mn-54 3.6E-2 I Cr-51 2E-2 I I-131 2E-2 *- I-133 1.5E-2 Xe-131 ' 6E-2 - 4 Xe-135 6E-3 Kr-88 2E-3 Cross Activity 1.62E-1 ! THIS IS A DRILL 1 COC4/1651E
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'( 't MESSAGE NO. 7X ,
v .- TO: Shift Engineer , FROM:- Radeon Technician ~ '
' LOCATION: Main Control Room TIME: 1015 Central Time (T = + 02:15 hrs) i n Message: Phone call to be made by control room controller. [
i THIS IS A DRILL DO NOT initiata actions affecting normal plant operations. The leaking steam generator could not be determined af ter surveying the ' main steam lines in the Turbine Bldg. i Dose rates on all steam lines are approximately the same.
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'1 imain' steam lines in,the TURBINE Bldg.' ,
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c . , Lh-:> SE notify TSC. p N l ',I' -. , 4
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,' s SE may request Radcon to'try and sample.the steam- <
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% lines inside the' valve vaults. After time delay for trip'out'to valve vault, theLSE should be informed
'en that entry into the vaults could not be made. The g y-l ', ~ , : ' ' entry doors could not be opened., .
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s FROM: Control Room Controller l J LOCATION: Main Control Room J i
', TIME: 1030 Central Time (T = + 02:30 hrs)
Nessage: .
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-1 RCP #3 seal return flow indication suddenly Boos full scale high. )
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'1 THIS IS A DRILL I
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4, ,y+ , ; ' ml i.s > FROM: ' 4' W %, W,g=.Cw - a....2 . . , J, 4 p;;. 4
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DO .NOTiinitiate' actions af factitis' normal} plant' operations ~. . y s en m , u , , j,fa, , ;:1. ,
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. .lf " cRCP #3:seallreturn flow indication suddenly?goes. full scale high.'l(This s . 4 t . f, . hN.r.,, m 1v c , is due to:a fallure-of the #loseal.) The instrument line to PI-62-65L ruptures. 9 f.N , _ p - 1
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- Operators r_efer-to AOI-23. '
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-Power reduction should be started-to remove react'or; i 4Qm..--w : coolant pump #3 from service.1 Tt
, :,. a ..
.40 e m
g p,., u .. 's Controller Notes: ' (.' 7 af3' ' 3. ( 'CiN
- Provide'the following data if asked by.UO!"
n h , ,' Seal. Injection Water Temp @l10' F # T ["1 Seal Injection Flowrate '- 8 gpm to each RCP. f, @w * ' , -T,
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N'r ' LOCATION:l I Auxiliary l Building.- ! g ,; .w.- q .. m
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. . j .1 y % 'ef
. .(' E a W ..; Water is sprayingIfrom the' area'of theLseal' return lf11ter aresi(appears:
y, lto,be al rupture cfotho' sensing line to PI-62-65) Land' local radiation? *
+' b_
guy ; : _ monitors are alarming.- ' ' '
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MESSAGE NO i9' ' d > y
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" f Tot l Local Controller in Auxiliary Building , .g .. . A s. + 7 +
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,- . ',FRON: - . Y, .
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4 1,.
' C<LOCATIONt: , Auxiliary Building
+
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A R, :k : TIMEh- ' 1035 Central TimeJ(T m'+ . 02:35 hrs); 4 a t: t ; ,
+
,y
'I
, , i Nessages '
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- ,. THIS IS A DRILL- .
L u> 1s
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ELE 9,1 in)tiate' actions affocting normal plant operations. I l A.3 ) .
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+E '
' Water is spraying from the area of the seal return filter area-(appears a' ' [,
;to be ajrupturetof.the sensing'line.to PI-62-65)-and local radiation- >"
d' monitors are alarming.'-
>lt ,
7 , 4 m K4 .
~
5 ' As t . l Expected Actions:
,3 , .g .l , ; 4 1 % .' '
Notify control' room.- J $ ., 7
, 4 ,s F 6Uf
>s Control.. room attempts to isolate seal return withi
- J FCV-62-63.:
w Wb MS
+-
. Control room' attempts to manually isolate seal return ~ 7; <
..m r Iline a'nd backflow.from VCT.
lf -
- Control room status update ~to TSC p.A ' ;3 MY <
- TSC status update to CECC c
,11.
.Q 4
+
+
Controller Note:~ n im - '
+
Valve 1-62-653 must be closed manually in order to W4 ...' stop leak. Manual valve to isolate backflow from VCT [ g' . will not completely isolate. g+ + Auxiliary Building radiation readings and y- contamination levels are provided in the Inplant i
- a. Radiation and Contamination sections of this manual.
g'~ , A
.%,V ,
THIS IS A DRILL y
- q. , 4 i.
kll1, &. & COC4/1651E <
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ti% P l [ \ MESSAGE NO. 10
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TO: Site Emerghncy Director FRON: TSC Controller LOCATION: Technical Support Center TIME: 1030 Central Time (T = + 02:30 hrs) Message provide this message only if r.o action is being planned or initiated to shut down the unit. (A01-23 will require RCP with failed seal to be stopped within 30 minutes.) THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. Based on recommendations from the Operations Supervisor, you order the unit to be shut down in order to repair RCP #3.
.f l
\
i ; i THIS IS A DRILL 7s
\
x 1 COC4/1651E i 1
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, MESSAGE NO. 10-
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1 pg , y bq , 4 ~s
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M. .iT02
,4 'TSC Controller 1% < '
N y s u. a L_ e
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< gy (LOCATION 1 TechnicaliSupport Centera y
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..TIMEt i . 1030 Central'. Time'(T i + 02:30 hrs)-
y:,g ' ' 1 - ' g , ;;j <- ,
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THIS IS A DRILL
+ ,
1
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]29,_]!QI initiate actions affecting normal plant ' operations. '
1
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y : F,, ' v .y " 'Oi;' ' ' k ./ ef 'g .s g , s i 4'. , . .- Mil {,w
" 1 Based on recommendations:from the operations supervisor, you. order the. 'h' , (
'f' < unit (to be' shut'down in order toirepair RCP.#3 ' j ,
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' Expect'ed Actions s y,.-
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~A SITE AREA ENERGENCY should be declared based on;a-transient in progress with the annunciators"outtof:
w, ' h+O , , ,
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[[ylb,9 h(~$ y;j . - *. Follow requirements of.IP-4.' ' '
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+
RCP#3'shouldbestopped'withinapproximately -
*lj.i
.l g34 '30; minutes after seal failure per requirements ~in
- W,s j AOI -23.
.1 p%Q > '
.y[ -
% ,' ". Y
- Contlol room to commence unit shutdown in accordance i p' f -
with A01-32.
- l ws , i
<c Lop. ' ' .+j controller Note:
4 l ,; a.
/,, '
SAE declaretion is subject to interpretation of ( M,, " transient". With RCP seal failure and a release in 'f M+ progress, the definition for " transient" should be 1 g~Q (m * ' ", satisfied. However, it may take additional *
-discussions by TSC to arrive at that conclusion. '
y Controller needs to monitor this closely and use ' g/d!*- Contingency Message B if required. Ld y
,Ma !
67 1i
.s THIS IS A DRILL ,
gEy a COC4/1651E mm w r r
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.( NESSAGE NO. 11 l 1:
'3 1
[. ' \s- l h T0: Unit Operator l j i FRON:
- Control Room Controller .. . ~. ..- --
i l
> LOCATION: Main Control Room 1
TINE: 1040 Central Time (T = + O2:40 hrs) 1 Messages j j I I THIS IS A DRILL ! DO WOT initiate actions affecting normal-plant operations. i I Indications show that an Auxiliary Building Isolation has occurred. I l
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/ THIS IS A DRILL 1
C004/1651E 1 l
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TIME': t 1040~ Central-Time (T =L+ 02:40 hrs)
+
- 1 g'
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hgg . \j3 y (Controller Note:i 5 4 ", 31 34j
+
U: @(:ii ~M
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> [ ' fi'h i i n' , ;: 'f1/ a.nNi. .
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$N h I t
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('(pr a 8 r f; [1j?'.ur, , ELEqI .initlate ' actioris ; af fecting normal; plant operations.-
- N
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%l Indications:show'that'an. Auxiliary Building: Isolation'has occurred. 7, gh , 0. 9 .
.,: r s ip b4A ,gf{
,9 , . -. .
4 ;j JIl M pu . Expected Actions: -
, a 4
+ ,'
a; pl, e,, - Evacuation of the_ Auxiliary Building via,c ' announcement a
'j
% lf ;
- 2
.over the plant P.AE if the site emergency. siren has'notL
~ .
f'0 6 . been-sounded.
.j j m - 5
-+1 M, ~.
6 .ue-
~
Notify Radeon of;a reloase into the Auxiliary ' V-
-o s Sq
,' , A , Building. +
. , E:
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'C' N
,i t O y 9
THIS IS A DRILL l-
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s t n; ' AA , . o - C004/1651E : y,wLy,.- , s
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l t J
, ~' s' CONTINGENCY i s i
/
\~ / MESSAGE NO. 8 l TO:' Site Emergency _ Director !
1 FROM:- TSC' Controller , s LOCATION: Technical Support Center
-i i
TIME: 1100 Central Time (T = + 03:00 hrs) .j Message: i l
, THIS IS A DRILL l 1
DO NOT initiate actions affecting normal plant operations. !
)
1 The Site Emergency Director should have declared a SITE AREA EMERGENCY by this time. ,
/
( _ o l l 1 1 1
~
I i THIS IS A DRILL j f ^' N
.i COC4/1651E ! , i
i
~ .!
MESSAGE NO, 12 s '.i/ [ w TO: Shift Engineer FRON: Control. Room Controller , ,, , , ,. . l LOCATION: Control Room i TIME: 1100 Central Time (T = + 03:00 hrs) g Controller Note Provide this message only if SE wants to cool down ; I immediately. t i THIS IS A DRILL i DO NOT, initiate actions affecting normal plant operations, l With unit off line, preparations for unit cooldown may be initiated. :
. , - Reactor is shutdown with all cont'rol and shutdown rods fully inserted,
) but the reactor trip breakers are still closed. '
p . (V ( .- t I t i
)
I l l [ l' l . L ; a > l . I , t 1 l .. g~s THIS IS A DRILL l t [ : \. c C004/1651E 1 _. . . . - , . _ . - , ~. _ . , . , .,
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\;, CORTRQLLER WOTE * %.n/ L \ ':t x i :,
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. . utssAGE WO. 12 q.,, , ~\,.
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p . .-Contro'l Room Controller: " 4' W i
' YRONO '
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+ ,
1 4
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G ,
..i' : LOCATION: Con' trol Room . -
b en i. o ,
' TINE:i s1100' Central' Time: (T = + 03:00 hrs)1 '
.s. . . N g ( e r, , I y' - Message = ' l
~
p ;g' _ , d ,&i ,1 '
,g ;,, !! 's Q l iq .,;
5 i s Q.
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3~ s ,- -TH18 IS A DRILL c - w(. n x{
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a. s ,T{s* "
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g D0. MOT initiate actions affecting norma,l' plant operations. gf.le{_% i ^ rg. . ,'e _
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W ,3 n' . + l ': e i N! . - Expectod_. Actions:L 3> s . $f N , , 1 3y k..
+
Initiate- unit cooldown according' to plant 00Is af ter , h s N- '-
! consulting.with TSC.
s
' I 4 '
j . g
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3 E +y Co'nt' roller Motot-m ..a . s ,c . 3
/E- , .*- Reactor. trip breakers will remain. closed to facilitate.
y;:
-use of main feedwater to maintain' steam generator)S
J.' levels = .
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+
I
- q ' '
y THIS IS A DRILL
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