ML060370318
| ML060370318 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 11/07/2005 |
| From: | Walton R K NRC/RGN-III/DRS/OLB |
| To: | |
| References | |
| 50-266/05-301, 50-301/05-301 50-266/05-301, 50-301/05-301 | |
| Download: ML060370318 (20) | |
Text
1. 2005 ILT SRO 1 Consider the following Unit 1 conditions:
- A plant casualty occurred and the crew is preparing to implement Bleed and Feed steps of CSP-H.1, Response to Loss of Secondary Heat Sink. - A Pressurizer Safety valve has opened and will not reseat. - After several minutes in this condition, the following plant parameters are noted:- RCPs are OFF. - Core Exit Thermocouples read 710ºF and rising. - Subcooling reads minus 50ºF and degrading. - Reactor Vessel Narrow Range leve l is 23 Feet and lowering.
Based on these plant conditions, what is the appropriate procedure flowpath?
A. Continue in CSP-H.1 until completed, if conditions list ed persist, transition to CSP-C.2, Response to Degraded Core Cool ing, upon completion of CSP-H.1.
B. Continue in CSP-H.1 until completed, if conditions list ed persist, transition to CSP-C.1, Response to Inadequate Core Cool ing, upon completion of CSP-H.1.
C. Transition immediately to CSP-C.2, Response to Degraded Core Cooling.
D. Transition immediately to CSP-C.1, Response to Inadequate Core Cooling.
- Unit 1 was at 100% reactor power wit h all control systems in automatic. - A 1" RCS pipe has been sheared off inside Containment.
ALARMS PROCEDURAL FLOWPATH
- 4. Charging Pump Speed Control (Procedure Titles: AOP-1A, Reactor Coolant Leak; AOP-17A, Rapid Power Reduction; OP-3C, Hot Standby to Cold Shutdown; EOP-0, Reactor Trip or Safety Injection; EOP-1, Loss of Reactor or Secondary Coolant; EOP-1.2, Sma ll Break LOCA Cooldown and Depressurization)
Given the above lists of alarms and procedure flowpaths, select which alarms would be EXPECTED with these conditions and the EXPECTED procedural flowpath.
EXPECTED ALARMS PROCEDURAL FLOWPATH A. 4 A B. 1, 4 A C. 1, 2, 4 B D. 1, 2, 3, 4 B
- At 0600, the following conditions are noted: - Unit 1 is shutdown, preparing for refueling. - Initial RCS temperature was 175ºF. - Initial RCS pressure was 100 PSIG. - Normal Cooldown Alignments. - Subsequently, RHR is lost and the RCS heats up at 4ºF/minute.
Which of the following correctly identif ies the initial MODE and MODE at 0640?
Initial MODE MODE at 0640 A. MODE 6 MODE 5 B. MODE 5 MODE 4 C. MODE 6 MODE 3 D. MODE 5 MODE 3
- A Unit 1 Reactor Trip and Safety Injection has occurred. - EOP-0, Reactor Trip or Safety Inje ction, immediate actions have just been completed, EOP-0 Foldout page items are currently being addressed. - 'A' SG level is 67% and ri sing in an uncontrolled manner. - 'A' SG pressure is 1025 PSIG and rising in an uncontrolled manner. - Pressurizer level is 7% and lowering. - Containment pressure is 1 PSIG.
Which of the following actions should the OS direct at this time?
A. Direct CO to isolate feed flow to the 'A' SG since its level is rising in an uncontrolled manner. B. Direct RP Tech to immediately conduct radi ation survey of 'A' SG. If 'A' SG has verified abnormal radiation, imm ediately transition to EOP-3.
C. Direct CO to isolate flow from the 'A' SG by closing 'A' MSIV and securing blowdown from 'A' SG.
D. Immediately transition to EOP-3, Steam Generat or Tube Rupture, si nce 'A' SG level is rising in an uncontrolled manner.
- Unit 1 was at 100% reactor power. - Both Main Feed Water pumps have tripped. - Reactor Trip breakers did NOT open. - Efforts to de-energize 1B-01 have failed. - Reactor power is 17% and lowering. - No AFW pumps are running. - The CO is performing Imm ediate Actions at Step 1 of EOP-0, Reactor Trip or Safety Injection.
What procedure should be entered OR action directed NEXT and why?
A. Transition to CSP-S.1, Response to Nuclear Power Generation/ATWS, to insert negative reactivity from control rods and verify turbine trip.
B. Manually start AFW pump(s) to establish
>400 GPM AFW flow to protect the core from a Loss of Feedwater ATWS.
C. Continue with Step 2 of EOP-0 to verify turbine trip and conserve remaining SG inventory.
D. Dispatch operator to locally open R eactor Trip and Bypass breakers in the Rod Drive MG set room to reduce core power.
- Unit 1 was at 100% reactor power. - Unit 1 then experienced a Safety Injection due to a Small Break LOCA. - All components actuated normally. - Subsequently, a fault results in a loss of electrical panel D-11.
Which of the following describes the impact the loss of control power has on the AC electrical system? What pr ocedure should the OS implement to mitigate the electrical fault? A. The G01 EDG output break er, 1P-10A RHR pump and 1P
-15A SI pump breakers open, none of these breakers can be operated remotely. AO P-18, Electrical System Malfunction, should be implemented.
B. The G01 EDG output breaker remain s open but can be closed remotely, if necessary. 1P-10A RHR pump and 1P-15A SI pump breakers remain closed and may be opened remotely. AOP-18, Electrical System Malfunction, should be implemented.
C. The G01 EDG output breaker remains closed. 1P-10A RHR pump and 1P-15A SI pump breakers open, none of these breakers can be operated remotely. AOP-0.0, Vital DC System Malfuncti on, should be implemented.
D. The G01 EDG output breaker remains open without capability to close remotely.
1P-10A RHR pump and 1P-15A SI pump br eakers remain closed and cannot be operated remotely. AOP-0.0, Vital DC Syst em Malfunction, should be implemented.
- 7. 2005 ILT SRO 7 Normal Re adings 1 2 3 4 5 6 7 8 91 01 11 21 3 A B 5 7 7 599 C 5 7 4 5 9 6 5 95 565 D 561 58 7 6 00 56 7 E 5 95 59 6 F 59 7 G 5 5 3 594 594 59 1 H 593 58 5 597 558 I 595 59 3 J 5 7 9 5 9 3 5 88 595 K 5 6 2 573 L 596 M5 5 5 Current Readings 1 2 3 4 5 6 7 8 91 01 11 21 3 A B 5 7 9 603 C 5 7 5 6 0 0 5 97 563 D 562 59 1 6 04 56 4 E 59 9 5 92 F 59 7 G 5 5 5 602 595 57 3 H 588 57 3 582 551 I 599 58 6 J 58 4 5 90 5 8 3 592 K 5 6 3 570 L 598 M5 5 4 Unit 1 is operating at 75%
power. CO reports suspected dropped rod. Considering the provided Core Exit TC map, which rod has dropped?
A. F-1 2 B. H-1 2 C. J-1 0 D. H-8
- A toxic gas release has rendered the Control Room uninhabitable. - AOP-10, Control Ro om Inaccessibility, is in progress. - Letdown has been isolated and cannot be re-established. - The Unit 1 charging pump operator reports that Pres surizer level is 48% and rising. - The Control Room remains uninhabitable.
Which of the following represents the direct ion that the DOS shoul d provide to the Unit 1 Charging pump operator regarding Pressurizer level?
A. Operate the Charging pum ps as necessary. Use OI-15, Charging Pump Local Control Station Operation, to control Charging parameters.
B. Initiate Excess Letdown flow fr om Unit 1 local control panels.
C. Isolate instrument air to the running Charging pumps to lower their speed to minimum. D. Locally operate the Charging pump power supply transfer switches as necessary to start and stop Charging pumps.
- 9. 2005 ILT SRO 9 Which of the following is the Technical Specification Action Condit ion entry requirement for Technical Specification 3.4.16, RCS Specific Activity and what is the basis for the limit? A. >1.0 µCi/gm Dose Equivalent Iodine, limits off-site radiat ion dose to a small fraction of 10CFR100 limits during a LOCA OUTSIDE CONTAINMENT.
B. >1.0 µCi/gm Dose Equivalent Iodine, limits off-site radiat ion dose to a small fraction of 10CFR100 limits during a SG TUBE RUPTURE.
C. >0.8 µCi/gm Dose Equivalent Iodine, limits off-site radiat ion dose to a small fraction of 10CFR100 limits during a LOCA OUTSIDE CONTAINMENT.
D. >0.8 µCi/gm Dose Equivalent Iodine, limits off-site radiat ion dose to a small fraction of 10CFR100 limits during a SG TUBE RUPTURE.
- A Steam Line Break has occurred in Unit 1 Containment. The crew is responding per the EOP set. - You have assigned performance of EOP-0, Attachment A, Automatic Action Verification, to the Unit 1 BOP while you and CO1 continue in the EOP set. - Transition to EOP-2, Faulted Steam Generator Isolati on, is made while the Unit 1 BOP is still performing Attachment A. - Shortly after announcing the transiti on to EOP-2, the STA informs you that the entry conditions for C SP-P.1, Response to Imminent Pressurized Thermal Shock Conditions, are met.
Which of the following correctly describes your responsibilities for addressing these conditions?
A. Transition immediately to CSP-P.1 and perform actions as directed. The Red Path Condition has priority over EOP actions.
B. Return to EOP-0 at the EOP-2 transition step. Transit ion out of EOP-0, Reactor Trip or Safety Injection, should NOT be made until Attachment A is complete.
C. Acknowledge report from the STA but do NOT take any CSP-P.1 actions until the completion of EO P-0, Attachment A.
D. Complete EOP-2 Actions. CSP-P.1 entry will be addressed upon the transition to EOP-1, Loss of Reactor or Secondary Coolant.
- Unit 1 is at 95% reactor power, with a Containment inspection in progress. - Unit 2 has experienced a Reactor Trip and Safety Injection due to a failed open Main Steam Safety Valve on 'B' Steam Generator. - The Unit 1 BOP performing Attachment A of EOP-0, Reactor Trip or Safety Injection, reports the following conditions: - Due to electrical malfunctions, four required SW pumps did NOT start. - 2SW-2907 and 2908, SW to Unit 2 cont ainment cooler emergency outlet valves are OPEN. - 1SW-2907 and 2908, SW to Unit 1 c ontainment cooler emergency outlet valves are OPEN. - Service Water to Containment flow i ndicators for both units indicate 750 GPM. - C01 C 2-9, "Unit 2 Containment Recirc Coolers Water Flow Low" Alarm is LIT. - C01 B 2-3, "Unit 1 Containment Recirc Coolers Water Flow Low" Alarm is LIT. A re these Alarms consistent with plant conditions? What action, if any, should the SRO take regarding Containment Cooling? (Assume actions to restore power are already underway.)
A. The Alarms are consistent with plant conditions. Enter AOP-9A, Service Water Malfunction, and close UNIT 1 SW-2907/2908 va lves to maximize flow to Unit 2 Containment.
B. The Alarms are consistent with plant conditions. Enter AOP-9A and close BOTH UNITS' SW-2907/2908 valves, since SW flow would not be required to either Unit's Containment for this accident.
C. The Alarms are NOT consistent with plant conditions, Unit 1 Flow Low alarm should NOT be alarming. Ensure BOP closes UNIT 1 SW-2907/2908 valves during the performance of EOP-0, Reactor Trip or Safety Injection, Attachment A, to maximize flow to Unit 2 Containment.
D. The Alarms are NOT consistent with plant conditions, Unit 1 Flow Low alarm should NOT be alarming. Ensure BOP closes BOTH UNITS' SW-2907/
2908 valves during the performance of EOP-0, Attachment A, si nce flow would not be required to either Unit's Containment for this accident.
Low Head Injection, the SI test line is isolated.
Which of the following correctly describes the actions which will be directed IAW EOP-1.3 to protect the Containment Spray pumps and what is t he reason for these actions?
A. Direct the CO to secure the CS system prior to isolating t he SI test line. SI test line is isolated to prevent backflow of sump recirc water into the CS system.
B. Direct the CO to verify CS pump discharge va lves open prior to isolating the SI test line. SI test line is isolated to prevent radioactive water from being injected into the RWST during sump recirc.
C. Direct the CO to align the CS system to RHR Pump discharge prior to isolating the SI Test Line. SI test line is isolated to ensure maximum sump recirc flow.
D. Direct the CO to maintain SI Pu mp discharge valves open to prevent overpressurization of the CS system while SI test line is isolated. SI test line is isolated to prevent lifting of relief valves in the CS system while on sump recirc.
- Unit is at 48% Chemistry Hold following a ref ueling startup. - 'A' MFP, 'A' Condensate pump and
'A' HDT pump are in service. - CAP initiated by I&C states that a review of completed outage work orders indicates the following: - 'A' MFRV SI Vent Solenoid Circui t collected data was unsatisfactory. - 'A' HDT pump CPCI Trip Circuit collected data was unsatisfactory. - 'B' Condensate Pump CPCI Trip Cir cuit collected data was unsatisfactory.
Using the provided reference, which of the fo llowing is a complete list of actions to be entered with respect to LCO 3.7.3?
A. TSAC 3.7.3.A for MFRV Solenoid TSAC 3.7.3.B for 'A' HDT pump B. TSAC 3.7.3.A for MFRV Solenoid TSAC 3.7.3.B for 'A' HDT pump TSAC 3.7.3.C C. TSAC 3.7.3.A for MFRV Solenoid TSAC 3.7.3.B for 'A' HDT pump TSAC 3.7.3.B for 'B' Condensate pump TSAC 3.7.3.C D. TSAC 3.7.3.A for MFRV Solenoid TSAC 3.7.3.B for 'A' HDT pump TSAC 3.7.3.B for 'B' Condensate pump TSAC 3.7.3.C LCO 3.0.3
- Testing of 1P-29, Unit 1 TDAFW pump, was completed on the previous shift, using IT-8A, Cold Start of TDAFW Pump and Valve Test (Quarterly) Unit 1. - During your shift, the Unit 1 Turbine Ha ll AO is performing PC-8 Pt. 2, Monthly AFW Pump Discharge Piping Temperatur e Checks, and identifies that the piping temperature between 1AF-108, 1P-29 Discharge check valve , and 1P-29 is at 200ºF. - Pump bearing temperatures are 150ºF and steam is issuing from the pump seals. Which of the following identifies the most lik ely cause of the high temperature condition and what actions, if any, need to be taken?
A. Elevated temperatures ar e due to a loss of forward fl ow from 1P-29 that caused steam binding of the TDAFW pump during IT-8A. Utilize OI-62B, Turbine Driven Auxiliary Feedwater system, to correct the problem.
B. Elevated temperatures are due to a malfunction of turbine seals and subsequent steam leakage into the pump casing. Utilize AOP-2A, Secondary Coolant Leak, to correct condition.
C. Elevated temperatures are due to AFW check valve leakage. Utilize AOP-2C, Auxiliary Feed Pump Steam Binding or Overheating.
D. Elevated temperatures ar e expected for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> fo llowing a forward flow test of TDAFW pump . PC-8 Pt. 2 should be re-performed after AFW lines have cooled.
- Z-31, Instrument Air Drye r, Left Tower desiccant rete ntion element has failed. - Failure has resulted in partial and slo wly worsening blockage of the Z-31 After Filter. - Assume normal Instrument Air (IA) System alignment.
Using the provided reference, which of t he following correctly states the expected response of the Instrument Air System and the direction provi ded to the operators?
A. North and South IA header pressures as indicated on C01 remains unchanged.
Direct response to the failure IAW Unit 2 TH Logs Special Instructions which will direct isolation of the inlet to the Z-31 Air Dryer and blowdown of the clogged filter.
B. North IA header pressure as indicated on C01 will lower, South IA header pressure will remain unchanged. Direct response to the failure IAW ARP C01 D 1-2, Instrument Air Header Pressu re Low alarm, and direct t he AO to open IA-3094-S, IA Dryer Bypass valve, to bypass Z-31 Air Dryer.
C. North and South IA pressure will lower due to the high filter DP. PCV-3079, Service Air/Instrument Air Cross-connect valve will open to restore IA header pressure.
Direct operators to respond IAW AOP-5B, Loss of Instrument Air.
D. North and South IA header pressures as indicated on C01 will rise. The running IA compressor will trip on high pressure. Direc t the operators to respond to the failure IAW ARP C01 D 2-2, Inst Air Running Comp ressor Trip, to start the standby IA compressor.
- 16. 2005 ILT SRO 16 Technical Specification 3.7.
10, Fuel Storage Pool Water Level, requires that
> 23 feet of water be maintained above the fuel in the storage racks during the movement of irradiated fuel.
What is the basis for this requirement?
A. To ensure sufficient water volume for fuel cooling.
B. To ensure sufficient water depth for iodine scrubbing.
C. To ensure sufficient volume of borated water to prevent criticality.
D. To ensure sufficient time is available to provide makeup to the pool in case of a system leak.
- 17. 2005 ILT SRO 17 The Explosive Gas Monitoring Program (TRM 4.11) ensures that an explosive gas mixture is NOT present in the On-Service Waste Gas Decay Tank.
Which of the following correctly states the ac ceptance criteria for explosive gas mixture and corrective actions/compensatory measures?
A. < 4% Oxygen. If greater than 4%, addition of waste gas may continue to the tank for up to 14 days, provided grab samples are taken and analyzed daily during normal power operation.
B. < 10% Oxygen. If greater than 10%, addi tion of waste gas will be immediately suspended and the tank must be immediatel y discharged to minimize the potential for explosion.
C. < 4% Oxygen. If greater than 4%, addi tion of waste gas will be immediately suspended and the oxygen concentration r educed to < 4% as soon as possible.
D. <10% Oxygen. If greater than 10%, addition of waste gas may continue for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> provided grab samples are taken and analyzed every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during normal power operation.
- Both units are operating at 100% reactor power. - Unit 1 has just tripped due to a lo ckout on 1X-03, Hig h Voltage Station transformer, combined with a failure of the Fast Bus Transfer on the 13.8 kV system.
Which one of the following statem ents best describes the status of the circulating water system and procedure(s) that will mitigate circumstances related to the affected unit, if any? (Note: EOP-0 is "Reactor Trip or Safety In jection" and AOP-5A is "Loss of Condenser Vacuum".)
A. Unit 1 Circulating Water pumps trip and their associated discharge valves close; EOP-0 and AOP-5A are ent ered for Unit 1 only.
B. Unit 2 Circulating Water pumps trip, Unit 2 CW discharge valves remain open; EOP-0 is entered for Units 1 and 2, and AOP-5A for Unit 2.
C. There is no effect on any running Circula ting Water pump or discharge valve since these are still powered via Low Voltage Station Transformer 1X04; EOP-0 is entered on Unit 1 only.
D. Unit 1 Circulating Water pumps trip and their associated discharge valves remain open; EOP-0 and AOP-5A are entered for Unit 1 only.
- Unit 1 is in day 10 of a refueling outage. - Unlatching of rods is in progress. - Reactor Coolant System tem perature (RHR inlet) is 87ºF. - The running RHR pump trips. - The other RHR pump is tagged out for mino r maintenance, but can be restored if needed.
Using the provided reference, which of the following indicate s the minimum time (number of hours) at whic h RCS boiling will occur?
A. 15.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> B. 16.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> C. 18.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> D. 21.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />
- 20. 2005 ILT SRO 20 Both Units are at 100% reactor power. The cr ew is working regular 12-hour shifts. The time is 0015.
AO Staffing is as follows:
- Unit 1 Turbine Hall (TH) - Fully Qualified AO. - Unit 2 Turbine Hall (TH) - Fully Qualified AO. - PAB - Fully Qualified AO. - Water Treatment (WT) - AO Qua lified WT and Fire Brigade only. - AO Trainee - Fire Brigade qualified only, standing WT Under Instruction.
The Unit 1 TH Operator must leave immediately for a family emergency.
Which of the following correctly descri bes the actions that must be taken?
A. The Unit 2 TH operator will assume the Unit 1 TH responsibilities, AO Trainee will assume fire brigade duties. Staffing may be ma intained in this configuration up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. B. Immediately begin callout to replace the Unit 1 TH operator, t he operator must be replaced within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
C. Third or Fourth License may be utilized to cover the Unit 1 TH watchstation for the remainder of the shift, with AO Tr ainee assuming Fire Brigade Duties.
D. Notify duty and call personnel while attemp ting to replace Unit 1 TH watch. STA must remain in the Unit 1 TH watchsta tion until suitable replac ement has reported.
- 21. 2005 ILT SRO 21 Assume the core loading pattern will be changed during the next refueling outage such that more new fuel assemblies are placed toward the CENTER of the core and more "twice-burned" assemblies are loaded toward the PERIPHERY. What effect would this loading pattern have on the unit?
A. The expected full power loop delta-T val ue should be significantly LOWER for this fuel cycle when compared to the va lue from the previous cycle.
B. The expected full power loop delta-T value should be significantly HIGHER for this fuel cycle when compared to the va lue from the previous cycle.
C. IF Power Range NI channel gains are NOT changed during the refueling outage, the Power Range NI readings would be significantly BELOW actual power level when first calorimetric is performed after the outage.
D. IF Power Range NI channel gains are NOT changed during the refueling outage, the Power Range NI readings would be sign ificantly ABOVE ac tual power level when first calorimetric is performed after the outage.
- 22. 2005 ILT SRO 22 When a test or experiment is proposed which may affect the PBNP License or Technical Specifications, the activity is scr utinized using a multi-phase process.
Which part of the process determines if PBNP must obtain NRC approval PRIOR to carrying out the test or experiment?
A. 10CFR50.59 Pre-Screening B. 10CFR50.59 Screening C. 10CFR50.59 Evaluation D. 10CFR50.59 Review
- Waste Distillate Tank 'A' is being discharged overboard via Unit 2 service water. - 2RE-229, Unit 2 SW Overboard m onitor, momentarily goes into an ALERT status, then clears. - RE-223, Waste Distillate Tank Overboard monitor, is normal and is well below setpoint.
Which of the following describes how the system will respond and what actions are now required?
A. Waste Distillate Overboard valve, BE-FCV-LW-15, will automatically close. The alert condition on 2RE-229 will need to be evaluated and a new Liquid Waste Discharge Permit MUST be completed prior to continuing the discharge.
B. Waste Distillate Overboard valve, BE-FCV-LW-15, will automat ically close.
Discharge may continue using existing Liqu id Waste Discharge Permit following the performance of RAM 3.1.1, Restarting a Liquid Batch Release.
C. Discharge will need to be manually secured while the discharge path is switched to Unit 1 SW Overboard, then discharge may be recommenced. Document change of SW alignment on the existing Liquid Waste Discharge Permit.
D. Discharge will need to be manually secured. Discharge may continue using existing Liquid Waste Discharge Permit, following t he performance of RAM 3.1.1, Restarting a Liquid Batch Release.
- Unit 2 is at 100% reactor power. - T hot channel TE-401 A, Loop 'A' Hot Leg Temperature, has failed high. - Rods are stepping in. - CO places rods in manual but rods are continuing to move in at 8 steps/min.
Which of the following procedural actions should be directed?
A. Direct CO to initiate dilution IAW OP-5B, Blender Operation, to maintain T avg. If T avg cannot be maintained within allowed range, then shut down the reactor IAW AOP-17A, Rapid Power Reduction.
B. Direct CO to trip the r eactor IAW AOP-6C, Uncontrolled Rod Motion. Enter EOP-0, Reactor Trip or Safety Injection.
C. Direct the BOP operator to lower turbine load IAW AOP-17A, Rapid Power Reduction, to maintain T avg. If Tavg cannot be maintained within allowed range, then trip the reactor and enter EOP-0, R eactor Trip or Safety Injection.
D. Enter AOP-24, Response to Instrument Malfunction, and direct performance of appropriate section of 0-SO P-IC-001 RED, Removal of Safeguards or Protection Sensor from Service, to remove the failed T hot channel from service.
The Unit 1 Turbine Hall Watch reports fi nding a bomb in the Cable Spreading Room, attached to 1X-13, 1B-03 transformer.
How should the Shift Manager classify this event per the Emergency Plan?
A. Unusual Event B. Alert C. Site Area Emergency D. General Emergency