ML042990544

From kanterella
Jump to navigation Jump to search
RB-09-2004 - Final - Written Exam - RO
ML042990544
Person / Time
Site: River Bend Entergy icon.png
Issue date: 09/23/2004
From: Gody A
Operations Branch IV
To: Hinnenkamp P
Entergy Operations
References
50-458/04-301 50-458/04-301
Download: ML042990544 (117)


Text

QUESTION NO. 1 For RO Exam The plant was initially operating at 100% power. A transient occurred resulting in the following conditions:

- RPV level is 35 inches and stable after lowering to 25 inches.

- Reactor power lowered to 73% and is now stable

- Total core flow lowered to 51.5 Mlbm/hr and is now stable The cause of this plant configuration was the receipt of a signal from the . . .

A. EOC-RPT logic.

B. ATWS/ARI logic.

C. Recirculation Pump Cavitation Interlock circuitry.

D. Recirculation Flow Control Valve Runback logic.

ANSWER: D A - Flow and power would be significantly lower due to pump downshift B - Flow would be much lower and power would be <1% due to rod insertion from ARI C - Same as A due to pump downshift K/A Statement: Knowledge of the interrelations between Partial or Complete Loss of Forced Core Flow Circulation and the Recirculation System.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 295001 AK2.01 3.6 3.7 41.1 ARP-P680-4A-A03 STM-053 OBJ- 2c 41.5 AOP-0024, Att. 1 41.6 TIER/GROUP: 1/1 43.6 LOK: H LOD: 3 ORIGIN: BANK HISTORY: River Bend NRC Exam 10/2000 BANK QID: 419

QUESTION NO. 2 For RO Exam The plant is operating at rated conditions with Turbine Building Component Cooling Water pumps CCS-P1A and P1C running and CCS-P1B in standby. A partial loss of AC power to the plant occurs. As a result of the power loss, the following conditions now exist:

- CCS-P1A and P1B are running.

- Div 3 Standby Diesel is running and supplying the Div 3 Bus E22-S004 A loss of power to which one of the following caused the above conditions?

A. NNS-SWG1A B. NNS-SWG1B C. NNS-SWG1C D. Preferred Station Service Transformer RTX-XSR1C ANSWER: C A - Would result in loss of P1A and Div 3 DG would not be running B - Would result in loss of P1B and Div 3 DG would not be running D - Would result in loss of P1A & P1C and Div 1 DG would be running K/A Statement: Ability to determine/interpret the cause of partial or complete loss of A.C. power as it applies to partial or complete loss of A.C. power.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 295003 AA2.01 3.4 3.7 41.4 STM-300, Page 11 STM-300 OBJ- H2 SOP-0017, Page 59 TIER/GROUP: 1/1 LOK: H LOD: 2 ORIGIN: NEW HISTORY: BANK QID: 888

QUESTION NO. 3 For RO Exam The plant was operating at 100% power with the following conditions:

- Feed Water Level Control Level Channel A was selected with Channel B failed high.

- Offgas Post-Treat Rad Monitor RE-23B was in the High-High alarm condition.

A partial loss of DC power occurred and the reactor automatically scrammed. It has been determined that power was lost to BYS-PNL02A2.

AOP-0014, Attachment 1, is provided as EXAM HANDOUT MATERIAL.

Which one of the following was the reason for the automatic scram?

A. Turbine trip due to loss of vacuum caused by an Offgas isolation.

B. Turbine trip due to 2 out of 3 RPV High Water Level trip.

C. Turbine trip due to Generator output breaker trip.

D. ARI valves failed open on loss of power.

ANSWER: B AOP-0014, MUST BE INCLUDED IN EXAM HANDOUT MATERIALS.

Ch C High trip with Ch B failed high caused turbine trip which caused scram.

A - Offgas Rad Monitor isolates only if B in HI-HI-HI, Downscale or INOP, HI-HI is just alarm.

C - Loss of DC to aux relay circuit will not trip generator output breakers.

D - ARI valves energize to open. Remain closed on Loss of power.

K/A Statement: Knowledge of the reasons for Reactor SCRAM as it applies to partial or complete loss of D. C.

Power.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 295004 AK3.03 3.1 3.5 41.7 AOP-0014, Attachment 1 HLO-532 OBJ- 8 41.6 STM-107, Page 47 TIER/GROUP: 1/1 LOK: H LOD: 3 ORIGIN: NEW HISTORY: BANK QID: 889

QUESTION NO. 4 For RO Exam During a plant startup, after the generator has been placed on the grid, a turbine trip occurs. Following the trip, the Turbine Bypass Valves and steam line drains stabilize reactor pressure at 952 psig.

For the next 30 minutes, reactor power is held at 15% as the cause of the turbine trip is investigated. During this time, temperature of the feedwater entering the reactor vessel will . . .

A. remain constant due to feedwater flow and reactor power remaining constant.

B. lower due to the loss of extraction steam to the feedwater heaters.

C. lower due to the lower feedwater flow through the feedwater heaters.

D. rise due to the lower feedwater flow through the feedwater heaters.

ANSWER: B A - Heating steam to the feedwater heaters will be lost causing it to drop.

C - Feedwater flow will not lower with reactor power remaining at 15%.

D - Temp will lower due to loss of heating steam with feedwater flow remaining constant.

K/A Statement: Knowledge of the interrelations between Main Turbine Generator Trip and feedwater temperature.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 295005 AK2.02 2.9 3 41.4 STM-108 STM-108 OBJ- H16 41.14 TIER/GROUP: 1/1 LOK: H LOD: 2 ORIGIN: NEW HISTORY: BANK QID: 890

QUESTION NO. 5 For RO Exam The plant is operating at 100% power when an automatic reactor scram occurs due to a High Scram Discharge Volume Level.

Which one of the following describes the INITIAL response of reactor water level due to the reactor scram and the reason for that response?

Level will initially . . .

A. rise as control rod insertion lowers core void content.

B. rise as control rod insertion raises core void content.

C. lower as control rod insertion lowers core void content D. lower as the recirc pumps downshift to slow speed.

ANSWER: C A - Level lowers with lowing core void content B - Level and core voids initially lower due to control rods lowering fission rate D - Recirc pumps will not immediately downshift and a downshift causes level to rise not lower.

K/A Statement: Knowledge of the reasons for reactor water level response as they apply to SCRAM.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 295006 AK3.01 3.8 3.9 41.5 Simulator response HLO-315 OBJ- 2 41.14 TIER/GROUP: 1/1 LOK: H LOD: 3 ORIGIN: NEW HISTORY: BANK QID: 887

QUESTION NO. 6 For RO Exam The Main Control Room was abandoned due to toxic gas and control has been transferred to the Remote Shutdown panel. The following has occurred:

- At 2000 reactor was shutdown and RPV pressure stabilized at 950 psig.

- At 2015 after RCIC operation to raise RPV level, RPV pressure dropped to 800 psig.

- At 2030, RPV pressure has remained stable at 800 psig and all MSIVs are closed.

- At 2035, the CRS directs the operator at the Remote Shutdown Panel to establish a cooldown rate between 90°F/hr and 100°F/hr, not to exceed 100°F/hr using SRVs.

At 2100, which one of the following RPV pressures will meet the cooldown rate directed by the CRS? AOP-0031, Attachment 2 is included as EXAM HANDOUT MATERIAL.

A. 500 psig B. 400 psig C. 350 psig D. 300 psig ANSWER: B From shutdown pressure of 950 psig = 540°F to 400 psig = 448°F one hr later = 92°F/hr C/D rate A - 500 psig = 70°F/hr C/D rate.

C - 350 psig = 105°F/hr CD rate.

D - 300 psig = 119°F/hr CD rate.

K/A Statement: Ability to determine/interpret cooldown rate as it applies to Control Room Abandonment.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 295016 AA2.06 3.3 3.5 41.10 AOP-0031, Att 2 HLO-537 OBJ- 4 41.14 Steam Tables TIER/GROUP: 1/1 LOK: H LOD: 3 ORIGIN: NEW HISTORY: BANK QID: 942

QUESTION NO. 7 For RO Exam - DELETED FROM EXAM A total loss of CCP has occurred and the reactor has been scrammed. All automatic actions for the total loss of CCP have occurred including automatic initiation of Standby Service Water.

The CRS has directed the UO to align SSW to the CRD pump bearing coolers and to start a CRD pump per AOP-0011, Step 5.2. AOP-0011 is included as exam handout materials.

The purpose of placing the RPCCW DIV 1 TEST switch in TEST is to . . .

A. prevent auto initiation of DIV 1 Standby Service Water Pumps, if they aren't running.

B. prevent auto closure of the SSW-MOV510B when aligning CCP Loop B to the CRD pump coolers.

C. allow CCP-MOV163 to be opened.

D. allow starting either CRD pump.

ANSWER: D Requires Div 1 in test to bypass <56 psig in Div 1 CCP loop.

A - The TEST switch does not bypass SSW pump start signals only valve closures.

B - Division 2 valve with no isolation on 56 psig in CCP.

C - Division 2 valve with isolation bypassed by Div 2 TEST switch.

K/A Statement: Knowledge of the purpose and function of major system components and controls applicable to Partial or Total Loss of CCW.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 295018 2.1.28 3.2 3.3 41.4 AOP-0011, Step 5.2 STM-115 OBJ-41.7 STM-115, Page 15 41.10 TIER/GROUP: 1/1 LOK: H LOD: 3 ORIGIN: NEW HISTORY: BANK QID: 891

QUESTION NO. 8 For RO Exam A crack in the Instrument Air System (IAS) air compressor common discharge header has lowered header pressure to 100 psig. At this pressure, what is the expected status of the two automatic air-operated Service Air System valves listed below?

- SAS-AOV133, Service Air Header Block Valve

- SAS-AOV134, Instrument Air Header Cross-Tie Valve AOV133 AOV134 A. Open Open B. Closed Open C. Open Closed D. Closed Closed ANSWER: B.

A - 133 will auto close when pressure lowers to 110 psig.

C - Both A & D apply D - 134 will auto open when pressure lowers to 113 psig.

K/A Statement: Ability to operate/monitor service air isolation valves as they apply to Partial or Complete Loss of Instrument Air.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 295019 AA1.04 3.3 3.2 41.4 ARP-P870-51A-B02 STM-121 OBJ- H3 STM-121, Pages 28 & 29 TIER/GROUP: 1/1 LOK: H LOD: 2 ORIGIN: NEW HISTORY: BANK QID: 54

QUESTION NO. 9 For RO Exam While operating RHR "A" in the Shutdown Cooling Mode, a spurious isolation signal actuates the INBOARD (Div. 2) Containment and Reactor Vessel Isolation Control System (CRVICS) isolation logic for RHR Shutdown Cooling. The Shutdown Protection Plan per SOP-0031 has NOT been implemented.

What is the final state of the following RHR System components after all automatic actions have occurred?

SDC OUTBD ISOLATION VLV RHR E12-F008 PUMP A A. Closed Running B. Closed Tripped C. Open Running D. Open Tripped ANSWER: D A - F008 is not closed by INBD Isolation logic, but if closed pump would be tripped.

B - F008 is not closed by INBD Isolation logic.

C - Pump is automatically tripped by closure of INBD SDC Suction Isolation Valve E12-F009.

K/A Statement: Ability to operate/monitor RHR/Shutdown Cooling as it applies to Loss of Shutdown Cooling.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 295021 AA1.02 3.5 3.5 41.7 STM-204, Fig. 10 STM-204 OBJ- H AOP-0003, Page 15 TIER/GROUP: 1/1 LOK: F LOD: 3 ORIGIN: NEW HISTORY: BANK QID: 892

QUESTION NO. 10 For RO Exam Containment Purge is in operation for humidity control using HVR-FN14 during a refueling outage.

An irradiated fuel bundle is dropped in the Reactor Cavity where it strikes the tops of several other fuel bundles in the core. A large volume gas bubble was observed rising to the surface.

A short time later, the Containment Purge Radiation Monitors RMS-RE21A and B rapidly rise to above their High alarm on DRMS. How should the HVR-FN14, Containment Purge Filter Fan respond following this alarm?

A. It will stop when its suction damper HVR-AOD240 closes.

B. It will stop following the auto initiation of Standby Gas Treatment.

C. It will stop when the containment isolation damper HVR-AOV128 closes.

D. It will continue to run.

ANSWER: C A - HVR-FN14 interlocked to close AOD240 when fan stops, NOT interlocked to stop fan B - RE21 will not initiate Standby Gas treatment.

D - Interlocked to stop when AOV128 is closed by RE21.

K/A Statement: Ability to operate/monitor Containment Building Ventilation as it applies to Refueling Accidents.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 295023 AA1.08 3.3 3.4 41.7 STM-403, Page 19 STM-403 OBJ- H10 41.9 ARP-P863-71A-F02 ARP-RMS-DSPL230, Page 12 TIER/GROUP: 1/1 LOK: H LOD: 2 ORIGIN: NEW HISTORY: BANK QID: 893

QUESTION NO. 11 For RO Exam Given the following plant conditions:

- Reactor Power 0% (all rods in)

- Reactor Level +33 inches

- Reactor Pressure 890 psig

- Drywell Pressure 1.8 psid

- Drywell Temperature 138°F

- Containment Temperature 88°F

- Containment Pressure 0.35 psig

- Annulus Differential Pressure -4.5 in.WC Based on the above conditions, which one of the following describes the Emergency Operating Procedures that should be entered?

A. EOP-1 ONLY B. EOP-1 and 2 C. EOP-2 ONLY D. EOP-2 and 3 ANSWER: B A - High Containment pressure entry condition for EOP-2 also exists C - High Drywell DP entry condition for EOP-1 also exists D - Cont. Press is entry for EOP-2 but Annulus DP has not exceeded Max. Normal Operating for EOP-3 entry K/A Statement: Ability to recognize abnormal indications which are entry-level conditions for EOPs and AOPs applicable to High Drywell Pressure.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 295024 G2.4.4 4 4.3 41.10 EOP-0001 HLO-514 OBJ- 4 41.9 EOP-0002 43.2 TIER/GROUP: 1/1 LOK: F LOD: 3 ORIGIN: MODIFIED HISTORY: River Bend NRC Exam 2/2003 BANK QID: 444

QUESTION NO. 12 For RO Exam The reactor scrammed and the MSIVs have closed do to a small break in the piping from the Main Steam Line Equalizing Header. SRVs are now being cycled to control reactor pressure. Suppression Pool level has risen to 21 feet 3 inches.

If Suppression Pool level CANNOT be lowered, Emergency Depressurization is required because . . .

A. continued SRV operation may cause tailpipe damage and directly pressurize containment.

B. continued SRV operation may cause tailpipe vacuum breaker damage and directly pressurize containment.

C. continued SRV operation will cause extensive flooding of the drywell due to overflowing the weir wall.

D. a large break LOCA will result in drywell pressure exceeding design due to the higher pressure required to uncover the horizontal vent holes.

ANSWER: A B - Tailpipe vacuum breaker failure would pressurize the Drywell not containment.

C - may flood but not a reason for requiring ED D - Would not raise DW pressure significantly.

K/A Statement: Ability to determine/interpret suppression pool level as it applies to High Reactor Pressure.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 295025 EA2.04 3.9 3.9 41.9 EPSTG-0002, B-8-26 HLO-514 OBJ- 5 41.10 TIER/GROUP: 1/1 LOK: F LOD: 2 ORIGIN: NEW HISTORY: BANK QID: 948

QUESTION NO. 13 For RO Exam A MSIV Closure - ATWS has occurred with the plant at 100% power.

Injecting boron when it has been determined that Suppression Pool temperature CANNOT be maintained below 110°F is done to . . .

A. avoid exceeding the Heat Capacity Temperature Limit (HCTL) with the reactor still critical.

B. eliminate any need for Emergency Depressurization during ATWS conditions.

C. ensure Hot Shutdown Boron Weight will be injected before suppression pool temperature reaches the value at which a scram is required by Technical Specifications.

D. ensure Cold Shutdown Boron Weight will be injected before suppression pool temperature reaches the value at which a scram is required by Technical Specifications.

ANSWER: A B - ED may still be required due to inability to maintain RPV level or per EOP-3.

C - Boron Injection Initiation Temp is where TS requires scram. HSBW could not be injected if initiated at 109F.

D - Boron Injection Initiation Temp is where TS requires scram. CSBW could not be injected if initiated at 109F.

K/A Statement: Knowledge of the reasons for SBLC injection as it applies to Suppression Pool High Water Temperature.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 295026 EK3.04 3.7 4.1 41.9 EOP-1A HLO-513 OBJ- 4 41.10 EPSTG-0002, B-7-68 TIER/GROUP: 1/1 LOK: F LOD: 2 ORIGIN: MODIFIED HISTORY: River Bend NRC Exam 2/2003 BANK QID: 816

QUESTION NO. 14 For RO Exam At what locations can the Operator confirm an EOP-0002, entry condition has been reached when a High Containment Temperature annunciator alarms.

A. Emergency Response Information System (ERIS) in Technical Support Center (TSC) and CMS recorders on P808.

B. Emergency Response Data System (ERDS) link to NRC and Local Temperature Indicators in Containment C. CMS Recorders on P808 and the Leakage Computer D. Emergency Response Information System (ERIS) in Main Control Room and the Leakage Computer ANSWER: A B. ERDS does not transmit Containment Temperature; system is only started during emergencies.

C. Leakage computer does not read Containment Temperature D. Same as C.

K/A Statement: Knowledge of the interrelations between High Containment Temperature and ERIS.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 295027 EK2.04 2.6 3.2 41.7 STM-514, Pages 6 & 7 STM-514 OBJ- H4 41.9 TIER/GROUP: 1/1 LOK: F LOD: 2 ORIGIN: NEW HISTORY: BANK QID: 894

QUESTION NO. 15 For RO Exam Which one of the following describes why EOP 1, RPV Control," Caution number 2 directs the operator to open and leave open RHR Shutdown Cooling Inboard Isolation, lE12-F009, following a LOCA?

A. High temperature steam conditions in the drywell may cause thermal overloads in the motor to trip, rendering the valve inoperable, unless the valve is opened early in the transient.

B. High temperatures in the drywell could cause local boiling in the piping upstream of F009, resulting in water hammer if the valve is not open.

C. High temperature steam conditions in the drywell may cause accelerated corrosion of the motor rotor resulting in insufficient torque to operate the valve.

D. The motor on F009 is designed for only one cycle of operation at the maximum anticipated drywell temperatures.

ANSWER: C K/A Statement: Knowledge of the operational implications of equipment environmental qualification as they apply to High Drywell Temperature.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 295028 EK1.02 2.9 3.1 41.8 EOP-0002 HLO-511 OBJ- H6 41.10 EPSTG-0002, Page B-5-9 TIER/GROUP: 1/1 LOK: F LOD: 2 ORIGIN: BANK HISTORY: River Bend NRC Exam 1/1993 BANK QID: 895

QUESTION NO. 16 For RO Exam The High Pressure Core Spray pump is injecting into the RPV with its suction aligned to the Suppression Pool following a low CST level. RPV flooding is in progress and HPCS injection is required to maintain RPV pressure above 42 psig for the next 25 minutes to establish the Minimum Core Flooding Interval.

Suppression pool level has been lowering and is now approaching 15 feet. The CST has been restored to 10 feet above the low level setpoint.

The CRS has directed that HPCS suction again be aligned to the CST, while maintaining maximum HPCS flow to the RPV. Which one of the following describes how this must be accomplished?

A. First open the CST suction valve and when full open, close the Suppression Pool suction valve.

B. First close the Suppression Pool suction valve and when duel position indication is obtained, open the CST suction valve.

C. First open the CST suction valve and when dual position indication is obtained, close the Suppression Pool suction valve.

D. First close the Suppression Pool suction valve and when full closed position indication is obtained, open the CST suction valve.

ANSWER: B A - CST suction valve will not open with SP suction valve in full open position.

C - CST suction valve will not open with SP suction valve in full open position.

D - Flow to the RPV is interrupted.

K/A Statement: Ability to operate/monitor HPCS as it applies to Low Suppression Pool Water Level.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 295030 EA1.03 3.4 3.4 41.7 STM-203. Pages 13 & 14 STM-203 OBJ- H4 TIER/GROUP: 1/1 LOK: H LOD: 2 ORIGIN: NEW HISTORY: BANK QID: 896

QUESTION NO. 17 For RO Exam The setpoint setdown feature of the Feed Water Level Control System is activated _______(1)________ and initially causes the Feedwater Regulating Valves to ___(2)____ further .

(1) (2)

A. on any reactor scram open B. on any reactor scram close C. at <9.7" RPV level open D. at <9.7" RPV level close ANSWER: C A - Only on scrams where level reaches Level 3 B - Only on scrams where level reaches Level 3 and FWRVs open D - FWRVs open intially K/A Statement: Knowledge of the interrelations between Reactor Low Water Level and Reactor Water Level Control.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 295031 EK2.16 4.1 4.1 41.7 STM-107, Page 54 STM-107 OBJ- H4 TIER/GROUP: 1/1 LOK: F LOD: 2 ORIGIN: NEW HISTORY: BANK QID: 897

QUESTION NO. 18 For RO Exam - DELETED FROM EXAM A manual Reactor Scram has been inserted and the Scram Pilot Solenoid Valve white status lights are off but Control Rod Movement has not occurred. The Emergency Response Information System (ERIS) - Safety Parameter Display System (SPDS), Critical Plant Variables Screen will display the SCRAM condition in the box below the Power box as follows:

A. The box will change from NO SCRAM to ATWS based on the Scram Relay position and indicated power above the APRM Downscale B. The box will remain NO SCRAM and be highlighted in green based on the control rods not fully inserting.

C. The box will change from NO SCRAM to ????? in a magenta box to indicate bad data, based on the failure to scram.

D. The box will remain NO SCRAM and be highlighted in red based on indicated power above the APRM Downscale ANSWER: B A - The box does not display the word ATWS C - The box would not display magenta (bad data) because signal is still present and in range.

D - Since the scram relays repositioned as indicated by the pilot lights, ERIS would receive a valid scram signal and change the box from NO SCRAM to SCRAM K/A Statement: Knowledge of the interrelations between Scram Condition Present and Reactor Power Above APRM Downscale or Unknown and ERIS.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 295037 EK2.08 2.7 3.1 41.1 STM-514 STM-514 OBJ- H3 41.2 41.7 TIER/GROUP: 1/1 LOK: F LOD: 2 ORIGIN: NEW HISTORY: BANK QID: 898

QUESTION NO. 19 For RO Exam EOP-3, Radioactive Release Control has been entered and is being executed due to a release occurring in the Turbine Building. Off-site power was lost during the event but has just been restored.

In order to restart Turbine Building Ventilation, per EOP-3, Step RR-2, it will be necessary for an operator to start . . .

A. ONLY an exhaust fan at panel HVT-PNL162 located on the West side of the Turbine Building 123' elevation.

B. BOTH an exhaust and supply fan at panel HVT-PNL162 located on the West side of the Turbine Building 123' elevation.

C. ONLY an exhaust fan at panel HVT-PNL163 located in the Offgas area of the Turbine Building 123' elevation.

D. BOTH an exhaust and supply fan at panel HVT-PNL163 located in the Offgas area of the Turbine Building 123' elevation.

ANSWER: B A - Must also start Supply Fan or Exhaust will trip in 15 seconds.

C - Wrong local HVT panel and must also start Supply Fan or Exhaust will trip in 15 seconds.

D - Wrong local HVT panel.

K/A Statement: Ability to locate and operate components, including local controls applicable to High Off-Site Release Rate.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 295038 2.1.30 3.9 3.4 41.4 SOP-0064, Pages 4 & 6 STM-408 OBJ- 5 41.10 41.13 TIER/GROUP: 1/1 LOK: F LOD: 2 ORIGIN: NEW HISTORY: BANK QID: 886

QUESTION NO. 20 For RO Exam Which one of the following describes the response of the Fire Protection System to a fire in the charcoal bed of one of the Standby Gas Treatment Trains.

The fire would be detected by a . . .

A. a smoke detector above the charcoal bed that causes an alarm in the Main Control Room AND auto opens a Fire Water valve to spray the bed.

B. a smoke detector above the charcoal bed that causes an alarm in the Main Control Room. A manual Fire Water valve must be locally opened to spray the bed.

C. a thermal detector inside the charcoal bed that causes an alarm in the Main Control Room AND auto initiates Fire Water flow to spray nozzles in the bed.

D. a thermal detector inside the charcoal bed that causes an alarm in the Main Control Room. A manual Fire Water valve must be locally opened to spray the bed.

ANSWER: D A - Thermal detector is used with no automatic initiation feature.

B - Thermal detector is used.

C - No automatic initiation feature.

K/A Statement: Knowledge of the interrelations between Plant Fire On Site and Fire Protection System sensors, detectors and valves.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 286000 A3.06 3 3.1 41.4 ARP-863-73-D04 STM-257 OBJ- H6 STM-257, Page 6 TIER/GROUP: 1/1 LOK: F LOD: 2 ORIGIN: NEW HISTORY: BANK QID: 923

QUESTION NO. 21 For RO Exam The plant is operating at 10% power. The Feedwater Level Control (FWLC) System is operating with the Startup Feedwater Regulating valve in AUTO. The A Reactor Water Level Channel selected. A rupture occurs on the A reference leg causing a level change.

Assuming no other instruments are affected by the rupture, which one of the following describes the required operator action?

A. Select the "B" Reactor Water Level Channel.

B. Place the Startup Level Controller in MANUAL and depress CLOSE.

C. Transfer level control to the Master Level Controller in single element.

D. Allow the level dominant signal to take control and return level to normal.

ANSWER: A B - The instrument failure is lowering level so going to OPEN would be correct.

C - Failed channel also inputs to Master Controller D - Level instrument is failed so level dominance will cause low level scram K/A Statement: Ability to operate/monitor Reactor Water Level Control as it applies to Low Reactor Water Level.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 295009 AA1.02 4 4 41.7 AOP-0006 STM-107B OBJ- H8 TIER/GROUP: 1/2 LOK: F LOD: 2 ORIGIN: MODIFIED HISTORY: River Bend NRC Exam 2/2003 BANK QID: 954

QUESTION NO. 22 For RO Exam Following a Large Break LOCA inside the Drywell, Drywell temperature reached 265°F and Drywell-to-Containment P peaked at 15 psid. Ten minutes later, Drywell temperature has lowered to 205°F and Drywell-to-Containment P is -4 psid.

If NO OPERATOR ACTIONS have occurred since the LOCA, this value of Drywell-to-Containment P indicates which one of the following conditions?

A. Excessive bypass leakage exists between the Drywell and Containment.

B. The air in the drywell is being cooled by operation of all Drywell coolers.

C. The steam in the drywell is being condensed by operation of all Drywell coolers.

D. The steam in the drywell is being condensed by ECCS flow from the break.

ANSWER: D A - Could cause P to lower to 0 psid, but not become negative.

B - Would be little if any air in Drywell and its coolers have no cooling water or power due to high drywell P.

C - Drywell coolers have no cooling water or power due to high drywell P.

K/A Statement: Ability to determine/interpret drywell pressure as it applies to High Drywell Pressure.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 295010 AA2.02 3.8 3.9 41.9 HLO-322, Page 10 HLO-322 OBJ- 3 USAR Figure 6.2-4 TIER/GROUP: 1/2 LOK: H LOD: 2 ORIGIN: NEW HISTORY: BANK QID: 899

QUESTION NO. 23 For RO Exam When Containment Temperature CANNOT be maintained below 90°F, EOP-0002 directs operating all available containment cooling to avoid . . .

A. Suppression Pool temperature rising due to Containment heating.

B. Emergency Depressurization being required.

C. reference leg flashing in RPV level instrumentation.

D. implementing Containment Flooding to lower containment temperatures.

ANSWER: B A - No significant rise in SP temperature would result from containment temps rising above 90°F.

C - No mechanism for containment temps to reach >212°F D - Would cool containment but not used for that purpose in the EOPs.

K/A Statement: Knowledge of the reasons for increased containment cooling as they apply to High Containment Temperature.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 295011 AK3.01 3.6 3.9 41.8 EOP-0002, Step CT-3 HLO-514 OBJ- 5 41.9 EPSTG-0002, Page B-8-9 & 10 41.10 TIER/GROUP: 1/2 43.5 LOK: F LOD: 2 ORIGIN: NEW HISTORY: BANK QID: 900

QUESTION NO. 24 For RO Exam Following a scram due to high Drywell pressure, EOP-2 was entered with Drywell temperature rising.

At a Drywell temperature of 145°F, Enclosure 20, Defeating Drywell Cooling Isolation Interlocks, was installed and all Drywell Unit Coolers placed in operation by 160°F. Drywell temperature reached a peak value of 230°F before beginning to lower. The following conditions now exist:

- RPV level reached a minimum of -35 inches and is now stable at 30 inches.

- Drywell pressure is 1.55 psid and lowering rapidly.

- Drywell temperature is 143°F and lowering rapidly.

With the above conditions, which one of the following is true?

A. Enclosure 20 must be removed with Drywell temperature below 145°F.

B. All Drywell Unit Coolers must remain ON per EOP-2, Step DWT-3, WHEN Drywell temperature cannot be maintained below 145°F.

C. All Drywell Unit Coolers must be secured. Drywell temperature was >200°F.

D. Individual Drywell Unit Coolers can be secured to avoid a negative Drywell pressure.

ANSWER: D A - Unless directed by EOP step, enclosures, once installed, are NOT to be removed until EOPs are exited.

B - "Operate all available" does not preclude turning on and off as necessary EPSTG/ OSP-0009.

C - NA. Service water was never completely isolated.

K/A Statement: Knowledge of operator responsibilities during all modes of plant operation applicable to High Drywell Temperature.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 295012 2.1.2 3 4 41.10 EOP-2, Steps DWT-2 & 3 HLO-514 OBJ- 6 41.9 EPSTG-0002, Page B-8-6 43.5 TIER/GROUP: 1/2 LOK: H LOD: 3 ORIGIN: BANK HISTORY: River Bend NRC Exam 2/2003 BANK QID: 901

QUESTION NO. 25 For RO Exam While operating RCIC pump flow surveillance testing, one of the RHR loops is placed in Suppression Pool Cooling Mode to ensure . . .

A. adequate mixing of the suppression pool water to avoid temperature stratification.

B. maximum RCIC turbine efficiency for the most conservative pump flow test data.

C. the RCIC suction strainer remains free of any debris that could affect test results.

D. minimum RCIC exhaust line check valve chatter during the test.

ANSWER: A B - Will not significantly affect RCIC turbine efficiency and affect would be nonconservative.

C - Would want test results to show any suction strainer fouling.

D - RHR suppression pool cooling would not affect exhaust line check valve chatter.

K/A Statement: Knowledge of the operational implications of pool stratification as they apply to High Suppression Pool Temperature.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 295013 AK1.01 2.5 2.6 41.8 SOP-0035, Page 4 STM-209 OBJ- H6 41.10 41.14 TIER/GROUP: 1/2 LOK: F LOD: 2 ORIGIN: NEW HISTORY: BANK QID: 953

QUESTION NO. 26 For RO Exam A fuel bundle has been dropped and fuel pins have ruptured in the spent fuel pool. The Fuel Building Exhaust Rad Monitors are both in alarm condition and automatic realignment of Fuel Building Ventilation is in progress.

Under these conditions, the Alternate Air Supply Dampers HVF-AOD37A and B automatically open to . . .

A. provide air flow across the spent fuel pools.

B. provide a permissive for the Charcoal Filtration Fans to auto start.

C. prevent damage to the Exhaust Filter Charcoal Filtration Trains.

D. prevent damage to the Fuel Building due to excessive internal negative pressure.

ANSWER: A B - Only the inlet isolation dampers for the Filter train fans are intlocked with the fans.

C - Filtration trains will operate without damage with no alternate air supply dampers open.

D - The filtration trains do not create a negative pressure high enough to damage the Fuel Building with HVF-AOD37A and B closed.

K/A Statement: Knowledge of the reasons for the Fuel Building Ventilation responses as they apply to Secondary Containment Ventilation High Radiation.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 295034 EK3.04 3.7 3.8 41.9 STM-406 Pages16 &17 STM-406 OBJ- H3 TIER/GROUP: 1/2 LOK: F LOD: 2 ORIGIN: NEW HISTORY: BANK QID: 903

QUESTION NO. 27 For RO Exam A leak in the RCIC room has resulted in the RCIC room sump overflowing and a rise in the Auxiliary Building Ventilation Radiation Monitor RMS-RE110 indication on DRMS.

After RMS-RE110 exceeds the High Alarm, if NO OPERATOR ACTION is taken, what type of radioactive release will be in progress?

A. Monitored AND filtered B. Monitored, BUT NOT filtered C. Unmonitored, BUT filtered D. Unmonitored AND NOT filtered ANSWER: B No automatic isolation of Aux Building Vent so it remains monitored, and no filter trains start on RE110 alarm.

A - Requires operator action to isolate the Aux Building Ventilation and/or start SGTS C - Has rad monitior but no filter train on the Aux Building Ventilation D - Only if operator action was taken to isolate Aux Building with no SGTS operation.

K/A Statement: Knowledge of the operational implications of radiation releases as they apply to Secondary Containment High Sump/Area Water Level.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 295036 EK1.01 2.9 3.1 41.11 ARP-RMS-DSPL230/GP110 STM-409 OBJ- H6 41.12 STM-409, Page 15 41.13 TIER/GROUP: 1/2 LOK: F LOD: 2 ORIGIN: NEW HISTORY: BANK QID: 904

QUESTION NO. 28 For RO Exam To ensure that the RHR Low Pressure Coolant Injection can provide core cooling such that the ECCS Acceptance Criteria are met, the plant must be operating within the limits specified in which one of the following Technical Specification LCOs prior to the DBA LOCA?

A. Average Planar Linear Heat Generation Rate (APLHGR).

B. Fraction of Core Boiling Boundary (FCBB).

C. Minimum Critical Power Ratio (MCPR).

D. Linear Heat Generation Rate (LHGR).

ANSWER: A B - Applies to normal operation in Restricted Region of P/F map to prevent instability.

C - Applies to normal power operation and transients, not accident conditions.

D - Applies to normal power operations and transients, not accident conditions.

K/A Statement: Knowledge of the operational implications of core cooling methods as applied to RHR/LPCI.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 203000 K5.02 3.5 3.7 41.8 TS Bases, Page 3.2-1 HLO-321 OBJ- 1 41.14 43.2 TIER/GROUP: 2/1 LOK: F LOD: 2 ORIGIN: NEW HISTORY: BANK QID: 905

QUESTION NO. 29 For RO Exam Given the following initial plant conditions:

RHR loop "B" is in Shutdown Cooling (SDC) mode.

Coolant temperature is 300°F.

RPV pressure is 125 psig and rising.

SELECT the statement that describes the effect on the Shutdown Cooling (SDC) Suction Isolation Inboard and Outboard Valves (E12-MOVF009 and E12-MOVF008) if the 4.16 KV bus ENS-SWG1B trips and locks out.

A. F008 and F009 will both auto close on loss of power to the SDC isolation logic.

B. F008 and F009 will remain open until RPV pressure reaches 135 psig then both will close.

C. F009 will close when RPV pressure reaches 135 psig, F008 will not due to loss of power.

D. F008 will close when RPV pressure reaches 135 psig, F009 will not due to loss of power.

ANSWER: D Isolation logic will initiate closure of both valves at 135 psig but MOVF009 has no power to close with ENS-SWG1B lost.

A - Isolation logic is powered from RPS and an inverter which remain energized.

B - loss of power to MOVF009 will prevent it from closing.

C - Outboard valve MOVF008 is powered from ENS-SWG1A and will not lose power.

K/A Statement: Knowledge of the electrical power supplies to Shutdown Cooling motor operated valves.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 205000 K2.02 2.5 2.7 41.4 SOP-0031, Pages 114 & 115 STM-204 OBJ- H10 41.7 AOP-0003, Page 15 TIER/GROUP: 2/1 LOK: F LOD: 3 ORIGIN: MODIFIED HISTORY: Perry NRC Exam 1994 BANK QID: 906

QUESTION NO. 30 For RO Exam The Division 1 Standby Diesel Generator has been operating in parallel with off-site power for a one-hour load test surveillance. It's load is at 1000 KW and being lowered to remove it from the bus when a spurious LPCS/RHR A LOCA initiation signal is received.

Which one of the following describes the response of the Standby Diesel and ENS Bus to the LOCA signal and LPCS pump breaker closing?

A. The normal feeder breaker to ENS-SWGR1A will trip due to the LOCA signal and the LPCS pump will start with the Diesel Generator supplying the bus.

B. The Standby Diesel Output Breaker will trip due to overcurrent from the LPCS pump starting current and the LPCS pump will start with Off-site power supplying the bus.

C. The Standby Diesel Output Breaker will trip due to the LOCA signal and the LPCS pump will start on Off-site power.

D. The load from the LPCS pump start will be shared between Off-site power and the Diesel Generator operating in Droop Mode. NO breakers will trip.

ANSWER: C A - No undervoltage on bus. LOCA signal does not trip normal breaker.

B - EDG output breaker will open then LPCS pump will start on Off-site power as designed for a non-LOP LOCA.

D - See B.

K/A Statement: Knowledge of the effect a loss or malfunction of the LPCS will have on emergency generators.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 209001 K3.03 2.9 3 41.7 SOP-0053, Page 5 STM-309 OBJ- H8 41.8 TIER/GROUP: 2/1 LOK: H LOD: 3 ORIGIN: MODIFIED HISTORY: River Bend NRC Exam 2/2003 BANK QID: 819

QUESTION NO. 31 For RO Exam An inadvertent initiation of High Pressure Core Spray occurred at rated power. Conditions stabilized as follows:

- Reactor power is 97%

- RPV water level is 44 inches

- Reactor pressure is 1005 psig The CRS has directed the Unit Operator to secure HPCS injection by closing the injection valve. As the injection valve is closed, reactor pressure will . . .

A. Remain constant.

B. Rise and stabilize at 1020 psig.

C. Lower and stabilize at 1000 psig.

D. Rise, then lower and stabilize at 1000 psig.

ANSWER: B A - Power will return to rated and EHC will respond raising pressure.

C - Pressure will rise as HPCS spray is removed from core exit.

D - Power will return to rated and EHC will respond with higher flow raising RPV pressure K/A Statement: Ability to predict/monitor changes in reactor pressure with operating HPCS controls.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 209002 A1.04 3.3 3.3 41.5 USAR Fig. 15.5-1 HLO-318 OBJ- H2 41.8 TIER/GROUP: 2/1 LOK: H LOD: 2 ORIGIN: NEW HISTORY: BANK QID: 907

QUESTION NO. 32 For RO Exam The Standby Liquid Control injection sparger senses ____(1)____ core plate pressure to provide the

____(2)____ pressure side of core plate differential pressure.

(1) (2)

A. below high B. below low C. above high D. above low ANSWER: A B - High not low pressure side C - Below core plate pressure D - B and C apply K/A Statement: Knowledge of the physical connections/cause-effect relationships between SLC and core plate P indication.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 211000 K1.02 2.7 2.7 41.2 STM-201, Page 5 STM-201 OBJ- H6 TIER/GROUP: 2/1 LOK: F LOD: 2 ORIGIN: NEW HISTORY: BANK QID: 1078

QUESTION NO. 33 For RO Exam After resetting RPS for a reactor startup, all four CRD SCRAM DISCH VOL HI WTR LVL BYPASS keylocked switches were inadvertently left in the BYPASS position. The Mode switch was placed in START/HOT STBY.

After withdrawing 10 control rods for the approach to critical, one of the RPS Scram Discharge Volume level transmitters fails high.

Which one of the following is the expected plant response?

A. BOTH a control rod withdrawal block and a RPS half scram will occur.

B. ONLY a control rod withdrawal block will occur.

C. ONLY a RPS half scram will occur.

D. NEITHER a control rod withdrawal block NOR a RPS half scram will occur.

ANSWER: C A and B - The control rod block transmitters are separate from RPS, no rod block D - Placing the mode switch in START / HOT STBY position disables the keylock switch CRD SDV Bypass.

K/A Statement: Knowledge of the effect that a loss or malfunction of the sensor inputs will have on the RPS.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 212000 K6.05 3.5 3.8 41.7 STM-508, Page 19 STM-508 OBJ- H5 TIER/GROUP: 2/1 LOK: H LOD: 4 ORIGIN: NEW HISTORY: BANK QID: 885

QUESTION NO. 34 For RO Exam Given the following plant conditions:

IRM "G" is bypassed Reactor Mode switch is in START/HOT STANDBY All operable IRMs are reading 65/125 on Range 9 During the troubleshooting of IRM "G," I&C requests that the ATC operator withdraw IRM "G." In error, the ATC withdraws IRM "C" instead.

How does the plant respond?

A. An IRM Detector Wrong Position rod block is generated in RC&IS.

B. An IRM Downscale rod block is generated when the detector gets full-out.

C. Nothing, at this time all IRM rod blocks and scrams are bypassed.

D. An IRM INOP rod block and 1/2 scram signal are generated when the detector leaves the "full-in" position.

ANSWER: A K/A Statement: Ability to manually operate/monitor IRMs in the CR to verify proper functioning/operability.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 215003 A4.07 3.6 3.6 41.2 SOP-0074, ATT4 STM-503 OBJ- H4 41.7 TIER/GROUP: 2/1 LOK: H LOD: 2 ORIGIN: BANK HISTORY: River Bend NRC Exam 7/1997 BANK QID: 29

QUESTION NO. 35 For RO Exam A plant startup is in progress and the reactor is nearing critical when RPS MG Set A generator output breaker trips.

What will be the status of the SRM A trip unit indicating lights on P680?

A. The UPSC TRIP, ALARM OR INOP, and DNSC lights will ALL be lit.

B. ONLY the ALARM OR INOP, and DNSC lights will be lit.

C. ONLY the ALARM OR INOP light will be lit.

D. NONE of the trip unit lights will be lit.

ANSWER: A B and C - All trip units on SRM output fail to trip condition on loss of power.

D - Trip unit status indication on P680 will still have power and indicate their status.

K/A Statement: Knowledge of the effect a loss or malfunction of RPS will have on the SRMs.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 215004 K6.01 3.2 3.3 41.7 AOP-0010, Page 3 STM-503 OBJ- H7 41.2 TIER/GROUP: 2/1 LOK: H LOD: 2 ORIGIN: NEW HISTORY: BANK QID: 908

QUESTION NO. 36 For RO Exam A plant startup is in progress and the following conditions exist:

- The reactor is critical with a positive 60 second period.

- Overlap between the IRMs and SRMs has been verified.

- The ATC operator has selected all SRM detectors for withdrawal.

Drawing of SRM Period response included in EXAM HANDOUT MATERIAL.

With no change in core reactivity, as the detectors are withdrawn from the core, their indicated reactor period will . . .

A. remain at positive 60 seconds or become slightly shorter initially, then lengthen to infinity becoming negative as the detectors move away from the core midplane.

B. remain at positive 60 seconds, continuing to accurately indicate actual reactor period as the detectors are withdrawn from the core.

C. immediately lengthen to infinity, then gradually become negative as the detectors pass the bottom of the core.

D. immediately drop through infinity to the shortest indicated negative value of period and will remain there throughout detector withdrawal.

ANSWER: A REQUIRES DRAWING FOR QUESTION INCLUDED IN EXAM HANDOUT MATERIAL B - changes throughout because flux levels the detector sees are changing throughout.

C & D - initially remains positive or shortens as it moves through the high flux region toward core midplane and becomes negative before reaching bottom.

K/A Statement: Ability to predict/monitor changes in reactor power indication with operating the SRM controls.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 215004 A1.02 3.6 3.7 41.2 STM-503, Page 12 STM-503 OBJ- 6 TIER/GROUP: 2/1 LOK: H LOD: 3 ORIGIN: NEW HISTORY: BANK QID: 799

QUESTION NO. 37 For RO Exam With the reactor operating at 60% power and 70% of rated flow, the Recirculation System Flow Converter for APRM Channel C fails to its full scale value.

Which one of the following describes the expected status of theAPRM C rod block and scram trip units?

A. Neither the APRM C Flow Biased Upscale Rod Block nor the Flow Biased Thermal Scram trip unit will be tripped.

B. ONLY the APRM C Flow Biased Upscale Rod Block trip unit will be tripped.

C. ONLY the APRM C Flow Biased Thermal Scram trip unit will be tripped.

D. BOTH the APRM C Flow Biased Upscale Rod Block and the Flow Biased Thermal Scram trip units will be tripped.

ANSWER: A B - Flow converter upscale will raise APRM flow biased rod block setpoint. However, a Flow Converter Upscale rod block will occur.

C - Flow converter upscale will raise APRM flow biased scram setpoint.

D - See B and C K/A Statement: Knowledge of the effect a loss or malfunction of flow converter/comparator network will have on APRM/LPRM.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 215005 K6.07 3.2 3.3 41.2 STM-503, Page 63 STM-503 OBJ- 28 ARP-P680-6A-B02 TIER/GROUP: 2/1 LOK: H LOD: 3 ORIGIN: NEW HISTORY: BANK QID: 884

QUESTION NO. 38 For RO Exam The following conditions exist,

- Reactor core thermal power is 100% of rated

- APRM Channel B is reading 100%

- The lowest reading LPRM input to APRM B isLPRM 06-31D and it is reading 50%

LPRM 06-31D then failed to its full scale value of 125% and subsequently was bypassed.

Which one of the following describes how the indicated value of APRM B was affected by (1) the LPRM failing upscale and (2) after the failed LPRM was bypassed?

(1) with failed LPRM (2) after failed LPRM was bypassed A. It indicated power greater than 100% It indicated power less than 100%

B. It indicated power greater than 100% It indicated power greater than 100%

C. It indicated power equal to 100% It indicated power greater than 100%

D. It indicated power equal to 100% It indicated power less than 100%

ANSWER: B (1) Raises the flux sum of LPRM inputs, raising average flux calculated by averaging amplifier (2) When bypassed lowers count by one and removes what was a low flux reading input so new APRM average of remaining LPRMs will be higher for the same core power.

A - See (2)

C - See (1)

D - See (1) & (2)

K/A Statement: Knowledge of the effect a loss or malfunction of the APRM/LPRM will have on reactor power indication.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 215005 K3.05 3.8 3.8 41.2 STM-503, Pages 60 & 61 STM-503 OBJ- H31 TIER/GROUP: 2/1 LOK: H LOD: 3 ORIGIN: NEW HISTORY: BANK QID: 952

QUESTION NO. 39 For RO Exam Following a plant transient, RCIC is being operated with its flow controller in AUTO set at 600 gpm. RCIC is aligned with flow to both the RPV and the CST to maintain RPV water level AND remove decay heat from the RPV.

As RPV water level begins rising and approaches the high end of the level control band provided by the CRS, which one of the following control manipulations at P601 will lower RCIC flow to the RPV while maintaining maximum decay heat removal by RCIC?

A. Throttle E51-F013, RCIC INJECT ISOL VALVE closed.

B. Adjust RCIC Flow Controller tape setting to a lower value.

C. Throttle E51-F022, RCIC TEST BYPASS VLV TO CST open.

D. Throttle E51-F022, RCIC TEST BYPASS VLV TO CST closed.

ANSWER: C Lowers injection flow while maintaining total flow and max decay heat removal.

A - Will go fully closed reducing decay heat removal.

B - Total system flow is lowered by lowering steam flow to RCIC turbine reducing decay heat removal.

D - Will raise, not lower flow to RPV.

K/A Statement: Ability to manually operate (RCIC)/monitor in the control room reactor water level.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 217000 A4.05 4.1 4.1 41.7 SOP-0035, Page 11 STM-209 OBJ- H12 41.8 41.10 TIER/GROUP: 2/1 LOK: H LOD: 3 ORIGIN: NEW HISTORY: BANK QID: 943

QUESTION NO. 40 For RO Exam Shortly after an automatic initiation, the RCIC turbine tripped. On Main Control Room Panel P601, the DIV 1 RCIC ISOL TURB EXH PRESS HIGH annunciator is alarming.

Under these conditions, the RCIC turbine Trip & Throttle valve may be reset . . .

A. using the Trip & Throttle Valve hand switch in the control room after the trip condition is cleared.

B. locally at the turbine after the trip condition is cleared.

C. locally at the turbine at any time even if the condition is not cleared.

D. using the trip reset push button on panel P601, in the control room after the condition is clear.

ANSWER: A K/A Statement: Knowledge of annunciators alarms and indications, and use of the response instructions.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 217000 2.4.31 3.3 3.4 41.10 ARP-P601-21-C03 STM-209 OBJ- H10 41.7 41.8 TIER/GROUP: 2/1 LOK: F LOD: 2 ORIGIN: BANK HISTORY: River Bend NRC Exam 7/1997 BANK QID: 820

QUESTION NO. 41 For RO Exam An earthquake has resulted in a Loss of Offsite Power and the following conditions exist:

- The reactor is shutdown, all rods inserted.

- Drywell pressure is 2.2 psig (changed to 2.2 psid during exam administration).

- RHR A is the only ECCS pump running and aligned to the RPV.

- RPV pressure is 500 psig and slowly lowering.

- RPV level is -163" and slowly lowering.

EOP-0004, Alternate Level Control has just been entered after determining that RPV level cannot be restored and maintained above -162 inches. The CRS has directed the Unit Operator (UO) to inhibit ADS per Step ALC-2.

The UO places the DIV 2 ADS INHIBIT switch in INHIBIT, but the DIV 1 ADS INHIBIT switch will NOT rotate to the INHIBIT position.

What action(s), if any, are appropriate to Inhibit ADS?

A. No action required, Div 1 ADS logic will not actuate without the LPCS pump running.

B. RHR A pump must be tripped to prevent ADS from initiating.

C. The DIV 1 ADS TIMER/LEVEL 3 SEAL-IN RESET Pushbutton must be depressed at least every 105 seconds to prevent ADS from initiating.

D. The DIV 1 ADS TIMER/LEVEL 3 SEAL-IN RESET Pushbutton must be depressed at least every 5 minutes to prevent ADS from initiating.

ANSWER: C A - Div 1 ADS logic will initiate with RHR A running B - RHR A is currently the only injection source available and should not be shutdown before adequate core cooling is assured.

D - With high drywell pressure, the 5 minute timer for Level 1 is not affecting the ADS logic.

K/A Statement: Ability to predict impacts of initiation signals present on the ADS; and use procedures to correct, control, or mitigate.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 218000 A2.06 4.2 4.3 41.10 SOP-0011, Page 19 STM-202 OBJ- H7 41.7 TIER/GROUP: 2/1 LOK: H LOD: 3 ORIGIN: NEW HISTORY: BANK QID: 910

QUESTION NO. 42 For RO Exam A Loss of RPS Bus A has occurred. After the RPS bus is transferred to alternate power, AOP-0010 directs the operator to depress the INBD and OUTBD SEAL-IN RESET pushbuttons to reset the CRVICS logic.

The INBD SEAL-IN RESET pushbutton must be depressed to reset the trip in which CRVICS logic channel that was sealed in on the loss of RPS Bus A?

A. B Channel of the BOP Isolation Logic B. B Channel of the MSIV Isolation Logic C. C Channel of the BOP Isolation Logic D. C Channel of the MSIV Isolation Logic ANSWER: D A - INBD pushbutton resets but did not lose power on loss of RPS Bus A.

B - INBD pushbutton resets but logic is powered by RPS Bus B.

C - INBD pushbutton resets and lost power, but single logic channel trip does not seal-in. Resets when re-enrgized.

K/A Statement: Knowledge of the electrical power supplies to the PCIS/NSSSS logic power supplies.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 223002 K2.01 2.4 2.7 41.7 STM-058, Pages 8 & 10 STM-058 OBJ- H3 AOP-0010, Page 8 TIER/GROUP: 2/1 LOK: F LOD: 3 ORIGIN: NEW HISTORY: BANK QID: 911

QUESTION NO. 43 For RO Exam A faulty MSIV pilot solenoid valve results in a FAST CLOSURE of one MSIV at 100% power during a surveillance test of the CRVICS MSIV isolation logic. Which one of the following describes the result of this condition?

RPV pressure will . . .

A. rise rapidly, then lower due to a MSIV closure scram.

B. rise slightly as the EHC stabilizes turbine throttle pressure.

C. rise rapidly until a High RPV Pressure reactor scram occurs.

D. remain constant due to the EHC control actions and steam flow rising in the three other main steam lines.

ANSWER: C A - MSIV closure scram requires at least two MSIVs closing to actuate.

B - EHC will not be able to stabilize pressure before high press. scram is reached.

D - Pressure will rise, EHC will not be able to stabilize pressure before high press. scram is reached.

K/A Statement: Knowledge of the effect a loss or malfunction of the PCIS/NSSSS will have on reactor pressure.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 223002 K3.07 3.7 3.8 41.5 USAR Page 15.2-20 HLO-316 OBJ- 2 TIER/GROUP: 2/1 LOK: H LOD: 2 ORIGIN: NEW HISTORY: BANK QID: 912

QUESTION NO. 44 For RO Exam A plant scram has occurred as a result of an MSIV Closure. The ATC Operator is controlling level between 10" and 51" with MANUAL operation of the Startup Feedwater Regulating Valve. The Unit Operator is controlling pressure between 800 and 1000 psig by cycling an SRV as necessary. Currently, the following conditions exist:

- RPV level is stable at 30" with the Startup FWRV closed.

- RPV pressure is approaching 1000 psig.

Which one of the following describes the expected RPV level response as the Unit Operator cycles one SRV open, then closed to lower pressure to 800 psig?

Assuming NO OTHER OPERATOR ACTION(S), when the SRV is opened, RPV water level will . . .

A. rise while the SRV is open, then drop and stabilize at a level slightly below 30" when the SRV is closed.

B. rise while the SRV is open, then drop and stabilize at 30" when the SRV is closed.

C. gradually lower, then rise and stabilizes at nearly 30" when the SRV is closed.

D. gradually lower, then stabilize at the level reached at the time the SRV is closed.

ANSWER: A Rises due to core voiding then drops to below original level due to inventory removed.

B - Loss of inventory through SRV results in final level less than original (30").

C - rises due to core voiding while SRV is open D - rises due to core voiding while SRV is open K/A Statement: Ability to predict/monitor changes in reactor water level associated with operating SRV controls.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 239002 A1.05 3.7 3.8 41.5 USAR Figure 15.2-8 HLO-315 OBJ- 2 TIER/GROUP: 2/1 LOK: H LOD: 3 ORIGIN: NEW HISTORY: BANK QID: 913

QUESTION NO. 45 For RO Exam Which one of the following describes the plant response to the loss of ONE steam flow signal input to the Feedwater Level Control System while operating in three element control at 50% power?

A. Reactor level will rise high enough to cause a High Reactor Water Level scram.

B. Reactor level will rise but stabilize at a higher level below the High Reactor Water Level scram setpoint.

C. Reactor level will drop low enough to cause the Low Reactor Water Level scram.

D. Reactor level will lower, but stabilize at a lower level above the Low Reactor Water Level scram setpoint.

ANSWER: D A - Will lower total SF causing SF/FF error closing FWRVs and lowering level.

B - Will lower total SF causing SF/FF error closing FWRVs and lowering level.

C - At 50% power the SF/FF error will be nulled by level error before reaching Level 3 9.7" K/A Statement: Knowledge of the physical connections/cause-effect relationships between Reactor Water Level Control and main steam flow.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 259002 K1.02 3.2 3.3 41.5 STM-107, Page 50 STM-107 OBJ- H7 41.14 TIER/GROUP: 2/1 LOK: H LOD: 3 ORIGIN: NEW HISTORY: BANK QID: 941

QUESTION NO. 46 For RO Exam With containment pressures above 2 psig, the EOP's direct the use of Enclosure 21, Emergency Containment Venting rather than normal containment venting when it becomes necessary to vent containment.

Above 2 psig, Emergency Containment Venting is used to . . .

A. bypass Standby Gas Treatment which may fail at pressures above 2 psig.

B. bypass the Containment Ventilation ductwork which may fail at pressures above 2 psig.

C. bypass the Annulus Mixing System which may fail at pressures above 2 psig.

D. align the Standby Gas Treatment suction to the Annulus Pressure Control System for a more rapid containment pressure reduction.

ANSWER: B A - SGTS is used in Emergency Containment Venting.

C and D - SGTS is aligned to Annulus Mixing, not APC.

K/A Statement: Knowledge symptom based EOP mitigation strategies.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 261000 2.4.6 3.1 4 41.8 EOP-0005, Encl 21 HLO-514 OBJ- 5 41.9 EPSTG-0002, B-8-12 41.10 TIER/GROUP: 2/1 43.5 LOK: F LOD: 3 ORIGIN: NEW HISTORY: BANK QID: 812

QUESTION NO. 47 For RO Exam The plant is operating at rated conditions when a fault in the primary windings of transformer RCS-X1A results in NPS-SWG1A voltage lowering to 50% of rated.

Which one of the following describes the (1) final state of Reactor Recirculation Pump A and (2) any actions required for this condition (NO automatic scram occurred)?

A. (1) Recirc Pump A is operating at slow speed (2) Lower flow in Recirc Loop B to < 33 kgpm B. (1) Recirc Pump A is operating at slow speed (2) Downshift Recirc Pump B to slow speed C. (1) Recirc Pump A is tripped (2) Lower flow in Recirc Loop B to < 33 kgpm D. (1) Recirc Pump A is tripped (2) Initiate a Manual Scram ANSWER: C A - Recirc Pump A will not start on slow speed, LFMG also lost power from NPS-SWG1A and if A in slow no requirement to lower flow in B.

B - Recirc Pump A will not start on slow speed LFMG also lost power from NPS-SWG1A and would deliberately enter Power-to-flow exclusion zone on B downshift D - Scram not required by procedure K/A Statement: Ability to predict the impacts of exceeding voltage limitations on AC Distribution; and use procedures to correct, control, or mitigate.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 262001 A2.09 3.1 3.4 41.4 GOP-0004, Page 7 HLO-503 OBJ- 2 41.7 ARP-P680-4A-A01 TIER/GROUP: 2/1 LOK: F LOD: 3 ORIGIN: NEW HISTORY: BANK QID: 914

QUESTION NO. 48 For RO Exam The UO is preparing to parallel the Division I Standby Diesel Generator with ENS-SWG1A through ENS-ACB07, STBY D/G A OUTPUT BRKR. At P877, the UO has the following indications:

- V1IN-1SYDA01 (Incoming Voltage): 120 VAC

- V1RUN-1SYDA01 (Running Voltage): 120 VAC

- SY-1-1SYDA01 (Stby Bus A Synchroscope): Rotating slowly in the SLOW direction Which one of the following describes the action that must be taken by the UO to ensure that the EDG will pickup some KW load when it's output breaker is closed connecting it to the ENS-SWG1A bus?

A. Raise Incoming Voltage to be slightly higher than Running Voltage.

B. Raise Running Voltage to be slightly higher than Incoming Voltage.

C. Raise EDG speed until the synchroscope is rotating slowly in the FAST direction.

D. Lower EDG speed until the synchroscope is rotating slowly in the FAST direction..

ANSWER: C K/A Statement: Knowledge of the operational implications of the principle involved with paralleling two AC source as applied to AC Distribution.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 262001 K5.01 3.1 3.4 41.7 SOP-0053 STM-309 OBJ- H3 TIER/GROUP: 2/1 LOK: H LOD: 2 ORIGIN: MODIFIED HISTORY: River Bend NRC Exam 10/2000 BANK QID: 818

QUESTION NO. 49 For RO Exam The plant is operating at 100% power. An inverter malfunction results in the loss of Instrument Bus VBN-PNL01B1 supplying power to the Feedwater Level Control System.

Which one of the following describes the effect this loss of power will have on the Feedwater Regulating Valves?

A. No effect.

B. Fail shut.

C. Fail open.

D. Lock up.

ANSWER: D A - Will have control air and signal to close but will not move due to lock up B - Will have control air and signal to close but will not move due to lock up C - Would be closing if not locked up K/A Statement: Knowledge of the physical connections/cause-effect relationships between UPS (AC/DC) and Feedwater Level Control.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 262002 K1.01 2.8 3 41.7 AOP-0042, Att. 8, Page 3 HLO-540 OBJ- 4 TIER/GROUP: 2/1 LOK: F LOD: 2 ORIGIN: NEW HISTORY: BANK QID: 951

QUESTION NO. 50 For RO Exam The plant was operating at 100% power when a turbine trip occurred concurrent with a loss of 125 VDC bus ENB-PNL-02B.

The following conditions exist:

- The reactor is shutdown (all rods in)

- RPV pressure is 1050 psig

- RPV level is +4 inches on narrow range indication

- All MSIVs are closed Which one of the following statements correctly describes the pressure control for the plant?

A. Due to a loss of ENB-PNL02B, the SRVs are unable to actuate on high pressure RELIEF mode or MANUAL mode and will only control pressure in the SAFETY mode.

B. Due to a loss of ENB-PNL02B, the SRVs will actuate on high pressure RELIEF mode or MANUAL mode utilizing the "A" SRV solenoid ONLY.

C. Due to a loss of ENB-PNL02B, the SRVs are unable to actuate on high pressure RELIEF mode but may be manually operated using the "A" SRV solenoid.

D. Due to a loss of ENB-PNL02B, the SRVs will not operate in the Low-Low Set mode of operation however, the high pressure RELIEF mode and MANUAL mode is available using either the "A" or "B" SRV solenoids.

ANSWER: B K/A Statement: Knowledge of the effect a loss or malfunction of the DC Distribution will have on systems with DC components.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 263000 K3.03 3.4 3.8 41.7 AOP-0014, Att. 2 STM-109 OBJ- H4 41.4 ARP-P601-19A-C10 TIER/GROUP: 2/1 LOK: H LOD: 3 ORIGIN: BANK HISTORY: River Bend NRC Exam 10/2000 BANK QID: 679

QUESTION NO. 51 For RO Exam The Division 1 Emergency Diesel Generator (EDG) operability surveillance test STP-309-0201 is in progress with the following conditions:

- Div. 1 EDG is running and parallel to offsite via ENS-SWG1A.

- The STP is completed and the UO is unloading the Div 1 EDG.

- The EDG load has been lowered to 150 KW when a governor problem causes the diesel to reverse power.

Based on the above conditions, complete the statement that correctly predicts the response of the Div. 1 EDG and its output breaker, ENS-ACB07.

The reverse power condition will cause a . . .

A. trip of the output breaker and the EDG continues to run unloaded.

B. trip of the output breaker and the EDG will subsequently trip on overspeed.

C. generator lockout (86GB) resulting in a diesel shutdown and trip of the output breaker.

D. DIESEL GENERATOR EGS-EG1A SYSTEM TROUBLE alarm indicating the EDG is running with a reverse power condition.

ANSWER: C A. Logic for reverse Power and Diesel in Normal Start mode trips both ENS-ACB07 and energizes EGS-SOV24A Diesel Stop Solenoid.

B. following a reverse power condition the fuel setting for the EDG will be at minimum NO overspeed.

D. Same as A.

K/A Statement: Ability to predict/monitor maintaining minimum load associated with operating EDG controls.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 264000 A1.09 3 3.1 41.7 ARP-P877-31A-H02 STM-309S OBJ- H5 41.8 TIER/GROUP: 2/1 LOK: H LOD: 2 ORIGIN: BANK HISTORY: Peach Bottom 2 NRC Exam 9/2002 (INPO 24743) BANK QID: 916

QUESTION NO. 52 For RO Exam The instrument air compressors are all available and operating with the local SEQUENCE CONTROL switch in Postion 3 (C-A-B). Only the IAS-C2C compressor has been operating to maintain system pressure.

A relay failure in the control circuit for compressor IAS-C2C causes it to shutdown.

With no change in Instrument Air System usage, which one of the following describes the effect of the compressor shutdown on the Instrument Air System?

A. Compressor IAS-C2A operates alone to maintain a lower header pressure.

B. Compressor IAS-C2B operates alone to maintain a lower header pressure.

C. Both Compressors IAS-C2Aand C2B operate to maintain the same header pressure.

D. Both Compressors IAS-C2Aand C2B operate to maintain a lower header pressure.

ANSWER: A B - Sequencer setting cycles C2A at a higher pressure than C2B, so C2B will not start.

C - With no air load change the C2A can maintain pressure but lower than C2C, sequencer does not alternate the operating compressor.

D - With no air load change the C2A can maintain pressure and C2B start pressure is below C2A.

Sequencer does not alternate the operating compressor.

K/A Statement: Knowledge of the effect a loss or malfunction of breakers, relays and disconnects will have on the Instrument Air System.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 300000 K6.12 2.9 2.9 41.4 STM-121, Pages 13 & 15 STM-121 OBJ- H3 TIER/GROUP: 2/1 LOK: F LOD: 2 ORIGIN: NEW HISTORY: BANK QID: 917

QUESTION NO. 53 For RO Exam The plant is operating at rated conditions with no equipment out of service. The Reactor Plant Component Cooling Water (CCP) System is in normal operation with CCP-P1A and P1B running. CCP-P1C is in standby.

RPCCW SYSTEM LOW HEADER PRESSURE alarmed on P870-55. An investigation revealed that the CCP header pressure transmitter, PT-127 has failed low. No other alarms or automatic actions occurred.

What automatic feature failed to function as designed?

A. Trip of the running CRD pump.

B. Start of standby pump CCP-P1C.

C. Initiation of both Standby Service Water Divisions.

D. Isolation of cooling water to the CCP heat exchangers.

ANSWER: B A - Either CCP vital loop at <56 psig.

C - Both CCP vital loops at <56 psig.

D - Div II CCP vital loop at <56 psig.

K/A Statement: Knowledge of design feature(s)/interlocks which provide for automatic start of standby pump.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 400000 AK4.01 3.4 3.9 41.4 ARP-P870-55-F04 STM-115 OBJ- H4 STM-115, Page 9 TIER/GROUP: 2/1 LOK: F LOD: 2 ORIGIN: NEW HISTORY: BANK QID: 405

QUESTION NO. 54 For RO Exam The Control Rod Drive Hydraulic System is being placed in service in preparation for a cold reactor startup.

The next step in SOP-0002, Control Rod Drive Hydraulics, for placing the CRD System in Operation is as follows:

"Using C11-R600, CRD HYDRAULICS FLOW FLOW CONTROLLER C11-F002A/B in MANUAL mode, and C11-F003, CRD DRIVE WATER PRESSURE CONTROL VAVLE, establish a Drive Water Differential Pressure of 250 psid at a flow rate of 41 to 49 gpm."

Based on the conditions below, (1) What action(s) is/are necessary to accomplish the step and (2) why must CRD Drive Header P be raised to 250 psid?

- CRD Drive Header P is 200 psid

- CRDH System Flow is 41 gpm A. (1) Throttle C11-F003 further closed and adjust C11-R600 further closed (2) to establish normal rod movement speed.

B. (1) Throttle C11-F003 further closed and adjust C11-R600 further open (2) to establish normal rod movement speed.

C. (1) Throttle C11-F003 further open and adjust C11-R600 further closed (2) to meet Tech Spec control rod scram time limits.

D. (1) Throttle C11-F003 further open and adjust C11-R600 further open (2) to meet Tech Spec control rod scram time limits.

ANSWER: B A - Closing both will lower system flow out of the flow band required by the step.

C - Actions would lower P and adjustment not required to meet tech spec scram times.

D - Not required to meet tech spec scram times.

K/A Statement: Ability to predict the impacts of low drive header pressure on CRDH; and use procedures to correct, control, or mitigate.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 201001 A2.14 2.8 2.8 41.6 SOP-0002, Page 8 STM-052 OBJ- 1 43.6 STM-052, Page 19 TIER/GROUP: 2/2 LOK: H LOD: 3 ORIGIN: NEW HISTORY: BANK QID: 918

QUESTION NO. 55 For RO Exam During withdrawal of a control rod, a stabilizing valve ____(1)_____ to maintain _________(2)____________

constant.

(1) (2)

A. opens drive water pressure B. opens cooling water flow C. closes drive water pressure D. closes cooling water flow ANSWER: C A - Stab valve closes B - Stab valve closes and cooling water flow lowers D - Cooling water flow lowers K/A Statement: Ability to predict/monitor changes in CRD drive pressure with operating the CRDM controls.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 201003 A1.02 2.8 2.8 41.2 STM-052, Page 18 STM-052 OBJ- 2 41.14 TIER/GROUP: 2/2 LOK: F LOD: 2 ORIGIN: NEW HISTORY: BANK QID: 813

QUESTION NO. 56 For RO Exam RCI&S indicates power below the High Power Set Point. APRMs indicate a steady state reactor power of 71%.

Which one of the following can cause the discrepancy above?

A. A failed open Turbine Bypass Valve B. A Recirc flow control valve runback C. A loss of feedwater heating D. A xenon transient ANSWER: A With BPV open, pressure regulator will reduce steam flow through turbine reducing 1st stage press.

B - First stage shell pressure will follow power C - First stage shell pressure will follow power D - First stage shell pressure will follow power, APRMs will have representative sample of core K/A Statement: Knowledge of the physical connections/cause-effect relationships between RCIS and the reactor pressure control system.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 201005 K1.02 3.3 3.5 41.5 STM-500, Page 34 STM-500 OBJ- H5 41.6 TS Bases Page B 3.3-47 TIER/GROUP: 2/2 LOK: H LOD: 3 ORIGIN: NEW HISTORY: BANK QID: 811

QUESTION NO. 57 For RO Exam Which one of the following design features or interlocks prevents Reactor Recirc Pump damage from overheating at minimum flow conditions?

A. The pump start interlock requiring FCV position to be at 0% INDICATED position.

B. The design of the FCVs being physically 22% open at the 0% INDICATED position.

C. The capability of the Recirc Pump seal cooler to remove no-flow pump heat.

D. The pump downshift on low steam dome to loop suction T.

ANSWER: B A - Places FCV at minimum position to minimize pump starting current.

C - Does NOT have the capacity to remove enough heat from pump casing.

D - Protects the pump from inadequate NPSH.

K/A Statement: Knowledge of the Recirculation System design feature(s)/interlocks which provide for pump minimum flow limit.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 202001 K4.09 2.7 2.9 41.3 STM-053, Page 16 STM-053 OBJ- H2 TIER/GROUP: 2/2 LOK: F LOD: 2 ORIGIN: NEW HISTORY: BANK QID: 919

QUESTION NO. 58 For RO Exam The plant is operating at rated conditions with all systems in their normal full power lineup. A bus fault on 480V NHS-MCC10B in the Control Building causes a trip of its power supply breaker from NJS-SWG1D.

Following this bus loss, what is the status of the RWCU System?

A. The Inboard Containment isolation valves closed and both RWCU pumps tripped.

B. The Inboard Containment isolation valves closed and the 'B' RWCU pump tripped.

C. The Outboard Containment isolation valves closed and both RWCU pumps tripped.

D. The RWCU System continues to operate normally.

ANSWER: A Loss of RPS power to Div 2 Isolation Logic causes Inboard isolation resulting in pump trips due to Inboard isolation valve F001 closure.

B - Both pumps trip on loss of suction lineup due to F001 closure.

C - Outboard Isolation Logic remains energized.

D - Loss of power to Div 2 Isolation Logic causes Inboard isolation causes pump trips.

K/A Statement: Knowledge of the effect a loss or malfunction of AC power will have on RWCU.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 204000 K6.05 2.6 2.6 41.7 STM-601, Page 13 STM-601 OBJ- H7 STM-508, Page 36 AOP-0003, Page 18 TIER/GROUP: 2/2 LOK: F LOD: 3 ORIGIN: NEW HISTORY: BANK QID: 920

QUESTION NO. 59 For RO Exam While making local adjustments to the MSR-1 heating steam valves at 60% power, the following changes in Main Steam Line Flow are observed on P680:

- MSL A flow rises from 2 Mlbm/hr to 2.9 Mblm/hr

- MSL B flow falls from 1.9 Mlbm/hr to 1.6 Mblm/hr

- MSL C flow falls from 2.1 Mlbm/hr to 1.8 Mblm/hr

- MSL D flow falls from 2 Mlbm/hr to 1.7 Mblm/hr The above changes in MSL flows indicate which one of the following is full open?

A. SRV F047A B. Turbine Control Valve, CV-1 C. Turbine Steam Bypass Valve, BPV-1 D. MSR-1 heating steam supply High Load valve ANSWER: A F047A is downstream of MSL A flow elbow. EHC causes flow in other MSLs to lower.

B - TCV-1 is downstream of the Equalizing header and would cause all steam line flows to rise.

C - The BPV manifold is connected to Equalizing header and would cause all steam line flows to rise.

D - High Load valve is connected to equalizing header and would cause all steam line flows to rise.

K/A Statement: Ability to manually operate/monitor Main and Reheat Steam system flow in the control room.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 239001 A4.03 3.5 3.5 41.5 AOP-0035, Page 3 STM-109 OBJ- H13 STM-109, Pages 8 & 27 TIER/GROUP: 2/2 LOK: H LOD: 2 ORIGIN: NEW HISTORY: BANK QID: 921

QUESTION NO. 60 For RO Exam - DELETED FROM EXAM A LOCA has occurred inside the Drywell. Twenty minutes later the following annunciators were alarming:

- PERMISSIVE TO OPERATE INBOARD MSIV PLCS

- PERMISSIVE TO OPERATE OUTBOARD MSIV PLCS Both Divisions of the Main Steam Line Positive Leakage Control System were then initiated. Six minutes later the following annunciator is received:

- INBOARD MSIV PLCS HIGH AIR FLOW What should be the indicated position of the following valves on the Inboard MSIV PLCS control section of backpanel P655?

Injection Valve F005 Drain Valve F006 Isolation Valve F007 A. Open Closed Closed B. Closed Open Closed C. Closed Closed Open D. Closed Closed Closed ANSWER: D A - F005 should be closed to stop excessive air loss.

B - Normal configuration before initiation or if RPV pressure >25 psig. F006 should be closed.

C - F007 should be closed to isolate any possible rad release path if a break exists upstream.

K/A Statement: Ability to manually operate/monitor MSIV Leakage Control status lights and alarms in the control room.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 239003 A4.07 2.8 2.7 41.9 ARP-601-17A-C05 STM-208 OBJ- H4 TIER/GROUP: 2/2 LOK: F LOD: 3 ORIGIN: NEW HISTORY: BANK QID: 922

QUESTION NO. 61 For RO Exam The following conditions exist on the Main Generator:

- MVARs = negative 125 (leading power factor)

- MW = 500

- VOLTAGE REGULATOR MODE SELECT is in AUTO If the LOWER pushbutton on the VOLTAGE REGULATOR AUTO ADJUST is depressed, which one of the following describes the expected change in Main Generator output parameters?

A. MW will remain the same, MVARs will become more negative.

B. MW will remain the same, MVARs will become less negative.

C. MW will lower, MVARs will become more negative.

D. MW will lower, MVARs will remain the same.

ANSWER: A B - Must raise Auto voltage setting to reduce negative MVARs.

C - MW will not change, and must raise Auto voltage setting to reduce negative MVARs.

D - MW will not change, but MVARs will change with voltage adjust.

K/A Statement: Ability to monitor auto operations of the Main Turbine Generator output voltage/reactive load.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 245000 A3.10 2.5 2.6 41.7 HLO-154a, Page 59 STM-310 OBJ-STM-310, Pages 34 & Fig. 9 TIER/GROUP: 2/2 LOK: H LOD: 3 ORIGIN: NEW HISTORY: BANK QID: 404

QUESTION NO. 62 For RO Exam The plant is operating at 100 % power with Offgas Post Treatment Radiation Monitor Channel 'B' in a downscale trip condition when the Offgas Post Treatment Radiation Monitor 'A' channel fails high (to full scale).

Which one of the following describes the effects on the Offgas System and the Main Condenser?

A. Offgas will shift into a bypass mode to maintain Main Condenser vacuum constant.

B. Offgas will isolate only the charcoal adsorbers inlet and outlet valves causing Main Condenser vacuum to be lost.

C. Offgas will continue to operate normally to maintain Main Condenser vacuum constant.

D. Offgas will isolate causing Main Condenser vacuum to be lost.

ANSWER: D K/A Statement: Knowledge of the effect a loss or malfunction of the Offgas will have on condenser vacuum.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 271000 K3.01 3.5 3.5 41.4 ARP-P601-22A-E03 STM-606 OBJ- H4 ARP-P601-22A-A03 TIER/GROUP: 2/2 LOK: H LOD: 3 ORIGIN: MODIFIED HISTORY: River Bend NRC Exam 2/1999 BANK QID: 881

QUESTION NO. 63 For RO Exam Given the following conditions:

- Reactor water level is -90 inches and lowering.

- Drywell pressure is 2.2 psig (changed to 2.2 psid during exam) and rising.

- Smoke from an outside fire is entering the Control Room.

An operator is attempting to manually place the Control Room ventilation in the smoke removal mode.

Under these conditions the Control Room Smoke Removal Dampers (AOD 107/108) will:

A. open and the Smoke Removal Fan will start.

B. open but the Smoke Removal Fan will be interlocked off.

C. remain closed and the Smoke Removal Fan will run on recirc.

D. remain closed and the Smoke Removal Fan will be interlocked off.

ANSWER: D K/A Statement: Ability to monitor automatic operations of the Fire Protection System fire dampers.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 600000 AK2.01 2.6 2.7 41.4 AOP-0003, Pages 10 & 19 STM-402 OBJ- 7 STM-402, Page 11 & 23 TIER/GROUP: 2/2 LOK: H LOD: 3 ORIGIN: BANK HISTORY: River Bend NRC Exam 7/1997 BANK QID: 167

QUESTION NO. 64 For RO Exam A pipe rupture has resulted in a complete loss of Normal Service Water. All automatic actions for the loss of Normal Service Water have occurred.

Which one of the following describes how this event ultimately affects the Containment Unit Coolers?

A. The cooling capability of HVR-UC1A will be lost and cannot be restored.

B. The cooling capability of HVR-UC1B will be lost and cannot be restored.

C. The cooling capability of HVR-UC1C will be lost and cannot be restored.

D. Loss of Normal Service Water will have no affect on the Containment Unit Coolers.

ANSWER: C Loss of NSW will result in loss of TB Chill Water the only cooling to UC1C.

A - Loss of NSW will result in loss of TB Chill Water to UC1A, but SSW can be aligned to restore.

B - Loss of NSW will result in loss of TB Chill Water to UC1B, but SSW can be aligned to restore.

C - Loss of NSW will result in loss of TB Chill Water to all three UCs.

K/A Statement: Knowledge of the effect a loss or malfunction of the applicable component cooling water system will have on the Plant Ventilation.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 288000 K6.02 2.5 2.5 41.4 STM-403, Fig 3 STM-403 OBJ- H11 41.9 AOP-0009, Page 3 SOP-0059, Page 41 TIER/GROUP: 2/2 LOK: F LOD: 2 ORIGIN: NEW HISTORY: BANK QID: 924

QUESTION NO. 65 For RO Exam Following a LOCA, Drywell pressure is 1.80 psid. The B Charcoal Filter Train of the Control Room HVAC is tagged out for CR Filter Unit Fan HVC-FN1B replacement. The following indication exists for A Charcoal Filter Train in the Control Room on P863:

- Filter Inlet Damper HVC-AOD43A - BOTH red and green lights lit

- CR Filter Unit Fan HVC-FN1A - green light lit

- Filter Fan Discharge Damper HVC-AOD3A - red light lit All other Control Room Ventilation automatic actions have occurred. Which one of the following describes the actions required for the above conditions and the expected results?

A. Locally open HVC-AOD43A fully in order to start HVC-FN1A and establish POSITIVE pressure in the control room.

B. Locally open HVC-AOD43A fully in order to start HVC-FN1A to establish NEGATIVE pressure in the control room.

C. Place the P863 control switch for HVC-FN1A to START and establish POSITIVE pressure in the control room.

D. Place the P863 control switch for HVC-FN1A to START to establish NEGATIVE pressure in the control room.

ANSWER: A B - Will establish a positive pressure in the control room.

C - Fan can't be started until inlet damper is full open.

D - See B and C.

K/A Statement: Ability to predict impact of Control Room HVAC reconfiguration failure and correct,control, or mitigate.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 290003 A2.03 3.4 3.6 41.7 SOP-0058, Page 11 STM-402 OBJ- H7 STM-402, Page 13 TIER/GROUP: 2/2 LOK: H LOD: 3 ORIGIN: BANK HISTORY: River Bend NRC Exam 2/2003 BANK QID: 864

QUESTION NO. 66 For RO Exam The following conditions exist:

- Reactor coolant temperature is 135°F.

- All ECCS systems are in standby.

- The Reactor Mode Switch is in SHUTDOWN.

- All reactor vessel head closure bolts are fully tensioned.

- Primary and Secondary Containment are SET (OPERABLE).

Which one of the following is the Plant Operational Mode?

A. Mode 2 B. Mode 3 C. Mode 4 D. Mode 5 ANSWER: C K/A Statement: Ability to determine Mode of Operation.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 2.1.22 2.8 3.3 41.5 TS 1.1-1 HLO-419 OBJ- 4 43.2 TIER/GROUP: 3 LOK: H LOD: 2 ORIGIN: MODIFIED HISTORY: River Bend NRC Exam 2/2003 BANK QID: 870

QUESTION NO. 67 For RO Exam Which one of the following describes the conventions used to depict:

(1) the state of electrical relays in a S & W Electrical Schematic Drawing (ESK) and (2) the state of manually-operated gate or globe valves in a EOI Piping and Instrumention Diagram (PID)?

A. (1) ESK relays are shown in their energized state.

(2) PID valve positions are shown for the plant in normal operating mode.

B. (1) ESK relays are shown in their de-energized state.

(2) PID valve positions are shown for the plant in normal operating mode.

C. (1) ESK relays are shown in their energized state.

(2) PID valve positions are shown for the plant in shutdown mode.

D. (1) ESK relays are shown in their de-energized state.

(2) PID valve positions are shown for the plant in shutdown mode.

ANSWER: B A - Relays shown de-energized.

C - Relays shown de-energized. Valves in normal operating mode.

D - Valves in normal operating mode.

K/A Statement: Ability to obtain and interpret station electrical and mechanical drawings.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 2.1.24 2.8 3.1 41.7 Print Reading Handout, Page HLO-542 OBJ- 3 PID Notes TIER/GROUP: 3 LOK: F LOD: 2 ORIGIN: MODIFIED HISTORY: Browns Ferry NRC Exam 6/1995 BANK QID: 925

QUESTION NO. 68 For RO Exam Which of the following describes how an independent verification is performed on a valve that is already locked open per a valve lineup?

The independent verifier shall . . .

A. verify the locking device is in place as required.

B. remove the locking device, verify the valve is fully open and reinstall the locking device.

C. attempt to move the valve in the closed direction to verify the locking device holds the valve open.

D. have another individual verify the position and then verify the locking device installed.

ANSWER: A K/A Statement: Knowledge of how to conduct and verify valve lineups.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 2.1.29 3.4 3.3 41.10 ADM-0076, Page 12 HLO-258 OBJ- 3 TIER/GROUP: 3 LOK: F LOD: 2 ORIGIN: BANK HISTORY: River Bend NRC Exam 1/1997 BANK QID: 949

QUESTION NO. 69 For RO Exam An in plant surveillance test is being performed. When the test was stopped for a lunch break, a test pressure guage was removed with OSM permission and individuals conducting the surveillance left the job site for 45 minutes.

Upon returning to the job site following lunch, the test pressure gage was reinstalled and the OSM notified.

What, as a MINIMUM, is required to proceed with the surveillance?

A. Verify prerequisites and re-perform all steps of the surveillance test.

B. Only verify that previously performed steps are in the same state, then continue.

C. Only verify that the prerequisites are met before continuing.

D. Verify prerequisites and previously performed steps are in the same state, then continue.

ANSWER: D A - Not required to reperform steps.

B - Must also verify prerequisites.

C - Must also verify previously performed steps.

K/A Statement: Knowledge of surveillance procedures.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 2.2.12 3 3.4 41.10 ADM-0015, Page 33 HLO-221 OBJ- 6 TIER/GROUP: LOK: F LOD: 2 ORIGIN: BANK HISTORY: River Bend NRC Exam 2/2003 BANK QID: 164

QUESTION NO. 70 For RO Exam During a refueling outage, fuel assemblies designated to be moved from the core to the spent fuel pool are being transferred from the core to the upper fuel storage racks. Which one of the following would require that the transfer of fuel be suspended?

A. Realigning SFC to place the B Cleanup pump on the Fuel Building Spent Fuel Pool.

B. Transferring fuel from the refuel floor to the Fuel Building with the Inclined Fuel Transfer System.

C. Moving fuel assemblies in the Fuel Building spent fuel pool.

D. Aligning SFC to lower water level several inches in the Fuel Building spent fuel pool.

ANSWER: A Potential to inadvertently lower level in refuel cavity due to many hidden pathways in SFC.

B - Both are allowed to be performed simultaneously.

C - Can do both simultaneously.

D - Exception made for this to make minor adjustments in level required during IFTS ops.

K/A Statement: Knowledge of refueling administrative requirements.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 2.2.26 2.5 3.7 41.10 SOP-0091, Page 5 STM-602 OBJ- H6 43.6 TIER/GROUP: 3 LOK: F LOD: 2 ORIGIN: NEW HISTORY: BANK QID: 927

QUESTION NO. 71 For RO Exam A 28 year old nuclear worker has been contracted to work during the upcoming refuel outage. His NRC Form 4 is current and his annual whole-body (TEDE) dose to date is 1.25 rem.

What is the MAXIMUM additional radiation dose he can be authorized to receive during the remainder of this year in accordance with NRC limits?

A. 1.75 rem B. 2.75 rem C. 3.75 rem D. 5.00 rem ANSWER: C K/A Statement: Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 2.3.4 2.5 3.1 41.12 RWT Page 22 RWT-013 OBJ- 30 TIER/GROUP: 3 LOK: H LOD: 2 ORIGIN: BANK HISTORY: River Bend NRC Exam 7/1997 BANK QID: 434

QUESTION NO. 72 For RO Exam The plant was operating at 100% power with the 'A' train of Steam Jet Air Ejectors in service. The Offgas Vent Discharge Isolation Valve, N64-F060, automatically closed due to high Offgas Post-treatment radiation levels.

The following are indicated on the Control Room Offgas Control Panel P845:

- Recombiner 'B' Purge Flow Valve, N64-SOV3B, is OPEN

- Prefilter Inlet Drain Valve, N64-F054, is OPEN

- Cooler Condenser Drain Valves, N64-F34A/B, are both CLOSED

- Holdup Line Drain Valve, N64-F023, is CLOSED With the above conditions, what operator action, if any, is required at P845?

A. Open the Holdup Line Drain Valve, N64-F023.

B. Close the Prefilter Inlet Drain Valve, N64-F054.

C. Close Recombiner 'B' Purge Flow Valve, N64-SOV3B.

D. No action required.

ANSWER: B Isolates loop seal drain to Chemical Drain Sump to prevent radioactive release to Turbine Bldg.

(failed to auto close on F060 closure)

A - Required Auto Isolation on closure of F060.

C - Required to be open with SJAE A in service.

D - Auto isolation action failed to occur (N64-F054 still open) requiring operator action to complete K/A Statement: Ability to control radiation releases.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 2.3.11 2.7 3.2 41.10 ARP-P601-22A-A03 STM-606 OBJ- H7 41.13 43.4 TIER/GROUP: LOK: H LOD: 2 ORIGIN: NEW HISTORY: BANK QID: 955

QUESTION NO. 73 For RO Exam A containment isolation has resulted in entry into AOP-0003, Automatic Isolations. Shortly after an annunciator alerts the crew that EOP entry is required.

At this point, a step yet to be completed in AOP-0003 can only be executed . . .

A. before the EOPs are entered.

B. after the EOPs have been exited.

C. concurrently with EOP execution if it does NOT degrade EOP-required equipment.

D. concurrently with EOP execution provided it is specifically directed in an EOP step.

ANSWER: C A - Can be executed concurrently.

B - Can be executed concurrently.

D - Not required and typically not in EOP steps.

K/A Statement: Knowledge of how the event-based emergency/abnormal operating procedures are used in conjunction with the symptom-based EOPs.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 2.4.8 3 3.7 41.10 EPSTG-0002, Page B-4-7 HLO-511 OBJ- 1 43.5 TIER/GROUP: 3 LOK: F LOD: 2 ORIGIN: NEW HISTORY: BANK QID: 928

QUESTION NO. 74 For RO Exam Should it become necessary to lower reactor level during an ATWS per EOP-0001A Step RLA-15, the following systems are specified for use to maintain level when injection is reinitiated in Step RLA-20:

Condensate/feedwater CRD RCIC RHR through SDC injection valves The reason only these systems are to be used is because . . .

A. these systems provide the cleanest source of water for injection into the reactor.

B. their point of injection ensures mixing of the cold injection water with warmer water prior to core entry.

C. these systems can operate automatically so the operator need only verify lineups when this step is reached.

D. at this point in the ATWS, reactor pressure precludes use of other systems.

ANSWER: B K/A Statement: Knowledge of the specific bases for EOPs.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 2.4.18 2.7 3.6 41.1 EPSTG-0002, B-7-30 HLO-513 OBJ- 4 41.2 41.5 TIER/GROUP: 3 41.10 LOK: F LOD: 2 43.6 ORIGIN: BANK HISTORY: River Bend NRC Exam 1/1995 BANK QID: 210

QUESTION NO. 75 For RO Exam A plant startup is in progress at 45% power following the upshift of both Reactor Recirc Pumps to fast speed.

Recirc flow is being raised when the RECIRC LOOP A LOW T annunciator alarms. The following conditions exist:

- PMS displays are out of service.

- Reactor Dome Pressure on P680 meter C33-R605 is 985 psig.

- A Recirc loop suction temperature on recorder B33-R604 is 538°F.

The CRS directs you to consult the ARP and validate the low T condition. 16 minutes later the alarm is still in and no automatic actions have occurred.

Which one of the following is the correct assessment of the alarm condition and required action? ARP for RECIRC LOOP A LOW T included in exam handout materials.

A. Alarm condition is NOT VALID and key operated switch B33-S125A should be placed in BYPASS.

B. Alarm condition IS VALID and the A Recirc Pump XFER TO LFMG pushbutton should be depressed.

C. Alarm condition IS VALID and both Recirc Pump XFER TO LFMG pushbuttons should be depressed.

D. Alarm condition IS VALID and the A Recirc Pump STOP pushbutton should be depressed.

ANSWER: D ARP-P680-4A-A05 MUST BE INCLUDED IN EXAM HANDOUT MATERIALS Alarm condition is valid per A below and auto action (which failed to occur) per ARP with both pumps in fast speed.

A - Based on dome pressure of 1000 psia, dome temp = 544.6°F. T=6.6°F which is <8.6.

B - With both pumps on fast speed downshift is not automatic action for this condition.

C - Normal action for downshift of both pumps.

K/A Statement: Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 2.4.50 3.3 3.3 41.10 ARP-P680-4A-A05 STM-053 OBJ- H12 41.14 TIER/GROUP: 3 LOK: H LOD: 4 ORIGIN: NEW HISTORY: BANK QID: 852

HANDOUT MATERIALS for the September 17, 2004 River Bend NRC RO Written Exam

For RO Question 3

For RO Question 6

CONTINUOUS USE ATTACHMENT 2 PAGE 1 OF 6 REACTOR COOLDOWN DATA START ACTUAL RPV PRESSURE RPV TEMPERATURE RPV TEMPERATURE TIME TIME FROM STEAM FROM PYROMETER PLUS TABLES (RPV COOLANT LESS THAN 212°F)

HRS MIN 0 15 30 45 60 1 15 30 45 60 2 15 30 45 60 3 15 30 45 60 4 15 30 45 60 5 15 30 45 60 AOP-0031 REV - 19 PAGE 40 OF 118

CONTINUOUS USE ATTACHMENT 2 PAGE 2 OF 6 REACTOR COOLDOWN DATA START ACTUAL RPV PRESSURE RPV TEMPERATURE RPV TEMPERATURE TIME TIME FROM STEAM FROM PYROMETER PLUS TABLES (RPV COOLANT LESS THAN 212°F)

HRS MIN 6 15 30 45 60 7 15 30 45 60 8 15 30 45 60 9 15 30 45 60 10 15 30 45 60 11 15 30 45 60 AOP-0031 REV - 19 PAGE 41 OF 118

CONTINUOUS USE ATTACHMENT 2 PAGE 3 OF 6 REACTOR COOLDOWN DATA START ACTUAL RPV PRESSURE RPV TEMPERATURE RPV TEMPERATURE TIME TIME FROM STEAM FROM PYROMETER PLUS TABLES (RPV COOLANT LESS THAN 212°F)

HRS MIN 12 15 30 45 60 13 15 30 45 60 14 15 30 45 60 15 15 30 45 60 16 15 30 45 60 17 15 30 45 60 AOP-0031 REV - 19 PAGE 42 OF 118

CONTINUOUS USE ATTACHMENT 2 PAGE 4 OF 6 REACTOR COOLDOWN DATA START ACTUAL RPV PRESSURE RPV TEMPERATURE RPV TEMPERATURE TIME TIME FROM STEAM FROM PYROMETER PLUS TABLES (RPV COOLANT LESS THAN 212°F)

HRS MIN 18 15 30 45 60 19 15 30 45 60 20 15 30 45 60 21 15 30 45 60 22 15 30 45 60 23 15 30 45 60 AOP-0031 REV - 19 PAGE 43 OF 118

CONTINUOUS USE ATTACHMENT 2 PAGE 5 OF 6 REACTOR COOLDOWN DATA STEAM TABLE RPV Pressure (psig) Sat. Steam Temperature (°F) 1100 557 1050 552 1000 546 950 540 900 533 850 527 800 520 750 513 700 505 650 497 600 489 550 479 500 470 450 459 400 448 350 435 300 421 250 406 200 388 150 366 100 338 50 298 AOP-0031 REV - 19 PAGE 44 OF 118

CONTINUOUS USE ATTACHMENT 2 PAGE 6 OF 6 REACTOR COOLDOWN DATA Remarks:

Performed By: /

Signature KCN Initials Date/Time

/

Signature KCN Initials Date/Time

/

Signature KCN Initials Date/Time Reviewed By:

OSM/CRS KCN Date/Time AOP-0031 REV - 19 PAGE 45 OF 118

For RO Question 7

For RO Question 36

DRAWING FOR QUESTION 36 10 s A 60 s

-100 s Core Core Midplane Bottom 10 s B 60 s

-100 s Core Core Midplane Bottom 10 s C 60 s

-100 s Core Core Midplane Bottom 10 s D 60 s

-100 s Core Core Midplane Bottom

For RO Question 75

RECIRC LOOP A LOW T ALARM NO. 2158 H13-P680/04A/A05 INITIATING DEVICES SETPOINTS

1. K702A Relay 1. Less than 8.6°F difference between Reactor Steam Dome temperature and Recirc Pump A suction temperature.

AUTOMATIC ACTIONS

1. IF Recirc Pump B AND Recirc Pump A are 95% speed, THEN Recirc Pump A trips to OFF after a 15 minute time delay.
2. IF Recirc Pump B is <95% speed AND Recirc Pump A is 95% speed, THEN Recirc Pump A downshifts to 25% speed (Slow Speed) after a 15 minute time delay.

OPERATOR ACTIONS

1. Verify Automatic Actions.
2. Perform the following:
  • Monitor Recirc Pump vibration levels.
  • IF Recirc Pump vibration levels are excessive, THEN downshift the Recirc Pump to 25% speed AND Go To AOP-0024, Thermal Hydraulic Stability Controls.

NOTE Video Service Screen 46 can be used to validate the low T condition.

  • Validate the low T condition.
3. IF the Recirc Pump trips, THEN Refer To GOP-0004, Single Loop Operation.
4. IF Recirc Pump downshifts to 25% speed, THEN Go To AOP-0024, Thermal Hydraulic Stability Controls.
5. IF the low T condition is not valid, THEN place key operated switch B33-S125A, STEAM DOME/PUMP SUCTION T INTERLOCK BYPASS, in BYPASS.

LONG TERM ACTIONS

1. IF B33-S125A was placed in BYPASS, THEN continuously monitor the following which may indicate possible Jet Pump or Recirc Pump cavitation:
a. Power to Flow Map,
b. Recirc Pump vibration, and
c. Jet Pump Performance.
2. IF the low T condition is valid, THEN initiate a Condition Report to track the cumulative time for pump cavitation (maximum = 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />).

ARP-680-04 REV 20 PAGE 11 OF 87

RECIRC LOOP A LOW T ALARM NO. 2158 H13-P680/04A/A05 POSSIBLE CAUSES

1. Reactor pressure decrease.
2. Instrument malfunction (steam dome pressure temperature conversion, recirc pump suction temperature).

REFERENCES

1. GE-NE-B3300280-01 (CR95-1216)
2. MR 96-0004 ARP-680-04 REV 20 PAGE 12 OF 87