ML090780656
| ML090780656 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 03/13/2009 |
| From: | - No Known Affiliation |
| To: | NRC/RGN-II |
| References | |
| Download: ML090780656 (28) | |
Text
Q#
Item #
Topic KEY 76 A
n A
78 C
79 B
80 0
81 8
82 C
83 0
84 A
85 C
86 C
87 0
88 A
89 C
90 C
91 A
92 C
93 A
94 C
95 A
96 B
97 C
98 8
99 A
100 8
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.~ VLDI3~ SRo ~~NC£..s SRO NRC Exam Attachments
- 76 Unit 1 EOP Encl. 5.18
- 98 RP/10001001 (Emergency Classification) all
ES-401 Name:
Date: 03/13/2009 Region: II Start Time: 0900 Site-Specific SRO Written Examination Cover Sheet
- u. S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Facility/Unit: Oconee 1, 2, 3 Reactor Type: BW Finish Time: 1700 Instructions Form ES-401-8 Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination you must achieve a final grade of at least 80.00 percent overall, with a 70.00 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require an 80.00 percent to pass. You have eight hours to complete the combined examination, and three hours if you are only taking the SRO portion.
Applicant Certification All work done on this examination is my own. I have neither given nor received aid.
Applicant's Signature Results RO / SRO-Only / Total Examination Values Applicant's Scores Applicant's Grade
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Points Points Points
2009 NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Question 76 Unit 1 initial conditions:
Reactor power = 100%
Current conditions:
Tcold =532 of slowly decreasing CETCs = 477 of slowly decreasing RCS pressure =535 psig decreasing pzr Level = 0 inches 1A SG Pressure = 750 psig slowly decreasing 1B SG Pressure = 680 psig slowly decreasing 1RIA-49 in HIGH alarm Based on the above, which ONE of the following is the procedure path to mitigate this event?
REFERENCE PROVIDED A. Loss of Subcooling Margin tab to LOCA Cooldown tab B. Loss of Subcooling Margin tab to Forced Cooldown tab C. Excessive Heat Transfer tab to Loss of Subcooling Margin tab D. Excessive Heat Transfer tab to Forced Cooldown tab
2009 NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Question 77 Unit 1 initial conditions:
Time = 0900 Reactor power = 100%
1SA2/C2 HP INJECTION PUMP DISCH HEADER PRESSURE LOW actuated HPI Pump discharge pressure =2300 psig stable pzr Level = 209 inches decreasing LOST Level =84 inches decreasing Seal Injection flow =32 gpm stable RC Makeup Flow = 140 gpm increasing Current conditions:
Time =0905 Pressurizer level =200 inches decreasing LOST Level = 65 inches decreasing Seal Injection flow =32 gpm stable RC Makeup Flow = 160 gpm stable Repairs will require 7 days to complete Based on the above conditions, which ONE of the following describes the current plant condition and whether a Tech Spec shutdown is required?
A. HPI Normal Injection header break Shutdown is required B. HPI Normal Injection header break Shutdown is NOT required C. Letdown Line leak Shutdown is required D. Letdown Line leak Shutdown is NOT required
2009 NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Question 78 Unit 1 initial conditions:
Reactor power = 100 Current conditions:
Pressurizer level = 72 inches increasing Pressurizer heaters energized RCS Pressure = 1910 psig Based on the conditions above, which ONE of the following describes whether Pressurizer heaters should be energized and the TS bases for the availability of a minimum capacity of pressurizer heaters?
A. Pressurizer Heaters should be energized Ensure the ability to control system pressure and maintain subcooling with an extended loss of offsite power B. Pressurizer Heaters should be energized To prevent solid plant operations and subsequent pressure transients that could damage RCS piping C. Pressurizer Heaters should NOT be energized Ensure the ability to control system pressure and maintain subcooling with an extended loss of offsite power D. Pressurizer Heaters should NOT be energized To prevent solid plant operations and subsequent pressure transients that could damage RCS piping
2009 NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Question 79 Unit 3 plant conditions:
Reactor power = 100 CC CRD Return Flow = 142 gpm slowly decreasing CC Return Flow = 563 gpm decreasing Letdown Temperature =138°F stable One or more of the following alarms have actuated:
y 3SA-9/B-1 (CC CRD Return Flow Low).
y 3SA-2/C-1 (HP Letdown Temperature High) y 3SA-9/C-1 (CC Component Cooling Return Flow Low)
Based on the above conditions, which ONE of the following describes a required action from the associated ARG(s) to mitigate this event? If the ARG directed actions are NOT successful, which Abnormal Procedure is required to be entered first?
A. Verify CC Surge Tank level> 15 inches and start the standby CC pump AP/32 (Loss of Letdown)
B. Verify CC Surge Tank level> 15 inches and start the standby CC pump AP/20 (Loss of Component Cooling)
C. Decrease letdown flow using 3HP-7 (LETDOWN CONTROL)
AP/32 (Loss of Letdown)
D. Decrease letdown flow using 3HP-7 (LETDOWN CONTROL)
AP/20 (Loss of Component Cooling)
2009 NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Question 80 Unit 1 initial conditions:
Startup from refueling outage in progress Reactor power = 5%
stable 1A Main FDW Pump in service Current conditions:
Switchyard isolate 1A Main FDW Pump tripped EOP IMAs and Symptom Checks complete Which ONE of the following describes how EFW will be controlled based on the above conditions and which design bases scenario requires the highest initial post-trip EFW flow?
A. Emergency feedwater will be allowed to control SG levels in AUTO Loss of Main FDW and loss of offsite power B. Emergency feedwater will be allowed to control SG levels in AUTO Loss of Main FDW with offsite power available C. Emergency feedwater will be manually throttled to prevent RCS overcooling Loss of Main FDW and loss of offsite power D. Emergency feedwater will be manually throttled to prevent RCS overcooling Loss of Main FDW with offsite power available
2009 NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Question 81 Unit 3 initial conditions:
Reactor power = 100%
Current conditions:
3DIA supply breaker to CRD breaker shunt trip device in RPS channel "A" tripped OPEN Based on current plant conditions, which ONE of the following describes the status of RPS channel "A" and the required administrative actions?
A. 3A RPS channel is NOT operable.
TS 3.3.1 (RPS Instrumentation) action statements are required to be performed.
B. 3A RPS channel is operable.
TS 3.3.4 (Control Rod Drive Trip Devices) action statements are required to be performed.
C. 3A RPS channel is NOT operable.
TS 3.3.1 (RPS Instrumentation) action statements are NOT required to be performed.
D. 3A RPS channel is operable.
TS 3.3.4 (Control Rod Drive Trip Devices) action statements are NOT required to be performed.
2009 NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Question 82 Unit 1 initial conditions:
Reactor power =100%
1C HPIP is declared inoperable Current conditions:
1HP-120 valve controller air line blows off HPI FLOW TRAIN "A" indication fails to zero gpm Based on the conditions above, which ONE of the following describes the impact on 1HP-120 and whether performing actions of TS LCO 3.0.3 are required?
ASSUME NO OPERATOR ACTIONS A.1HP-120failsOPEN Actions of LCO 3.0.3 are required B.1HP-120failsOPEN Actions of LCO 3.0.3 are NOT required C. 1HP-120 fails CLOSED Actions of LCO 3.0.3 are required D. 1HP-120 fails CLOSED Actions of LeO 3.0.3 are NOT required
2009 NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Question 83 Unit 1 initial conditions:
Time =0600 Reactor Power = 36%
Pressurizer level = 220 inches LOST Level =85 inches Current conditions:
Time =0610 Reactor Power =36%
Pressurizer level =220 inches LOST Level = 77.5 inches 1RIA-40 Alert and High Alarm actuated Based on the above conditions, which ONE of the following describes the procedure required to be entered and actions directed by the procedure?
A. EOP (Emergency Operating Procedure) SGTR Tab Initiate a Maximum Runback to 15% then manually trip the reactor and isolate the affected SG B. EOP (Emergency Operating Procedure) SGTR Tab Initiate a plant shutdown to 5%
then manually trip the reactor. Maintain Pressurizer level 140 - 180 inches while cooling down to isolate the affected SG C. AP/31 (Primary to Secondary Leakage)
Initiate Enclosure 5.2 (Reduction of Secondary leakage and Cross-Unit Contamination) and perform Enclosure 5.8 (Resetting 1RIA-40 and OAC Setpoints)
O. AP/31 (Primary to Secondary Leakage)
Initiate a shutdown using AP/29 (Rapid Unit Shutdown) and perform Enclosure 5.2 (Reduction of Secondary leakage and Cross-Unit Contamination) to control Secondary Leakage.
2009 NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Question 84 Unit 2 initial conditions:
Reactor power = 70%
stable 2A2 RCP secured 10 days ago Current conditions Control Rod Group 4 Rod 1 dropped to 00/0 withdrawn Excore and Incore Ouadrant Power Tilt (OPT) readings exceed the TRANSIENT limits, but are less than the MAXIMUM limits Based on the above conditions and per AP/15 (Dropped or Misaligned Control Rods),
which ONE of the following describes the runback requirement and the TS bases for OPT limits?
An ICS runback and OPT limits ensure A. and operator action is required to reduce power to ~ 60%
of Allowable Thermal Power clad failure does not occur due to power peaking B. and operator action is required to reduce power to ~ 600/0 of Allowable Thermal Power a flat flux profile is maintained as the core ages C. automatically reduces power to ~ 600/0 of Allowable Thermal Power clad failure does not occur due to power peaking D. automatically reduces power to ~ 60%
of Allowable Thermal Power a flat flux profile is maintained as the core ages
2009 NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Question 85 Unit 1 initial conditions:
Reactor power = 100%
1B HPI Pump OOS Current conditions:
LOSCM tab in progress Rule 2 is complete RCS pressure =825 psig increasing slowly Core SCM = 4°F increasing Loop SCM =OaF pzr level = 0 inches 1C HPI Pump has a sheared shaft Based on the above conditions, which ONE of the following states how SG pressure will be controlled per the LOSCM tab and which EOP tab will be used to cool down the unit to decay heat removal conditions?
A. Control SG steaming and feeding rates to establish RCS cooldown rate within TS limits / LOCA CD B. Control SG steaming and feeding rates to establish RCS cooldown rate within TS limits
/ FCD C. Establish EFDW Flow to both SGs and fully depressurize both SGs / LOCA CD D. Establish EFDW Flow to both SGs and fully depressurize both SGs / FCD
2009 NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Question 86 Unit 3 initial conditions:
Reactor Power = 1000/0 stable 3A1 RCP vibration =4 mils slowly increasing Current conditions:
Reactor Power =100%
stable 3SA-9/E2 (RC PUMP VIBRATION EMERG HIGH) actuates 3A1 RCP vibration =22 mils slowly increasing Based on the current conditions above, which ONE of the following describes how the SRO will direct the sequence of actions to mitigate this event?
The OATC wilL..
A. perform a rapid runback per AP/29 (Rapid Unit Shutdown) to <70%
and then the BOP will manually trip the 3A1 RCP.
B. perform a rapid runback per AP/16 (Abnormal RCP Operation) to <70%
and then the BOP will manually trip the 3A1 RCP.
C. manually trip the reactor and then perform IMAs; the BOP will manually trip 3A1 Rep and then perform a symptom check.
D. manually trip the reactor and then perform IMAs; the BOP will perform a symptom check and then manually trip 3A1 RCP.
2009 NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Question 87 Unit 1 plant conditions:
Date/Time = 12-2 / 2100 RCS Loops "dropped" 1A LPI pump operating SR 3.4.8.1 is discovered to have NOT been performed since 12-1 / 2100 SR 3.4.8.1 cannot be performed Based on the above conditions, which ONE of the following states the time that the operating DHR loop shall be declared inoperable due to not meeting surveillance requirements per Tech Spec 3.4.8 (RCS Loops - MODE 5, Loops Not Filled) including any applicable extensions?
REFERENCE PROVIDED Declare the operating DHR loop inoperable at...
A. 2100 on 12-2.
B. 1200 on 12-2.
C. 0900 on 12-3.
D. 2100 on 12-3.
2009 NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Question 88 Unit 1 plant conditions:
EOP LOCA Cooldown tab in progress RC temperature = 240QF slowly decreasing RC pressure = 180 psig slowly decreasing BWST level =5.5 ft stable Radiation Levels in the LPI pump rooms allow access Based on the above conditions, which ONE of the following describes the alignment for the in-progress cooldown to accomplish decay heat removal provided by the EOP?
A. One LPI train in High Pressure Mode and one LPI train in ECCS alignment with suction from the RBES.
B. One LPI train in series Mode and one LPI train in ECCS alignment with suction from the RBES.
C. Both LPI trains in ECCS alignment with suction from the RBES.
D. Both LPI trains in normal DHR alignment.
2009 NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Question 89 Unit 3 initial conditions:
LOCA in progress RB Pressure = 16 psig increasing Current conditions:
BWST Level =5 feet stable 3SA8/D11, BS "A" HEADER FLOW HIGH/LOW, actuated 3A RBS Pump amps are oscillating 3B Train RBS parameters are normal for the plant conditions Based on the above conditions, which ONE of the following describes the actions required by the Alarm Response Guide and the design basis for RBS?
A. Allow 3A RBS Pump to run, throttle discharge valve (3BS-1), and vent the pump.
RBS is necessary to maintain RB pressure and temperature within design values.
B. Allow 3A RBS Pump to run, throttle discharge valve (3BS-1), and vent the pump.
RBS is necessary to maintain RB pressure within design value. No design value exists for RB temperature.
C. Secure the 3A RBS Pump.
RBS is necessary to maintain RB pressure and temperature within design values.
D. Secure the 3A RBS Pump.
RBS is necessary to maintain RB pressure within design value. No design value exists for RB temperature.
2009 NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Question 90 Unit 1 initial conditions:
Reactor power = 100%
Current conditions:
Main Turbine trips 1FDW-35 (1A FDW Control Valve) fails OPEN Statalarm 1SA-2/B-9 (MS Stm Gen A Level High/Emerg Low) actuates 1A SG level = 98%
OR increasing 1B SG level =53 inches XSUR decreasing Based on the above conditions, which ONE of the following describes the required action in accordance with the EOP Subsequent Actions and the bases for the SLC limit on SG Level?
A. Take manual control 1FDW-35 and reduce 1A SG level/ensure overcooling event due to steam generator overfill will not lead to pressurized thermal shock of the reactor vessel.
B. Take manual control 1FDW-35 and reduce 1A SG level/ensure containment pressure remains within the maximum design limits assumed in the accident analysis for a MSLB C. Trip both Main FDW Pumps and stop steaming 1A SG / ensure overcooling event due to steam generator overfill will not lead to pressurized thermal shock of the reactor vessel.
D. Trip both Main FDW Pumps and stop steaming 1A SG / ensure containment pressure remains within the maximum design limits assumed in the accident analysis for a MSLB
2009 NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Question 91 Unit 1 plant conditions:
Station Blackout occurred approximately one hour ago Power has NOT been restored SSF is activated per AP/25 (SSF EOP)
SSF Control Room indications:
Both Loop's Tc:
Both Loop's Th:
RCS Pressure:
pzr level:
RC M/U Flow:
Unit 1 Total ASW flow:
1A SG Level:
1B SG Level pzr Heaters Group B & C 555°F slowly decreasing 570°F slowly decreasing 570°F slowly decreasing 2170 psig slowly increasing 250 inches slowly increasing 28.3 gpm 175 gpm 200 inches slowly increasing 200 inches slowly increasing ON Based on the above conditions, which ONE of the following describes actions directed by AP/25 and the design bases of the SSF?
A. Establish letdown and cycle pzr Heaters I provide an alternate and independent means to achieve and maintain MODE 3 with an average RC temperature 2:: 525°F for all three units for a minimum of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> B. Establish letdown and cycle pzr Heaters I provide an alternate and independent means to cooldown the plant from MODE 3 to placing Decay Heat in service for all three units within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> C. Reduce ASW flow and RC M/U Flow I provide an alternate and independent means to achieve and maintain MODE 3 with an average RC temperature 2:: 525°F for all three units for a minimum of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> D. Reduce ASW flow and RC M/U Flow I provide an alternate and independent means to cooldown the plant from MODE 3 to placing Decay Heat in service for all three units within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
2009 NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Question 92 Unit 1 initial conditions:
Reactor power =100%
Current conditions:
Condenser vacuum =6 inches Hg stable 1A SG Outlet pressure =985 psig stable 1B SG Outlet pressure =982 psig stable One Main Steam (MS) Relief valve is open Based on the above conditions, which ONE of the following describes the method used to control Main Steam header pressure in accordance with the EOP Subsequent Actions and the bases for the minimum RCS temperature allowed during this process?
A. Adjust the Turbine Header setpoint to reduce MS pressure until the valve reseats Ensure shutdown margin is maintained provided all safety and regulating control rods are fully inserted.
B. Adjust the Turbine Header setpoint to reduce MS pressure until the valve reseats Ensure shutdown margin is maintained provided BWST suction to the HPI pumps is aligned C. Use Atmospheric Dump Valves to reduce MS pressure until the valve reseats Ensure shutdown margin is maintained provided all safety and regulating control rods are fully inserted.
D. Use Atmospheric Dump Valves to reduce MS pressure until the valve reseats Ensure shutdown margin is maintained provided BWST suction to the HPI pumps is aligned
2009 NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Question 93 Unit 1 initial conditions:
Reactor power = 100 1A GWD tank release in progress Current conditions:
Loss of power to RM-80 skid of 1RIA-45 (Norm Vent Gas) 1SA8/B-9 RM PROCESS MONITOR RADIATION HIGH in alarm 1SA8/B-1 0 RM PROCESS MONITOR FAULT in alarm Based on the above conditions, which ONE of the following states the action required per the Alarm Response Guideline and the SLC bases for the determination of the setpoints for the RIA alarms for this release?
A. Manually close 1GWD-4 Setpoints ensure that releases are within the limits of 10CFR20 B. Manually close 1GWD-4 Setpoints ensure that resulting 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> dose at the Exclusion Area boundary will not exceed 10CFR1 00 limits C. Verify 1GWD-4 has automatically closed Setpoints ensure that releases are within the limits of 10CFR20 D. Verify 1GWD-4 has automatically closed Setpoints ensure that resulting 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> dose at the Exclusion Area boundary will not exceed 10CFR1 00 limits
2009 NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Question 94 Plant conditions:
The work list for night shift has detailed instructions (not contained in a specific procedure) for stroking a valve to flush a hot spot from down stream piping Each step has a signoff blank provided Based on the above conditions, which ONE of the following is correct per aMP 1-23 (Operations Worklist Process)?
A. Perform the task using the provided signoff steps after verifying the worklist was signed by a qualified preparer and reviewer.
B. Perform the task using the provided signoff steps after face to face communications with the Unit Coordinator confirms the intent and potential consequences of the task.
C. Do NOT perform the worklist task because the worklist cannot take the place of an approved procedure.
D. Do NOT perform the worklist task unless the OSM gives approval to use the provided instructions.
2009 NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Question 95 Unit 2 initial conditions:
Defueling in progress y
Withdrawing first fuel assembly FTC level = 22.0 feet stable No water additions are being made to the system 2A LPI train is operable and in service 2B LPI train operable Current conditions:
2LP-18 failed closed Refueling SRO desires stopping the 2A LPI Pump to aid in inserting a fuel assembly Based on the above conditions, which ONE of the following describes whether the 2A LPI pump may be stopped in accordance with OP/2/A/1502/007 (Operations Defueling IRefueling Responsibilities) and the TS bases for operation of the pump?
A. 2A LPI Pump may be stopped for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period.
FTC level is within TS limits and provides adequate backup decay heat removal.
B. 2A LPI Pump may be stopped for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period..
Spent Fuel Cooling system provides adequate backup decay heat removal.
C. 2A LPI Pump may be NOT be stopped FTC level is below TS limits and cannot provide adequate backup decay heat removal.
D. 2A LPI Pump may be NOT be stopped Spent Fuel Cooling system can NOT provide adequate backup decay heat removal.
2009 NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Question 96 Which ONE of the following may be used to operate the plant short-term until procedure changes are completed and what is the minimum level of approval required?
A. Operations Guidelines (Ops Guides) / PORC B. Operations Guidelines (Ops Guides) / Superintendent of Operations C. Operational Decision Making Issue (ODMI) / PORC D. Operational Decision Making Issue (ODMI) / Superintendent of Operations
2009 NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Question 97 Unit 1 plant conditions:
Startup in progress Control rod group 1 = 100%
withdrawn Control rod group 2 = 1000/0 withdrawn Control rod group 3 =100%
withdrawn Control rod group 4 =0 % withdrawn TO EFDW pump is red tagged for maintenance Based on the above conditions, which ONE of the following describes the current operational MODE in accordance with OP/11 02/001 (Controlling Procedure For Unit Startup), and whether a change to the next higher Mode is allowed?
A. Mode 2 No B. Mode 2 Yes
- c. Mode 3 No D. Mode 3 Yes
2009 NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Question 98 Unit 1 plant conditions Time =0210 Reactor trip Time =0300 Tc = 490°F RCS Pressure =650 psig DEI =6 uCi/ml 1RIA-57 =45 R/hr 1RIA-58 =25 R/hr Time =0330 Tc = 482°F RCS Pressure =600 psig DEI = 287 uCi/ml 1RIA-57 = 492 R/hr 1RIA-58 = 253 R/hr Based on the above conditions, which ONE of the following describes the EAL classification at 0300 and 0330?
REFERENCE PROVIDED 0300 A. Alert B. Alert C. Unusual Event D. Unusual Event 0330 Site Area Emergency General Emergency Site Area Emergency General Emergency
2009 NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Question 99 Unit 1 initial conditions:
Reactor power =1000/0 Current conditions:
RCS pressure = 1136 psig slowly decreasing Core SCM = OQF RB pressure = 11.6 psig slowly decreasing 1A SG pressure = 1010 psig slowly decreasing 1B SG pressure = 1008 psig slowly decreasing Based on the above conditions, which ONE of the following describes whether Emergency Dose Limits are in affect and what is the maximum (TEDE) dose that an NEO can receive while performing a task outside of the control room without exceeding any applicable limits?
A. Yes / 5 rem for performing Time Critical Tasks B. Yes / 25 rem for protecting property C. No / 2 rem for performing Time Critical Tasks D. No / 25 rem for lifesaving activities
2009 NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Question 100 Unit 3 plant conditions:
Control room staffing at minimum No other SROs or the OSM are available Time is not available for a procedure change An abnormal procedure (AP) is in progr~ss Based on the above conditions and per OMP 1-18 (Implementation Standard During Abnormal and Emergency Events), which ONE of the following conditions allows taking actions outside of the AP and the minimum level of approval required?
Taking actions outside of the AP is allowed if a procedure step
. This would require a minimum level of approval of A. is incorrect / One RO and CR SRO B. is incorrect / CR SRO only C. will result in unplanned TS entry / One RO and CR SRO D. will result in unplanned TS entry / CR SRO only