ML21309A732
| ML21309A732 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 11/05/2021 |
| From: | Progress Energy Carolinas |
| To: | NRC/RGN-II |
| References | |
| 50-261/21-301 50-261/OL-21 | |
| Download: ML21309A732 (37) | |
Text
Question: 76 (1 point)
Given the following:
Robinson Nuclear Plant ILT21 RNP SRO NRC Examination The plant is in MODE 3 at 547°F following a Reactor Trip due to a Seismic Event A large leak on the Condensate Storage Tank (CST) reduces level to 22%
Current Conditions:
The leak was repaired and the CST is being refilled; current level is 36%
The SDAFW did NOT operate at any time during the event An alternate water source to the AFW pumps has not been aligned ONLY the suction line to the SDAFW pump has been vented Which ONE of the following correctly completes the statements below?
IAW ITS 3.7.5, CONDENSATE STORAGE TANK (CST), the CURRENT status of the CST is (1) and IAW OP-402, AUXILIARY FEEDWATER SYSTEM, the CURRENT status of the SDAFW pump is (2)
A.
(1) OPERABLE (2) INOPERABLE C.
(1) INOPERABLE (2) OPERABLE D.
(1) INOPERABLE (2) INOPERABLE REFERENCE PROVIDED Page 76 of 100 ML21309A732
Question:
77 (1 point)
Given the following:
Robinson Nuclear Plant ILT21 RNP SRO NRC Examination The plant is operating at 100% RTP when the following occurs:
o PCV-455C, PZR PORV fully opens o Attempts to close PCV-455C have failed o The OATC places RC-536, PORV BLOCK Valve control switch to CLOSED o The OATC observes that RC-536 indication at the RTGB shows both SHUT and OPEN lights extinguished o An automatic reactor trip occurs o The OATC manually initiates Safety Injection Subsequently:
RCS subcooling is 58°F and lowering RCS pressure is 1900 psig AND slowly lowering Pressurizer Level is 27% and rising SG NR level are A: 4%, B: 7%, C: 16% and all rising CV radiation is normal CV pressure is normal CV sump level is normal Which ONE of the following correctly completes the statements below?
Based on these conditions, Pressurizer PORV Block Valve RC-536 is _ __....(1'--'-) __
IAW EOP-E-0, REACTOR TRIP OR SAFETY INJECTION, the CRS is required to transition to (2)
EOP-ES-1.1, SI TERMINATION EOP-E-1, LOSS OF REACTOR OR SECONDARY COOLANT A.
(1) INOPERABLE (2) EOP-ES-1.1 C.
(1) OPERABLE (2) EOP-ES-1.1 D.
(1) INOPERABLE (2) EOP-E-1 Page 77 of I 00
Question:
78 (1 point)
Given the following:
Robinson Nuclear Plant ILT21 RNP SRO NRC Examination An ATWS has occurred The crew is performing FRP-S.1, Response to Nuclear Power Generation/A TWS RCS Boration is in progress Current Conditions:
Reactor Power indicates approximately 4%
Intermediate Range SUR= -0.2 dpm Rods H-4 and M-8 are indicating 218 steps All other rods have been fully inserted and the Rx Trip Breakers are open RCS Temperature is 505°F and trending up SG pressures are 850 psig and slowly rising RCS Boron concentration is 2200 ppm
- , RESTORATION OF RCSNCT MAKE-UP CONTROLS AND ADMINISTRATIVE ACTIONS is handed off to the BOP Which ONE of the following correctly completes the statements below?
The CRS (1) required to complete performance of FRP-S.1 Attachment 4 before making a transition out of FRP-S.1.
Independent of the status of Attachment 4, based only on the current PLANT conditions, FRP-S.1 (2) direct a transition out of FRP-S.1.
A.
(1) is (2) does B.
(1)isNOT (2) does C.
(1) is (2) does NOT D.
(1)isNOT (2) does NOT Page 78 of 100
Question: 79 (1 point)
Given the following:
Robinson Nuclear Plant ILT21 RNP SRO NRC Examination The plant is at 75% RTP The SDAFW Pump was tagged out 9/20/21 (yesterday) at 0700 for oil replacement, and is expected to return in three shifts Subsequently, the following timeline of events occur today (9/21/21);
Time 1300:00 - A large electrical transient occurs 1301 :00 - A loss of normal power to 480V Bus E1 causes EOG "A" to start and restore power to E 1, but the transient causes a LOSS of MCC-10 1301: 15 - A Feed Water Isolation occurs due to erratic level control in one steam generator Which ONE of the following completes the statements below?
The earliest time that ALL available AFW pumps will have automatically started is (1)
If the status of the AFW system components does not change from the current conditions at time 1301 :15, then IAW ITS 3.7.4, AUXILIARY FEEDWATER (AFW)
SYSTEM, the LATEST time the Plant is required to be in MODE 3 is (2)
REFERENCE PROVIDED A.
(1)1301:15 (2) by 1901 :00 today B.
(1) 1301:15 (2) on 9/27/21 at 1300 C.
(1) 1301 :40 (2) by 1901 :00 today D.
(1)1301:40 (2) on 9/27/21 at 1300 Page 79 of 100
Question:
80 (1 point)
Given the following:
Robinson Nuclear Plant ILT21 RNP SRO NRC Examination The plant is at 100% power APP-01 0-A3 EOG B TROUBLE is received The IAO reports that EOG "B" trips defeat key switch is in TRIPS IN SERVICE Subsequently, A Loss of Offsite Power occurs Which ONE of the following correctly completes the statements below?
IAW TS 3.8.1 BASES, with the trips defeat key switch in the TRIPS IN SERVICE position EOG "B" is considered (1)
After the loss of offsite power, EOG "B" -~(2_) __ automatically start and load emergency bus E-2.
A.
(1) OPERABLE (2) will B.
(1) INOPERABLE (2) will C.
(1) OPERABLE (2) will NOT
- 0.
(1) INOPERABLE (2) will NOT Page 80 of 100
Question:
81 (1 point)
Given the following:
Robinson Nuclear Plant ILT21 RNP SRO NRC Examination A reactor trip and Safety Injection has occurred.
The BOP operator notes the following annunciators are lit:
APP-007-F1, AFW PMP A LO DISCH PRESS/MTR TRIP APP-007-F2, AFW PMP B LO DISCH PRESS/MTR TRIP APP-007-FS, SDAFW PMP LO DISCH PRESS TRIP CST level is 5% and lowering due to sabotage and is INACCESSIBLE Which ONE of the following correctly completes the statements below?
The earliest transition to FRP-H.1 in EOP-E-0 is (1}
checking the major accident diagnostic steps (Faulted SIG, Ruptured S/G, LOCA in containment) and SI termination criteria.
IAW FRP-H.1, the preferred source of water to supply suction to AFW pumps is (2)
EOP-E-0, REACTOR TRIP OR SAFETY INJECTION FRP-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK A
(1) before (2) Deepwell Pumps B.
(1) before (2) Service Water C.
(1) after (2) Service Water D.
(1) after (2) Deepwell Pumps Page 81 of 100
Question:
82 (1 point)
Given the following:
Robinson Nuclear Plant ILT21 RNP SRO NRC Examination The plant is at 100% RTP Rod Control is in Manual Subsequently, Control Rod E-7 drops fully into the core.
Current plant conditions:
Power stabilized at 90% by NI average power readings When the plant is stabilized Tave is 7°F below Tref The CRS is directing the actions of AOP-001, MALFUNCTION OF ROD CONTROL SYSTEM, Section A, Dropped Rod Which ONE of the following correctly completes the statements below?
IAW AOP-001 Attachment 1,Secondary Load Adjustment, the CRS is required to match Tave and Tref by (1)
IAW ITS BASES 3.1.4, ROD GROUP ALIGNMENT LIMITS, Control Rod E-7 (2)
A.
(1) adjusting turbine load ONLY (2) is B.
(1) adjusting turbine load ONLY (2) is NOT C.
(1) adjusting turbine load and RCS boron concentration (2) is D.
(1) adjusting turbine load and RCS boron concentration (2) is NOT Page 82 of 100
Question:
83 (1 point)
Given the following:
Robinson Nuclear Plant ILT21 RNP SRO NRC Examination A startup is in progress, with the plant in MODE 2 The OATC receives APP-005-A1, SR DET LOSS OF DC, releases the Rods motion switch to the HOLD osition rod motion STOPS and observes followin on NR-45:
Which ONE of the following correctly completes the statement below?
IAW GP-003, NORMAL PLANT STARTUP FROM HOT STANDBY TO CRITICAL, the source range I intermediate range channel overlap (1) been met satisfactorily.
A decision was made by management to terminate the startup and trip the reactor. Once the Reactor Trip Breakers are OPEN, the CRS (2) allowed to exit ITS LCO 3.3.1, RPS INSTRUMENTATION.
A.
(1) has (2) is B.
(1) has (2) is NOT C.
(1) has NOT (2) is D.
(1) has NOT (2) is NOT REFERENCE PROVIDED Page 83 of 100
Question:
84 (1 point)
Given the following:
Robinson Nuclear Plant ILT21 RNP SRO NRC Examination The plant is at 100% RTP New fuel assemblies are being transferred to the Spent Fuel Pool IAW FHP-003, FUEL ASSEMBLY MOVEMENT IN THE SPENT FUEL PIT The control room receives a report of a New Fuel Assembly that is leaning onto another in the spent fuel pool Which ONE of the following correctly completes the statements below?
The CRS _~(_1)~
_ REQUIRED to enter AOP-013, FUEL HANDLING ACCIDENT.
With regards to the postulated Fuel Handling Accident analysis, the BASES for LCO 3.9.7 CONTAINMENT PURGE FILTER SYSTEM, states that recently irradiated fuel is fuel that has occupied part of a critical reactor core within the previous (2) hours.
A (1) is (2) 116 B.
(1) is (2) 125 C.
(1) is NOT (2) 116 D.
(1) is NOT (2) 125 Page 84 of 100
Question:
85 (1 point)
Given the following:
Robinson Nuclear Plant ILT21 RNP SRO NRC Examination A Reactor trip and Safety Injection have occurred due to a SGTR on the "B" SIG EOP-E-3, STEAM GENERATOR TUBE RUPTURE has been implemented Which ONE of the following correctly completes the statements below?
In accordance with EOP-E-3, transition to a contingency procedure (ECA) is required if the RUPTURED SIG pressure lowers to LESS THAN A MAXIMUM of (1) above the pressure of the intact SIG used for cooldown.
IAW the applicable EOP BASIS DOCUMENT, if SIG overfill becomes a concern, the contingency procedure which will be most effective at preventing an overfill condition is (2)
EOP-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED EOP-ECA-3.2, SGTR WITH LOSS OF REACTOR COOLANT-SATURATED RECOVERY DESIRED A.
(1) 250 PSID (2) ECA-3.2
- 8.
(1) 500 PSID (2) ECA-3.2 C.
(1) 250 PSID (2) ECA-3.1 D.
(1) 500 PSID (2) ECA-3.1 Page 85 of 100
Question:
86 (1 point)
Given the following:
Robinson Nuclear Plant ILT21 RNP SRO NRC Examination The plant is operating at 100% RTP Subsequently the following occurs:
APP-001 -BS, RCP HIGH VIB and APP-001 -F3, RCP C BEARING HI TEMP alarms are received RCP "C" thrust and pump bearing temperatures have reached 220°F and stabilized RCP "C" vibration analysis shows that MOTOR vibrations have increased from 2.0 to 3.0 mils in the last 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Seal Injection Flows are as follows:
RCP 'A' = 8.3 gpm RCP 'B' = 8.4 gpm RCP 'C' = 9.0 gpm APP-001-D1, RCP #1 SEAL LEAKOFF HI FLOW is extinguished.
Which ONE of the following correctly completes the statements below?
The CRS is required to enter AOP-018 Section _
___._(1....... ) __
IAW AOP-018, REACTOR COOLANT PUMP ABNORMAL CONDITIONS, the CRS will direct a Reactor Trip and Trip the "C" RCP because the (2) has exceeded the bearing temperature limit.
A.
(1) B for High Reactor Coolant Pump Vibration (2) Thrust bearing B.
(1) c for Loss of RCP Seal Cooling (2) Th rust bearing C.
(1) B for High Reactor Coolant Pump Vibration (2) Pump bearing D.
(1) C for Loss of RCP Seal Cooling (2) Pump bearing Page 86 of 100
Question:
87 (1 point)
Given the following:
Robinson Nuclear Plant ILT21 RNP SRO NRC Examination A Steam Break inside Containment occurred The crew progressed through the EOP Network, isolating the "C" SIG, and SI termination criteria was met The crew is now in EOP-ES-1.1, SI TERMINATION Subsequently, BOTH SI Pumps are stopped, and the following indications exist:
RCS pressure = 1780 psig and lowering slowly RCS subcooling = 52°F and lowering slowly Containment pressure = 8 psig lowering slowly "A" and "B" SIG pressure= 900 psig at 50% NR level and stable "C" SIG pressure = depressurized PZR level is 18% and lowering Which ONE of the following correctly completes the statement below?
Based on the current plant conditions, the CRS is required to direct the crew to...
EOP-E-0, REACTOR TRIP AND SAFETY INJECTION EOP-E-1, LOSS OF REACTOR OR SECONDARY COOLANT A.
continue performing steps in EOP-ES-1.1; a procedural transition is not required at this time.
B.
manually start SI and RHR pumps with their individual control switches and return to EOP-E-0.
C.
manually start SI and RHR pumps with their individual control switches and transition to EOP-E-1.
D.
initiate Safety Injection by Manually depressing both SI Initiation Pushbuttons and transition to EOP-E-1.
Page 87 of 100
Question:
88 (1 point)
Given the following:
Robinson Nuclear Plant ILT21 RNP SRO NRC Examination The Plant is in MODE 4.
While in the process of adjusting PRT pressure, a regulator fails causing the waste gas header pressure and PRT pressure to rise APP-003-C3, PRT HI PRESS, is in alarm PRT Pressure is 10 psig and rising at 2 psig per minute Which ONE of the following correctly completes the statements below?
If the nitrogen supply is not isolated, PRT pressure will rise for _.....,(....,_1,_} __ before the rupture disk relieves pressure.
Specific procedural steps to lower PRT pressure are contained in ----=(2=---} __
(Assume the nitrogen supply is isolated and the rupture disk did not relieve)
OP-702, WASTE DISPOSAL-GAS A.
(1) 45 minutes (2) the APP-003-C3 actions B.
(1) 45 minutes (2) OP-702 C.
(1) 52 minutes (2) the APP-003-C3 actions D.
(1) 52 minutes (2) OP-702 Page 88 of 100
Question:
89 (1 point)
Given the following:
Robinson Nuclear Plant ILT21 RNP SRO NRC Examination A plant heatup following a refueling outage is in progress RCS Pressure = 650 PSIG RCS Temperature= 430°F PT-951, SIS CV PRESSURE TRANSMITTER is operating erratically An OWP was just implemented, and work on the transmitter has not yet begun An l&C tech preparing to perform maintenance and testing associated with PT-951,
inadvertently places PT-950, SIS CV PRESSURE TRANSMITTER in TRIP.
Which ONE of the following correctly completes the statements below?
When the PT-950 Bistable is repositioned to TRIP, a Containment Spray Actuation (1) occur.
IAW ITS B 3.3.2, ESFAS INSTRUMENTATION Bases, the Containment Pressure trip of Phase B Containment Isolation circuitry is designed to minimize the potential of spurious trips that (2)
A.
(1) does (2) may prevent containment flooding beyond design basis B.
(1) does (2) may damage the RCPs C.
(1) does NOT (2) may damage the RCPs D.
(1) does NOT (2) may prevent containment flooding beyond design basis Page 89 of 100
Question:
90 (1 point)
Given the following:
Robinson Nuclear Plant ILT21 RNP SRO NRC Examination The plant is operating at 100% power Subsequently:
A Large Break LOCA and loss of offsite power has occurred The "A" EOG has failed to start HVH-3, CV RECIRC FAN C, failed to AUTO start on the SI actuation Sl-8800, CV SPRAY PUMP "B" DISCHARGE, failed to automatically OPEN Containment pressure is 13 psig and rising The Shift Manager is evaluating whether or not the EAL Threshold "Containment pressure.::: 10 psig with ~ one full train of depressurizing equipment," is met.
Which ONE of the following assesses whether or not one full train of depressurization equipment is operating, and if not, identifies the MINIMUM action, if ANY, that must be taken from the CONTROL ROOM to ensure that one full train is running?
A.
One full train of depressurization equipment is operating.
B.
One full train of depressurization equipment is NOT operating; LOCAL operator actions are required to establish one full train.
C.
One full train of depressurization equipment is NOT operating; HVH-3 must be manually started OR SI-8800 must be OPENED.
D.
One full train of depressurization equipment is NOT operating; HVH-3 must be manually started AND Sl-8800 must be OPENED.
Page 90 of 100
Question:
91 (1 point)
Given the following:
Robinson Nuclear Plant ILT21 RNP SRO NRC Examination The plant is at 400°F during a plant heatup The following indications are observed for the "A" S/G A STEAM GENERATOR Which ONE of the following identifies ALL the Tech Spec Limiting Conditions for Operation (LCO(s)) that have current required action(s) due to the given conditions?
REFERENCE PROVIDED A.
LCO 3.3.1, ONLY B.
LCO 3.3.8, ONLY C.
LCO 3.3.1 and LCO 3.3.3, ONLY D.
LCO 3.3.3 and LCO 3.3.8, ONLY Page 91 of 100
Question:
92 (1 point)
Given the following:
Robinson Nuclear Plant ILT21 RNP SRO NRC Examination The plant is in MODE 1 Non-Refueling Fuel and Insert Shuffle in the Spent Fuel Pool and New Fuel Vault operations were in progress A Spent Fuel Hoist issue required that a New Fuel assembly be placed in a Temporary Storage The Spent Fuel Hoist is being repaired and is expected to take 3 shifts to complete While the repairs are on-going, an administrative error is discovered, and 8 New and Spent Fuel Assemblies have been placed in the INCORRECT locations in the Spent Fuel Pool.
Which ONE of the following correctly completes the statements below?
JAW FMP-019, FUEL INSERT AND SHUFFLE if a fuel assembly must be placed in a Temporary Fuel Storage location, it is required to obtain approval from (1)
Based on the inability to move fuel assemblies, ITS 3.7.14, NEW AND SPENT FUEL ASSEMBLY STORAGE is not MET, and LCO 3.0.3 (2) applicable.
A.
(1) the Reactor Engineer ONLY (2) is B.
(1) an on-duty SRO AND the Reactor Engineer (2) is C.
(1) an on-duty SRO AND the Reactor Engineer (2) is NOT D.
(1) the Reactor Engineer ONLY (2) is NOT Page 92 of 100
Question:
93 (1 point)
Given the following:
Robinson Nuclear Plant ILT21 RNP SRO NRC Examination The plant is operating at 100% RTP The Engine Driven Fire Pump (EDFP) is inoperable for annual inspection and preventative maintenance The Motor Driven Fire Pump (MDFP) and Fire Jockey Pump are operating to supply the system pressure and flush water Subsequently, The breaker for the MDFP trips open and cannot be re-closed The Fire Jockey Pump continues to operate Based on the given conditions, if the status of the fire protection system remains unchanged, which ONE of the following identifies the most restrictive action(s) required IAW FP-012, FIRE PROTECTION SYSTEMS MINIMUM EQUIPMENT AND COMPENSATORY ACTIONS?
REFERENCE PROVIDED A.
Be in Mode 3 within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> and Mode 5 within 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br />.
B.
Restore at least 1 Fire Pump to operable status within 7 days.
C.
Restore at least 1 Fire Pump to operable status within 14 days.
D.
Establish a backup fire suppression water system within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Page 93 of 100
Robinson Nuclear Plant ILT21 RNP SRO NRC Examination Question:
94 (1 point)
Which ONE of the following correctly completes the statements below concerning Standing Instructions?
IAW AD-OP-ALL-0111, OPERATIONS COMMUNICATIONS, a Standing Instruction (1) be used in place of an INCORRECT or INACCURATE procedure.
IAW AD-OP-ALL-0111, if a revision to a Standing Instruction is issued, the CRS (2) the lowest level authorized to review and sign the revision.
A.
(1) can (2) is B.
(1) can (2) is NOT C.
(1) can NOT (2) is D.
(1) can NOT (2) is NOT Page 94 of 100
Question: 95 (1 point)
Robinson Nuclear Plant ILT21 RNP SRO NRC Examination IAW OMM-001-18 OUTAGES, the Refueling SRO is responsible for which of the following?
A.
Oversight and safety assessment of refueling outage activities.
- 8.
Authorizing gripper unlatching for fuel assemblies placed in the core.
C.
Ensuring proper fuel transfers, refueling activity log keeping, and maintaining the master copy of fuel handling documentation.
D.
Ensuring compatibility of fuel movement operations with other refueling outage activities and makes appropriate decisions to allow or discontinue fuel movement.
Page 95 of I 00
Question:
96 (1 point)
Given the following:
Robinson Nuclear Plant ILT21 RNP SRO NRC Examination An outage is planned in which the plant is to be taken from MODE 1 to a complete core off-load into the Spent Fuel Pit Which ONE of the following correctly completes the statements below?
The EARLIEST that the requirements of AD-WC-RNP-0420, SHUTDOWN SAFETY FUNCTION GUIDELINES, must be implemented during the shutdown is when (1) is entered.
The requirements of AD-WC-RNP-0420 _----.:;(2_,_) __ when the core is completely off-loaded to the Spent Fuel Pit.
A.
(1)MODE3 (2) do NOT apply B.
(1) MODE 3 (2) apply C.
(1)MODE4 (2) apply D.
(1) MODE 4 (2) do NOT apply Page 96 of 100
Robinson Nuclear Plant ILT21 RNP SRO NRC Examination Question:
97 (1 point)
Given the following:
The plant is operating at 100% power Subsequently, the following timeline of events occurs:
0130 The 230kV SUT L TC fails to position 3, and CANNOT be manually adjusted 0200 0400 0400 0500 0900 EOG "A" is declared inoperable due to wrong oil being added during maintenance EOG "B" is declared inoperable due to mechanical issues The crew enters Technical Specification LCO 3.0.3 A downpower is initiated MODE 3 is entered Which ONE of the following correctly completes the statements below?
IAW Technical Specifications LCO 3.8.1, AC SOURCES - OPERATING, the operator must verify the correct breaker alignment and indicated power availability for the offsite circuit (offsite power checks) no later than (1}
Based on the given timeline, the LATEST time that the plant must be placed in MODE 4 is (2}
A (1) 0230 (2) 1500
- 8.
(1) 0230 (2) 1700 C.
(1) 0300 (2) 1500 D.
(1) 0300 (2) 1700 Page 97 of 100
Question:
98 (1 point)
Given the following:
Robinson Nuclear Plant ILT21 RNP SRO NRC Examination The on-shift E&C Technician arrives with a Liquid Waste Release Permit for a batch release of Waste Condensate Tank "C", which is ready for Operations review and approval.
The E&C Technician states that:
FIT-1064, LIQUID RADWASTE EFFLUENT FLOW MONITOR, is inoperable This release will result in 51 % of the quarterly, and 13% of the annual 1 0CFR50 total body dose limits being reached.
Which ONE of the following correctly completes the statements below?
The EC Supervisor _
____._(1'"""} _
_ required to sign this Release Permit.
With FIT-1064 inoperable, this release --'-"(2:;.<.) __
A.
(1) is (2) must be delayed until the flow instrument is restored to OPERABLE status B.
(1) is NOT (2) must be delayed until the flow instrument is restored to OPERABLE status C.
(1) is (2) may be initiated provided that the flow rate is estimated once every four hours during the release D.
(1) is NOT (2) may be initiated provided that the flow rate is estimated once every four hours during the release Page 98 of I 00
Question:
99 (1 point)
Given the following:
Robinson Nuclear Plant ILT21 RNP SRO NRC Examination The plant is operating at 8% raising power in preparations to sync the Main Generator to the grid At 1400, the following events occurred:
An Automatic Rx Trip signal fails to trip the Rx The OATC successfully manually trips the Rx At 1405 a Safety Injection was required to maintain pressurizer level greater than 7% due to a subsequent RCS leak Which ONE of the following correctly completes the statements below?
IAW, AD-EP-ALL-0111, CONTROL ROOM ACTIVATION OF THE ERO, the LATEST time that the initial NRC notification must be made is (1)
IAW AD-EP-ALL-0111, CONTROL ROOM ACTIVATION OF THE ERO, for the above events the earliest time conditions exist that will REQUIRE facility activation is (2)
A.
(1) 1430 (2) 1400 B.
(1)1515 (2) 1400 C.
(1) 1430 (2) 1405 D.
(1) 1515 (2) 1405 REFERENCES PROVIDED Page 99 of 100
Robinson Nuclear Plant ILT21 RNP SRO NRC Examination Question: 100 (1 point)
IAW AD-EP-ALL-0111, CONTROL ROOM ACTIVATION OF THE ERO, which ONE of the following correctly completes the statements below?
Site Evacuation is required for EAL declarations of _~(1~) __ or higher.
When accountability is required, the LATEST time at which all personnel in the Protected Area must be accounted for is (2) following EAL declaration.
A.
(1) ALERT (2) 30 minutes B.
(1) SITE AREA EMERGENCY (2) 30 minutes C.
(1) ALERT (2) 60 minutes D.
(1) SITE AREA EMERGENCY (2) 60 minutes Page 100 of I 00
ATTACHMENT 10.1 Page 19 of 22 HBRSEP UNIT NO. 2, CYCLE 33 CORE OPERATING LIMITS REPORT REVISION 0 Figure 5 Axial Flux Difference Limit s as a Function of Rated Thermitl Power Unacceptable Operation 90 so Unacceptable Operation
(-30, 50)
-50
-40
-JO
-2.0 I FMP-001 ILC-21 NRC SRO Written 70 Acceptable Operation 60
-10 50 40 30 10 0
10 A""Oal Flux Drnerilace {% De!t;-i I)
Rev. 38 1 of 47
(+24, 50)
'.lO 30 40 50 Page 29 of 33 1 Reference Package
CORE MAPPING FOLLOWING FUEL LOADING FMP-017 Rev. 16 Page 22 of 34 ATTACHMENT 3 Page 1 of 1
<< (Reference Use) - Verification Of Fuel Assembly Orientation >>
R p
N 1
N-42 2
3 4
5 6
7 8
9 10 11 12 13 14 15 N-43 R
p N
Performed By:
ILC-21 NRC SRO Written M
L M
L K
K NORTH 180° H
H SOUTH 0° G
G Engineering Representative Print / Sign 2 of47 F
E D
C B
A 1
N-44 2
3 4
5 6
7 8
9 10 11 12 13 14 N-41 15 F
E D
C B
A Date Reference Package
200000 180000 160000 140000 Condensate Storage Tank Curve 8.4 I
~ 120000 m
I-V C ;; 100000 C
.2 iii C,
80000 60000
~~
40000 CST Level shall be maintained above 26% to 20000 provide 35,000 gallons available to AFW Suction 0
LOWEST TAP I
I I
I 0
0.75 10 3.30 20 5.85 30 8.40 40 50 60 10.95 13.50 16.05 Indicated Level Mote:
Percent of water indicated based on lowest tap centerline.
Feet & Gallons of water indicated based on bottom of tank.
Calibrated span of level transmitter is 0 to 100 percent= 5388 to 188,588 Gallons Calculation RNP*I/INST-1015
- Condensate Storage Tanlc Level Alarm Setpoints Analysis 84065*M*06*F New Basis for CST Level Indication ILC-21 NRC SRO Written 3 of 47 I
70 18.60 BOTTOM OF OVERFLOW 80 21.15 90 23.70
- f!IJIL,,, J.&o;~
Drawn By / Date Rev 172 188,588 100 Percent 26.25 Feet
~.
r ~
l*AIA'-'i'l
- nate Reference Package
- 3. 7 PLANT SYSTEMS 3.7.4 Auxiliary Feedwater (AFW) System LCO 3.7.4 Four AFW flow paths and three AFW pumps shall be OPERABLE.
NOTE----------------------------------------------------------
Only one AFW flow path with one motor driven pump is required to be OPERABLE in MODE 4.
APPLICABILITY:
MODES 1, 2, and 3, MODE 4 when steam generator is being used for heat removal.
ACTIONS
NOTE-----------------------------------------------------------
LCO 3.0.4.b is not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A.
One AFW pump A.1 Restore AFW pump or 7 days inoperable in MODE 1, 2, flow path(s) to or 3.
OPERABLE status.
AND OR 8 days from discovery of One or two AFW flow failure to paths inoperable in MODE meet the LCO 1, 2, or 3.
- 8.
Two motor driven AFW 8.1 Restore one motor 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> pumps inoperable in driven AFW pump or MODE 1, 2, or 3.
one flow path to AND OPERABLE status.
OR 8 days from discovery of Three motor driven AFW failure to flow paths inoperable in meet the LCO MODE 1, 2, or 3.
(continued)
ILC-21 NRC SRO Written 4 of 47 Reference Package
ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C.
Required Action and C.1 Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time for Condition A or B AND not met.
C.2 Be in MODE 4.
18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> D.
Steam driven AFW pump D.1 Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or flow path inoperable in MODE 1, 2, or 3.
AND AND D.2 Be in MODE 4.
18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> One motor driven AFW pump or flow path inoperable in MODE 1, 2, or 3.
E.
Four AFW flow paths E.1
NO TE------------
inoperable in MODE 1, 2, LCO 3.0.3 and all other or 3.
LCO Required Actions requiring MODE OR changes are suspended until one AFW pump Three AFW pumps and flow path are inoperable in MODE 1, 2, restored to OPERABLE or 3.
status.
Initiate action to restore Immediately one AFW pump and flow path to OPERABLE status.
F.
Required AFW pump and F.1 Initiate action to restore Immediately flow path inoperable in AFW pump and flow MODE4.
path to OPERABLE status.
ILC-21 NRC SRO Written 5 of 47 Reference Package
SURVEILLANCE REQUIREMENTS SR 3.7.4.1 SR 3.7.4.2 SR 3.7.4.3 ILC-21 NRC SRO Written SURVEILLANCE Verify each AFW manual, power operated, and automatic valve in each water flow path, and in the steam supply flow path to the steam driven AFW pump, that is not locked, sealed, or otherwise secured in position, is in the correct position.
NOTE--------------------------------
Not required to be performed for the steam driven AFW pump until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after ~ 1000 psig in the steam generator.
Verify the developed head of each AFW pump at the flow test point is greater than or equal to the required developed head.
NOTE---------------------------------
N ot applicable in MODE 4 when steam generator is being used for heat removal.
Verify each AFW automatic valve that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.
6 of 47 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program (continued)
Reference Package
SURVEILLANCE REQUIREMENTS (continued)
SR 3.7.4.4 SR 3.7.4.5 SURVEILLANCE
NO TES----------------------------------
- 1. Not required to be performed for the steam driven AFW pump until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after~ 1000 psig in the steam generator.
- 2. Not applicable in MODE 4 when steam generator is being used for heat removal.
Verify each AFW pump starts automatically on an actual or simulated actuation signal.
NOTE------------------------------------
N ot required to be performed for the steam driven AFW pump until prior to entering MODE 1.
Verify proper alignment of the required AFW flow paths by verifying flow from the condensate storage tank to each steam generator.
SR 3. 7.4.6 Verify the AFW automatic bus transfer switch associated with discharge valve V2-16A operates automatically on an actual or simulated actuation signal.
ILC-21 NRC SRO Written 7 of 47 FREQUENCY In accordance with the Surveillance Frequency Control Program Prior to entering MODE 2, whenever unit has been in MODE 5 or 6 for> 30 days In accordance with the Surveillance Frequency Control Program Reference Package
Table 3.3.1-1 (page 3 of 7)
Reactor Protection System Instrumentation APPLICABLE MODES OR NOMINAL OTHER TRIP SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE SETPOINT FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE (1)
- 9.
Reactor Coolant Flow-Low
- a.
Single Loop 1 (g) 3 per loop N
SR 3.3.1.1 SR 3.3.1.7 SR 3.3.1.10
- b.
Two Loops 1(h) 3 per loop M
SR 3.3.1.1 SR 3.3.1.7 SR 3.3.1.10
- 10.
Reactor Coolant Pump (RCP) Breaker Position
- a.
Single Loop 1(9) 1 per RCP 0
SR 3.3.1.14
- b.
Two Loops 1 (h) 1 per RCP M
SR 3.3.1.14
- 11.
Undervoltage 1 (f) 1 per bus M
- 12.
U nderfrequency 1 (f) 1 per bus M
- 13.
Steam Generator (SG) 1,2 3 perSG E
SR 3.3.1.1 Water Level - Low SR 3.3.1.7 Low SR 3.3.1.10 (continued)
ILC-21 NRC SRO Written 8 of 47 Reference Package
Table 3.3.3-1 (page 1 of 1)
Post Accident Monitoring Instrumentation CONDITION REFERENCED FROM FUNCTION REQUIRED CHANNELS REQUIRED ACTION E.1
- 1. Power Range Neutron Flux 2
F
- 2. Source Range Neutron Flux 2
F
- 3. Reactor Coolant System (RCS) Hot Leg Temperature 1 per loop F
- 4. RCS Cold Leg Temperature 1 per loop F
- 5. RCS Pressure (Wide Range) 2 F
- 6. Refueling Water Storage Tank Level 2
F
- 7. Containment Sump Water Level (Wide Range) 2 G
- 8. Containment Pressure (Wide Range) 2 G
- 9. Containment Isolation Valve Position 2 per penetration flow F
path (a)(b)
- 10. Containment Area Radiation (High Range) 2 G
- 11. Not used
- 12. Pressurizer Level 2
F
- 13. Steam Generator Water Level (Narrow Range) 2 per SG F
- 14. Condensate Storage Tank Level 2
F
- 15. Core Exit Temperature - Quadrant 1 2(c)
F
- 16. Core Exit Temperature - Quadrant 2 2(C)
F
- 17. Core Exit Temperature - Quadrant 3 2(C)
F
- 18. Core Exit Temperature - Quadrant 4 2(c)
F
- 19. Auxiliary Feedwater Flow SDAFWPump 1 per SG G
- 20. Steam Generator Pressure 2 per SG F
21. Containment Spray Additive Tank Level 2
F
- 22. PORV Position (Primary)
G
- 23. PORV Block Valve Position (Primary)
G
- 24. Safety Valve Position (Primary)
G (a)
Not required for isolation valves whose associated penetration is isolated by at least one closed and deactivated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured.
(b) Only one position indication channel is required for penetration flow paths with only one installed automatic containment isolation valve.
(c) A channel consists of one core exit thermocouple (CET).
ILC-21 NRC SRO Written 9 of 47 Reference Package
- 1.
- 2.
- 3.
- 4.
- 5.
FUNCTION SG Water Level-Low Low Safety Injection Loss of Offsite Power Undervoltage Reactor Coolant Pump Trip of all Main Feedwater Pumps Table 3.3.8-1 (page 1 of 1)
Auxiliary Feedwater System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE CONDITIONS CHANNELS CONDITIONS REQUIREMENTS 1,2,3 3 per SG C
SR 3.3.8.1 SR 3.3.8.2 SR 3.3.8.4 NOMINAL TRIP ALLOWABLE SETPOINT VALUE (1)
Refer to LCO 3.3.2, "ESFAS Instrumentation," Function 1, for all initiation functions and requirements.
1,2,3 2 per bus 1,2,3 2 per bus 1,2 1 per pump D
B E
SR 3.3.8.3 SR 3.3.8.4 SR 3.3.8.3 SR 3.3.8.4 SR 3.3.8.3 (1 )
A channel is OPERABLE with an actual Trip Setpoint value found outside its calibration tolerance band provided the Trip Setpolnt value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established calibration tolerance band of the Nominal Trip Setpoint.
ILC-21 NRC SRO Written 10 of 47 Reference Package
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W/1-5 f~ovt/JEIJ, ILC-21 NRC SRO Written 11 of 47 Reference Package
Examination KEY ILT21 RNP SRO NRC Examination Q A Q A Q A Q A 1
A 26 C
51 D
76 B
2 C
27 B
52 D
77 D
3 B
28 D
53 D
78 B
4 D
29 D
54 A
79 C
5 B
30 C
55 B
80 B
6 C
31 D
56 C
81 B
7 B
32 C
57 D
82 A
8 B
33 D
58 A
83 C
9 A
34 D
59 C
84 C
10 A
35 D
60 B
85 A
11 D
36 A
61 C
86 A
12 B
37 D
62 D
87 C
13 A
38 C
63 A
88 A
14 B
39 B
64 C
89 C
15 D
40 C
65 A
90 D
16 D
41 A
66 A
91 B
17 A
42 C
67 A
92 C
18 D
43 B
68 B
93 D
19 C
44 C
69 C
94 D
20 C
45 C
70 C
95 B
21 B
46 B
71 C
96 C
22 B
47 D
72 D
97 B
23 C
48 A
73 D
98 C
24 C
49 B
74 B
99 D
25 D
50 A
75 B
100 B
Printed 9/28/2021 9:05:01 AM Page 1 of 1