ML18057B051
| ML18057B051 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 02/26/2018 |
| From: | NRC/RGN-II |
| To: | |
| References | |
| Download: ML18057B051 (28) | |
Text
ILT-11 NRC Exam (SRO)
- 76. 204000G2.2.44 001/00301G31/H-OP-90000.007/NEW/TECH SPEC/SRO/204000G2.2.44/2/2/H/2/RAG Unit 2 is operating at 100% RTP when the following events occur:
A leak develops in the RWCU Pump Room causing the Area Ventilation differential temperatures to INCREASE.
o At 12:00, Area Ventilation differential temperature is 31°F o At 12:05, Area Ventilation differential temperature is 60°F At 12:10, the following conditions exist:
o 2G31-F004, RWCU Outboard Isolation valve, is CLOSED o 2G31-F001, RWCU Inboard Isolation valve, is OPEN and will NOT close Subsequently, 2G31-F001 is declared INOPERABLE.
Based on the above conditions, The EARLIEST listed time RWCU will have RECEIVED an AUTOMATIC isolation signal is __________ .
IAW Tech Spec 3.6.1.3, PCIVs, periodic verifications that the RWCU line is ISOLATED __________ .
A. 12:00; is required to be accomplished by actual hands on verification at the component B. 12:00; can be accomplished remotely by administrative means C. 12:05; is required to be accomplished by actual hands on verification at the component D. 12:05; can be accomplished remotely by administrative means 76
ILT-11 NRC Exam (SRO)
- 77. 212000A2.12 001/01001C71/300.006.A.19/BANK/TECH SPEC/SRO/212000A2.12/2/1/H/3/RAG Unit 2 is operating at 35% RTP.
34SV-C71-005-2, Turbine Control Valve (TCV) Fast Closure Instrument Functional Test, is in progress.
o The section for testing TCV #1 was performed satisfactorily When TCV #2 was tested, TCV #2 CLOSED but NONE of the RPS relays associated with TCV #2 changed state.
Based on the above conditions, When TCV #1 is CLOSED, a RPS Half Scram from TCV Closure __________ be received.
IAW Tech Specs 3.3.1.1, RPS Instrumentation, entry into a Required Action Statement for TCV #2 being INOPERABLE __________ .
A. will; is required immediately B. will; can be delayed up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> C. will NOT; is required immediately D. will NOT; can be delayed up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 77
ILT-11 NRC Exam (SRO)
- 78. 214000A2.03 001/05401C11/H-OP-90000.005/MOD/TECH SPECS/SRO/214000A2.03/2/2/H/3/ARB Unit 2 is at 90% RTP with eight (8) control rods INOPERABLE.
o 34SV-C11-003-2, Control Rod Exercise, for fully withdrawn control rods, is in progress At 05:45, during the coupling check on Control rod 18-19, the following observations were noted:
o ROD OVERTRAVEL, 603-248 ILLUMINATED o 18-19 four rod display position BLANK o 18-19 Full-Out light EXTINGUISHED At 05:46, the operator releases all rod movement control switches.
At 06:00, Control rod 18-19 can NOT be re-coupled.
Based on the above conditions, At 05:46, Control rod 18-19 four rod display position indication will __________ .
IAW Tech Spec 3.1.3, Control Rod Operability, the MINIMUM required condition statements to be entered are __________ .
Reference Provided A. have returned to position 48; C.1, C.2 and E B. have returned to position 48; C.1 and C.2 (Only)
C. remain BLANK; C.1, C.2 and E D. remain BLANK; C.1 and C.2 (Only) 78
ILT-11 NRC Exam (SRO)
- 79. 217000G2.2.12 001/30005TS/300.006.A.24/NEW/TECH SPEC/SRO/217000G2.2.12/2/1/H/3/RAG Unit 1 is operating at 100% RTP.
A review of surveillance records to ensure compliance with Tech Spec SR 3.5.3.3 shows that a 92 day surveillance, 34SV-E51-002-1, RCIC Pump Operability, has been performed on the following dates:
Date of Testing Days since previous test Jan 04 92 days Apr 06 92 days Jul 28 113 days Based on the above conditions, IAW SR 3.0.2, the specified frequency for the surveillance on Jul 28 __________ considered to be MET.
IAW SR 3.0.3, if it is discovered that 34SV-E51-002-1 has NOT been performed within its specified frequency, the requirement to declare RCIC inoperable __________ be DELAYED.
A. is; can B. is; can NOT C. is NOT; can D. is NOT; can NOT 79
ILT-11 NRC Exam (SRO)
- 80. 223002A2.03 001/30005TS/300.006.A.18/NEW/TECH SPEC/SRO/223002A2.03/2/1/H/2/ARB Unit 2 is in Mode 2 making preparations to enter Mode 1.
An operator performing a panel walkdown reports the following:
o The indication and output to the trip logic for Wide Range Drywell Radiation Monitor, 2D11-K621A, is 1000 R/hr o ALL other Drywell/Torus Radiation Monitors indicate a normal value o ALL Amber Lights on panel 2H11-P602, associated with this radiation monitor, are EXTINGUISHED The Shift Supervisor, after comfirming Drywell radiation values, declares 2D11-K621A inoperable.
Based on the above conditions, The TOTAL number of Amber Lights on panel 2H11-P602, associated with this radiation monitor, that SHOULD have ILLUMINATED is __________ .
IAW TS 3.0.4 & TS 3.3.6.1, WITHOUT performing a Risk Evaluation, TS __________
ALLOW the Reactor Mode switch to be placed in the RUN position.
Reference Provided A. zero (0);
will B. zero (0);
will NOT C. four (4);
will D. four (4);
will NOT 80
ILT-11 NRC Exam (SRO)
- 81. 239002G2.4.31 001/01401B21/200.009.A.02/NEW/SYS-I/SRO/239002G2.4.31/2/1/H/3/RAG Unit 2 is operating at 100% RTP when a SRV inadvertently OPENS.
o Two (2) seconds after opening, the SRV goes CLOSED Based on the above conditions and IAW 34AB-B21-003-2, Failure Of Safety/Relief Valves, While the SRV is OPEN, total Main Steam Flow INDICATION will be __________ than the pre-event indication.
IAW 34AB-B21-003-2, Failure Of Safety/Relief Valves, within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of the SRV opening, __________ is REQUIRED to be performed.
A. less; 34SV-T48-002-2, Suppression Chamber To DW Vac Breaker System Operability B. less; 64CH-SAM-025-0, Reactor Coolant Sampling And Analysis C. greater; 34SV-T48-002-2, Suppression Chamber To DW Vac Breaker System Operability D. greater; 64CH-SAM-025-0, Reactor Coolant Sampling And Analysis 81
ILT-11 NRC Exam (SRO)
- 82. 262002G2.2.40 001/02703R23/300.006.A.32/NEW/TECH SPEC/SRO/262002G2.2.40/2/1/H/3/RAG Unit 1 is operating at 100% RTP.
o Critical Instrument Bus 1A is being powered from Essential Bus 1A o The Critical Instrument Bus 1A Inverter is Danger Tagged out of service Subsequently, the following conditions occur:
o At 01:00, the supply breaker to 600 VAC 1C trips OPEN o At 01:15, the Critical Instrument Buses are CROSS-TIED Based on the above conditions and IAW Tech Specs, At 01:01, a Required Action Statement (RAS) is REQUIRED to be entered for __________ .
At 01:16, Critical Instrument Bus 1A __________ considered OPERABLE.
A. 600 VAC 1C and Essential Bus 1A; is B. 600 VAC 1C and Essential Bus 1A; is NOT C. 600 VAC 1C (Only);
is D. 600 VAC 1C (Only);
is NOT 82
ILT-11 NRC Exam (SRO)
- 83. 286000G2.2.38 001/03601X43/200.024.A.01/BANK/TECH SPEC/SRO/286000G2.2.38/2/2/H/3/RAG IAW FHA Appendix B - Fire Protection Equipement Operating and Surveillance, Door 1D135 is is REQUIRED to be verified CLOSED every __________ .
If this fire door will NOT close and is declared nonfunctional, the EARLIEST time a Fire Watch is REQUIRED to be established is __________ .
Reference Provided A. 7 days; WITHIN one (1) hour of the door being declared nonfunctional B. 7 days; AFTER the door has been nonfunctional for 45 days C. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; WITHIN one (1) hour of the door being declared nonfunctional D. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; AFTER the door has been nonfunctional for 45 days 83
ILT-11 NRC Exam (SRO)
- 84. 295006G2.4.46 001/20309EOP/201.083.A.04/BANK/P-EOP/SRO/295006G2.4.46/1/1/H/3/RAG Unit 2 was operating at 100% RTP when BOTH RFPTs trip.
o All Control Rods are FULL IN o Recirc Pumps are operating at 61% speed At 07:00, the following alarms are ILLUMINATED:
o RECIRC A FLOW LIMIT, 602-134 o RECIRC B FLOW LIMIT, 602-234 o REACTOR VESSEL WATER LEVEL HIGH/LOW, 603-141 o REACTOR VESSEL LEVEL 2 DIV I TRIP, 603-205 o REACTOR VESSEL LEVEL 2 DIV II TRIP, 603-206 At 07:02, the following alarms are as indicated:
o REACTOR VESSEL LEVEL 2 DIV I TRIP, 603-205, is CLEAR o REACTOR VESSEL LEVEL 2 DIV II TRIP, 603-206, is CLEAR Based on the above conditions, IAW 34AR-602-134-2 & 34AR-602-234-2, the Recirc pumps are REQUIRED to be reduced to a FINAL speed of __________ .
At 07:03 and IAW the EOPs, RWL control is REQUIRED to be directed from __________ .
A. 33%;
31EO-EOP-015-2, CP-1 Alternate Level Control B. 33%;
31EO-EOP-010-2, RPV Control (Non-ATWS), RC/L path C. 22%;
31EO-EOP-015-2, CP-1 Alternate Level Control D. 22%;
31EO-EOP-010-2, RPV Control (Non-ATWS), RC/L path 84
ILT-11 NRC Exam (SRO)
- 85. 295014G2.4.21 001/30004ADMIN/300.004.B.03/NEW/ADMIN/SRO/295014G2.4.21/1/2/H/4/RAG Unit 2 is operating at 60% RTP.
o A spurious initiation signal results in an INVALID HPCI start One (1) minute later, the following conditions exist on panel 2H11-P601:
o 2E41-F001, Turb Steam Supply Valve OPEN o 2E41-F006, Pump Discharge Valve OPEN R
P M
Subsequently, HPCI is shutdown per the applicable operating procedure.
Based on the above conditions, Before HPCI was shutdown, HPCI __________ inject into the RPV.
IAW NMP-AD-031, SNC Reportability, Responsibilities, and Fleet Requirements, the INVALID initiation of HPCI __________ a four (4) hour reportable event.
A. did; is B. did; is NOT C. did NOT; is D. did NOT; is NOT 85
ILT-11 NRC Exam (SRO)
- 86. 295020AA2.05 001/20308EOP/201.085.A.01/BANK/P-AB/SRO/295020AA2.05/1/2/H/3/ARB Unit 2 is shutting down. Current reactor power is 40% RTP.
o HPCI & RCIC are INOPERABLE While shutting down, an event occurs resulting in the following conditions:
o RWL is-15 inches, being restored with RFPTs & CRD pump 2B Subsequently, an inadvertent Group 1 Isolation signal is received and can NOT be reset.
o Currently, RWL has lowered to -125 inches The Shift Supervisor has determined that RWL can NOT be restored and maintained above -155 inches.
Based on the above conditions, IAW 31EO-EOP-010-2, RPV Control (Non-ATWS), which ONE of the following is REQUIRED?
A. SAGs B. Steam Cooling C. Alternate Level Control D. Emergency RPV Depressurization 86
ILT-11 NRC Exam (SRO)
- 87. 295021AA2.03 001/20101EP/001.017.A/NEW/P-EP/SRO/295021AA2.03/1/1/H/3/ARB Unit 2 is in Mode 4. Type A Secondary Containment exists.
o RHR Loop 2A is in Shutdown Cooling A leak in the Drywell results in the following conditions:
o RWL is -140 inches, continuing to lower at 1 inch/minute o ALL injection systems are unavailable Ten (10) minutes later, an injection system is placed in service restoring RWL to 37 inches.
Based on the above conditions, IAW NMP-EP-110-GL02, HNP EALs - ICs, Threshold Values and Basis, the HIGHEST Emergency Classification declared will be a(an) __________ .
Reference Provided A. General Emergency B. Site Area Emergency C. Alert D. Notification of Unusual Event 87
ILT-11 NRC Exam (SRO)
- 88. 295023G2.2.40 001/03701Z41/H-OP-90000.014/MOD/EOP/SRO/295023G2.2.40/1/1/H/3/ARB Unit 2 is in day 5 of a Refueling outage with fuel movement in progress.
A Refueling accident occurs resulting in the following radiation levels:
o All Refueling Floor Area Radiation Monitors (ARMs) indicate between 20 and 50 mr/hr o 2D11-K611A-D, Refueling Floor Vent Exhaust Radiation Monitors indicate 8 mr/hr Based on the above conditions, The MCREC system __________ be operating in the Pressurization Mode.
IAW Tech Spec Bases, the MCREC System Pressurization Mode is designed to ensure that the Control Room operators will not exceed a __________ TEDE Whole Body dose.
A. will NOT; 2 Rem B. will NOT; 5 Rem C. will; 2 Rem D. will; 5 Rem 88
ILT-11 NRC Exam (SRO)
- 89. 295026EA2.03 001/20310EOP/201.074.A.13/NEW/P-EOP/SRO/295026EA2.03/1/1/H/3/ARB A transient has occurred on Unit 1 with RPV pressure at 1000 psig.
At 13:00, the SS directs an operator to lower RPV Pressure to 315 psig to remain in the SAFE region of the Heat Capacity Temperature Limit (HCTL).
At 13:30, the following conditions exist:
o RPV Pressure 315 psig o Torus Water Temperature 210°F o Torus Water Level 140 inches Based on the above conditions and IAW the EOPs, During the RPV Pressure reduction to 315 psig, exceeding the 100°F/hr cooldown rate __________ ALLOWED.
At 13:30, the REQUIRED action is to __________ .
Reference Provided A. was NOT; perform an Emergency Depressurization IAW 31EO-EOP-015-1, CP-1 Alternate Level Control, Steam Cooling & Emergency RPV Depressurization B. was NOT; lower and then maintain RPV Pressure between 150 psig and 200 psig IAW RC/P Path of 31EO-EOP-010-1, RPV Control (NON-ATWS)
C. was; perform an Emergency Depressurization IAW 31EO-EOP-015-1, CP-1 Alternate Level Control, Steam Cooling & Emergency RPV Depressurization D. was; lower and then maintain RPV Pressure between 150 psig and 200 psig IAW RC/P Path of 31EO-EOP-010-1, RPV Control (NON-ATWS) 89
ILT-11 NRC Exam (SRO)
- 90. 295028EA2.02 001/20310EOP/201.073.A.15/NEW/P-EOP/SRO/295028EA2.02/1/1/F/3/RAG Unit 1 was operating at 100% RTP when an event occurred causing Drywell temperature to begin increasing.
The following conditions exist:
At 10:20, Drywell temperature is 285°F and slowly INCREASING At 10:25, Drywell temperature is 290°F and STEADY Based on the above conditions and IAW 31EO-EOP-012-1, Primary Containment Control, At 10:20, RC[A] Point A, __________ REQUIRED to be performed concurrently.
At 10:25, RC/P path __________ be USED to control RPV pressure.
A. is; will B. is; will NOT C. is NOT; will D. is NOT; will NOT 90
ILT-11 NRC Exam (SRO)
- 91. 295029G2.4.18 001/20310EOP/201.075.B.15/BANK/P-EOP/SRO/295029G2.4.18/1/2/H/3/ARB On Unit 1 and IAW EOPs, which ONE of the choices below completes the following statements?
If Torus Water level increases to 206 inches and Drywell Sprays are INITIATED, Primary Containment __________ .
If Torus Water level stabilizes at 295 inches, 31EO-EOP-105-1, Primary Containment Water Level Determination, __________ REQUIRED to be performed.
A. differential pressure capability could be exceeded; is B. differential pressure capability could be exceeded; is NOT C. could be de-inerted from vacuum breaker operation; is D. could be de-inerted from vacuum breaker operation; is NOT 91
ILT-11 NRC Exam (SRO)
- 92. 295038G2.2.40 001/03101N62/300.010.A.30/BANK/TECH SPEC/SRO/295038G2.2.40/1/1/F/3/ARB Unit 1 is operating at 100% RTP.
Chemistry reports the following gross gamma activity rate for noble gases measured at the Offgas Pretreatment monitor station:
o 290 mCi/second Based on the above conditions and IAW TS and Bases 3.7.6, Main Condenser Offgas, Entry into a Required Action Statement (RAS) __________ REQUIRED for TS 3.7.6, Main Condenser Offgas.
The limit for TS 3.7.6 is based on __________ .
A. is; a significant break in the offgas piping B. is; the filtering capacity of the offgas charcoal beds C. is NOT; a significant break in the offgas piping D. is NOT; the filtering capacity of the offgas charcoal beds 92
ILT-11 NRC Exam (SRO)
- 93. 600000G2.4.46 001/20101EP/001.017.A/MOD/P-AB/SRO/600000G2.4.46/1/1/H/3/ARB Unit 1 is operating at 100% RTP when the following occurs:
o At 10:00 Fire alarm received on Unit 1 130' Turbine Building SO dispatched to investigate o At 10:05 SO reports the Unit 1 Hydrogen Seal Oil System is on fire o At 10:17 SO reports Unit 1 Hydrogen Seal Oil System fire is EXTINGUISHED Based on the above conditions, IAW 34AB-X43-001-1, Fire Procedure, at 10:05, entry into 34AB-C71-001-1, Scram Procedure, __________ REQUIRED.
IAW IAW NMP-EP-110-GL02, HNP EALs - ICs, Threshold Values and Basis, the 15 minute time period for making an emergency declaration BEGINS at __________ .
A. is NOT; 10:00 B. is NOT; 10:05 C. is; 10:00 D. is; 10:05 93
ILT-11 NRC Exam (SRO)
- 94. G2.1.5 001///BANK/P-ADMIN/SRO/G2.1.5/3/H/3/ARB NMP-AD-016, Fatigue Management Program, contains the following NOTE:
NOTE The term Covered as used in this procedure is different than the term Covered as it applies to membership in a labor union.
Which ONE of the choices below completes the following statements IAW NMP-AD-016?
If someone is performing duties of a Fire Brigade Leader, this is considered __________ .
If the On-shift Fire Brigade Leader contacted the Off-shift Fire Brigade Leader at home and discussed Fire Brigade concerns for 45 minutes, this 45 minutes __________ count toward the Off-shift Fire Brigade Leader's work hours.
A. Covered Work; will B. Covered Work; will NOT C. Incidental Duties; will D. Incidental Duties; will NOT 94
ILT-11 NRC Exam (SRO)
- 95. G2.1.31 001/02702R22/300.049.A.01/BANK/P-NORM/SRO/G2.1.31/3/H/3/ARB Unit 2 is operating at 100% RTP.
o 2P41-C001C, PSW pump 2C, trips on an overload/lockout condition Subsequently, the cause of the PSW Pump 2C trip is identified and repaired.
Based on the above conditions, The AMBER light above PSW pump 2C control switch is located on panel __________ .
The procedure which provides the list of personnel whose authorization is REQUIRED to RESET the PSW Pump 2C LOCKOUT relay is __________ .
A. 2H11-P650; 34SO-P41-001-2, Plant Service Water System B. 2H11-P650; 31GO-OPS-021, Manipulation of Controls and Equipment C. 2H11-P652; 34SO-P41-001-2, Plant Service Water System D. 2H11-P652; 31GO-OPS-021, Manipulation of Controls and Equipment 95
ILT-11 NRC Exam (SRO)
- 96. G2.2.2 001/30004ADMIN/300.032.A.02/NEW/P-NORM/SRO/G2.2.2/3/F/3/ARB Preparations are in progress on Unit 2 for starting up from the 2R24 Refueling Outage.
Which ONE of the choices below completes both statements?
IAW 10AC-MGR-001-0, Plant Organization Staff Responsibilities & Authorities, the order to start up the Unit 2 reactor from the 2R24 Refueling Outage is issued by the __________ ,
or designated alternate.
IAW 34GO-OPS-001-2, Plant Startup, the MINIMUM level of authorizations REQUIRED, confirming all prerequisites necessary to transfer the Reactor Mode switch to the START & HOT STBY position, is the __________ and the Shift Manager .
A. Vice President; Shift Operations Manager B. Vice President; Shift Supervisor C. Plant Manager; Shift Operations Manager D. Plant Manager; Shift Supervisor 96
ILT-11 NRC Exam (SRO)
- 97. G2.2.15 001/30004ADMIN/300.017.A.03/BANK/ADMIN/SRO/G2.2.15/3/H/2/ARB IAW NMP-ES-054, Temporary Modification, A Temporary Modification (TM) tag is REQUIRED for __________ ; AND, A Plant Review Board (PRB) review __________ REQUIRED prior to implementing the TM.
NOTE: Assume that neither activity is a tag hanging hazard.
A. pulling the annunciator card for CORE SPRAY SYSTEM II ACTUATED, (601-101) to disable a nuisance alarm; is B. pulling the annunciator card for CORE SPRAY SYSTEM II ACTUATED, (601-101) to disable a nuisance alarm; is NOT C. changing the Unit 2 HPCI oil filter from a standard cartridge oil filter to a water scavenging oil filter for one week; is D. changing the Unit 2 HPCI oil filter from a standard cartridge oil filter to a water scavenging oil filter for one week; is NOT 97
ILT-11 NRC Exam (SRO)
- 98. G2.3.11 001/20312EOP/4.B/BANK/P-EOP/SRO/G2.3.11/3/H/3/ARB A LOCA has occurred on Unit 2.
The following conditions currently exist:
o RWL -165 inches and stable o Drywell Pressure 54 psig and slowly INCREASING o Drywell Radiation 2,500 R/hr and slowly INCREASING o Torus Pressure 52 psig and slowly INCREASING o Torus Water Level > 300 inches Based on the above conditions and IAW 31EO-EOP-012-2, Primary Containment Control, The REQUIRED procedure to vent the Primary Containment is __________ .
While venting the Primary Containment, exceeding the offsite radioactivity release rate limits __________ permitted.
A. 34SO-T48-002-2, Containment Atmospheric Control & Dilution Systems, Section 4.3.3, Fast Drywell Vent; is NOT B. 34SO-T48-002-2, Containment Atmospheric Control & Dilution Systems, Section 4.3.3, Fast Drywell Vent; is C. 31EO-EOP-101-2, Emergency Containment Venting; is NOT D. 31EO-EOP-101-2, Emergency Containment Venting; is 98
ILT-11 NRC Exam (SRO)
- 99. G2.4.17 001/20306CURVES/201.084.A.02/BANK/P-EOP/SRO/G2.4.17/3/F/3/ARB Which ONE of the choices below completes the following statements?
The Minimum Zero-Injection RPV Water Level is defined to be the lowest RPV water level at which the covered portion of the Reactor core will generate sufficient steam to preclude any clad temperature in the uncovered portion of the core from exceeding a MAXIMUM of __________ .
INITIALLY when the Minimum Zero-Injection RPV Water Level is reached, then __________ flowchart will be used for RWL and RPV pressure control.
A. 1500°F; CP-1, 31EO-EOP-015, B. 1500°F; SAG-1, 31EO-SAG-001, C. 1800°F; CP-1, 31EO-EOP-015, D. 1800°F; SAG-1, 31EO-SAG-001, 99
ILT-11 NRC Exam (SRO) 100. G2.4.41 001/20101EP/001.017.A.01/NEW/P-EP/SRO/G2.4.41/3/H/3/RAG Unit 2 was operating at 100% RTP when the following events occur:
Time Event 12:00 A HPCI pipe break occurs in the Reactor Building 12:05 HPCI steam supply isolation valves, 2E41-F002 & F003, can NOT be closed 12:20 HPCI room temperature INCREASES to above the Max Normal Operating Temperature Based on the above conditions and IAW NMP-EP-110-GL02, HNP EALs - ICs, Threshold Values and Basis, The LATEST listed time the INITIAL emergency declaration is REQUIRED to be made is __________ .
At 12:40, the HIGHEST emergency classification REQUIRED is a(an) __________ .
Reference Provided A. 12:19; Alert B. 12:34; Alert C. 12:19; Site Area Emergency D. 12:34; Site Area Emergency End of Test 100
E. I. HATCH 2017-301 ILT EXAM ANSWER SHEET SRO EXAM 76 D 81 A 86 C 91 B 96 B 77 A 82 D 87 C 92 A 97 C 78 C 83 C 88 D 93 C 98 D 79 A 84 D 89 C 94 A 99 C 80 C 85 B 90 A 95 B 100 C
- 1. 34AB-N21-002-2, Feedwater/Reactor Water Level Control Issues, Attachment 2
- 2. Ui EOP Graphs 11A& liB, Core Spray NPSH Limit
- 3. NMP-EP-1l 1-002, Emergency Notification Network Communicator Instructions Hatch, Page 10
- 4. 34G0-OPS-005-2, Power Changes, Attachment 1
- 5. 34AB-C51-OOi-2, Entry Into The RPI Or Reactor Operations With Inoperable OPRM System, Attachment 1
- 1. 34AB-N21-002-2, feedwater/Reactor Water Level Control Issues, Attachment 2
- 2. Ui EOP Graphs 1 1A & 1 iB, Core Spray NPSH Limit
- 3. NMP-EP-1 11-002, Emergency Notification Network Communicator Instructions Hatch, Page 10
- 4. 34G0-OPS-005-2, Power Changes, Attachment 1
- 5. 34AB-C51-001-2, Entry Into The RPI Or Reactor Operations With Inoperable OPRM System, Attachment 1
- 6. U2 TS 3.1.3, Control Rod Operability, Pages 3.1-5 to 3.1-7 (Without SRs)
- 7. U2 IS 3.3.6.1, Primary Containment Isolation Instrumentation, Pages 3.3-48 3.3-50 &
3.3-53 (Without SRs & Table Values)
- 8. TRM Appendix B, Fire Protection Surveillance Requirements, Table 1.1-1