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{{#Wiki_filter:ES-401 | {{#Wiki_filter:ES-401 Site-Specific SRO Written Examination Form ES-401-8 Cover Sheet U. S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name: | ||
Date: 20 OCT 2015 Facility / Unit FARLEY 1 & 2 Region: I II X III IV Reactor Type: W X CE BW GE Start Time: Finish Time: | |||
Instructions 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 percent overall, with 70 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80 percent to pass. You have 8 hours to complete the combined examination, and 3 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 75 / ______ | |||
______ 25 / ______ | |||
100 Points Applicant's Score ______ / ______ / ______ | |||
Points Applicant's Grade ______ / ______ / ______ | |||
Percent ES-401, Page 38 of 50 | |||
QUESTIONS REPORT for ILT 38 SRO Ver 5 | |||
: 1. 003AG2.1.23 076 Unit 1 was operating at 100% power when the following occurred: | : 1. 003AG2.1.23 076 Unit 1 was operating at 100% power when the following occurred: | ||
At 1000: | At 1000: | ||
* All Control Banks are at 231 steps. | * All Control Banks are at 231 steps. | ||
At 1010:* Rod K4 fell to 130 steps.* Rod M6 fell to 150 steps. | At 1010: | ||
* Rod K4 fell to 130 steps. | |||
* Rod M6 fell to 150 steps. | |||
* RCS Tavg lowered. | * RCS Tavg lowered. | ||
* Pressurizer pressure lowered. | * Pressurizer pressure lowered. | ||
Which one of the following | Which one of the following completes the statement below? | ||
Per AOP-19, Malfunction of Rod Control System, the operating crew is required to | Per AOP-19, Malfunction of Rod Control System, the operating crew is required to . | ||
A. shutdown the unit using UOP-3.1, Power Operation B. trip the Reactor and go to EEP-0.0, Reactor Trip and Safety Injection C. reduce power to less than 75% within 1 hour using UOP-3.1, Power Operation D. address restoration of rods using SOP-41.0, Control Rod Drive and Position Indication System Tuesday, June 30, 2015 2:03:49 PM 1 | |||
QUESTIONS REPORT for ILT 38 SRO Ver 5 | |||
QUESTIONS | |||
: 2. 003G2.4.45 077 Unit 1 is operating at 100% power when the following occurs: | : 2. 003G2.4.45 077 Unit 1 is operating at 100% power when the following occurs: | ||
At 1000: | At 1000: | ||
* HH4, RCP VIB TRBL (WHITE | * HH4, RCP VIB TRBL (WHITE annunciator window), comes into alarm. | ||
* 1A RCP shaft vibration is reported as 21 mils and stable. | * 1A RCP shaft vibration is reported as 21 mils and stable. | ||
* DC2, RCP #1 SEAL LKOF FLOW HI (YELLOW annunciator window), | * DC2, RCP #1 SEAL LKOF FLOW HI (YELLOW annunciator window), | ||
* FR145A, | comes into alarm. | ||
* FR145A, RCP SEAL LKOF HIGH RANGE, for the 1A RCP indicates 6.5 gpm and stable. | |||
At 1600: | At 1600: | ||
* The Unit is in MODE 3. | * The Unit is in MODE 3. | ||
Line 50: | Line 51: | ||
* 1B and 1C RCPs are running. | * 1B and 1C RCPs are running. | ||
* 1A RCP is tagged out. | * 1A RCP is tagged out. | ||
Which one of the following | Which one of the following completes the statements below? | ||
At 1000 , the operating crew is required to (1) | At 1000, the operating crew is required to (1) , then secure the 1A RCP. | ||
At 1600 , RCS pressure control is via (2) | At 1600, RCS pressure control is via (2) . | ||
QUESTIONS | A. (1) trip the Reactor and go to EEP-0.0, Reactor Trip or Safety Injection (2) Normal Spray B. (1) perform a controlled shutdown per the appropriate Unit Operating Procedures (2) Normal Spray C. (1) trip the Reactor and go to EEP-0.0, Reactor Trip or Safety Injection (2) Auxiliary Spray D. (1) perform a controlled shutdown per the appropriate Unit Operating Procedures (2) Auxiliary Spray Tuesday, June 30, 2015 2:03:49 PM 2 | ||
: 3. 007A2.03 078 Unit 1 is operating at 100% | |||
power when the following occurs: | QUESTIONS REPORT for ILT 38 SRO Ver 5 | ||
* Due to a Pressurizer pressure | : 3. 007A2.03 078 Unit 1 is operating at 100% power when the following occurs: | ||
* Due to a Pressurizer pressure control malfunction, PCV-445A, PRZR PORV opens and reseats several times. | |||
* PRT level rises to 84% and is stable. | * PRT level rises to 84% and is stable. | ||
Which one of the following | Which one of the following completes the statements below? | ||
HE4, PRT LVL HI-LO, | HE4, PRT LVL HI-LO, (1) in alarm. | ||
The procedure used to lower PRT level is (2) | The procedure used to lower PRT level is (2) . | ||
A. (1) is NOT (2) SOP-1.2, Reactor Coolant Pressure Relief System B. (1) IS (2) SOP-1.2, Reactor Coolant Pressure Relief System C. (1) is NOT (2) SOP-50.0, Liquid Waste Processing System D. (1) IS (2) SOP-50.0, Liquid Waste Processing System Tuesday, June 30, 2015 2:03:49 PM 3 | |||
QUESTIONS REPORT for ILT 38 SRO Ver 5 | |||
: 4. 007EA2.03 079 Unit 1 is in MODE 3 with the following conditions: | : 4. 007EA2.03 079 Unit 1 is in MODE 3 with the following conditions: | ||
At 1000: | At 1000: | ||
Line 68: | Line 71: | ||
At 1005: | At 1005: | ||
* A complete loss of offsite power occurs. | * A complete loss of offsite power occurs. | ||
Which one of the following | Which one of the following completes the statements below? | ||
At 1005, manual action (1) | At 1005, manual action (1) required to generate a P-4 signal. | ||
Per the BASES of Tech Spec 3.3.2, ESFAS | Per the BASES of Tech Spec 3.3.2, ESFAS Instrumentation, P-4 is required to be OPERABLE to prevent (2) . | ||
A. (1) IS (2) excessive Containment pressure due to a steamline break B. (1) is NOT (2) excessive Containment pressure due to a steamline break C. (1) IS (2) damage to the Main Steam lines and SG safeties due to SG overfill D. (1) is NOT (2) damage to the Main Steam lines and SG safeties due to SG overfill Tuesday, June 30, 2015 2:03:49 PM 4 | |||
QUESTIONS REPORT for ILT 38 SRO Ver 5 | |||
: 5. 010G2.2.44 080 Unit 1 is operating at 100% | : 5. 010G2.2.44 080 Unit 1 is operating at 100% power with the following conditions: | ||
* PRT pressure, level and temperature are stable.* HA4, PRZR SAFETY VLV TEMP HI, is in alarm.* HA5, PRZR PORV TEMP HI, is in alarm. | * A malfunction occurred resulting in PCV-444B, PRZR PORV, opening. | ||
Subsequently, the immediate operator actions of AOP-100, Instrumentation Malfunction, were performed and the following conditions exist: | |||
* PCV-444B GREEN light is LIT. | |||
* MOV-8000B, PRZR PORV ISO, RED light is LIT. | |||
* RCS pressure is 2180 psig and stable. | |||
* PRT pressure, level and temperature are stable. | |||
* HA4, PRZR SAFETY VLV TEMP HI, is in alarm. | |||
* HA5, PRZR PORV TEMP HI, is in alarm. | |||
* HD1, PRZR PRESS REL VLV 445A OR B/U HTRS ON, is in alarm. | * HD1, PRZR PRESS REL VLV 445A OR B/U HTRS ON, is in alarm. | ||
Which one of the following | Which one of the following completes the statements below? | ||
PCV-444B | PCV-444B (1) leaking by. | ||
Per Tech Spec 3.4.11, Pressurizer Power Operated Relief Valves (PORVs), PCV-444B (2) | Per Tech Spec 3.4.11, Pressurizer Power Operated Relief Valves (PORVs), PCV-444B (2) OPERABLE. | ||
(1) (2) | |||
A. IS IS B. IS is NOT C. is NOT IS D. is NOT is NOT Tuesday, June 30, 2015 2:03:49 PM 5 | |||
QUESTIONS | |||
QUESTIONS REPORT for ILT 38 SRO Ver 5 | |||
: 6. 026A2.03 081 Unit 1 is at 100% power with the following conditions: | : 6. 026A2.03 081 Unit 1 is at 100% power with the following conditions: | ||
* PT-950, CTMT PRESS (Channel 1), was | * PT-950, CTMT PRESS (Channel 1), was declared INOPERABLE. | ||
* PT-950 bistables were positioned as required by Tech Spec 3.3.2, | * PT-950 bistables were positioned as required by Tech Spec 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, for continuous operation with an inoperable channel. | ||
Which one of the following | Which one of the following completes the statements below? | ||
Per Tech Spec 3.3.2, the | The Safety Injection function (1) affected by the PT-950 malfunction. | ||
Per Tech Spec 3.3.2, the REQUIRED ACTION is to place the PT-950 bistables in (2) . | |||
QUESTIONS | (1) (2) | ||
A. IS TRIP B. IS BYPASS C. is NOT TRIP D. is NOT BYPASS Tuesday, June 30, 2015 2:03:49 PM 6 | |||
QUESTIONS REPORT for ILT 38 SRO Ver 5 | |||
: 7. 026AA2.03 082 Unit 1 is in MODE 3 with the following conditions: | : 7. 026AA2.03 082 Unit 1 is in MODE 3 with the following conditions: | ||
* All RCPs are running. | * All RCPs are running. | ||
* A CCW leak occurs on the 1A RCP Oil Cooler inlet connection. | * A CCW leak occurs on the 1A RCP Oil Cooler inlet connection. | ||
Which one of the following | Which one of the following completes the statements below? | ||
The method used in the Main Control Room (MCR) to isolate the CCW leak is to (1) | The method used in the Main Control Room (MCR) to isolate the CCW leak is to (1) . | ||
QUESTIONS | Per the BASES of Tech Spec 3.7.7 - CCW System, once the CCW leak is isolated from the MCR, the CCW System is (2) . | ||
: 8. 028A2.02 083 Unit 1 has experienced a LOCA. | A. (1) isolate CCW to ALL RCPs (2) INOPERABLE B. (1) isolate CCW to the 1A RCP ONLY (2) INOPERABLE C. (1) isolate CCW to ALL RCPs (2) OPERABLE D. (1) isolate CCW to the 1A RCP ONLY (2) OPERABLE Tuesday, June 30, 2015 2:03:49 PM 7 | ||
The following conditions exist: | |||
QUESTIONS REPORT for ILT 38 SRO Ver 5 | |||
: 8. 028A2.02 083 Unit 1 has experienced a LOCA. The following conditions exist: | |||
* EEP-1.0, Loss of Reactor or Secondary Coolant, is in progress. | * EEP-1.0, Loss of Reactor or Secondary Coolant, is in progress. | ||
* Containment Hydrogen is 6% | * Containment Hydrogen is 6% by volume of dry air. | ||
by volume of dry air. | Which one of the following completes the statements below? | ||
Which one of the following | The hydrogen concentration (1) exceed the lower FLAMMABILITY limit. | ||
The hydrogen concentration (1) | Hydrogen concentration will be lowered using (2) . | ||
A. (1) DOES (2) SOP-10.0, POST LOCA Containment Pressurization and Vent System B. (1) DOES (2) Attachment 3 of EEP-1.0, Post LOCA Hydrogen Recombiner Operation C. (1) does NOT (2) SOP-10.0, POST LOCA Containment Pressurization and Vent System D. (1) does NOT (2) Attachment 3 of EEP-1.0, Post LOCA Hydrogen Recombiner Operation Tuesday, June 30, 2015 2:03:49 PM 8 | |||
QUESTIONS REPORT for ILT 38 SRO Ver 5 | |||
: 9. 028AG2.1.25 084 Unit 1 is operating at 100% | : 9. 028AG2.1.25 084 Unit 1 is operating at 100% when a Pressurizer level control malfunction occurs and the following conditions exist: | ||
when a Pressurizer level | |||
* Pressurizer level is 70% and rising. | * Pressurizer level is 70% and rising. | ||
* Charging flow is 120 gpm. | * Charging flow is 120 gpm. | ||
Line 111: | Line 128: | ||
* RCP seal injection is 8 gpm to each RCP. | * RCP seal injection is 8 gpm to each RCP. | ||
* RCP seal leakoff is 3 gpm per pump. | * RCP seal leakoff is 3 gpm per pump. | ||
* Actions in the field are being taken to regain | * Actions in the field are being taken to regain control of Charging. | ||
* It will take 8 minutes to regain control of Charging. | * It will take 8 minutes to regain control of Charging. | ||
Which one of the following | Which one of the following completes the statements below? | ||
An | An automatic reactor trip (1) occur before control of Charging is regained. | ||
Per the BASES of Tech Spec 3.3. | Per the BASES of Tech Spec 3.3.1, Reactor Trip System (RTS) | ||
1, Reactor Trip System (RTS) | Instrumentation, the purpose of the automatic Reactor Trip on Pressurizer Water Level - High is to (2) . | ||
Instrumentation, the purpose of the | Reference Provided A. (1) WILL (2) provide protection against water relief through the PORV's B. (1) WILL (2) prevent thermal shock of the Spray Nozzle C. (1) will NOT (2) provide protection against water relief through the PORV's D. (1) will NOT (2) prevent thermal shock of the Spray Nozzle Tuesday, June 30, 2015 2:03:49 PM 9 | ||
QUESTIONS REPORT for ILT 38 SRO Ver 5 | |||
: 10. 034G2.4.30 085 Unit 1 is conducting a fuel reload and the following conditions occur: | : 10. 034G2.4.30 085 Unit 1 is conducting a fuel reload and the following conditions occur: | ||
At 1000: | At 1000: | ||
Line 125: | Line 142: | ||
* A loss of power to the fuel transfer system occurs. | * A loss of power to the fuel transfer system occurs. | ||
At 1015: | At 1015: | ||
* It is determined that an Intermediate Leg leak is in progress on | * It is determined that an Intermediate Leg leak is in progress on the 1A RCS loop. | ||
* R-2, CTMT 155 FT, is in alarm. | * R-2, CTMT 155 FT, is in alarm. | ||
* EH2, SFP LVL HI-LO is in alarm. | * EH2, SFP LVL HI-LO is in alarm. | ||
* Both RHR pumps have been secured due to cavitation. | * Both RHR pumps have been secured due to cavitation. | ||
Which one of the following | Which one of the following completes the statements below? | ||
At 1030 , an emergency classification , per NMP-EP-110, Emergency Classification | At 1030, an emergency classification, per NMP-EP-110, Emergency Classification Determination and Initial Action, (1) required. | ||
If the RCS leak is not isolated, the spent fuel assembly in the upender (2) | If the RCS leak is not isolated, the spent fuel assembly in the upender (2) remain covered with water. | ||
(1) (2) | |||
A. IS will NOT B. IS WILL C. is NOT will NOT D. is NOT WILL Tuesday, June 30, 2015 2:03:49 PM 10 | |||
QUESTIONS REPORT for ILT 38 SRO Ver 5 | |||
: 11. 036AA2.02 086 A fuel shuffle is in progress in the Unit 1 SFP with the following conditions: | : 11. 036AA2.02 086 A fuel shuffle is in progress in the Unit 1 SFP with the following conditions: | ||
* An 1800 lb. load is | * An 1800 lb. load is being moved over spent fuel. | ||
Subsequently, the following occurs: | Subsequently, the following occurs: | ||
* The load is dropped causing damage to the spent fuel. | * The load is dropped causing damage to the spent fuel. | ||
* R-5, SFP ROOM, comes into alarm. | * R-5, SFP ROOM, comes into alarm. | ||
Which one of the following | Which one of the following completes the statements below? | ||
AOP-30, Refueling Accident, | AOP-30, Refueling Accident, (1) required to be entered. | ||
Per the Bases of TR 13.9.4, | Per the Bases of TR 13.9.4, Crane Travel-Spent Fuel Storage Building, the expected worst case consequences of dropping an 1800 lb. load onto the spent fuel is that the (2) . | ||
A. (1) IS (2) activity release will be limited to that contained in a single fuel assembly B. (1) IS (2) offsite dose may be as high as but not more than the 10 CFR 100 limit C. (1) is NOT (2) activity release will be limited to that contained in a single fuel assembly D. (1) is NOT (2) offsite dose may be as high as but not more than the 10 CFR 100 limit Tuesday, June 30, 2015 2:03:49 PM 11 | |||
QUESTIONS REPORT for ILT 38 SRO Ver 5 | |||
: 12. 056AG2.2.44 087 Unit 1 was operating at 100% power with the following conditions: | : 12. 056AG2.2.44 087 Unit 1 was operating at 100% power with the following conditions: | ||
At 1000: | At 1000: A complete loss of Offsite Power occurred. | ||
At 1015: A spurious Safety Injection | At 1015: A spurious Safety Injection occurs and the following indications exist: | ||
* On the Main Control Board: | * On the Main Control Board: | ||
- 1D SW PUMP Handswitch - GREEN and YELLOW lights LIT | |||
- 1E SW PUMP Handswitch - GREEN and YELLOW lights LIT | |||
* On the EPB: | * On the EPB: | ||
- BIG SEQUENCER LIGHTS: | |||
- BKR NOT CLOSED STEP 3 - LIT | |||
- BKR NOT CLOSED STEP 4 - LIT | |||
- ESS SEQ INCOMPLETE - LIT | |||
- LOSP MAN LOADING START - LIT At 1017: The UO takes the 1D and 1E SW pump handswitches to START and the following occurs: | |||
* 1D SW PUMP Handswitch - RED light LIT | * 1D SW PUMP Handswitch - RED light LIT | ||
* 1E SW PUMP | * 1E SW PUMP Handswitch - RED light LIT | ||
* PI 3001B, SW TO CCW HX HDR PRESS, rises to 100 psig. | * PI 3001B, SW TO CCW HX HDR PRESS, rises to 100 psig. | ||
Which one of the following | Which one of the following completes the statements below? | ||
At 1015: The 1B DG (1) | At 1015: The 1B DG (1) have cooling water supplied. | ||
At 1017: | At 1017: In addition to CONDITION C of Tech Spec 3.8.1, AC Sources - Operating, CONDITON(S) (2) is(are) required to be entered. | ||
Reference Provided (1) (2) | |||
A. WILL B&G B. WILL G ONLY C. will NOT B&G D. will NOT G ONLY Tuesday, June 30, 2015 2:03:49 PM 12 | |||
: 13. 065AG2.4.22 088 Unit 1 is operating at 100% | |||
* A rupture has occurred on the | QUESTIONS REPORT for ILT 38 SRO Ver 5 | ||
: 13. 065AG2.4.22 088 Unit 1 is operating at 100% power with the following conditions: | |||
* A rupture has occurred on the Instrument Air header piping in the MSVR. | |||
* A Reactor Trip has occurred. | * A Reactor Trip has occurred. | ||
* AOP-6.0, Loss of | * AOP-6.0, Loss of Instrument Air, is in progress. | ||
Which one of the following | Which one of the following completes the statements below? | ||
Procedure Names | After the Reactor Trip, Pressurizer level will (1) due to the loss of Instrument Air. | ||
: AOP-16.0, CVCS Malfunction | Per AOP-6.0, to maintain Pressurizer level, the operating crew is required to perform actions of (2) in conjunction with AOP-6.0. | ||
Procedure Names: AOP-16.0, CVCS Malfunction SOP-2.1, CVCS Plant Startup and Operation (1) (2) | |||
: 14. 072A2.03 089 Unit 1 is operating at 100% | A. lower AOP-16.0 B. rise AOP-16.0 C. lower SOP-2.1 D. rise SOP-2.1 Tuesday, June 30, 2015 2:03:49 PM 13 | ||
power when the following occurs: | |||
QUESTIONS REPORT for ILT 38 SRO Ver 5 | |||
: 14. 072A2.03 089 Unit 1 is operating at 100% power when the following occurs: | |||
* R-27B, CTMT HIGH RANGE, is tagged out. | * R-27B, CTMT HIGH RANGE, is tagged out. | ||
* The instrument power supply fuse to R-27A, CTMT HIGH RANGE, blows. | * The instrument power supply fuse to R-27A, CTMT HIGH RANGE, blows. | ||
Which one of the following | Which one of the following completes the statements below? | ||
The loss of R-27A (1) | The loss of R-27A (1) affect the ability to evaluate the loss of Fuel Clad Barrier per NMP-EP-110-GL01, FNP EALs - ICs, Threshold Values and Basis. | ||
Per Tech Spec 3.3.3, Post | Per Tech Spec 3.3.3, Post Accident Monitoring Instrumentation, the REQUIRED ACTION is to (2) . | ||
Reference Provided A. (1) will NOT (2) immediately initiate action in accordance with Specification 5.6.8 B. (1) will NOT (2) restore R-27A OR R-27B to OPERABLE status in 7 days C. (1) WILL (2) immediately initiate action in accordance with Specification 5.6.8 D. (1) WILL (2) restore R-27A OR R-27B to OPERABLE status in 7 days Tuesday, June 30, 2015 2:03:50 PM 14 | |||
QUESTIONS REPORT for ILT 38 SRO Ver 5 | |||
: 15. 073A2.01 090 Unit 1 is operating at 100% | : 15. 073A2.01 090 Unit 1 is operating at 100% power and the following occurs: | ||
power and the following occurs: | * R-15A, SJAE EXH, power supply becomes erratic causing its indication to become unreliable but it does not alarm. | ||
* R-15A, SJAE EXH, power supply | Per the ODCM, which one of the following actions are required to continue the release via this pathway, if any? | ||
No actions are required. | A. No actions are required. | ||
Continuously collect samples using auxiliary equipment. | B. Continuously collect samples using auxiliary equipment. | ||
Place SJAE filtration in service until R-15A is restored to operable. | C. Place SJAE filtration in service until R-15A is restored to operable. | ||
Perform grab samples at least once per 8 hours and analyze them within 24 hours. | D. Perform grab samples at least once per 8 hours and analyze them within 24 hours. | ||
Tuesday, June 30, 2015 2:03:50 PM 15 | |||
QUESTIONS REPORT for ILT 38 SRO Ver 5 | |||
: 16. G2.1.41 091 Unit 1 is in MODE 6 with the following conditions: | : 16. G2.1.41 091 Unit 1 is in MODE 6 with the following conditions: | ||
* Core reload is complete. | * Core reload is complete. | ||
* Control Rod Drive Shaft Latching and RCCA Drag Testing is about to begin per | * Control Rod Drive Shaft Latching and RCCA Drag Testing is about to begin per FHP-5.1, Control Rod Drive Shaft Latching/Unlatching Tool Operating Instruction. | ||
Per FHP-1.0, Refueling | Per FHP-1.0, Refueling Operations, which one of the following requirements must be met prior to latching control rods? | ||
The Maintenance Supervisor is in Containment. | A. The Maintenance Supervisor is in Containment. | ||
The Fuel Handling | B. The Fuel Handling Supervisor is in Containment. | ||
The Maintenance Supervisor is in the Control Room | C. The Maintenance Supervisor is in the Control Room and in direct communication with Containment. | ||
The Fuel Handling Supervisor is in the Control Room and in direct communication with Containment. | D. The Fuel Handling Supervisor is in the Control Room and in direct communication with Containment. | ||
Tuesday, June 30, 2015 2:03:50 PM 16 | |||
: 17. G2.2.13 092 A tagout is required to be cleared during | |||
Per NMP-AD-003, Equipment Clearance and Tagging, which one of the following can sign off | QUESTIONS REPORT for ILT 38 SRO Ver 5 | ||
Shift Manager Operations Director Maintenance Director Maintenance Manager | : 17. G2.2.13 092 A tagout is required to be cleared during night shift and the Work Document Holder is not on site and cannot be contacted to gain their approval. | ||
: 18. G2.2.40 093 Unit 1 is at 6% power | Per NMP-AD-003, Equipment Clearance and Tagging, which one of the following can sign off the Work Document Holder? | ||
A. Shift Manager B. Operations Director C. Maintenance Director D. Maintenance Manager Tuesday, June 30, 2015 2:03:50 PM 17 | |||
QUESTIONS REPORT for ILT 38 SRO Ver 5 | |||
: 18. G2.2.40 093 Unit 1 is at 6% power with the following conditions: | |||
* The 1A SGFP has been started. | * The 1A SGFP has been started. | ||
* AFW is secured. | * AFW is secured. | ||
* The Main Feed Regulating Valves are closed. | * The Main Feed Regulating Valves are closed. | ||
At 1000 on January 1, 2015: | At 1000 on January 1, 2015: | ||
* MOV-3232B, MAIN FW TO 1B SG | * MOV-3232B, MAIN FW TO 1B SG STOP VLV , is declared INOPERABLE. | ||
At 1200 on January 1, 2015 | At 1200 on January 1, 2015: | ||
: | |||
* FCV-489, 1B SG FW BYP FLOW, is declared INOPERABLE. | * FCV-489, 1B SG FW BYP FLOW, is declared INOPERABLE. | ||
Subsequently it is determined that | Subsequently it is determined that repairs will take 96 hours for each valve. | ||
Which one of the following | Which one of the following completes the statement below? | ||
Per Tech Spec 3.7.3, Main Feedwater | Per Tech Spec 3.7.3, Main Feedwater Stop Valves and Main Feedwater Regulation Valves (MFRVs) and Associated Bypass Valves, the earliest time that feed flow to the 1B SG must be isolated is . | ||
Reference Provided A. 1800 on January 1, 2015 B. 2000 on January 1, 2015 C. 1000 on January 4, 2015 D. 1200 on January 4, 2015 Tuesday, June 30, 2015 2:03:50 PM 18 | |||
QUESTIONS REPORT for ILT 38 SRO Ver 5 | |||
: 19. G2.3.12 094 A General Emergency on | : 19. G2.3.12 094 A General Emergency on Unit 1 has been declared with following conditions: | ||
* An Emergency Response Team is required to be dispatched to isolate an | * An Emergency Response Team is required to be dispatched to isolate an offsite release source. | ||
* The TSC has not yet been manned. | * The TSC has not yet been manned. | ||
* The expected exposure for the job is 35 REM TEDE per person. | * The expected exposure for the job is 35 REM TEDE per person. | ||
Which one of the following | Which one of the following completes the statements below? | ||
To receive the dose listed above, operators (1) | To receive the dose listed above, operators (1) required to be volunteers. | ||
The (2) will authorize the exposure. | |||
(1) (2) | |||
A. are NOT RP Supervisor B. are NOT Shift Manager C. ARE RP Supervisor D. ARE Shift Manager Tuesday, June 30, 2015 2:03:50 PM 19 | |||
20 QUESTIONS | QUESTIONS REPORT for ILT 38 SRO Ver 5 | ||
: 21. G2.4.30 096 Unit 2 reactor startup is in | : 20. G2.3.14 095 Unit 1 is in MODE 6 with core offload in progress with the following condition: | ||
* NI31, SR1 COUNT RATE is | * A spent fuel assembly is being moved from its assigned location in the core to the upender. | ||
* NI32, SR2 COUNT RATE is | Subsequently, AOP-30.0, Refueling Accident, is entered Which one of the following completes the statements below? | ||
Per AOP-30.0, the Refueling SRO will direct the fuel assembly to be (1) . | |||
Per the BASES of Tech Spec 3.9.6, Refueling Cavity Water Level, 23 ft of water is required to be maintained above the fuel to (2) . | |||
A. (1) placed in any empty fuel location in the core (2) provide back up decay heat removal B. (1) placed in any empty fuel location in the core (2) retain iodine fission product activity in the water during a fuel handling accident C. (1) returned to its assigned location in the core (2) provide back up decay heat removal D. (1) returned to its assigned location in the core (2) retain iodine fission product activity in the water during a fuel handling accident Tuesday, June 30, 2015 2:03:50 PM 20 | |||
QUESTIONS REPORT for ILT 38 SRO Ver 5 | |||
: 21. G2.4.30 096 Unit 2 reactor startup is in progress and the following conditions exist: | |||
* NI31, SR1 COUNT RATE is 106 cps and stable. | |||
* NI32, SR2 COUNT RATE is 104 cps and stable. | |||
* TSLB-3 1-1, SR HI Q NC-31D is lit. | * TSLB-3 1-1, SR HI Q NC-31D is lit. | ||
* TSLB-3 1-2, SR HI Q NC-32D is NOT lit. | * TSLB-3 1-2, SR HI Q NC-32D is NOT lit. | ||
* GA1, SR HI FLUX TRIP, is in alarm. | * GA1, SR HI FLUX TRIP, is in alarm. | ||
* The Reactor Trip breakers are closed.Subsequently, The Shift Supervisor directs a manual Reactor trip. | * The Reactor Trip breakers are closed. | ||
* The | Subsequently, The Shift Supervisor directs a manual Reactor trip. | ||
* The Reactor Trip breakers open. | |||
Which one of the following completes the statements below? | |||
: 22. G2.4.35 097 Unit 1 is performing the actions of EEP-0.0, Reactor Trip or Safety Injection, and AOP-9, Loss of Component Cooling | An emergency classification threshold value (1) been exceeded per NMP-EP-110-GL01, FNP EALS - ICs, Threshold Values And Basis. | ||
The latest time the NRC can be notified is (2) hour(s) after the event / emergency declaration. | |||
(1) (2) | |||
A. has NOT 4 B. HAS 4 C. has NOT 1 D. HAS 1 Tuesday, June 30, 2015 2:03:50 PM 21 | |||
QUESTIONS REPORT for ILT 38 SRO Ver 5 | |||
: 22. G2.4.35 097 Unit 1 is performing the actions of EEP-0.0, Reactor Trip or Safety Injection, and AOP-9, Loss of Component Cooling Water. Conditions are as follows: | |||
* 1F 4160V bus is de-energized. | * 1F 4160V bus is de-energized. | ||
* B Train CCW is the | * B Train CCW is the on service Train. | ||
* 1B CCW pump is Tagged Out. | * 1B CCW pump is Tagged Out. | ||
* 1A CCW pump tripped. | * 1A CCW pump tripped. | ||
* 1C CHG PUMP is running. | * 1C CHG PUMP is running. | ||
Subseqently, the Shift | Subseqently, the Shift Supervisor determines that Firewater is required to be aligned to the 1B Charging pump. | ||
Which one of the following actions are required by AOP-9.0 for these conditions, and the effect during the alignment of firewater to the 1B charging pump? | |||
A. | |||
* Secure 1C CHG pump. | * Secure 1C CHG pump. | ||
* An evaluation must be | * RCP number 1 seal outlet temperature may rise to greater than 235°F. | ||
B. | |||
* Secure 1C CHG pump. | |||
* An evaluation must be performed prior to reinitiating Seal Injection or CCW to the thermal barriers. | |||
C. | |||
* Maintain 1C CHG pump running. | * Maintain 1C CHG pump running. | ||
* 1C CHG pump may be damaged. | * 1C CHG pump may be damaged. | ||
D. | |||
* Maintain 1C CHG pump running. | * Maintain 1C CHG pump running. | ||
* 1C CHG pump CCW oil cooler piping will be chemically contaminated. | * 1C CHG pump CCW oil cooler piping will be chemically contaminated. | ||
Tuesday, June 30, 2015 2:03:50 PM 22 | |||
QUESTIONS REPORT for ILT 38 SRO Ver 5 | |||
: 23. WE04EG2.1.2 098 Unit 1 operating crew has exited EEP-0.0, Reactor Trip or Safety Injection, and is now performing ECP-1.2, LOCA Outside Containment with the following conditions: | : 23. WE04EG2.1.2 098 Unit 1 operating crew has exited EEP-0.0, Reactor Trip or Safety Injection, and is now performing ECP-1.2, LOCA Outside Containment with the following conditions: | ||
* The leak isolation steps are completed. | * The leak isolation steps are completed. | ||
* RWST level is 12.5 ft. | * RWST level is 12.5 ft. | ||
* RCS pressure continues to lower. | * RCS pressure continues to lower. | ||
Which one of the following | Which one of the following completes the statement below? | ||
The next procedure the operating crew is required to transition to is . | |||
A. EEP-0.0, Reactor Trip or Safety Injection B. ESP-1.3, Transfer to Cold Leg Recirculation C. EEP-1.0, Loss of Reactor or Secondary Coolant D. ECP-1.1, Loss of Emergency Coolant Recirculation Tuesday, June 30, 2015 2:03:50 PM 23 | |||
QUESTIONS REPORT for ILT 38 SRO Ver 5 | |||
: 24. WE05EA2.1 099 Unit 2 is performing the | : 24. WE05EA2.1 099 Unit 2 is performing the actions of FRP-H.1, Response to Loss of Secondary Heat Sink, and the following conditions exist: | ||
* The TDAFW pump has been returned to service. | * The TDAFW pump has been returned to service. | ||
* Containment pressure is 0 psig. | * Containment pressure is 0 psig. | ||
* RCS Bleed and Feed was | * RCS Bleed and Feed was initiated, but has now been secured. | ||
* RCS pressure is 1600 psig and rising. | * RCS pressure is 1600 psig and rising. | ||
* Pressurizer level is 23% and rising. | * Pressurizer level is 23% and rising. | ||
Which one of the following | Which one of the following completes the statements below? | ||
(2) ESP-1.1, SI Termination(1) Wide Range level at 14% | The minimum SG level that permitted securing Bleed and Feed was at least one SG (1) . | ||
(2) EEP-1, Loss of Reactor or Secondary Coolant (1) Narrow Range level at 33% | The operating crew will transition to (2) from FRP-H.1. | ||
(2) ESP-1.1, SI Termination (1) | A. (1) Wide Range level at 14% | ||
(2) EEP-1, Loss of Reactor or Secondary Coolant | (2) ESP-1.1, SI Termination B. (1) Wide Range level at 14% | ||
: 25. WE10EA2.2 100 Unit 1 is cooling down per ESP-0.2, | (2) EEP-1, Loss of Reactor or Secondary Coolant C. (1) Narrow Range level at 33% | ||
(2) ESP-1.1, SI Termination D. (1) Narrow Range level at 33% | |||
(2) EEP-1, Loss of Reactor or Secondary Coolant Tuesday, June 30, 2015 2:03:50 PM 24 | |||
QUESTIONS REPORT for ILT 38 SRO Ver 5 | |||
: 25. WE10EA2.2 100 Unit 1 is cooling down per ESP-0.2, Natural Circulation Cooldown to Prevent Reactor Vessel Head Steam Voiding, and the following conditions exist: | |||
* RVLIS is not available. | * RVLIS is not available. | ||
* RCS Hot leg is 450°F and slowly lowering. | * RCS Hot leg is 450°F and slowly lowering. | ||
* RCS Cold leg is 425°F and slowly lowering. | * RCS Cold leg is 425°F and slowly lowering. | ||
* The crew is cooling down at | * The crew is cooling down at the maximum rate allowed by procedure. | ||
* Pressurizer level has just | * Pressurizer level has just rapidly risen to 78% and is stable | ||
* RCS pressure reduction is not required. | * RCS pressure reduction is not required. | ||
* CST level is 9ft. | * CST level is 9ft. | ||
Which one of the following | Which one of the following completes the statements below? | ||
The operating crew will transition to ESP-0.4, | The operating crew will transition to ESP-0.4, Natural Circulation Cooldown with Allowance for Reactor Vessel Head Steam Voiding (Without RVLIS), based on (1) . | ||
The maximum allowable cooldown rate in ESP-0.4 is (2) . | |||
Reference Provided A. (1) CST Level (2) <100°F in any 60 minute period B. (1) CST Level (2) <50°F/hr C. (1) Reactor Vessel void formation being indicated (2) <100°F in any 60 minute period D. (1) Reactor Vessel void formation being indicated (2) <50°F/hr Tuesday, June 30, 2015 2:03:50 PM 25 | |||
U. S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name: Date: Facility / Unit Region: | ES-401 Site-Specific SRO Written Examination Form ES-401-8 Cover Sheet U. S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name: | ||
Date: 20 OCT 2015 Facility / Unit FARLEY 1 & 2 Region: I II X III IV Reactor Type: W X CE BW GE Start Time: Finish Time: | |||
Instructions 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 percent overall, with 70 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80 percent to pass. You have 8 hours to complete the combined examination, and 3 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 75 / ______ | |||
______ 25 / ______ | |||
100 Points Applicant's Score ______ / ______ / ______ | |||
Points Applicant's Grade ______ / ______ / ______ | |||
Percent ES-401, Page 38 of 50 | |||
QUESTIONS REPORT for ILT 38 SRO Ver 5 | |||
: 1. 003AG2.1.23 076 Unit 1 was operating at 100% power when the following occurred: | : 1. 003AG2.1.23 076 Unit 1 was operating at 100% power when the following occurred: | ||
At 1000: | At 1000: | ||
* All Control Banks are at 231 steps. | * All Control Banks are at 231 steps. | ||
At 1010:* Rod K4 fell to 130 steps.* Rod M6 fell to 150 steps. | At 1010: | ||
* Rod K4 fell to 130 steps. | |||
* Rod M6 fell to 150 steps. | |||
* RCS Tavg lowered. | * RCS Tavg lowered. | ||
* Pressurizer pressure lowered. | * Pressurizer pressure lowered. | ||
Which one of the following | Which one of the following completes the statement below? | ||
Per AOP-19, Malfunction of Rod Control System, the operating crew is required to | Per AOP-19, Malfunction of Rod Control System, the operating crew is required to . | ||
A. shutdown the unit using UOP-3.1, Power Operation B. trip the Reactor and go to EEP-0.0, Reactor Trip and Safety Injection C. reduce power to less than 75% within 1 hour using UOP-3.1, Power Operation D. address restoration of rods using SOP-41.0, Control Rod Drive and Position Indication System Tuesday, June 30, 2015 2:03:49 PM 1 | |||
QUESTIONS REPORT for ILT 38 SRO Ver 5 | |||
QUESTIONS | |||
: 2. 003G2.4.45 077 Unit 1 is operating at 100% power when the following occurs: | : 2. 003G2.4.45 077 Unit 1 is operating at 100% power when the following occurs: | ||
At 1000: | At 1000: | ||
* HH4, RCP VIB TRBL (WHITE | * HH4, RCP VIB TRBL (WHITE annunciator window), comes into alarm. | ||
* 1A RCP shaft vibration is reported as 21 mils and stable. | * 1A RCP shaft vibration is reported as 21 mils and stable. | ||
* DC2, RCP #1 SEAL LKOF FLOW HI (YELLOW annunciator window), | * DC2, RCP #1 SEAL LKOF FLOW HI (YELLOW annunciator window), | ||
* FR145A, | comes into alarm. | ||
* FR145A, RCP SEAL LKOF HIGH RANGE, for the 1A RCP indicates 6.5 gpm and stable. | |||
At 1600: | At 1600: | ||
* The Unit is in MODE 3. | * The Unit is in MODE 3. | ||
Line 320: | Line 378: | ||
* 1B and 1C RCPs are running. | * 1B and 1C RCPs are running. | ||
* 1A RCP is tagged out. | * 1A RCP is tagged out. | ||
Which one of the following | Which one of the following completes the statements below? | ||
At 1000 , the operating crew is required to (1) | At 1000, the operating crew is required to (1) , then secure the 1A RCP. | ||
At 1600 , RCS pressure control is via (2) | At 1600, RCS pressure control is via (2) . | ||
QUESTIONS | A. (1) trip the Reactor and go to EEP-0.0, Reactor Trip or Safety Injection (2) Normal Spray B. (1) perform a controlled shutdown per the appropriate Unit Operating Procedures (2) Normal Spray C. (1) trip the Reactor and go to EEP-0.0, Reactor Trip or Safety Injection (2) Auxiliary Spray D. (1) perform a controlled shutdown per the appropriate Unit Operating Procedures (2) Auxiliary Spray Tuesday, June 30, 2015 2:03:49 PM 2 | ||
: 3. 007A2.03 078 Unit 1 is operating at 100% | |||
power when the following occurs: | QUESTIONS REPORT for ILT 38 SRO Ver 5 | ||
* Due to a Pressurizer pressure | : 3. 007A2.03 078 Unit 1 is operating at 100% power when the following occurs: | ||
* Due to a Pressurizer pressure control malfunction, PCV-445A, PRZR PORV opens and reseats several times. | |||
* PRT level rises to 84% and is stable. | * PRT level rises to 84% and is stable. | ||
Which one of the following | Which one of the following completes the statements below? | ||
HE4, PRT LVL HI-LO, | HE4, PRT LVL HI-LO, (1) in alarm. | ||
The procedure used to lower PRT level is (2) | The procedure used to lower PRT level is (2) . | ||
A. (1) is NOT (2) SOP-1.2, Reactor Coolant Pressure Relief System B. (1) IS (2) SOP-1.2, Reactor Coolant Pressure Relief System C. (1) is NOT (2) SOP-50.0, Liquid Waste Processing System D. (1) IS (2) SOP-50.0, Liquid Waste Processing System Tuesday, June 30, 2015 2:03:49 PM 3 | |||
QUESTIONS REPORT for ILT 38 SRO Ver 5 | |||
: 4. 007EA2.03 079 Unit 1 is in MODE 3 with the following conditions: | : 4. 007EA2.03 079 Unit 1 is in MODE 3 with the following conditions: | ||
At 1000: | At 1000: | ||
Line 338: | Line 398: | ||
At 1005: | At 1005: | ||
* A complete loss of offsite power occurs. | * A complete loss of offsite power occurs. | ||
Which one of the following | Which one of the following completes the statements below? | ||
At 1005, manual action (1) | At 1005, manual action (1) required to generate a P-4 signal. | ||
Per the BASES of Tech Spec 3.3.2, ESFAS | Per the BASES of Tech Spec 3.3.2, ESFAS Instrumentation, P-4 is required to be OPERABLE to prevent (2) . | ||
A. (1) IS (2) excessive Containment pressure due to a steamline break B. (1) is NOT (2) excessive Containment pressure due to a steamline break C. (1) IS (2) damage to the Main Steam lines and SG safeties due to SG overfill D. (1) is NOT (2) damage to the Main Steam lines and SG safeties due to SG overfill Tuesday, June 30, 2015 2:03:49 PM 4 | |||
QUESTIONS REPORT for ILT 38 SRO Ver 5 | |||
: 5. 010G2.2.44 080 Unit 1 is operating at 100% | : 5. 010G2.2.44 080 Unit 1 is operating at 100% power with the following conditions: | ||
* PRT pressure, level and temperature are stable.* HA4, PRZR SAFETY VLV TEMP HI, is in alarm.* HA5, PRZR PORV TEMP HI, is in alarm. | * A malfunction occurred resulting in PCV-444B, PRZR PORV, opening. | ||
Subsequently, the immediate operator actions of AOP-100, Instrumentation Malfunction, were performed and the following conditions exist: | |||
* PCV-444B GREEN light is LIT. | |||
* MOV-8000B, PRZR PORV ISO, RED light is LIT. | |||
* RCS pressure is 2180 psig and stable. | |||
* PRT pressure, level and temperature are stable. | |||
* HA4, PRZR SAFETY VLV TEMP HI, is in alarm. | |||
* HA5, PRZR PORV TEMP HI, is in alarm. | |||
* HD1, PRZR PRESS REL VLV 445A OR B/U HTRS ON, is in alarm. | * HD1, PRZR PRESS REL VLV 445A OR B/U HTRS ON, is in alarm. | ||
Which one of the following | Which one of the following completes the statements below? | ||
PCV-444B | PCV-444B (1) leaking by. | ||
Per Tech Spec 3.4.11, Pressurizer Power Operated Relief Valves (PORVs), PCV-444B (2) | Per Tech Spec 3.4.11, Pressurizer Power Operated Relief Valves (PORVs), PCV-444B (2) OPERABLE. | ||
(1) (2) | |||
A. IS IS B. IS is NOT C. is NOT IS D. is NOT is NOT Tuesday, June 30, 2015 2:03:49 PM 5 | |||
QUESTIONS | |||
QUESTIONS REPORT for ILT 38 SRO Ver 5 | |||
: 6. 026A2.03 081 Unit 1 is at 100% power with the following conditions: | : 6. 026A2.03 081 Unit 1 is at 100% power with the following conditions: | ||
* PT-950, CTMT PRESS (Channel 1), was | * PT-950, CTMT PRESS (Channel 1), was declared INOPERABLE. | ||
* PT-950 bistables were positioned as required by Tech Spec 3.3.2, | * PT-950 bistables were positioned as required by Tech Spec 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, for continuous operation with an inoperable channel. | ||
Which one of the following | Which one of the following completes the statements below? | ||
Per Tech Spec 3.3.2, the | The Safety Injection function (1) affected by the PT-950 malfunction. | ||
Per Tech Spec 3.3.2, the REQUIRED ACTION is to place the PT-950 bistables in (2) . | |||
QUESTIONS | (1) (2) | ||
A. IS TRIP B. IS BYPASS C. is NOT TRIP D. is NOT BYPASS Tuesday, June 30, 2015 2:03:49 PM 6 | |||
QUESTIONS REPORT for ILT 38 SRO Ver 5 | |||
: 7. 026AA2.03 082 Unit 1 is in MODE 3 with the following conditions: | : 7. 026AA2.03 082 Unit 1 is in MODE 3 with the following conditions: | ||
* All RCPs are running. | * All RCPs are running. | ||
* A CCW leak occurs on the 1A RCP Oil Cooler inlet connection. | * A CCW leak occurs on the 1A RCP Oil Cooler inlet connection. | ||
Which one of the following | Which one of the following completes the statements below? | ||
The method used in the Main Control Room (MCR) to isolate the CCW leak is to (1) | The method used in the Main Control Room (MCR) to isolate the CCW leak is to (1) . | ||
QUESTIONS | Per the BASES of Tech Spec 3.7.7 - CCW System, once the CCW leak is isolated from the MCR, the CCW System is (2) . | ||
: 8. 028A2.02 083 Unit 1 has experienced a LOCA. | A. (1) isolate CCW to ALL RCPs (2) INOPERABLE B. (1) isolate CCW to the 1A RCP ONLY (2) INOPERABLE C. (1) isolate CCW to ALL RCPs (2) OPERABLE D. (1) isolate CCW to the 1A RCP ONLY (2) OPERABLE Tuesday, June 30, 2015 2:03:49 PM 7 | ||
The following conditions exist: | |||
QUESTIONS REPORT for ILT 38 SRO Ver 5 | |||
: 8. 028A2.02 083 Unit 1 has experienced a LOCA. The following conditions exist: | |||
* EEP-1.0, Loss of Reactor or Secondary Coolant, is in progress. | * EEP-1.0, Loss of Reactor or Secondary Coolant, is in progress. | ||
* Containment Hydrogen is 6% | * Containment Hydrogen is 6% by volume of dry air. | ||
by volume of dry air. | Which one of the following completes the statements below? | ||
Which one of the following | The hydrogen concentration (1) exceed the lower FLAMMABILITY limit. | ||
The hydrogen concentration (1) | Hydrogen concentration will be lowered using (2) . | ||
A. (1) DOES (2) SOP-10.0, POST LOCA Containment Pressurization and Vent System B. (1) DOES (2) Attachment 3 of EEP-1.0, Post LOCA Hydrogen Recombiner Operation C. (1) does NOT (2) SOP-10.0, POST LOCA Containment Pressurization and Vent System D. (1) does NOT (2) Attachment 3 of EEP-1.0, Post LOCA Hydrogen Recombiner Operation Tuesday, June 30, 2015 2:03:49 PM 8 | |||
QUESTIONS REPORT for ILT 38 SRO Ver 5 | |||
: 9. 028AG2.1.25 084 Unit 1 is operating at 100% | : 9. 028AG2.1.25 084 Unit 1 is operating at 100% when a Pressurizer level control malfunction occurs and the following conditions exist: | ||
when a Pressurizer level | |||
* Pressurizer level is 70% and rising. | * Pressurizer level is 70% and rising. | ||
* Charging flow is 120 gpm. | * Charging flow is 120 gpm. | ||
Line 381: | Line 455: | ||
* RCP seal injection is 8 gpm to each RCP. | * RCP seal injection is 8 gpm to each RCP. | ||
* RCP seal leakoff is 3 gpm per pump. | * RCP seal leakoff is 3 gpm per pump. | ||
* Actions in the field are being taken to regain | * Actions in the field are being taken to regain control of Charging. | ||
* It will take 8 minutes to regain control of Charging. | * It will take 8 minutes to regain control of Charging. | ||
Which one of the following | Which one of the following completes the statements below? | ||
An | An automatic reactor trip (1) occur before control of Charging is regained. | ||
Per the BASES of Tech Spec 3.3. | Per the BASES of Tech Spec 3.3.1, Reactor Trip System (RTS) | ||
1, Reactor Trip System (RTS) | Instrumentation, the purpose of the automatic Reactor Trip on Pressurizer Water Level - High is to (2) . | ||
Instrumentation, the purpose of the | Reference Provided A. (1) WILL (2) provide protection against water relief through the PORV's B. (1) WILL (2) prevent thermal shock of the Spray Nozzle C. (1) will NOT (2) provide protection against water relief through the PORV's D. (1) will NOT (2) prevent thermal shock of the Spray Nozzle Tuesday, June 30, 2015 2:03:49 PM 9 | ||
QUESTIONS REPORT for ILT 38 SRO Ver 5 | |||
: 10. 034G2.4.30 085 Unit 1 is conducting a fuel reload and the following conditions occur: | : 10. 034G2.4.30 085 Unit 1 is conducting a fuel reload and the following conditions occur: | ||
At 1000: | At 1000: | ||
Line 395: | Line 469: | ||
* A loss of power to the fuel transfer system occurs. | * A loss of power to the fuel transfer system occurs. | ||
At 1015: | At 1015: | ||
* It is determined that an Intermediate Leg leak is in progress on | * It is determined that an Intermediate Leg leak is in progress on the 1A RCS loop. | ||
* R-2, CTMT 155 FT, is in alarm. | * R-2, CTMT 155 FT, is in alarm. | ||
* EH2, SFP LVL HI-LO is in alarm. | * EH2, SFP LVL HI-LO is in alarm. | ||
* Both RHR pumps have been secured due to cavitation. | * Both RHR pumps have been secured due to cavitation. | ||
Which one of the following | Which one of the following completes the statements below? | ||
At 1030 , an emergency classification , per NMP-EP-110, Emergency Classification | At 1030, an emergency classification, per NMP-EP-110, Emergency Classification Determination and Initial Action, (1) required. | ||
If the RCS leak is not isolated, the spent fuel assembly in the upender (2) | If the RCS leak is not isolated, the spent fuel assembly in the upender (2) remain covered with water. | ||
(1) (2) | |||
A. IS will NOT B. IS WILL C. is NOT will NOT D. is NOT WILL Tuesday, June 30, 2015 2:03:49 PM 10 | |||
QUESTIONS REPORT for ILT 38 SRO Ver 5 | |||
: 11. 036AA2.02 086 A fuel shuffle is in progress in the Unit 1 SFP with the following conditions: | : 11. 036AA2.02 086 A fuel shuffle is in progress in the Unit 1 SFP with the following conditions: | ||
* An 1800 lb. load is | * An 1800 lb. load is being moved over spent fuel. | ||
Subsequently, the following occurs: | Subsequently, the following occurs: | ||
* The load is dropped causing damage to the spent fuel. | * The load is dropped causing damage to the spent fuel. | ||
* R-5, SFP ROOM, comes into alarm. | * R-5, SFP ROOM, comes into alarm. | ||
Which one of the following | Which one of the following completes the statements below? | ||
AOP-30, Refueling Accident, | AOP-30, Refueling Accident, (1) required to be entered. | ||
Per the Bases of TR 13.9.4, | Per the Bases of TR 13.9.4, Crane Travel-Spent Fuel Storage Building, the expected worst case consequences of dropping an 1800 lb. load onto the spent fuel is that the (2) . | ||
A. (1) IS (2) activity release will be limited to that contained in a single fuel assembly B. (1) IS (2) offsite dose may be as high as but not more than the 10 CFR 100 limit C. (1) is NOT (2) activity release will be limited to that contained in a single fuel assembly D. (1) is NOT (2) offsite dose may be as high as but not more than the 10 CFR 100 limit Tuesday, June 30, 2015 2:03:49 PM 11 | |||
QUESTIONS REPORT for ILT 38 SRO Ver 5 | |||
: 12. 056AG2.2.44 087 Unit 1 was operating at 100% power with the following conditions: | : 12. 056AG2.2.44 087 Unit 1 was operating at 100% power with the following conditions: | ||
At 1000: | At 1000: A complete loss of Offsite Power occurred. | ||
At 1015: A spurious Safety Injection | At 1015: A spurious Safety Injection occurs and the following indications exist: | ||
* On the Main Control Board: | * On the Main Control Board: | ||
- 1D SW PUMP Handswitch - GREEN and YELLOW lights LIT | |||
- 1E SW PUMP Handswitch - GREEN and YELLOW lights LIT | |||
* On the EPB: | * On the EPB: | ||
- BIG SEQUENCER LIGHTS: | |||
- BKR NOT CLOSED STEP 3 - LIT | |||
- BKR NOT CLOSED STEP 4 - LIT | |||
- ESS SEQ INCOMPLETE - LIT | |||
- LOSP MAN LOADING START - LIT At 1017: The UO takes the 1D and 1E SW pump handswitches to START and the following occurs: | |||
* 1D SW PUMP Handswitch - RED light LIT | * 1D SW PUMP Handswitch - RED light LIT | ||
* 1E SW PUMP | * 1E SW PUMP Handswitch - RED light LIT | ||
* PI 3001B, SW TO CCW HX HDR PRESS, rises to 100 psig. | * PI 3001B, SW TO CCW HX HDR PRESS, rises to 100 psig. | ||
Which one of the following | Which one of the following completes the statements below? | ||
At 1015: The 1B DG (1) | At 1015: The 1B DG (1) have cooling water supplied. | ||
At 1017: | At 1017: In addition to CONDITION C of Tech Spec 3.8.1, AC Sources - Operating, CONDITON(S) (2) is(are) required to be entered. | ||
Reference Provided (1) (2) | |||
A. WILL B&G B. WILL G ONLY C. will NOT B&G D. will NOT G ONLY Tuesday, June 30, 2015 2:03:49 PM 12 | |||
: 13. 065AG2.4.22 088 Unit 1 is operating at 100% | |||
* A rupture has occurred on the | QUESTIONS REPORT for ILT 38 SRO Ver 5 | ||
: 13. 065AG2.4.22 088 Unit 1 is operating at 100% power with the following conditions: | |||
* A rupture has occurred on the Instrument Air header piping in the MSVR. | |||
* A Reactor Trip has occurred. | * A Reactor Trip has occurred. | ||
* AOP-6.0, Loss of | * AOP-6.0, Loss of Instrument Air, is in progress. | ||
Which one of the following | Which one of the following completes the statements below? | ||
Procedure Names | After the Reactor Trip, Pressurizer level will (1) due to the loss of Instrument Air. | ||
: AOP-16.0, CVCS Malfunction | Per AOP-6.0, to maintain Pressurizer level, the operating crew is required to perform actions of (2) in conjunction with AOP-6.0. | ||
Procedure Names: AOP-16.0, CVCS Malfunction SOP-2.1, CVCS Plant Startup and Operation (1) (2) | |||
: 14. 072A2.03 089 Unit 1 is operating at 100% | A. lower AOP-16.0 B. rise AOP-16.0 C. lower SOP-2.1 D. rise SOP-2.1 Tuesday, June 30, 2015 2:03:49 PM 13 | ||
power when the following occurs: | |||
QUESTIONS REPORT for ILT 38 SRO Ver 5 | |||
: 14. 072A2.03 089 Unit 1 is operating at 100% power when the following occurs: | |||
* R-27B, CTMT HIGH RANGE, is tagged out. | * R-27B, CTMT HIGH RANGE, is tagged out. | ||
* The instrument power supply fuse to R-27A, CTMT HIGH RANGE, blows. | * The instrument power supply fuse to R-27A, CTMT HIGH RANGE, blows. | ||
Which one of the following | Which one of the following completes the statements below? | ||
The loss of R-27A (1) | The loss of R-27A (1) affect the ability to evaluate the loss of Fuel Clad Barrier per NMP-EP-110-GL01, FNP EALs - ICs, Threshold Values and Basis. | ||
Per Tech Spec 3.3.3, Post | Per Tech Spec 3.3.3, Post Accident Monitoring Instrumentation, the REQUIRED ACTION is to (2) . | ||
Reference Provided A. (1) will NOT (2) immediately initiate action in accordance with Specification 5.6.8 B. (1) will NOT (2) restore R-27A OR R-27B to OPERABLE status in 7 days C. (1) WILL (2) immediately initiate action in accordance with Specification 5.6.8 D. (1) WILL (2) restore R-27A OR R-27B to OPERABLE status in 7 days Tuesday, June 30, 2015 2:03:50 PM 14 | |||
QUESTIONS REPORT for ILT 38 SRO Ver 5 | |||
: 15. 073A2.01 090 Unit 1 is operating at 100% | : 15. 073A2.01 090 Unit 1 is operating at 100% power and the following occurs: | ||
power and the following occurs: | * R-15A, SJAE EXH, power supply becomes erratic causing its indication to become unreliable but it does not alarm. | ||
* R-15A, SJAE EXH, power supply | Per the ODCM, which one of the following actions are required to continue the release via this pathway, if any? | ||
No actions are required. | A. No actions are required. | ||
Continuously collect samples using auxiliary equipment. | B. Continuously collect samples using auxiliary equipment. | ||
Place SJAE filtration in service until R-15A is restored to operable. | C. Place SJAE filtration in service until R-15A is restored to operable. | ||
Perform grab samples at least once per 8 hours and analyze them within 24 hours. | D. Perform grab samples at least once per 8 hours and analyze them within 24 hours. | ||
Tuesday, June 30, 2015 2:03:50 PM 15 | |||
QUESTIONS REPORT for ILT 38 SRO Ver 5 | |||
: 16. G2.1.41 091 Unit 1 is in MODE 6 with the following conditions: | : 16. G2.1.41 091 Unit 1 is in MODE 6 with the following conditions: | ||
* Core reload is complete. | * Core reload is complete. | ||
* Control Rod Drive Shaft Latching and RCCA Drag Testing is about to begin per | * Control Rod Drive Shaft Latching and RCCA Drag Testing is about to begin per FHP-5.1, Control Rod Drive Shaft Latching/Unlatching Tool Operating Instruction. | ||
Per FHP-1.0, Refueling | Per FHP-1.0, Refueling Operations, which one of the following requirements must be met prior to latching control rods? | ||
The Maintenance Supervisor is in Containment. | A. The Maintenance Supervisor is in Containment. | ||
The Fuel Handling | B. The Fuel Handling Supervisor is in Containment. | ||
The Maintenance Supervisor is in the Control Room | C. The Maintenance Supervisor is in the Control Room and in direct communication with Containment. | ||
The Fuel Handling Supervisor is in the Control Room and in direct communication with Containment. | D. The Fuel Handling Supervisor is in the Control Room and in direct communication with Containment. | ||
Tuesday, June 30, 2015 2:03:50 PM 16 | |||
: 17. G2.2.13 092 A tagout is required to be cleared during | |||
Per NMP-AD-003, Equipment Clearance and Tagging, which one of the following can sign off | QUESTIONS REPORT for ILT 38 SRO Ver 5 | ||
Shift Manager Operations Director Maintenance Director Maintenance Manager | : 17. G2.2.13 092 A tagout is required to be cleared during night shift and the Work Document Holder is not on site and cannot be contacted to gain their approval. | ||
: 18. G2.2.40 093 Unit 1 is at 6% power | Per NMP-AD-003, Equipment Clearance and Tagging, which one of the following can sign off the Work Document Holder? | ||
A. Shift Manager B. Operations Director C. Maintenance Director D. Maintenance Manager Tuesday, June 30, 2015 2:03:50 PM 17 | |||
QUESTIONS REPORT for ILT 38 SRO Ver 5 | |||
: 18. G2.2.40 093 Unit 1 is at 6% power with the following conditions: | |||
* The 1A SGFP has been started. | * The 1A SGFP has been started. | ||
* AFW is secured. | * AFW is secured. | ||
* The Main Feed Regulating Valves are closed. | * The Main Feed Regulating Valves are closed. | ||
At 1000 on January 1, 2015: | At 1000 on January 1, 2015: | ||
* MOV-3232B, MAIN FW TO 1B SG | * MOV-3232B, MAIN FW TO 1B SG STOP VLV , is declared INOPERABLE. | ||
At 1200 on January 1, 2015 | At 1200 on January 1, 2015: | ||
: | |||
* FCV-489, 1B SG FW BYP FLOW, is declared INOPERABLE. | * FCV-489, 1B SG FW BYP FLOW, is declared INOPERABLE. | ||
Subsequently it is determined that | Subsequently it is determined that repairs will take 96 hours for each valve. | ||
Which one of the following | Which one of the following completes the statement below? | ||
Per Tech Spec 3.7.3, Main Feedwater | Per Tech Spec 3.7.3, Main Feedwater Stop Valves and Main Feedwater Regulation Valves (MFRVs) and Associated Bypass Valves, the earliest time that feed flow to the 1B SG must be isolated is . | ||
Reference Provided A. 1800 on January 1, 2015 B. 2000 on January 1, 2015 C. 1000 on January 4, 2015 D. 1200 on January 4, 2015 Tuesday, June 30, 2015 2:03:50 PM 18 | |||
QUESTIONS REPORT for ILT 38 SRO Ver 5 | |||
: 19. G2.3.12 094 A General Emergency on | : 19. G2.3.12 094 A General Emergency on Unit 1 has been declared with following conditions: | ||
* An Emergency Response Team is required to be dispatched to isolate an | * An Emergency Response Team is required to be dispatched to isolate an offsite release source. | ||
* The TSC has not yet been manned. | * The TSC has not yet been manned. | ||
* The expected exposure for the job is 35 REM TEDE per person. | * The expected exposure for the job is 35 REM TEDE per person. | ||
Which one of the following | Which one of the following completes the statements below? | ||
To receive the dose listed above, operators (1) | To receive the dose listed above, operators (1) required to be volunteers. | ||
The (2) will authorize the exposure. | |||
(1) (2) | |||
A. are NOT RP Supervisor B. are NOT Shift Manager C. ARE RP Supervisor D. ARE Shift Manager Tuesday, June 30, 2015 2:03:50 PM 19 | |||
20 QUESTIONS | QUESTIONS REPORT for ILT 38 SRO Ver 5 | ||
: 21. G2.4.30 096 Unit 2 reactor startup is in | : 20. G2.3.14 095 Unit 1 is in MODE 6 with core offload in progress with the following condition: | ||
* NI31, SR1 COUNT RATE is | * A spent fuel assembly is being moved from its assigned location in the core to the upender. | ||
* NI32, SR2 COUNT RATE is | Subsequently, AOP-30.0, Refueling Accident, is entered Which one of the following completes the statements below? | ||
Per AOP-30.0, the Refueling SRO will direct the fuel assembly to be (1) . | |||
Per the BASES of Tech Spec 3.9.6, Refueling Cavity Water Level, 23 ft of water is required to be maintained above the fuel to (2) . | |||
A. (1) placed in any empty fuel location in the core (2) provide back up decay heat removal B. (1) placed in any empty fuel location in the core (2) retain iodine fission product activity in the water during a fuel handling accident C. (1) returned to its assigned location in the core (2) provide back up decay heat removal D. (1) returned to its assigned location in the core (2) retain iodine fission product activity in the water during a fuel handling accident Tuesday, June 30, 2015 2:03:50 PM 20 | |||
QUESTIONS REPORT for ILT 38 SRO Ver 5 | |||
: 21. G2.4.30 096 Unit 2 reactor startup is in progress and the following conditions exist: | |||
* NI31, SR1 COUNT RATE is 106 cps and stable. | |||
* NI32, SR2 COUNT RATE is 104 cps and stable. | |||
* TSLB-3 1-1, SR HI Q NC-31D is lit. | * TSLB-3 1-1, SR HI Q NC-31D is lit. | ||
* TSLB-3 1-2, SR HI Q NC-32D is NOT lit. | * TSLB-3 1-2, SR HI Q NC-32D is NOT lit. | ||
* GA1, SR HI FLUX TRIP, is in alarm. | * GA1, SR HI FLUX TRIP, is in alarm. | ||
* The Reactor Trip breakers are closed.Subsequently, The Shift Supervisor directs a manual Reactor trip. | * The Reactor Trip breakers are closed. | ||
* The | Subsequently, The Shift Supervisor directs a manual Reactor trip. | ||
* The Reactor Trip breakers open. | |||
Which one of the following completes the statements below? | |||
: 22. G2.4.35 097 Unit 1 is performing the actions of EEP-0.0, Reactor Trip or Safety Injection, and AOP-9, Loss of Component Cooling | An emergency classification threshold value (1) been exceeded per NMP-EP-110-GL01, FNP EALS - ICs, Threshold Values And Basis. | ||
The latest time the NRC can be notified is (2) hour(s) after the event / emergency declaration. | |||
(1) (2) | |||
A. has NOT 4 B. HAS 4 C. has NOT 1 D. HAS 1 Tuesday, June 30, 2015 2:03:50 PM 21 | |||
QUESTIONS REPORT for ILT 38 SRO Ver 5 | |||
: 22. G2.4.35 097 Unit 1 is performing the actions of EEP-0.0, Reactor Trip or Safety Injection, and AOP-9, Loss of Component Cooling Water. Conditions are as follows: | |||
* 1F 4160V bus is de-energized. | * 1F 4160V bus is de-energized. | ||
* B Train CCW is the | * B Train CCW is the on service Train. | ||
* 1B CCW pump is Tagged Out. | * 1B CCW pump is Tagged Out. | ||
* 1A CCW pump tripped. | * 1A CCW pump tripped. | ||
* 1C CHG PUMP is running. | * 1C CHG PUMP is running. | ||
Subseqently, the Shift | Subseqently, the Shift Supervisor determines that Firewater is required to be aligned to the 1B Charging pump. | ||
Which one of the following actions are required by AOP-9.0 for these conditions, and the effect during the alignment of firewater to the 1B charging pump? | |||
A. | |||
* Secure 1C CHG pump. | * Secure 1C CHG pump. | ||
* An evaluation must be | * RCP number 1 seal outlet temperature may rise to greater than 235°F. | ||
B. | |||
* Secure 1C CHG pump. | |||
* An evaluation must be performed prior to reinitiating Seal Injection or CCW to the thermal barriers. | |||
C. | |||
* Maintain 1C CHG pump running. | * Maintain 1C CHG pump running. | ||
* 1C CHG pump may be damaged. | * 1C CHG pump may be damaged. | ||
D. | |||
* Maintain 1C CHG pump running. | * Maintain 1C CHG pump running. | ||
* 1C CHG pump CCW oil cooler piping will be chemically contaminated. | * 1C CHG pump CCW oil cooler piping will be chemically contaminated. | ||
Tuesday, June 30, 2015 2:03:50 PM 22 | |||
QUESTIONS REPORT for ILT 38 SRO Ver 5 | |||
: 23. WE04EG2.1.2 098 Unit 1 operating crew has exited EEP-0.0, Reactor Trip or Safety Injection, and is now performing ECP-1.2, LOCA Outside Containment with the following conditions: | : 23. WE04EG2.1.2 098 Unit 1 operating crew has exited EEP-0.0, Reactor Trip or Safety Injection, and is now performing ECP-1.2, LOCA Outside Containment with the following conditions: | ||
* The leak isolation steps are completed. | * The leak isolation steps are completed. | ||
* RWST level is 12.5 ft. | * RWST level is 12.5 ft. | ||
* RCS pressure continues to lower. | * RCS pressure continues to lower. | ||
Which one of the following | Which one of the following completes the statement below? | ||
The next procedure the operating crew is required to transition to is . | |||
A. EEP-0.0, Reactor Trip or Safety Injection B. ESP-1.3, Transfer to Cold Leg Recirculation C. EEP-1.0, Loss of Reactor or Secondary Coolant D. ECP-1.1, Loss of Emergency Coolant Recirculation Tuesday, June 30, 2015 2:03:50 PM 23 | |||
QUESTIONS REPORT for ILT 38 SRO Ver 5 | |||
: 24. WE05EA2.1 099 Unit 2 is performing the | : 24. WE05EA2.1 099 Unit 2 is performing the actions of FRP-H.1, Response to Loss of Secondary Heat Sink, and the following conditions exist: | ||
* The TDAFW pump has been returned to service. | * The TDAFW pump has been returned to service. | ||
* Containment pressure is 0 psig. | * Containment pressure is 0 psig. | ||
* RCS Bleed and Feed was | * RCS Bleed and Feed was initiated, but has now been secured. | ||
* RCS pressure is 1600 psig and rising. | * RCS pressure is 1600 psig and rising. | ||
* Pressurizer level is 23% and rising. | * Pressurizer level is 23% and rising. | ||
Which one of the following | Which one of the following completes the statements below? | ||
(2) ESP-1.1, SI Termination(1) Wide Range level at 14% | The minimum SG level that permitted securing Bleed and Feed was at least one SG (1) . | ||
(2) EEP-1, Loss of Reactor or Secondary Coolant (1) Narrow Range level at 33% | The operating crew will transition to (2) from FRP-H.1. | ||
(2) ESP-1.1, SI Termination (1) | A. (1) Wide Range level at 14% | ||
(2) EEP-1, Loss of Reactor or Secondary Coolant | (2) ESP-1.1, SI Termination B. (1) Wide Range level at 14% | ||
: 25. WE10EA2.2 100 Unit 1 is cooling down per ESP-0.2, | (2) EEP-1, Loss of Reactor or Secondary Coolant C. (1) Narrow Range level at 33% | ||
(2) ESP-1.1, SI Termination D. (1) Narrow Range level at 33% | |||
(2) EEP-1, Loss of Reactor or Secondary Coolant Tuesday, June 30, 2015 2:03:50 PM 24 | |||
QUESTIONS REPORT for ILT 38 SRO Ver 5 | |||
: 25. WE10EA2.2 100 Unit 1 is cooling down per ESP-0.2, Natural Circulation Cooldown to Prevent Reactor Vessel Head Steam Voiding, and the following conditions exist: | |||
* RVLIS is not available. | * RVLIS is not available. | ||
* RCS Hot leg is 450°F and slowly lowering. | * RCS Hot leg is 450°F and slowly lowering. | ||
* RCS Cold leg is 425°F and slowly lowering. | * RCS Cold leg is 425°F and slowly lowering. | ||
* The crew is cooling down at | * The crew is cooling down at the maximum rate allowed by procedure. | ||
* Pressurizer level has just | * Pressurizer level has just rapidly risen to 78% and is stable | ||
* RCS pressure reduction is not required. | * RCS pressure reduction is not required. | ||
* CST level is 9ft. | * CST level is 9ft. | ||
Which one of the following | Which one of the following completes the statements below? | ||
The operating crew will transition to ESP-0.4, | The operating crew will transition to ESP-0.4, Natural Circulation Cooldown with Allowance for Reactor Vessel Head Steam Voiding (Without RVLIS), based on (1) . | ||
The maximum allowable cooldown rate in ESP-0.4 is (2) . | |||
Reference Provided A. (1) CST Level (2) <100°F in any 60 minute period B. (1) CST Level (2) <50°F/hr C. (1) Reactor Vessel void formation being indicated (2) <100°F in any 60 minute period D. (1) Reactor Vessel void formation being indicated (2) <50°F/hr Tuesday, June 30, 2015 2:03:50 PM 25}} |
Latest revision as of 05:59, 5 February 2020
ML16049A495 | |
Person / Time | |
---|---|
Site: | Farley ![]() |
Issue date: | 02/18/2016 |
From: | Division of Reactor Safety II |
To: | Southern Nuclear Operating Co |
References | |
Download: ML16049A495 (26) | |
Text
ES-401 Site-Specific SRO Written Examination Form ES-401-8 Cover Sheet U. S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name:
Date: 20 OCT 2015 Facility / Unit FARLEY 1 & 2 Region: I II X III IV Reactor Type: W X CE BW GE Start Time: Finish Time:
Instructions 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 percent overall, with 70 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80 percent to pass. You have 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to complete the combined examination, and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> 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 75 / ______
______ 25 / ______
100 Points Applicant's Score ______ / ______ / ______
Points Applicant's Grade ______ / ______ / ______
Percent ES-401, Page 38 of 50
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 1. 003AG2.1.23 076 Unit 1 was operating at 100% power when the following occurred:
At 1000:
- All Control Banks are at 231 steps.
At 1010:
- Rod K4 fell to 130 steps.
- Rod M6 fell to 150 steps.
- RCS Tavg lowered.
- Pressurizer pressure lowered.
Which one of the following completes the statement below?
Per AOP-19, Malfunction of Rod Control System, the operating crew is required to .
A. shutdown the unit using UOP-3.1, Power Operation B. trip the Reactor and go to EEP-0.0, Reactor Trip and Safety Injection C. reduce power to less than 75% within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> using UOP-3.1, Power Operation D. address restoration of rods using SOP-41.0, Control Rod Drive and Position Indication System Tuesday, June 30, 2015 2:03:49 PM 1
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 2. 003G2.4.45 077 Unit 1 is operating at 100% power when the following occurs:
At 1000:
- HH4, RCP VIB TRBL (WHITE annunciator window), comes into alarm.
- 1A RCP shaft vibration is reported as 21 mils and stable.
- DC2, RCP #1 SEAL LKOF FLOW HI (YELLOW annunciator window),
comes into alarm.
At 1600:
- The Unit is in MODE 3.
- The Reactor Trip Breakers are open.
- 1B and 1C RCPs are running.
- 1A RCP is tagged out.
Which one of the following completes the statements below?
At 1000, the operating crew is required to (1) , then secure the 1A RCP.
At 1600, RCS pressure control is via (2) .
A. (1) trip the Reactor and go to EEP-0.0, Reactor Trip or Safety Injection (2) Normal Spray B. (1) perform a controlled shutdown per the appropriate Unit Operating Procedures (2) Normal Spray C. (1) trip the Reactor and go to EEP-0.0, Reactor Trip or Safety Injection (2) Auxiliary Spray D. (1) perform a controlled shutdown per the appropriate Unit Operating Procedures (2) Auxiliary Spray Tuesday, June 30, 2015 2:03:49 PM 2
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 3. 007A2.03 078 Unit 1 is operating at 100% power when the following occurs:
- Due to a Pressurizer pressure control malfunction, PCV-445A, PRZR PORV opens and reseats several times.
- PRT level rises to 84% and is stable.
Which one of the following completes the statements below?
HE4, PRT LVL HI-LO, (1) in alarm.
The procedure used to lower PRT level is (2) .
A. (1) is NOT (2) SOP-1.2, Reactor Coolant Pressure Relief System B. (1) IS (2) SOP-1.2, Reactor Coolant Pressure Relief System C. (1) is NOT (2) SOP-50.0, Liquid Waste Processing System D. (1) IS (2) SOP-50.0, Liquid Waste Processing System Tuesday, June 30, 2015 2:03:49 PM 3
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 4. 007EA2.03 079 Unit 1 is in MODE 3 with the following conditions:
At 1000:
- The Shutdown Banks are withdrawn.
At 1005:
- A complete loss of offsite power occurs.
Which one of the following completes the statements below?
At 1005, manual action (1) required to generate a P-4 signal.
Per the BASES of Tech Spec 3.3.2, ESFAS Instrumentation, P-4 is required to be OPERABLE to prevent (2) .
A. (1) IS (2) excessive Containment pressure due to a steamline break B. (1) is NOT (2) excessive Containment pressure due to a steamline break C. (1) IS (2) damage to the Main Steam lines and SG safeties due to SG overfill D. (1) is NOT (2) damage to the Main Steam lines and SG safeties due to SG overfill Tuesday, June 30, 2015 2:03:49 PM 4
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 5. 010G2.2.44 080 Unit 1 is operating at 100% power with the following conditions:
- A malfunction occurred resulting in PCV-444B, PRZR PORV, opening.
Subsequently, the immediate operator actions of AOP-100, Instrumentation Malfunction, were performed and the following conditions exist:
- PCV-444B GREEN light is LIT.
- RCS pressure is 2180 psig and stable.
- PRT pressure, level and temperature are stable.
- HA4, PRZR SAFETY VLV TEMP HI, is in alarm.
- HA5, PRZR PORV TEMP HI, is in alarm.
Which one of the following completes the statements below?
PCV-444B (1) leaking by.
Per Tech Spec 3.4.11, Pressurizer Power Operated Relief Valves (PORVs), PCV-444B (2) OPERABLE.
(1) (2)
A. IS IS B. IS is NOT C. is NOT IS D. is NOT is NOT Tuesday, June 30, 2015 2:03:49 PM 5
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 6. 026A2.03 081 Unit 1 is at 100% power with the following conditions:
- PT-950, CTMT PRESS (Channel 1), was declared INOPERABLE.
- PT-950 bistables were positioned as required by Tech Spec 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, for continuous operation with an inoperable channel.
Which one of the following completes the statements below?
The Safety Injection function (1) affected by the PT-950 malfunction.
Per Tech Spec 3.3.2, the REQUIRED ACTION is to place the PT-950 bistables in (2) .
(1) (2)
A. IS TRIP B. IS BYPASS C. is NOT TRIP D. is NOT BYPASS Tuesday, June 30, 2015 2:03:49 PM 6
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 7. 026AA2.03 082 Unit 1 is in MODE 3 with the following conditions:
- All RCPs are running.
Which one of the following completes the statements below?
The method used in the Main Control Room (MCR) to isolate the CCW leak is to (1) .
Per the BASES of Tech Spec 3.7.7 - CCW System, once the CCW leak is isolated from the MCR, the CCW System is (2) .
A. (1) isolate CCW to ALL RCPs (2) INOPERABLE B. (1) isolate CCW to the 1A RCP ONLY (2) INOPERABLE C. (1) isolate CCW to ALL RCPs (2) OPERABLE D. (1) isolate CCW to the 1A RCP ONLY (2) OPERABLE Tuesday, June 30, 2015 2:03:49 PM 7
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 8. 028A2.02 083 Unit 1 has experienced a LOCA. The following conditions exist:
- EEP-1.0, Loss of Reactor or Secondary Coolant, is in progress.
- Containment Hydrogen is 6% by volume of dry air.
Which one of the following completes the statements below?
The hydrogen concentration (1) exceed the lower FLAMMABILITY limit.
Hydrogen concentration will be lowered using (2) .
A. (1) DOES (2) SOP-10.0, POST LOCA Containment Pressurization and Vent System B. (1) DOES (2) Attachment 3 of EEP-1.0, Post LOCA Hydrogen Recombiner Operation C. (1) does NOT (2) SOP-10.0, POST LOCA Containment Pressurization and Vent System D. (1) does NOT (2) Attachment 3 of EEP-1.0, Post LOCA Hydrogen Recombiner Operation Tuesday, June 30, 2015 2:03:49 PM 8
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 9. 028AG2.1.25 084 Unit 1 is operating at 100% when a Pressurizer level control malfunction occurs and the following conditions exist:
- Pressurizer level is 70% and rising.
- Charging flow is 120 gpm.
- Letdown is 60 gpm.
- RCP seal leakoff is 3 gpm per pump.
- Actions in the field are being taken to regain control of Charging.
- It will take 8 minutes to regain control of Charging.
Which one of the following completes the statements below?
An automatic reactor trip (1) occur before control of Charging is regained.
Per the BASES of Tech Spec 3.3.1, Reactor Trip System (RTS)
Instrumentation, the purpose of the automatic Reactor Trip on Pressurizer Water Level - High is to (2) .
Reference Provided A. (1) WILL (2) provide protection against water relief through the PORV's B. (1) WILL (2) prevent thermal shock of the Spray Nozzle C. (1) will NOT (2) provide protection against water relief through the PORV's D. (1) will NOT (2) prevent thermal shock of the Spray Nozzle Tuesday, June 30, 2015 2:03:49 PM 9
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 10. 034G2.4.30 085 Unit 1 is conducting a fuel reload and the following conditions occur:
At 1000:
- A spent fuel assembly is in the Containment Upender and lowered.
- A loss of power to the fuel transfer system occurs.
At 1015:
- It is determined that an Intermediate Leg leak is in progress on the 1A RCS loop.
- R-2, CTMT 155 FT, is in alarm.
- EH2, SFP LVL HI-LO is in alarm.
- Both RHR pumps have been secured due to cavitation.
Which one of the following completes the statements below?
At 1030, an emergency classification, per NMP-EP-110, Emergency Classification Determination and Initial Action, (1) required.
If the RCS leak is not isolated, the spent fuel assembly in the upender (2) remain covered with water.
(1) (2)
A. IS will NOT B. IS WILL C. is NOT will NOT D. is NOT WILL Tuesday, June 30, 2015 2:03:49 PM 10
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 11. 036AA2.02 086 A fuel shuffle is in progress in the Unit 1 SFP with the following conditions:
- An 1800 lb. load is being moved over spent fuel.
Subsequently, the following occurs:
- The load is dropped causing damage to the spent fuel.
- R-5, SFP ROOM, comes into alarm.
Which one of the following completes the statements below?
AOP-30, Refueling Accident, (1) required to be entered.
Per the Bases of TR 13.9.4, Crane Travel-Spent Fuel Storage Building, the expected worst case consequences of dropping an 1800 lb. load onto the spent fuel is that the (2) .
A. (1) IS (2) activity release will be limited to that contained in a single fuel assembly B. (1) IS (2) offsite dose may be as high as but not more than the 10 CFR 100 limit C. (1) is NOT (2) activity release will be limited to that contained in a single fuel assembly D. (1) is NOT (2) offsite dose may be as high as but not more than the 10 CFR 100 limit Tuesday, June 30, 2015 2:03:49 PM 11
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 12. 056AG2.2.44 087 Unit 1 was operating at 100% power with the following conditions:
At 1000: A complete loss of Offsite Power occurred.
At 1015: A spurious Safety Injection occurs and the following indications exist:
- On the Main Control Board:
- 1D SW PUMP Handswitch - GREEN and YELLOW lights LIT
- 1E SW PUMP Handswitch - GREEN and YELLOW lights LIT
- On the EPB:
- BIG SEQUENCER LIGHTS:
- BKR NOT CLOSED STEP 3 - LIT
- BKR NOT CLOSED STEP 4 - LIT
- ESS SEQ INCOMPLETE - LIT
- LOSP MAN LOADING START - LIT At 1017: The UO takes the 1D and 1E SW pump handswitches to START and the following occurs:
- 1D SW PUMP Handswitch - RED light LIT
- 1E SW PUMP Handswitch - RED light LIT
Which one of the following completes the statements below?
At 1015: The 1B DG (1) have cooling water supplied.
At 1017: In addition to CONDITION C of Tech Spec 3.8.1, AC Sources - Operating, CONDITON(S) (2) is(are) required to be entered.
Reference Provided (1) (2)
A. WILL B&G B. WILL G ONLY C. will NOT B&G D. will NOT G ONLY Tuesday, June 30, 2015 2:03:49 PM 12
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 13. 065AG2.4.22 088 Unit 1 is operating at 100% power with the following conditions:
- A rupture has occurred on the Instrument Air header piping in the MSVR.
- A Reactor Trip has occurred.
- AOP-6.0, Loss of Instrument Air, is in progress.
Which one of the following completes the statements below?
After the Reactor Trip, Pressurizer level will (1) due to the loss of Instrument Air.
Per AOP-6.0, to maintain Pressurizer level, the operating crew is required to perform actions of (2) in conjunction with AOP-6.0.
Procedure Names: AOP-16.0, CVCS Malfunction SOP-2.1, CVCS Plant Startup and Operation (1) (2)
A. lower AOP-16.0 B. rise AOP-16.0 C. lower SOP-2.1 D. rise SOP-2.1 Tuesday, June 30, 2015 2:03:49 PM 13
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 14. 072A2.03 089 Unit 1 is operating at 100% power when the following occurs:
- R-27B, CTMT HIGH RANGE, is tagged out.
- The instrument power supply fuse to R-27A, CTMT HIGH RANGE, blows.
Which one of the following completes the statements below?
The loss of R-27A (1) affect the ability to evaluate the loss of Fuel Clad Barrier per NMP-EP-110-GL01, FNP EALs - ICs, Threshold Values and Basis.
Per Tech Spec 3.3.3, Post Accident Monitoring Instrumentation, the REQUIRED ACTION is to (2) .
Reference Provided A. (1) will NOT (2) immediately initiate action in accordance with Specification 5.6.8 B. (1) will NOT (2) restore R-27A OR R-27B to OPERABLE status in 7 days C. (1) WILL (2) immediately initiate action in accordance with Specification 5.6.8 D. (1) WILL (2) restore R-27A OR R-27B to OPERABLE status in 7 days Tuesday, June 30, 2015 2:03:50 PM 14
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 15. 073A2.01 090 Unit 1 is operating at 100% power and the following occurs:
- R-15A, SJAE EXH, power supply becomes erratic causing its indication to become unreliable but it does not alarm.
Per the ODCM, which one of the following actions are required to continue the release via this pathway, if any?
A. No actions are required.
B. Continuously collect samples using auxiliary equipment.
C. Place SJAE filtration in service until R-15A is restored to operable.
D. Perform grab samples at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and analyze them within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Tuesday, June 30, 2015 2:03:50 PM 15
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 16. G2.1.41 091 Unit 1 is in MODE 6 with the following conditions:
- Core reload is complete.
- Control Rod Drive Shaft Latching and RCCA Drag Testing is about to begin per FHP-5.1, Control Rod Drive Shaft Latching/Unlatching Tool Operating Instruction.
Per FHP-1.0, Refueling Operations, which one of the following requirements must be met prior to latching control rods?
A. The Maintenance Supervisor is in Containment.
B. The Fuel Handling Supervisor is in Containment.
C. The Maintenance Supervisor is in the Control Room and in direct communication with Containment.
D. The Fuel Handling Supervisor is in the Control Room and in direct communication with Containment.
Tuesday, June 30, 2015 2:03:50 PM 16
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 17. G2.2.13 092 A tagout is required to be cleared during night shift and the Work Document Holder is not on site and cannot be contacted to gain their approval.
Per NMP-AD-003, Equipment Clearance and Tagging, which one of the following can sign off the Work Document Holder?
A. Shift Manager B. Operations Director C. Maintenance Director D. Maintenance Manager Tuesday, June 30, 2015 2:03:50 PM 17
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 18. G2.2.40 093 Unit 1 is at 6% power with the following conditions:
- The 1A SGFP has been started.
- AFW is secured.
- The Main Feed Regulating Valves are closed.
At 1000 on January 1, 2015:
- MOV-3232B, MAIN FW TO 1B SG STOP VLV , is declared INOPERABLE.
At 1200 on January 1, 2015:
- FCV-489, 1B SG FW BYP FLOW, is declared INOPERABLE.
Subsequently it is determined that repairs will take 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> for each valve.
Which one of the following completes the statement below?
Per Tech Spec 3.7.3, Main Feedwater Stop Valves and Main Feedwater Regulation Valves (MFRVs) and Associated Bypass Valves, the earliest time that feed flow to the 1B SG must be isolated is .
Reference Provided A. 1800 on January 1, 2015 B. 2000 on January 1, 2015 C. 1000 on January 4, 2015 D. 1200 on January 4, 2015 Tuesday, June 30, 2015 2:03:50 PM 18
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 19. G2.3.12 094 A General Emergency on Unit 1 has been declared with following conditions:
- An Emergency Response Team is required to be dispatched to isolate an offsite release source.
- The TSC has not yet been manned.
Which one of the following completes the statements below?
To receive the dose listed above, operators (1) required to be volunteers.
The (2) will authorize the exposure.
(1) (2)
A. are NOT RP Supervisor B. are NOT Shift Manager C. ARE RP Supervisor D. ARE Shift Manager Tuesday, June 30, 2015 2:03:50 PM 19
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 20. G2.3.14 095 Unit 1 is in MODE 6 with core offload in progress with the following condition:
- A spent fuel assembly is being moved from its assigned location in the core to the upender.
Subsequently, AOP-30.0, Refueling Accident, is entered Which one of the following completes the statements below?
Per AOP-30.0, the Refueling SRO will direct the fuel assembly to be (1) .
Per the BASES of Tech Spec 3.9.6, Refueling Cavity Water Level, 23 ft of water is required to be maintained above the fuel to (2) .
A. (1) placed in any empty fuel location in the core (2) provide back up decay heat removal B. (1) placed in any empty fuel location in the core (2) retain iodine fission product activity in the water during a fuel handling accident C. (1) returned to its assigned location in the core (2) provide back up decay heat removal D. (1) returned to its assigned location in the core (2) retain iodine fission product activity in the water during a fuel handling accident Tuesday, June 30, 2015 2:03:50 PM 20
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 21. G2.4.30 096 Unit 2 reactor startup is in progress and the following conditions exist:
- NI31, SR1 COUNT RATE is 106 cps and stable.
- NI32, SR2 COUNT RATE is 104 cps and stable.
- TSLB-3 1-1, SR HI Q NC-31D is lit.
- TSLB-3 1-2, SR HI Q NC-32D is NOT lit.
- GA1, SR HI FLUX TRIP, is in alarm.
- The Reactor Trip breakers are closed.
Subsequently, The Shift Supervisor directs a manual Reactor trip.
- The Reactor Trip breakers open.
Which one of the following completes the statements below?
An emergency classification threshold value (1) been exceeded per NMP-EP-110-GL01, FNP EALS - ICs, Threshold Values And Basis.
The latest time the NRC can be notified is (2) hour(s) after the event / emergency declaration.
(1) (2)
A. has NOT 4 B. HAS 4 C. has NOT 1 D. HAS 1 Tuesday, June 30, 2015 2:03:50 PM 21
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 22. G2.4.35 097 Unit 1 is performing the actions of EEP-0.0, Reactor Trip or Safety Injection, and AOP-9, Loss of Component Cooling Water. Conditions are as follows:
- 1F 4160V bus is de-energized.
- B Train CCW is the on service Train.
- 1B CCW pump is Tagged Out.
- 1A CCW pump tripped.
- 1C CHG PUMP is running.
Subseqently, the Shift Supervisor determines that Firewater is required to be aligned to the 1B Charging pump.
Which one of the following actions are required by AOP-9.0 for these conditions, and the effect during the alignment of firewater to the 1B charging pump?
A.
- Secure 1C CHG pump.
- RCP number 1 seal outlet temperature may rise to greater than 235°F.
B.
- Secure 1C CHG pump.
- An evaluation must be performed prior to reinitiating Seal Injection or CCW to the thermal barriers.
C.
- Maintain 1C CHG pump running.
- 1C CHG pump may be damaged.
D.
- Maintain 1C CHG pump running.
- 1C CHG pump CCW oil cooler piping will be chemically contaminated.
Tuesday, June 30, 2015 2:03:50 PM 22
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 23. WE04EG2.1.2 098 Unit 1 operating crew has exited EEP-0.0, Reactor Trip or Safety Injection, and is now performing ECP-1.2, LOCA Outside Containment with the following conditions:
- The leak isolation steps are completed.
- RWST level is 12.5 ft.
- RCS pressure continues to lower.
Which one of the following completes the statement below?
The next procedure the operating crew is required to transition to is .
A. EEP-0.0, Reactor Trip or Safety Injection B. ESP-1.3, Transfer to Cold Leg Recirculation C. EEP-1.0, Loss of Reactor or Secondary Coolant D. ECP-1.1, Loss of Emergency Coolant Recirculation Tuesday, June 30, 2015 2:03:50 PM 23
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 24. WE05EA2.1 099 Unit 2 is performing the actions of FRP-H.1, Response to Loss of Secondary Heat Sink, and the following conditions exist:
- The TDAFW pump has been returned to service.
- Containment pressure is 0 psig.
- RCS Bleed and Feed was initiated, but has now been secured.
- RCS pressure is 1600 psig and rising.
- Pressurizer level is 23% and rising.
Which one of the following completes the statements below?
The minimum SG level that permitted securing Bleed and Feed was at least one SG (1) .
The operating crew will transition to (2) from FRP-H.1.
A. (1) Wide Range level at 14%
(2) ESP-1.1, SI Termination B. (1) Wide Range level at 14%
(2) EEP-1, Loss of Reactor or Secondary Coolant C. (1) Narrow Range level at 33%
(2) ESP-1.1, SI Termination D. (1) Narrow Range level at 33%
(2) EEP-1, Loss of Reactor or Secondary Coolant Tuesday, June 30, 2015 2:03:50 PM 24
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 25. WE10EA2.2 100 Unit 1 is cooling down per ESP-0.2, Natural Circulation Cooldown to Prevent Reactor Vessel Head Steam Voiding, and the following conditions exist:
- RVLIS is not available.
- RCS Hot leg is 450°F and slowly lowering.
- RCS Cold leg is 425°F and slowly lowering.
- The crew is cooling down at the maximum rate allowed by procedure.
- Pressurizer level has just rapidly risen to 78% and is stable
- RCS pressure reduction is not required.
- CST level is 9ft.
Which one of the following completes the statements below?
The operating crew will transition to ESP-0.4, Natural Circulation Cooldown with Allowance for Reactor Vessel Head Steam Voiding (Without RVLIS), based on (1) .
The maximum allowable cooldown rate in ESP-0.4 is (2) .
Reference Provided A. (1) CST Level (2) <100°F in any 60 minute period B. (1) CST Level (2) <50°F/hr C. (1) Reactor Vessel void formation being indicated (2) <100°F in any 60 minute period D. (1) Reactor Vessel void formation being indicated (2) <50°F/hr Tuesday, June 30, 2015 2:03:50 PM 25
ES-401 Site-Specific SRO Written Examination Form ES-401-8 Cover Sheet U. S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name:
Date: 20 OCT 2015 Facility / Unit FARLEY 1 & 2 Region: I II X III IV Reactor Type: W X CE BW GE Start Time: Finish Time:
Instructions 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 percent overall, with 70 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80 percent to pass. You have 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to complete the combined examination, and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> 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 75 / ______
______ 25 / ______
100 Points Applicant's Score ______ / ______ / ______
Points Applicant's Grade ______ / ______ / ______
Percent ES-401, Page 38 of 50
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 1. 003AG2.1.23 076 Unit 1 was operating at 100% power when the following occurred:
At 1000:
- All Control Banks are at 231 steps.
At 1010:
- Rod K4 fell to 130 steps.
- Rod M6 fell to 150 steps.
- RCS Tavg lowered.
- Pressurizer pressure lowered.
Which one of the following completes the statement below?
Per AOP-19, Malfunction of Rod Control System, the operating crew is required to .
A. shutdown the unit using UOP-3.1, Power Operation B. trip the Reactor and go to EEP-0.0, Reactor Trip and Safety Injection C. reduce power to less than 75% within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> using UOP-3.1, Power Operation D. address restoration of rods using SOP-41.0, Control Rod Drive and Position Indication System Tuesday, June 30, 2015 2:03:49 PM 1
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 2. 003G2.4.45 077 Unit 1 is operating at 100% power when the following occurs:
At 1000:
- HH4, RCP VIB TRBL (WHITE annunciator window), comes into alarm.
- 1A RCP shaft vibration is reported as 21 mils and stable.
- DC2, RCP #1 SEAL LKOF FLOW HI (YELLOW annunciator window),
comes into alarm.
At 1600:
- The Unit is in MODE 3.
- The Reactor Trip Breakers are open.
- 1B and 1C RCPs are running.
- 1A RCP is tagged out.
Which one of the following completes the statements below?
At 1000, the operating crew is required to (1) , then secure the 1A RCP.
At 1600, RCS pressure control is via (2) .
A. (1) trip the Reactor and go to EEP-0.0, Reactor Trip or Safety Injection (2) Normal Spray B. (1) perform a controlled shutdown per the appropriate Unit Operating Procedures (2) Normal Spray C. (1) trip the Reactor and go to EEP-0.0, Reactor Trip or Safety Injection (2) Auxiliary Spray D. (1) perform a controlled shutdown per the appropriate Unit Operating Procedures (2) Auxiliary Spray Tuesday, June 30, 2015 2:03:49 PM 2
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 3. 007A2.03 078 Unit 1 is operating at 100% power when the following occurs:
- Due to a Pressurizer pressure control malfunction, PCV-445A, PRZR PORV opens and reseats several times.
- PRT level rises to 84% and is stable.
Which one of the following completes the statements below?
HE4, PRT LVL HI-LO, (1) in alarm.
The procedure used to lower PRT level is (2) .
A. (1) is NOT (2) SOP-1.2, Reactor Coolant Pressure Relief System B. (1) IS (2) SOP-1.2, Reactor Coolant Pressure Relief System C. (1) is NOT (2) SOP-50.0, Liquid Waste Processing System D. (1) IS (2) SOP-50.0, Liquid Waste Processing System Tuesday, June 30, 2015 2:03:49 PM 3
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 4. 007EA2.03 079 Unit 1 is in MODE 3 with the following conditions:
At 1000:
- The Shutdown Banks are withdrawn.
At 1005:
- A complete loss of offsite power occurs.
Which one of the following completes the statements below?
At 1005, manual action (1) required to generate a P-4 signal.
Per the BASES of Tech Spec 3.3.2, ESFAS Instrumentation, P-4 is required to be OPERABLE to prevent (2) .
A. (1) IS (2) excessive Containment pressure due to a steamline break B. (1) is NOT (2) excessive Containment pressure due to a steamline break C. (1) IS (2) damage to the Main Steam lines and SG safeties due to SG overfill D. (1) is NOT (2) damage to the Main Steam lines and SG safeties due to SG overfill Tuesday, June 30, 2015 2:03:49 PM 4
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 5. 010G2.2.44 080 Unit 1 is operating at 100% power with the following conditions:
- A malfunction occurred resulting in PCV-444B, PRZR PORV, opening.
Subsequently, the immediate operator actions of AOP-100, Instrumentation Malfunction, were performed and the following conditions exist:
- PCV-444B GREEN light is LIT.
- RCS pressure is 2180 psig and stable.
- PRT pressure, level and temperature are stable.
- HA4, PRZR SAFETY VLV TEMP HI, is in alarm.
- HA5, PRZR PORV TEMP HI, is in alarm.
Which one of the following completes the statements below?
PCV-444B (1) leaking by.
Per Tech Spec 3.4.11, Pressurizer Power Operated Relief Valves (PORVs), PCV-444B (2) OPERABLE.
(1) (2)
A. IS IS B. IS is NOT C. is NOT IS D. is NOT is NOT Tuesday, June 30, 2015 2:03:49 PM 5
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 6. 026A2.03 081 Unit 1 is at 100% power with the following conditions:
- PT-950, CTMT PRESS (Channel 1), was declared INOPERABLE.
- PT-950 bistables were positioned as required by Tech Spec 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, for continuous operation with an inoperable channel.
Which one of the following completes the statements below?
The Safety Injection function (1) affected by the PT-950 malfunction.
Per Tech Spec 3.3.2, the REQUIRED ACTION is to place the PT-950 bistables in (2) .
(1) (2)
A. IS TRIP B. IS BYPASS C. is NOT TRIP D. is NOT BYPASS Tuesday, June 30, 2015 2:03:49 PM 6
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 7. 026AA2.03 082 Unit 1 is in MODE 3 with the following conditions:
- All RCPs are running.
Which one of the following completes the statements below?
The method used in the Main Control Room (MCR) to isolate the CCW leak is to (1) .
Per the BASES of Tech Spec 3.7.7 - CCW System, once the CCW leak is isolated from the MCR, the CCW System is (2) .
A. (1) isolate CCW to ALL RCPs (2) INOPERABLE B. (1) isolate CCW to the 1A RCP ONLY (2) INOPERABLE C. (1) isolate CCW to ALL RCPs (2) OPERABLE D. (1) isolate CCW to the 1A RCP ONLY (2) OPERABLE Tuesday, June 30, 2015 2:03:49 PM 7
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 8. 028A2.02 083 Unit 1 has experienced a LOCA. The following conditions exist:
- EEP-1.0, Loss of Reactor or Secondary Coolant, is in progress.
- Containment Hydrogen is 6% by volume of dry air.
Which one of the following completes the statements below?
The hydrogen concentration (1) exceed the lower FLAMMABILITY limit.
Hydrogen concentration will be lowered using (2) .
A. (1) DOES (2) SOP-10.0, POST LOCA Containment Pressurization and Vent System B. (1) DOES (2) Attachment 3 of EEP-1.0, Post LOCA Hydrogen Recombiner Operation C. (1) does NOT (2) SOP-10.0, POST LOCA Containment Pressurization and Vent System D. (1) does NOT (2) Attachment 3 of EEP-1.0, Post LOCA Hydrogen Recombiner Operation Tuesday, June 30, 2015 2:03:49 PM 8
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 9. 028AG2.1.25 084 Unit 1 is operating at 100% when a Pressurizer level control malfunction occurs and the following conditions exist:
- Pressurizer level is 70% and rising.
- Charging flow is 120 gpm.
- Letdown is 60 gpm.
- RCP seal leakoff is 3 gpm per pump.
- Actions in the field are being taken to regain control of Charging.
- It will take 8 minutes to regain control of Charging.
Which one of the following completes the statements below?
An automatic reactor trip (1) occur before control of Charging is regained.
Per the BASES of Tech Spec 3.3.1, Reactor Trip System (RTS)
Instrumentation, the purpose of the automatic Reactor Trip on Pressurizer Water Level - High is to (2) .
Reference Provided A. (1) WILL (2) provide protection against water relief through the PORV's B. (1) WILL (2) prevent thermal shock of the Spray Nozzle C. (1) will NOT (2) provide protection against water relief through the PORV's D. (1) will NOT (2) prevent thermal shock of the Spray Nozzle Tuesday, June 30, 2015 2:03:49 PM 9
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 10. 034G2.4.30 085 Unit 1 is conducting a fuel reload and the following conditions occur:
At 1000:
- A spent fuel assembly is in the Containment Upender and lowered.
- A loss of power to the fuel transfer system occurs.
At 1015:
- It is determined that an Intermediate Leg leak is in progress on the 1A RCS loop.
- R-2, CTMT 155 FT, is in alarm.
- EH2, SFP LVL HI-LO is in alarm.
- Both RHR pumps have been secured due to cavitation.
Which one of the following completes the statements below?
At 1030, an emergency classification, per NMP-EP-110, Emergency Classification Determination and Initial Action, (1) required.
If the RCS leak is not isolated, the spent fuel assembly in the upender (2) remain covered with water.
(1) (2)
A. IS will NOT B. IS WILL C. is NOT will NOT D. is NOT WILL Tuesday, June 30, 2015 2:03:49 PM 10
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 11. 036AA2.02 086 A fuel shuffle is in progress in the Unit 1 SFP with the following conditions:
- An 1800 lb. load is being moved over spent fuel.
Subsequently, the following occurs:
- The load is dropped causing damage to the spent fuel.
- R-5, SFP ROOM, comes into alarm.
Which one of the following completes the statements below?
AOP-30, Refueling Accident, (1) required to be entered.
Per the Bases of TR 13.9.4, Crane Travel-Spent Fuel Storage Building, the expected worst case consequences of dropping an 1800 lb. load onto the spent fuel is that the (2) .
A. (1) IS (2) activity release will be limited to that contained in a single fuel assembly B. (1) IS (2) offsite dose may be as high as but not more than the 10 CFR 100 limit C. (1) is NOT (2) activity release will be limited to that contained in a single fuel assembly D. (1) is NOT (2) offsite dose may be as high as but not more than the 10 CFR 100 limit Tuesday, June 30, 2015 2:03:49 PM 11
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 12. 056AG2.2.44 087 Unit 1 was operating at 100% power with the following conditions:
At 1000: A complete loss of Offsite Power occurred.
At 1015: A spurious Safety Injection occurs and the following indications exist:
- On the Main Control Board:
- 1D SW PUMP Handswitch - GREEN and YELLOW lights LIT
- 1E SW PUMP Handswitch - GREEN and YELLOW lights LIT
- On the EPB:
- BIG SEQUENCER LIGHTS:
- BKR NOT CLOSED STEP 3 - LIT
- BKR NOT CLOSED STEP 4 - LIT
- ESS SEQ INCOMPLETE - LIT
- LOSP MAN LOADING START - LIT At 1017: The UO takes the 1D and 1E SW pump handswitches to START and the following occurs:
- 1D SW PUMP Handswitch - RED light LIT
- 1E SW PUMP Handswitch - RED light LIT
Which one of the following completes the statements below?
At 1015: The 1B DG (1) have cooling water supplied.
At 1017: In addition to CONDITION C of Tech Spec 3.8.1, AC Sources - Operating, CONDITON(S) (2) is(are) required to be entered.
Reference Provided (1) (2)
A. WILL B&G B. WILL G ONLY C. will NOT B&G D. will NOT G ONLY Tuesday, June 30, 2015 2:03:49 PM 12
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 13. 065AG2.4.22 088 Unit 1 is operating at 100% power with the following conditions:
- A rupture has occurred on the Instrument Air header piping in the MSVR.
- A Reactor Trip has occurred.
- AOP-6.0, Loss of Instrument Air, is in progress.
Which one of the following completes the statements below?
After the Reactor Trip, Pressurizer level will (1) due to the loss of Instrument Air.
Per AOP-6.0, to maintain Pressurizer level, the operating crew is required to perform actions of (2) in conjunction with AOP-6.0.
Procedure Names: AOP-16.0, CVCS Malfunction SOP-2.1, CVCS Plant Startup and Operation (1) (2)
A. lower AOP-16.0 B. rise AOP-16.0 C. lower SOP-2.1 D. rise SOP-2.1 Tuesday, June 30, 2015 2:03:49 PM 13
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 14. 072A2.03 089 Unit 1 is operating at 100% power when the following occurs:
- R-27B, CTMT HIGH RANGE, is tagged out.
- The instrument power supply fuse to R-27A, CTMT HIGH RANGE, blows.
Which one of the following completes the statements below?
The loss of R-27A (1) affect the ability to evaluate the loss of Fuel Clad Barrier per NMP-EP-110-GL01, FNP EALs - ICs, Threshold Values and Basis.
Per Tech Spec 3.3.3, Post Accident Monitoring Instrumentation, the REQUIRED ACTION is to (2) .
Reference Provided A. (1) will NOT (2) immediately initiate action in accordance with Specification 5.6.8 B. (1) will NOT (2) restore R-27A OR R-27B to OPERABLE status in 7 days C. (1) WILL (2) immediately initiate action in accordance with Specification 5.6.8 D. (1) WILL (2) restore R-27A OR R-27B to OPERABLE status in 7 days Tuesday, June 30, 2015 2:03:50 PM 14
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 15. 073A2.01 090 Unit 1 is operating at 100% power and the following occurs:
- R-15A, SJAE EXH, power supply becomes erratic causing its indication to become unreliable but it does not alarm.
Per the ODCM, which one of the following actions are required to continue the release via this pathway, if any?
A. No actions are required.
B. Continuously collect samples using auxiliary equipment.
C. Place SJAE filtration in service until R-15A is restored to operable.
D. Perform grab samples at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and analyze them within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Tuesday, June 30, 2015 2:03:50 PM 15
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 16. G2.1.41 091 Unit 1 is in MODE 6 with the following conditions:
- Core reload is complete.
- Control Rod Drive Shaft Latching and RCCA Drag Testing is about to begin per FHP-5.1, Control Rod Drive Shaft Latching/Unlatching Tool Operating Instruction.
Per FHP-1.0, Refueling Operations, which one of the following requirements must be met prior to latching control rods?
A. The Maintenance Supervisor is in Containment.
B. The Fuel Handling Supervisor is in Containment.
C. The Maintenance Supervisor is in the Control Room and in direct communication with Containment.
D. The Fuel Handling Supervisor is in the Control Room and in direct communication with Containment.
Tuesday, June 30, 2015 2:03:50 PM 16
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 17. G2.2.13 092 A tagout is required to be cleared during night shift and the Work Document Holder is not on site and cannot be contacted to gain their approval.
Per NMP-AD-003, Equipment Clearance and Tagging, which one of the following can sign off the Work Document Holder?
A. Shift Manager B. Operations Director C. Maintenance Director D. Maintenance Manager Tuesday, June 30, 2015 2:03:50 PM 17
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 18. G2.2.40 093 Unit 1 is at 6% power with the following conditions:
- The 1A SGFP has been started.
- AFW is secured.
- The Main Feed Regulating Valves are closed.
At 1000 on January 1, 2015:
- MOV-3232B, MAIN FW TO 1B SG STOP VLV , is declared INOPERABLE.
At 1200 on January 1, 2015:
- FCV-489, 1B SG FW BYP FLOW, is declared INOPERABLE.
Subsequently it is determined that repairs will take 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> for each valve.
Which one of the following completes the statement below?
Per Tech Spec 3.7.3, Main Feedwater Stop Valves and Main Feedwater Regulation Valves (MFRVs) and Associated Bypass Valves, the earliest time that feed flow to the 1B SG must be isolated is .
Reference Provided A. 1800 on January 1, 2015 B. 2000 on January 1, 2015 C. 1000 on January 4, 2015 D. 1200 on January 4, 2015 Tuesday, June 30, 2015 2:03:50 PM 18
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 19. G2.3.12 094 A General Emergency on Unit 1 has been declared with following conditions:
- An Emergency Response Team is required to be dispatched to isolate an offsite release source.
- The TSC has not yet been manned.
Which one of the following completes the statements below?
To receive the dose listed above, operators (1) required to be volunteers.
The (2) will authorize the exposure.
(1) (2)
A. are NOT RP Supervisor B. are NOT Shift Manager C. ARE RP Supervisor D. ARE Shift Manager Tuesday, June 30, 2015 2:03:50 PM 19
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 20. G2.3.14 095 Unit 1 is in MODE 6 with core offload in progress with the following condition:
- A spent fuel assembly is being moved from its assigned location in the core to the upender.
Subsequently, AOP-30.0, Refueling Accident, is entered Which one of the following completes the statements below?
Per AOP-30.0, the Refueling SRO will direct the fuel assembly to be (1) .
Per the BASES of Tech Spec 3.9.6, Refueling Cavity Water Level, 23 ft of water is required to be maintained above the fuel to (2) .
A. (1) placed in any empty fuel location in the core (2) provide back up decay heat removal B. (1) placed in any empty fuel location in the core (2) retain iodine fission product activity in the water during a fuel handling accident C. (1) returned to its assigned location in the core (2) provide back up decay heat removal D. (1) returned to its assigned location in the core (2) retain iodine fission product activity in the water during a fuel handling accident Tuesday, June 30, 2015 2:03:50 PM 20
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 21. G2.4.30 096 Unit 2 reactor startup is in progress and the following conditions exist:
- NI31, SR1 COUNT RATE is 106 cps and stable.
- NI32, SR2 COUNT RATE is 104 cps and stable.
- TSLB-3 1-1, SR HI Q NC-31D is lit.
- TSLB-3 1-2, SR HI Q NC-32D is NOT lit.
- GA1, SR HI FLUX TRIP, is in alarm.
- The Reactor Trip breakers are closed.
Subsequently, The Shift Supervisor directs a manual Reactor trip.
- The Reactor Trip breakers open.
Which one of the following completes the statements below?
An emergency classification threshold value (1) been exceeded per NMP-EP-110-GL01, FNP EALS - ICs, Threshold Values And Basis.
The latest time the NRC can be notified is (2) hour(s) after the event / emergency declaration.
(1) (2)
A. has NOT 4 B. HAS 4 C. has NOT 1 D. HAS 1 Tuesday, June 30, 2015 2:03:50 PM 21
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 22. G2.4.35 097 Unit 1 is performing the actions of EEP-0.0, Reactor Trip or Safety Injection, and AOP-9, Loss of Component Cooling Water. Conditions are as follows:
- 1F 4160V bus is de-energized.
- B Train CCW is the on service Train.
- 1B CCW pump is Tagged Out.
- 1A CCW pump tripped.
- 1C CHG PUMP is running.
Subseqently, the Shift Supervisor determines that Firewater is required to be aligned to the 1B Charging pump.
Which one of the following actions are required by AOP-9.0 for these conditions, and the effect during the alignment of firewater to the 1B charging pump?
A.
- Secure 1C CHG pump.
- RCP number 1 seal outlet temperature may rise to greater than 235°F.
B.
- Secure 1C CHG pump.
- An evaluation must be performed prior to reinitiating Seal Injection or CCW to the thermal barriers.
C.
- Maintain 1C CHG pump running.
- 1C CHG pump may be damaged.
D.
- Maintain 1C CHG pump running.
- 1C CHG pump CCW oil cooler piping will be chemically contaminated.
Tuesday, June 30, 2015 2:03:50 PM 22
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 23. WE04EG2.1.2 098 Unit 1 operating crew has exited EEP-0.0, Reactor Trip or Safety Injection, and is now performing ECP-1.2, LOCA Outside Containment with the following conditions:
- The leak isolation steps are completed.
- RWST level is 12.5 ft.
- RCS pressure continues to lower.
Which one of the following completes the statement below?
The next procedure the operating crew is required to transition to is .
A. EEP-0.0, Reactor Trip or Safety Injection B. ESP-1.3, Transfer to Cold Leg Recirculation C. EEP-1.0, Loss of Reactor or Secondary Coolant D. ECP-1.1, Loss of Emergency Coolant Recirculation Tuesday, June 30, 2015 2:03:50 PM 23
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 24. WE05EA2.1 099 Unit 2 is performing the actions of FRP-H.1, Response to Loss of Secondary Heat Sink, and the following conditions exist:
- The TDAFW pump has been returned to service.
- Containment pressure is 0 psig.
- RCS Bleed and Feed was initiated, but has now been secured.
- RCS pressure is 1600 psig and rising.
- Pressurizer level is 23% and rising.
Which one of the following completes the statements below?
The minimum SG level that permitted securing Bleed and Feed was at least one SG (1) .
The operating crew will transition to (2) from FRP-H.1.
A. (1) Wide Range level at 14%
(2) ESP-1.1, SI Termination B. (1) Wide Range level at 14%
(2) EEP-1, Loss of Reactor or Secondary Coolant C. (1) Narrow Range level at 33%
(2) ESP-1.1, SI Termination D. (1) Narrow Range level at 33%
(2) EEP-1, Loss of Reactor or Secondary Coolant Tuesday, June 30, 2015 2:03:50 PM 24
QUESTIONS REPORT for ILT 38 SRO Ver 5
- 25. WE10EA2.2 100 Unit 1 is cooling down per ESP-0.2, Natural Circulation Cooldown to Prevent Reactor Vessel Head Steam Voiding, and the following conditions exist:
- RVLIS is not available.
- RCS Hot leg is 450°F and slowly lowering.
- RCS Cold leg is 425°F and slowly lowering.
- The crew is cooling down at the maximum rate allowed by procedure.
- Pressurizer level has just rapidly risen to 78% and is stable
- RCS pressure reduction is not required.
- CST level is 9ft.
Which one of the following completes the statements below?
The operating crew will transition to ESP-0.4, Natural Circulation Cooldown with Allowance for Reactor Vessel Head Steam Voiding (Without RVLIS), based on (1) .
The maximum allowable cooldown rate in ESP-0.4 is (2) .
Reference Provided A. (1) CST Level (2) <100°F in any 60 minute period B. (1) CST Level (2) <50°F/hr C. (1) Reactor Vessel void formation being indicated (2) <100°F in any 60 minute period D. (1) Reactor Vessel void formation being indicated (2) <50°F/hr Tuesday, June 30, 2015 2:03:50 PM 25