ML16049A495

Initial Exam 2015-301 Draft SRO Written Exam

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, Page 38 of 50 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: Facility / Unit Region: I II III IV Reactor Type: W 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 ______ / ______ / ______

Points Applicant's Score ______ / ______ / ______

Points Applicant's Grade ______ / ______ / ______

Percent QUESTIONS REPORTfor 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 co mpletes the statement below?

Per AOP-19, Malfunction of Rod Control System, the operating crew is required to

.shutdown the unit using UO P-3.1, Power Operation trip the Reactor and go to EEP-0.0, Reactor Trip and Safety Injection 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 address restoration of rods using SOP-41.0, Control Rod Drive and PositionIndication System A.B.C.D.Tuesday, June 30, 2015 2:03:49 PM 1

QUESTIONS REPORTfor 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 annunci ator 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.

• FR145A, RCP SEAL LKOF HIGH RANGE, for the 1A RCP indicates 6.5 gpm and stable.

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 co mpletes 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) . (1) trip the Reactor and go to EEP-0.0, Reactor Trip or Safety Injection(2) Normal Spray(1) perform a controlled shutdown per th e appropriate Unit Operating Procedures(2) Normal Spray(1) trip the Reactor and go to EEP-0.0, Reactor Trip or Safety Injection(2) Auxiliary Spray(1) perform a controlled shutdown per th e appropriate Unit Operating Procedures(2) Auxiliary Spray A.B.C.D.Tuesday, June 30, 2015 2:03:49 PM 2

QUESTIONS REPORTfor 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 contro l malfunction, PCV-445A, PRZR PORV opens and reseats several times.

• PRT level rises to 84% and is stable.

Which one of the following co mpletes the statements below?

HE4, PRT LVL HI-LO, (1) in alarm.

The procedure used to lower PRT level is (2) . (1) is NOT (2) SOP-1.2, Reactor Coolant Pressure Relief System (1) IS (2) SOP-1.2, Reactor Coolant Pressure Relief System (1) is NOT (2) SOP-50.0, Liquid Waste Processing System (1) IS (2) SOP-50.0, Liquid Waste Processing System A.B.C.D.Tuesday, June 30, 2015 2:03:49 PM

3 QUESTIONS REPORTfor 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 co mpletes 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 Instru mentation, P-4 is required to be OPERABLE to prevent (2) .(1) IS (2) excessive Containment pressu re due to a steamline break(1) is NOT (2) excessive Containment pressu re due to a steamline break(1) IS (2) damage to the Main Steam lines and SG safeties due to SG overfill (1) is NOT (2) damage to the Main Steam lines and SG safeties due to SG overfill A.B.C.D.Tuesday, June 30, 2015 2:03:49 PM

4 QUESTIONS REPORTfor ILT 38 SRO Ver 5

5. 010G2.2.44 080 Unit 1 is operating at 100% pow er with the following conditions:* A malfunction occurred result ing in PCV-444B, PRZR PORV, opening.Subsequently, the immediat e 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.

Which one of the following co mpletes 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) IS IS IS is NOT is NOT IS is NOT is NOT A.B.C.D.Tuesday, June 30, 2015 2:03:49 PM 5

QUESTIONS REPORTfor 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 decla red INOPERABLE.

• PT-950 bistables were positioned as required by Tech Spec 3.3.2, Engineered Safety Feature Actuation S ystem (ESFAS) Instrumentation, for continuous operation with an inoperable channel.

Which one of the following co mpletes the statements below?The Safety Injection function (1) affected by the PT-950 malfunction.

Per Tech Spec 3.3.2, the RE QUIRED ACTION is to place the PT-950 bistables in (2) . (1)

(2) IS TRIP IS BYPASS is NOT TRIP is NOT BYPASS A.B.C.D.Tuesday, June 30, 2015 2:03:49 PM 6

QUESTIONS REPORTfor ILT 38 SRO Ver 5

7. 026AA2.03 082 Unit 1 is in MODE 3 with the following conditions:

• All RCPs are running.

• A CCW leak occurs on the 1A RCP Oil Cooler inlet connection.

Which one of the following co mpletes 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 isolatedfrom the MCR, the CCW System is (2) . (1) isolate CCW to ALL RCPs(2) INOPERABLE(1) isolate CCW to the 1A RCP ONLY (2) INOPERABLE(1) isolate CCW to ALL RCPs (2) OPERABLE(1) isolate CCW to the 1A RCP ONLY (2) OPERABLE A.B.C.D.Tuesday, June 30, 2015 2:03:49 PM 7

QUESTIONS REPORTfor 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 co mpletes the statements below?

The hydrogen concentration (1) exceed the lower FLAMMABILITY limit.Hydrogen concentration will be lowered using (2) .(1) DOES (2) SOP-10.0, POST LOCA Containment Pressurization and Vent System (1) DOES (2) Attachment 3 of EEP-1.0, Post LOCA Hydrogen Recombiner Operation (1) does NOT (2) SOP-10.0, POST LOCA Containment Pressurization and Vent System (1) does NOT (2) Attachment 3 of EEP-1.0, Post LOCA Hydrogen Recombiner Operation A.B.C.D.Tuesday, June 30, 2015 2:03:49 PM

8 QUESTIONS REPORTfor ILT 38 SRO Ver 5

9. 028AG2.1.25 084 Unit 1 is operating at 100%

when a Pressurizer level c ontrol malfunction occurs and the following conditions exist:

• Pressurizer level is 70% and rising.

• Charging flow is 120 gpm.

• Letdown is 60 gpm.

• RCP seal injection is 8 gpm to each RCP.

• RCP seal leakoff is 3 gpm per pump.

• Actions in the field are being taken to regain c ontrol of Charging.

• It will take 8 minutes to regain control of Charging.

Which one of the following co mpletes 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 automat ic Reactor Trip on Pressurizer Water Level - High is to (2) .Reference Provided (1) WILL (2) provide protection against water relief th rough the PORV's(1) WILL (2) prevent thermal shock of the Spray Nozzle (1) will NOT (2) provide protection against water relief th rough the PORV's (1) will NOT (2) prevent thermal shock of the Spray Nozzle A.B.C.D.Tuesday, June 30, 2015 2:03:49 PM

9 QUESTIONS REPORTfor 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 co mpletes the statements below?

At 1030 , an emergency classification , per NMP-EP-110, Emergency Classification Determinatio n 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) IS will NOT IS WILL is NOT will NOT is NOT WILL A.B.C.D.Tuesday, June 30, 2015 2:03:49 PM 10 QUESTIONS REPORTfor 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 bei ng 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 co mpletes the statements below?

AOP-30, Refueling Accident, (1) required to be entered.

Per the Bases of TR 13.9.4, Cra ne Travel-Spent Fuel Storage Building, the expected worst case consequences of dropping an 1800 lb. load onto the spent fuel is that the (2) .(1) IS(2) activity release will be limited to th at contained in a single fuel assembly (1) IS(2) offsite dose may be as high as but not more than the 10 CFR 100 limit(1) is NOT(2) activity release will be limited to th at contained in a single fuel assembly(1) is NOT(2) offsite dose may be as high as but not more than the 10 CFR 100 limit A.B.C.D.Tuesday, June 30, 2015 2:03:49 PM

11 QUESTIONS REPORTfor 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 occu rs 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 pu mp handswitches to START and the following occurs:

• 1D SW PUMP Handswitch - RED light LIT

• 1E SW PUMP Handsw itch - RED light LIT

• PI 3001B, SW TO CCW HX HDR PRESS, rises to 100 psig.

Which one of the following co mpletes 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) WILL B & G WILL G ONLY will NOT B & G will NOT G ONLY A.B.C.D.Tuesday, June 30, 2015 2:03:49 PM 12 QUESTIONS REPORTfor ILT 38 SRO Ver 5

13. 065AG2.4.22 088 Unit 1 is operating at 100% pow er with the following conditions:

• A rupture has occurred on the Inst rument Air header pi ping in the MSVR.

• A Reactor Trip has occurred.

• AOP-6.0, Loss of Instru ment Air, is in progress.

Which one of the following co mpletes the statements below? After the Reactor Trip , Pressurizer level will (1) due to the loss ofInstrument 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 Pl ant Startup and Operation (1)

(2) lower AOP-16.0 rise AOP-16.0 lower SOP-2.1 rise SOP-2.1 A.B.C.D.Tuesday, June 30, 2015 2:03:49 PM 13 QUESTIONS REPORTfor 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 co mpletes 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 Acciden t Monitoring Instrumentation, theREQUIRED ACTION is to (2) . Reference Provided (1) will NOT (2) immediately initiate action in accordance with S pecification 5.6.8 (1) will NOT (2) restore R-27A OR R-27B to OPERABLE status in 7 days (1) WILL (2) immediately initiate action in accordance with S pecification 5.6.8 (1) WILL (2) restore R-27A OR R-27B to OPERABLE status in 7 days A.B.C.D.Tuesday, June 30, 2015 2:03:50 PM

14 QUESTIONS REPORTfor 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 beco mes erratic causi ng its indication to become unreliable but it does not alarm.Per the ODCM, which one of t he following actions are requi red to continue the releasevia this pathway, if any?

No actions are required.

Continuously collect samples using auxiliary equipment.

Place SJAE filtration in service until R-15A is restored to operable.

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 />.

A.B.C.D.Tuesday, June 30, 2015 2:03:50 PM

15 QUESTIONS REPORTfor 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 Oper ations, which one of the follo wing requirements must bemet prior to latching control rods?

The Maintenance Supervisor is in Containment.

The Fuel Handling Supervi sor is in Containment.

The Maintenance Supervisor is in the Control Room an d in direct communication with Containment.

The Fuel Handling Supervisor is in the Control Room and in direct communication with Containment.

A.B.C.D.Tuesday, June 30, 2015 2:03:50 PM 16 QUESTIONS REPORTfor ILT 38 SRO Ver 5

17. G2.2.13 092 A tagout is required to be cleared during ni ght 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 Docu ment Holder?

Shift Manager Operations Director Maintenance Director Maintenance Manager A.B.C.D.Tuesday, June 30, 2015 2:03:50 PM 17 QUESTIONS REPORTfor ILT 38 SRO Ver 5

18. G2.2.40 093 Unit 1 is at 6% power wi th 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 ST OP 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 r epairs 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 co mpletes the statement below?

Per Tech Spec 3.7.3, Main Feedwater St op 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 1800 on January 1, 2015 2000 on January 1, 2015 1000 on January 4, 2015 1200 on January 4, 2015 A.B.C.D.Tuesday, June 30, 2015 2:03:50 PM 18 QUESTIONS REPORTfor ILT 38 SRO Ver 5

19. G2.3.12 094 A General Emergency on Un it 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.

• The expected exposure for the job is 35 REM TEDE per person.

Which one of the following co mpletes the statements below?

To receive the dose listed above, operators (1) required to be volunteers. The (2) will authorize the exposure.

(1)

(2) are NOT RP Supervisor are NOT Shift Manager ARE RP Supervisor ARE Shift Manager A.B.C.D.Tuesday, June 30, 2015 2:03:50 PM 19 QUESTIONS REPORTfor ILT 38 SRO Ver 5

20. G2.3.14 095 Unit 1 is in MODE 6 with core offload in progress wi th the following condition:

• A spent fuel assembly is being moved from its assigned location in the core to the upender.

Subsequently, AOP-30.0, Ref ueling Accident, is entered Which one of the following co mpletes 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) .(1) placed in any empty fuel location in the core(2) provide back up decay heat removal(1) placed in any empty fuel location in the core(2) retain iodine fission product activity in the water during a f uel handling accident(1) returned to its assigned location in the core(2) provide back up decay heat removal(1) returned to its assigned location in the core(2) retain iodine fission product activity in the water during a f uel handling accident A.B.C.D.Tuesday, June 30, 2015 2:03:50 PM

20 QUESTIONS REPORTfor ILT 38 SRO Ver 5

21. G2.4.30 096 Unit 2 reactor startup is in progr ess and the following conditions exist:

• NI31, SR1 COUNT RATE is 10 6 cps and stable.

• NI32, SR2 COUNT RATE is 10 4 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 co mpletes the statements below?An emergency classifica tion 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) has NOT 4 HAS 4 has NOT 1 HAS 1 A.B.C.D.Tuesday, June 30, 2015 2:03:50 PM 21 QUESTIONS REPORTfor 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 Wate

r. 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 Superviso r determines that Firewater is required to be aligned to the 1B Charging pump

.Which one of the following actions are requir ed by AOP-9.0 for these conditions, and the effect during the a lignment of firewater to the 1B charging pump?* Secure 1C CHG pump.

• RCP number 1 seal outle t temperature may rise to greater than 235°F.

• Secure 1C CHG pump.

• An evaluation must be perfor med prior to reinitiating Seal Injection or CCW to the thermal barriers.

• Maintain 1C CHG pump running.

• 1C CHG pump may be damaged.

• Maintain 1C CHG pump running.

• 1C CHG pump CCW oil cooler piping will be chemically contaminated.

A.B.C.D.Tuesday, June 30, 2015 2:03:50 PM 22 QUESTIONS REPORTfor 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 co mpletes the statement below? The next procedure the operating crew is required to transition to is

.EEP-0.0, Reactor Trip or Safety Injection ESP-1.3, Transfer to Cold Leg Recirculation EEP-1.0, Loss of Reac tor or Secondary Coolant ECP-1.1, Loss of Emergency Coolant Recirculation A.B.C.D.Tuesday, June 30, 2015 2:03:50 PM

23 QUESTIONS REPORTfor ILT 38 SRO Ver 5

24. WE05EA2.1 099 Unit 2 is performing the acti ons 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 initiat ed, but has now been secured.

• RCS pressure is 1600 psig and rising.

• Pressurizer level is 23% and rising.

Which one of the following co mpletes the statements below?The minimum SG level that permitt ed securing Bleed and Feed was at least one SG (1) .The operating crew will transition to (2) from FRP-H.1. (1) Wide Range level at 14%

(2) ESP-1.1, SI Termination(1) Wide Range level at 14%

(2) EEP-1, Loss of Reactor or Secondary Coolant (1) Narrow Range level at 33%

(2) ESP-1.1, SI Termination (1) Narrow Range level at 33%

(2) EEP-1, Loss of Reactor or Secondary Coolant A.B.C.D.Tuesday, June 30, 2015 2:03:50 PM 24 QUESTIONS REPORTfor ILT 38 SRO Ver 5

25. WE10EA2.2 100 Unit 1 is cooling down per ESP-0.2, Natura l 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 t he maximum rate al lowed by procedure.

• Pressurizer level has just r apidly risen to 78% and is stable

• RCS pressure reduction is not required.

• CST level is 9ft.

Which one of the following co mpletes 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 (1) CST Level (2) <100°F in any 60 minute period (1) CST Level(2) <50°F/hr (1) Reactor Vessel void formation being indicated (2) <100°F in any 60 minute period (1) Reactor Vessel void formation being indicated(2) <50°F/hr A.B.C.D.Tuesday, June 30, 2015 2:03:50 PM 25 ES-401, Page 38 of 50 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: Facility / Unit Region: I II III IV Reactor Type: W 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 ______ / ______ / ______

Points Applicant's Score ______ / ______ / ______

Points Applicant's Grade ______ / ______ / ______

Percent QUESTIONS REPORTfor 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 co mpletes the statement below?

Per AOP-19, Malfunction of Rod Control System, the operating crew is required to

.shutdown the unit using UO P-3.1, Power Operation trip the Reactor and go to EEP-0.0, Reactor Trip and Safety Injection 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 address restoration of rods using SOP-41.0, Control Rod Drive and PositionIndication System A.B.C.D.Tuesday, June 30, 2015 2:03:49 PM 1

QUESTIONS REPORTfor 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 annunci ator 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.

• FR145A, RCP SEAL LKOF HIGH RANGE, for the 1A RCP indicates 6.5 gpm and stable.

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 co mpletes 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) . (1) trip the Reactor and go to EEP-0.0, Reactor Trip or Safety Injection(2) Normal Spray(1) perform a controlled shutdown per th e appropriate Unit Operating Procedures(2) Normal Spray(1) trip the Reactor and go to EEP-0.0, Reactor Trip or Safety Injection(2) Auxiliary Spray(1) perform a controlled shutdown per th e appropriate Unit Operating Procedures(2) Auxiliary Spray A.B.C.D.Tuesday, June 30, 2015 2:03:49 PM 2

QUESTIONS REPORTfor 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 contro l malfunction, PCV-445A, PRZR PORV opens and reseats several times.

• PRT level rises to 84% and is stable.

Which one of the following co mpletes the statements below?

HE4, PRT LVL HI-LO, (1) in alarm.

The procedure used to lower PRT level is (2) . (1) is NOT (2) SOP-1.2, Reactor Coolant Pressure Relief System (1) IS (2) SOP-1.2, Reactor Coolant Pressure Relief System (1) is NOT (2) SOP-50.0, Liquid Waste Processing System (1) IS (2) SOP-50.0, Liquid Waste Processing System A.B.C.D.Tuesday, June 30, 2015 2:03:49 PM

3 QUESTIONS REPORTfor 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 co mpletes 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 Instru mentation, P-4 is required to be OPERABLE to prevent (2) .(1) IS (2) excessive Containment pressu re due to a steamline break(1) is NOT (2) excessive Containment pressu re due to a steamline break(1) IS (2) damage to the Main Steam lines and SG safeties due to SG overfill (1) is NOT (2) damage to the Main Steam lines and SG safeties due to SG overfill A.B.C.D.Tuesday, June 30, 2015 2:03:49 PM

4 QUESTIONS REPORTfor ILT 38 SRO Ver 5

5. 010G2.2.44 080 Unit 1 is operating at 100% pow er with the following conditions:* A malfunction occurred result ing in PCV-444B, PRZR PORV, opening.Subsequently, the immediat e 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.

Which one of the following co mpletes 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) IS IS IS is NOT is NOT IS is NOT is NOT A.B.C.D.Tuesday, June 30, 2015 2:03:49 PM 5

QUESTIONS REPORTfor 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 decla red INOPERABLE.

• PT-950 bistables were positioned as required by Tech Spec 3.3.2, Engineered Safety Feature Actuation S ystem (ESFAS) Instrumentation, for continuous operation with an inoperable channel.

Which one of the following co mpletes the statements below?The Safety Injection function (1) affected by the PT-950 malfunction.

Per Tech Spec 3.3.2, the RE QUIRED ACTION is to place the PT-950 bistables in (2) . (1)

(2) IS TRIP IS BYPASS is NOT TRIP is NOT BYPASS A.B.C.D.Tuesday, June 30, 2015 2:03:49 PM 6

QUESTIONS REPORTfor ILT 38 SRO Ver 5

7. 026AA2.03 082 Unit 1 is in MODE 3 with the following conditions:

• All RCPs are running.

• A CCW leak occurs on the 1A RCP Oil Cooler inlet connection.

Which one of the following co mpletes 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 isolatedfrom the MCR, the CCW System is (2) . (1) isolate CCW to ALL RCPs(2) INOPERABLE(1) isolate CCW to the 1A RCP ONLY (2) INOPERABLE(1) isolate CCW to ALL RCPs (2) OPERABLE(1) isolate CCW to the 1A RCP ONLY (2) OPERABLE A.B.C.D.Tuesday, June 30, 2015 2:03:49 PM 7

QUESTIONS REPORTfor 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 co mpletes the statements below?

The hydrogen concentration (1) exceed the lower FLAMMABILITY limit.Hydrogen concentration will be lowered using (2) .(1) DOES (2) SOP-10.0, POST LOCA Containment Pressurization and Vent System (1) DOES (2) Attachment 3 of EEP-1.0, Post LOCA Hydrogen Recombiner Operation (1) does NOT (2) SOP-10.0, POST LOCA Containment Pressurization and Vent System (1) does NOT (2) Attachment 3 of EEP-1.0, Post LOCA Hydrogen Recombiner Operation A.B.C.D.Tuesday, June 30, 2015 2:03:49 PM

8 QUESTIONS REPORTfor ILT 38 SRO Ver 5

9. 028AG2.1.25 084 Unit 1 is operating at 100%

when a Pressurizer level c ontrol malfunction occurs and the following conditions exist:

• Pressurizer level is 70% and rising.

• Charging flow is 120 gpm.

• Letdown is 60 gpm.

• RCP seal injection is 8 gpm to each RCP.

• RCP seal leakoff is 3 gpm per pump.

• Actions in the field are being taken to regain c ontrol of Charging.

• It will take 8 minutes to regain control of Charging.

Which one of the following co mpletes 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 automat ic Reactor Trip on Pressurizer Water Level - High is to (2) .Reference Provided (1) WILL (2) provide protection against water relief th rough the PORV's(1) WILL (2) prevent thermal shock of the Spray Nozzle (1) will NOT (2) provide protection against water relief th rough the PORV's (1) will NOT (2) prevent thermal shock of the Spray Nozzle A.B.C.D.Tuesday, June 30, 2015 2:03:49 PM

9 QUESTIONS REPORTfor 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 co mpletes the statements below?

At 1030 , an emergency classification , per NMP-EP-110, Emergency Classification Determinatio n 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) IS will NOT IS WILL is NOT will NOT is NOT WILL A.B.C.D.Tuesday, June 30, 2015 2:03:49 PM 10 QUESTIONS REPORTfor 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 bei ng 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 co mpletes the statements below?

AOP-30, Refueling Accident, (1) required to be entered.

Per the Bases of TR 13.9.4, Cra ne Travel-Spent Fuel Storage Building, the expected worst case consequences of dropping an 1800 lb. load onto the spent fuel is that the (2) .(1) IS(2) activity release will be limited to th at contained in a single fuel assembly (1) IS(2) offsite dose may be as high as but not more than the 10 CFR 100 limit(1) is NOT(2) activity release will be limited to th at contained in a single fuel assembly(1) is NOT(2) offsite dose may be as high as but not more than the 10 CFR 100 limit A.B.C.D.Tuesday, June 30, 2015 2:03:49 PM

11 QUESTIONS REPORTfor 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 occu rs 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 pu mp handswitches to START and the following occurs:

• 1D SW PUMP Handswitch - RED light LIT

• 1E SW PUMP Handsw itch - RED light LIT

• PI 3001B, SW TO CCW HX HDR PRESS, rises to 100 psig.

Which one of the following co mpletes 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) WILL B & G WILL G ONLY will NOT B & G will NOT G ONLY A.B.C.D.Tuesday, June 30, 2015 2:03:49 PM 12 QUESTIONS REPORTfor ILT 38 SRO Ver 5

13. 065AG2.4.22 088 Unit 1 is operating at 100% pow er with the following conditions:

• A rupture has occurred on the Inst rument Air header pi ping in the MSVR.

• A Reactor Trip has occurred.

• AOP-6.0, Loss of Instru ment Air, is in progress.

Which one of the following co mpletes the statements below? After the Reactor Trip , Pressurizer level will (1) due to the loss ofInstrument 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 Pl ant Startup and Operation (1)

(2) lower AOP-16.0 rise AOP-16.0 lower SOP-2.1 rise SOP-2.1 A.B.C.D.Tuesday, June 30, 2015 2:03:49 PM 13 QUESTIONS REPORTfor 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 co mpletes 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 Acciden t Monitoring Instrumentation, theREQUIRED ACTION is to (2) . Reference Provided (1) will NOT (2) immediately initiate action in accordance with S pecification 5.6.8 (1) will NOT (2) restore R-27A OR R-27B to OPERABLE status in 7 days (1) WILL (2) immediately initiate action in accordance with S pecification 5.6.8 (1) WILL (2) restore R-27A OR R-27B to OPERABLE status in 7 days A.B.C.D.Tuesday, June 30, 2015 2:03:50 PM

14 QUESTIONS REPORTfor 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 beco mes erratic causi ng its indication to become unreliable but it does not alarm.Per the ODCM, which one of t he following actions are requi red to continue the releasevia this pathway, if any?

No actions are required.

Continuously collect samples using auxiliary equipment.

Place SJAE filtration in service until R-15A is restored to operable.

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 />.

A.B.C.D.Tuesday, June 30, 2015 2:03:50 PM

15 QUESTIONS REPORTfor 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 Oper ations, which one of the follo wing requirements must bemet prior to latching control rods?

The Maintenance Supervisor is in Containment.

The Fuel Handling Supervi sor is in Containment.

The Maintenance Supervisor is in the Control Room an d in direct communication with Containment.

The Fuel Handling Supervisor is in the Control Room and in direct communication with Containment.

A.B.C.D.Tuesday, June 30, 2015 2:03:50 PM 16 QUESTIONS REPORTfor ILT 38 SRO Ver 5

17. G2.2.13 092 A tagout is required to be cleared during ni ght 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 Docu ment Holder?

Shift Manager Operations Director Maintenance Director Maintenance Manager A.B.C.D.Tuesday, June 30, 2015 2:03:50 PM 17 QUESTIONS REPORTfor ILT 38 SRO Ver 5

18. G2.2.40 093 Unit 1 is at 6% power wi th 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 ST OP 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 r epairs 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 co mpletes the statement below?

Per Tech Spec 3.7.3, Main Feedwater St op 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 1800 on January 1, 2015 2000 on January 1, 2015 1000 on January 4, 2015 1200 on January 4, 2015 A.B.C.D.Tuesday, June 30, 2015 2:03:50 PM 18 QUESTIONS REPORTfor ILT 38 SRO Ver 5

19. G2.3.12 094 A General Emergency on Un it 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.

• The expected exposure for the job is 35 REM TEDE per person.

Which one of the following co mpletes the statements below?

To receive the dose listed above, operators (1) required to be volunteers. The (2) will authorize the exposure.

(1)

(2) are NOT RP Supervisor are NOT Shift Manager ARE RP Supervisor ARE Shift Manager A.B.C.D.Tuesday, June 30, 2015 2:03:50 PM 19 QUESTIONS REPORTfor ILT 38 SRO Ver 5

20. G2.3.14 095 Unit 1 is in MODE 6 with core offload in progress wi th the following condition:

• A spent fuel assembly is being moved from its assigned location in the core to the upender.

Subsequently, AOP-30.0, Ref ueling Accident, is entered Which one of the following co mpletes 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) .(1) placed in any empty fuel location in the core(2) provide back up decay heat removal(1) placed in any empty fuel location in the core(2) retain iodine fission product activity in the water during a f uel handling accident(1) returned to its assigned location in the core(2) provide back up decay heat removal(1) returned to its assigned location in the core(2) retain iodine fission product activity in the water during a f uel handling accident A.B.C.D.Tuesday, June 30, 2015 2:03:50 PM

20 QUESTIONS REPORTfor ILT 38 SRO Ver 5

21. G2.4.30 096 Unit 2 reactor startup is in progr ess and the following conditions exist:

• NI31, SR1 COUNT RATE is 10 6 cps and stable.

• NI32, SR2 COUNT RATE is 10 4 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 co mpletes the statements below?An emergency classifica tion 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) has NOT 4 HAS 4 has NOT 1 HAS 1 A.B.C.D.Tuesday, June 30, 2015 2:03:50 PM 21 QUESTIONS REPORTfor 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 Wate

r. 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 Superviso r determines that Firewater is required to be aligned to the 1B Charging pump

.Which one of the following actions are requir ed by AOP-9.0 for these conditions, and the effect during the a lignment of firewater to the 1B charging pump?* Secure 1C CHG pump.

• RCP number 1 seal outle t temperature may rise to greater than 235°F.

• Secure 1C CHG pump.

• An evaluation must be perfor med prior to reinitiating Seal Injection or CCW to the thermal barriers.

• Maintain 1C CHG pump running.

• 1C CHG pump may be damaged.

• Maintain 1C CHG pump running.

• 1C CHG pump CCW oil cooler piping will be chemically contaminated.

A.B.C.D.Tuesday, June 30, 2015 2:03:50 PM 22 QUESTIONS REPORTfor 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 co mpletes the statement below? The next procedure the operating crew is required to transition to is

.EEP-0.0, Reactor Trip or Safety Injection ESP-1.3, Transfer to Cold Leg Recirculation EEP-1.0, Loss of Reac tor or Secondary Coolant ECP-1.1, Loss of Emergency Coolant Recirculation A.B.C.D.Tuesday, June 30, 2015 2:03:50 PM

23 QUESTIONS REPORTfor ILT 38 SRO Ver 5

24. WE05EA2.1 099 Unit 2 is performing the acti ons 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 initiat ed, but has now been secured.

• RCS pressure is 1600 psig and rising.

• Pressurizer level is 23% and rising.

Which one of the following co mpletes the statements below?The minimum SG level that permitt ed securing Bleed and Feed was at least one SG (1) .The operating crew will transition to (2) from FRP-H.1. (1) Wide Range level at 14%

(2) ESP-1.1, SI Termination(1) Wide Range level at 14%

(2) EEP-1, Loss of Reactor or Secondary Coolant (1) Narrow Range level at 33%

(2) ESP-1.1, SI Termination (1) Narrow Range level at 33%

(2) EEP-1, Loss of Reactor or Secondary Coolant A.B.C.D.Tuesday, June 30, 2015 2:03:50 PM 24 QUESTIONS REPORTfor ILT 38 SRO Ver 5

25. WE10EA2.2 100 Unit 1 is cooling down per ESP-0.2, Natura l 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 t he maximum rate al lowed by procedure.

• Pressurizer level has just r apidly risen to 78% and is stable

• RCS pressure reduction is not required.

• CST level is 9ft.

Which one of the following co mpletes 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 (1) CST Level (2) <100°F in any 60 minute period (1) CST Level(2) <50°F/hr (1) Reactor Vessel void formation being indicated (2) <100°F in any 60 minute period (1) Reactor Vessel void formation being indicated(2) <50°F/hr A.B.C.D.Tuesday, June 30, 2015 2:03:50 PM 25