ML17319A654

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09 Post Exam Analysis
ML17319A654
Person / Time
Site: South Texas  STP Nuclear Operating Company icon.png
Issue date: 10/09/2017
From: Vincent Gaddy
Operations Branch IV
To:
South Texas
References
Download: ML17319A654 (13)


Text

LOT 21 NRC EXAM ANALYSIS - 10/9/2017 Bank # RO# SRO# ANSWER A B C D Total Missed 2506 1 B 2661 2 A 2707 3 D 2651 4 B 2687 5 C 2682 6 D 1329 7 A 2712 8 A 1 1 2689 9 C 2560 10 A 2693 11 B 674 12 A 1844 13 B 1813 14 D 1 1 921 15 A 2643 16 C 1 3 4 2694 17 D 5 5 1359 18 B 2692 19 B 1113 20 C 2 2 2700 21 A 2677 22 C 2 2 516 23 B 2647 24 C 5 5 2658 25 C 2650 26 A 1 1 2729 27 A 2705 28 D 2039 29 C 2 1 3 2704 30 B 2645 31 A 3 3 2716 32 C 5 1 6 1479 33 D 1 1 2702 34 A 1 1 704 35 B 83 36 C 1 1 2666 37 C 1 1 2640 38 C 2698 39 A 870 40 D 1 2 3 790 41 A 2685 42 A 4 4 2653 43 C 4 4

LOT 21 NRC EXAM ANALYSIS - 10/9/2017 Bank # RO# SRO# ANSWER A B C D Total Missed 2659 44 C 2714 45 C 2667 46 A 2652 47 D 1 1 2642 48 B 1 1 2708 49 B 2200 50 B 1061 51 C 2091 52 B 2 2 2663 53 A 4 1 5 2561 54 B 2548 55 D 2657 56 C 1 1 2 2641 57 D 1 1 1867 58 B 1 1 2116 59 D 1 1 2696 60 D 1 1 2 2672 61 D 2644 62 A 2 2 2648 63 B 2715 64 A 1 1 2649 65 B 2646 66 D 1 1 1226 67 D 1 1 2675 68 C 1 1 2 1858 69 B 2 2 2536 70 D 2664 71 C 1 1 1101 72 C 2665 73 D 1346 74 B 2655 75 D 1 1 2668 76 A 2291 77 A 2673 78 D 2697 79 C 2686 80 D 2706 81 D 1 1 2688 82 B 2681 83 B 2711 84 A 2710 85 B 416 86 C 1 1 2577 87 C 2 2

LOT 21 NRC EXAM ANALYSIS - 10/9/2017 Bank # RO# SRO# ANSWER A B C D Total Missed 2684 88 C 1 1 2683 89 D 2679 90 B 2690 91 C 1 1 2703 92 B 2 2 2447 93 D 7 7 2717 94 A 1 1 2695 95 C 2691 96 A 1 1 2 2676 97 D 2 2 2701 98 A 1 1 2670 99 A 1 1 2709 100 B RO #17 - 5 candidates chose distracter B; (correct answer is D).

Question is based knowledge of procedures associated with Main Generator Hydrogen (H2) Gas.

The distracter chosen indicates a lack of knowledge of actions needed to be taken given the level of indicated H2 purity. Training on the annunciator procedure requirements are given in the lesson plan for Main Generator H2 Gas. LOT 202.19.

No changes to the exam are warranted.

RO #24 - 5 candidates chose distracter D; (correct answer is C).

Question is based knowledge of how the ESF DG governor is controlled when the engine receives an emergency start signal due to a loss of power to its associated BUS. The distracter chosen indicates a lack of knowledge of how generator frequency changes with an adjustment using the GOV control switch. Training on the governor controls for an ESF DG are given in the lesson plan for ESF DG. LOT 201.39.

No changes to the exam are warranted.

RO #32 - 5 candidates chose distracter A; 1 candidate chose distracter D (correct answer is C).

Question is based on operator understanding of Component Cooling Water (CCW) heat exchanger controls and their effects on CCW temperatures. The distracters chosen indicate a lack of knowledge of which CCW valve would be procedurally used to control temperature. Training on CCW heat exchanger controls and the procedure are given in the lesson plan for CCW. LOT 201.12.

No changes to the exam are warranted.

LOT 21 NRC EXAM ANALYSIS - 10/9/2017 RO #53 - 4 candidates chose distracter B; 1 candidate chose distracter C (correct answer is A).

Question is based on off-normal procedural requirements during a fuel handling accident. The distracters chosen indicate a lack of knowledge for actions to take during a shutdown condition and fuel assemblies are being off-loaded from the reactor core when a fuel handling accident occurs in containment. Training on 0POP04-FH-0001, Fuel Handling Accident, is covered in off-normal procedure training. LOT 505.

No changes to the exam are warranted.

SRO #93 - 7 candidates chose distracter B; (correct answer is D).

Question is based knowledge of Technical Specifications (TS) associated with offsite power. The distracter chosen indicates a lack of knowledge of how to apply TS 3.8.1.1 with a loss of power to one of the switchyard BUSES. (North or South BUS) Seven out of eight SRO candidates missed this question, however, a review of the lesson plan on non-class 13.8 and 4.16KV power, LOT 201.31, and the lesson on TSs, LOT 503, indicates that the knowledge needed to answer the question is being given. In addition the ESF Power Availability Surveillance, 0PSP03-EA-0002, clearly states in the notes and pre-cautions the knowledge needed to answer the question. This surveillance is covered during time on shift.

No changes to the exam are warranted.

STPEGS LOT 21 Written Exam Student Questions and Clarifications 10/9/2017 The following are clarifications given to questions on the LOT 21 Written Exam:

Question #80 The crew is performing actions of 0POP05-EO-EO10, Loss of Reactor or Secondary Coolant, with the following conditions:

  • Containment Pressure is 12 psig and slowly lowering
  • SG levels are all 50% and stable
  • Pressurizer level is 48% and slowly rising
  • RCS pressure is 1800 psig and stable
  • Subcooling is 50° and stable
  • RWST level is 125,000 gal and lowering
  • CNTMT SUMP TO SI SUCT HDR ISOL MOV-0016B has lost power.
  • CNTMT SUMP TO SI SUCT HDR ISOL MOV-0016C is danger tagged closed.

The Unit Supervisor will NEXT perform steps in A. 0POP05-EO-EC11, Loss of Emergency Coolant Recirculation.

B. 0POP05-EO-EO10, Loss of Reactor or Secondary Coolant.

C. 0POP05-EO-ES13, Transfer to Cold Leg Recirculation.

D. 0POP05-EO-ES11, SI termination.

Correct Answer D Student Question - named removed - Referring to the 2nd bullet: Narrow Range levels?

Proctor Response - Yes. Wrote the following on white board: SRO Q80 - 2nd bullet - SG NR levels Note: Question updated in exam bank.

STPEGS LOT 21 Written Exam Student Questions and Clarifications 10/9/2017 Question #83 The crew was performing actions of 0POP04-RC-0004, Steam Generator Tube Leakage, in response to a tube leak on SG A.

Subsequently;

  • The leak became larger and was approximately 250 gpm.

The crew is currently performing steps of 0POP05-EO-EO30, Steam Generator Tube Rupture.

SG A has been isolated and the RCS cooldown is in progress when the following parameters are observed:

Pressure Level Main Steamline Radiation SG A 1190 psig and lowering 44% NR and stable 1.8 E-1 and rising SG B 910 psig and lowering 22% NR and stable 9.2 E-2 and rising SG C 910 psig and lowering 17% NR and lowering 2.0 E-2 and stable SG D 910 psig and lowering 23% NR and lowering 2.0 E-2 and stable Based on these indications, the Unit Supervisor should A. stop the cooldown when the required CET temperature is reached and continue in 0POP05-EO-EO30.

B. stop the cooldown immediately and return to step 1 of 0POP05-EO-EO30.

C. transition to 0POP05-EO-EO20, Faulted Steam Generator Isolation.

D. transition to 0POP05-EO-EC31, SGTR with Loss of Reactor Coolant - Subcooled Recovery Desired.

Correct Answer B Student Question - name removed - Do I assume the same amount of AFW is going to SGs B, C, and D?

Proctor Response - Yes. Wrote the following on white board: SRO Q83 -

Assume same amount of AFW going to SG B, C, and D

STPEGS LOT 21 Written Exam Student Questions and Clarifications 10/9/2017 Question #96 The crew is performing a plant startup with the following conditions:

  • Source Range NIs are reading 9.0 x 104 counts per second.
  • Intermediate Range NIs are reading 5.0 x 10-10 amps.

Subsequently,

  • DP 1201 loses power.

Only considering the Technical Specifications required for NIs, what is the appropriate LCO statement the Unit Supervisor would enter?

A. Restore the inoperable channel to operable status prior to raising power above 10%.

B. Restore the inoperable channel to operable status prior to raising power above P-6.

C. Startup may proceed up to 75% if the inoperable channel is tripped within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

D. Suspend all operations involving positive reactivity changes immediately.

Correct Answer A Student Question - name removed - Is the snap shot taken before the trip or after?

Proctor Response - Called chief examiner to discuss. Agreed to add clarification to the stem. Informed applicant of the decision and wrote the following on white board: SRO Q96 - Prior to any Reactor Trip occurring, only considering the Technical Specifications required for NIs Note: Question updated in exam bank.

STPEGS LOT 21 Written Exam Student Questions and Clarifications 10/9/2017 The following are questions asked by students but NO clarifications were given:

Question #58 The Unit is operating at 100% power with the following conditions:

  • Pressurizer level is at 32%, trending down slowly.

In accordance with 0POP04-RC-0004, the crew should (1) letdown flow and raise charging flow to control Pressurizer level.

AND If Pressurizer level cannot be maintained greater than (2) , then the crew should trip the Reactor and initiate Safety Injection.

A. (1) lower (2) 15%

B. (1) lower (2) 17%

C. (1) isolate (2) 15%

D. (1) isolate (2) 17%

Correct Answer B Student Question - name removed - I believe there is a note in RC-0004 that allows isolation or lowering. (referring to letdown)

Proctor Response - Read as written. No clarification given.

STPEGS LOT 21 Written Exam Student Questions and Clarifications 10/9/2017 Question #60 The Unit is at 45% power with the following conditions:

  • CW Pump #14 is OOS for maintenance.
  • CW Pump #12 was tripped 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ago due to a sheared shaft.

Subsequently;

  • CW Pump #13 trips on overcurrent.

The Steam Dumps will (1) available.

AND Per 0POP04-CW-0001, the Crew will next perform actions of (2) .

A. (1) be (2) 0POP04-TM-0003, Turbine Trip Below P-9 B. (1) be (2) 0POP05-EO-EO00, Reactor Trip or Safety Injection C. (1) NOT be (2) 0POP04-TM-0003, Turbine Trip Below P-9 D. (1) NOT be (2) 0POP05-EO-EO00, Reactor Trip or Safety Injection Correct Answer D Student Question _ name removed- How many Circ Water Pumps are running?

Proctor Response - Read as written. No clarification given.

STPEGS LOT 21 Written Exam Student Questions and Clarifications 10/9/2017 Question #81 The crew is responding to a Loss of All AC Power per 0POP05-EO-EC00 with the following conditions:

  • Steps 1-7 were completed and the crew was on step 8 when power was restored to Train A AC ESF Bus.

Subsequently;

  • The crew goes to step 26 to start recovery actions.
  • SG pressures are being stabilized using SG PORVs.
  • While re-energizing the Train A Sequencer a SG PORV sticks open and cannot be closed locally.

If SG pressure lowers to the SI setpoint, the SI equipment (1) .

AND The Unit Supervisor would transition to (2) .

A. (1) will automatically start (2) 0POP05-EO-EO00, Reactor Trip or Safety Injection B. (1) will automatically start (2) 0POP05-EO-EC02, Loss of All AC Power Recovery with SI Required C. (1) must be manually started (2) 0POP05-EO-EO00, Reactor Trip or Safety Injection D. (1) must be manually started (2) 0POP05-EO-EC02, Loss of All AC Power Recovery with SI Required Correct Answer D Student Question - name removed - referring to the last bullet in stem: Was it energized?

Proctor Response - Read as written. No clarification given.