ML120880648

DC-2012-03-Examination Analysis

ML120880648
Person / Time
Site:	Diablo Canyon
Issue date:	03/09/2012
From:	Division of Reactor Safety IV
To:
References
DC-2012-03
Download: ML120880648 (8)

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TEST ITEM ANALYSIS WORKSHEET - L091 NRC Adrion Van Beurden (SR Analysis Results Charles Bowler (SRO) 1 - Poorly Written Question

% CORRECT 2 - Excessive Dificulty QUESTION QUESTION CORRECT 3 - Knowledge Weakness ANSWER 4 - Open Ref Question 5 - Poor Test Taking Skills 6 - Poor Job Validity Question 7 - Outdated/Invalid Question 50% Requires Analysis 1 D D D 100% 1 2 C C C 100% 2 3 C C C 100% 3 4 A A A 100% 4 5 A A A 100% 5 6 B B B 100% 6 7 B B B 100% 7 8 B B B 100% 8 9 B B B 100% 9 10 B A B 50% 10 SI & Spray logic w/inop channel 11 C C C 100% 11 12 B B B 100% 12 13 D D A 50% 13 CFCU oper from HSDP 14 C C D 50% 14 Spray and Phase B reset 15 B B B 100% 15 16 A A B 50% 16 MFW response to MFP trip 17 B B B 100% 17 18 D D D 100% 18 19 A D C 0% 19 3 - afw pump starts 20 C C C 100% 20 21 D D D 100% 21 22 B B B 100% 22 23 B B B 100% 23 24 D D D 100% 24 25 A A A 100% 25 26 A A A 100% 26 27 B B B 100% 27 28 D D D 100% 28 29 B B B 100% 29 30 A A A 100% 30 31 D D D 100% 31 32 A D A 50% 32 how low SFP level could drain 33 A A A 100% 33 34 B B B 100% 34 35 D D D 100% 35 36 B B B 100% 36 37 A A A 100% 37 38 B A A 0% 38 3 - when to trip CWPs-high DP 39 A A A 100% 39 40 B B B 100% 40 41 C C C 100% 41 42 D D D 100% 42 43 B B B 100% 43 44 C C A 50% 44 basis for thrttling 637/638 45 B B B 100% 45 46 A B A 50% 46 load rej w/ppc control in MAN 47 D D D 100% 47 1of3

TEST ITEM ANALYSIS WORKSHEET - L091 NRC Charles Bowler (SRO 1 - Poorly Written Question Adrion Van Beurden

% CORRECT 2 - Excessive Dificulty QUESTION QUESTION CORRECT 3 - Knowledge Weakness ANSWER 4 - Open Ref Question 5 - Poor Test Taking Skills 6 - Poor Job Validity Question 7 - Outdated/Invalid Question 50% Requires Analysis 48 B B B 100% 48 49 B C B 50% 49 Vital UPS failure 50 A A C 50% 50 EDG caution in 8A 51 C C C 100% 51 52 B B B 100% 52 53 B B B 100% 53 54 B B B 100% 54 55 D D D 100% 55 56 B B B 100% 56 57 A B A 50% 57 rod control dead band 58 C C C 100% 58 59 D D D 100% 59 60 D D D 100% 60 61 B B B 100% 61 62 B B B 100% 62 63 C C C 100% 63 64 D D A 50% 64 shutdwn equip on opp. Trains 65 C A C 50% 65 impact of fail to block MSLP SI 66 C C C 100% 66 67 D D D 100% 67 68 D D D 100% 68 69 C C C 100% 69 70 B B B 100% 70 71 A A A 100% 71 72 D D D 100% 72 73 D D D 100% 73 74 B B B 100% 74 75 D D D 100% 75 89.3% 89.3% #REF! Class Average (RO Exam) 2 Number 50% Correct (1-75) 2of3

TEST ITEM ANALYSIS WORKSHEET - L091 NRC Charles Bowler (SRO 1 - Poorly Written Question Adrion Van Beurden

% CORRECT 2 - Excessive Dificulty QUESTION QUESTION CORRECT 3 - Knowledge Weakness ANSWER 4 - Open Ref Question 5 - Poor Test Taking Skills 6 - Poor Job Validity Question 7 - Outdated/Invalid Question 50% Requires Analysis 76 D C C 0% 76 3-OP1.DC10 &EOP steps 77 D B C 0% 77 3-C.1 RCP start req. w/ht sink 78 C C B 50% 78 Ap-3 and EOP usage 79 B B B 100% 79 80 A A A 100% 80 81 A A A 100% 81 82 A A A 100% 82 83 C C C 100% 83 84 C C D 50% 84 E-0 trnsition, E-1 step 2 basis 85 B A B 50% 85 F-0 monitoring frequency 86 A A A 100% 86 87 B B B 100% 87 88 D D D 100% 88 89 A A A 100% 89 90 D A D 50% 90 ASW tech spec basis 91 C C B 50% 91 CSF priority 92 A A B 50% 92 EOP flowpath w/tube leak 93 D D D 100% 93 94 C C C 100% 94 95 D D D 100% 95 96 B D B 50% 96 OP1.DC20 seal author 97 A A A 100% 97 98 C A C 50% 98 R-2 rad values source 99 C C C 100% 99 100 D D D 100% 100 76.0% 76.0% #REF! Class Average (SRO Exam) 86.0% 86.0% 86.0% Class Ave (RO and SRO Exams) 2 Number 50% Correct (76-100) 4 Total Questions 50% Correct 3of3

All NRC Written exam questions were reviewed by the Training staff with the candidates. The following questions were missed by more than 50% of the candidates and remediated with the candidates. Any additional actions are documented at the end of the question.

19.

Unit 1 is at 18%. Motor Driven AFW pump 1-2 is out of service.

The operator trips the reactor due to loss of 12 kV bus D.

When the operator checks AFW status, steam generator narrow range levels have lowered to 58%.

Without operator action, what is the expected status of the AFW pumps and AFW flow indication?

A. None of the AFW pumps started; no AFW indicated to all four steam generators.

B. Only the Motor Driven AFW pump 1-3 started; AFW indicated to only the 1-1 and 1-2 Steam Generators.

C. The Turbine Drive AFW pump and Motor Driven AFW pump 1-3 started; max AFW indicated to all four steam generators.

D. Only the Turbine Driven AFW pumps started; max AFW indicated to all four Steam Generators.

Answer: A Missed by 100% (2 of 2)

• 1 selected answer C

• 1 selected answer D Additional action: none

38.

GIVEN:

• Unit 1 is at 70% power, ramping down at 5 MW/minute due to screen DP alarms

• The crew has entered OP AP-7, Degraded Condenser, section C, Travelling Screen Problem

• All screens are in HIGH speed in MANUAL

• Circ Water pump 11 screen DP is 80 inches and rising

• Circ Water pump 12 screen DP is 40 inches and rising Which of the following actions should be taken by the crew in accordance with OP AP-7?

A. Trip the reactor and then trip both Circ Water pumps.

B. Trip the Circ Water pump 11 and monitor pump 12 screens for increased loading due to backflow from the 11 pump.

C. Trip Circ Water pump 12 and monitor pump 11 screens for decreased loading due to backflow from the 12 pump.

D. Continue to monitor screen DP and increase the ramp rate to reduce power to less than 50%, then remove Circ Water pump 11 from service.

Answer: B.

Missed by 100% (2 of 2) 2 selected A Additional action: none.

76.

GIVEN:

• A LOCA has occurred

• The crew is performing the actions of E-1, Loss of Reactor or Secondary Coolant

• No CCW pumps are running

• The Work Control Lead is reviewing OP AP-11, Malfunction of Component Cooling Water

• All ECCS pumps and RCPs are secured due to the loss of cooling

• Core exit thermocouples are 620°F and rising Based on a recommendation from the Work Control Lead, the Shift Foreman considers directing the operator to start Charging Pump 1-3.

What action should be taken by the Shift Foreman regarding starting of the 1-3 Charging pump?

A. Do not direct the action because it is not a step in E-1.

B. Invoke 50.54x, notify the NRC and then direct the operator to start the pump.

C. Pull a step forward from E-1 forward and then direct the operator to start the 1-3 CCP.

D. Direct the operator to start the pump, this is allowed by OP1.DC10, Conduct of Operations.

Answer: D Missed by 100% (2 of 2) 2 selected C Additional action: none.

77.

GIVEN:

• The crew is performing step 19, Restore Temporary Core Cooling of FR-C.1, Response to Inadequate Core Cooling

• Core Exit Thermocouples are 1350°F and rising

• RCP seal cooling was lost to all RCPs but has been re-established

• Narrow Range Steam Generator Levels:

o 11 = 35%

o 12 = 50%

o 13 = 5%

o 14 = 0%

Per the guidance of FR-C.1, what action should the Shift Foreman take regarding starting the RCPs?

A. Wait for an evaluation of the RCP seals to be performed prior to starting any RCP.

B. Direct the operator to start either the 1-3 or the 1-4 RCP.

C. Direct the operator to start the 1-2 RCP.

D. Direct the operator to start the 1-1 RCP.

Answer: D Missed by 100% (2 of 2) 1 selected C 1 selecteed B Additional action: none