ML043170238

Initial Submital of the Written Exam for the Fermi Initial Exam September 2004

ML043170238
Person / Time
Site:	Fermi
Issue date:	11/05/2004
From:	Pederson C Division of Reactor Safety III
To:	O'Connor W Detroit Edison
References
50-341/04-301
Download: ML043170238 (124)

Text

ES-401 Record of Rejected K/As Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A ES-401 295007 High This K/A was the same as 295025 High Reactor Pressure / 3 A2.2, Tier 1/Grp 1 Reactor which was already selected. Selected 295007 A2.1 instead.

Pressure / 3 A2.2 Ability to determine and/or interpret the following as they apply to HIGH REACTOR PRESSURE :

(CFR: 41.10 /

43.5 / 45.13)

Reactor Power NUREG 1021, Draft Revision 9 28 of 34

ES-401 Written Examination Form ES-401-9 Fermi September 2004 Exam Review Worksheet

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) U/E/S Explanation Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO Focus Dist. Link units ward K/A Only 1 H 2 X x U Bank. Distractors A and B are NOT plausible that total core flow would rise when MG Set A is tripped.

RESOLUTION: Rewrote distractors A and B.

2 H 3 X x E Bank. 1) Distractor A is NOT plausible that the EDG 14 would shutdown during an emergency start condition. Suggest replacing distractor A with the same items as distractor B, except state the EDG would be in the Droop mode. 2) Add to distractor B that the EDG would be in the isochronous mode (please verify that this is correct, otherwise make the new distractor A the correct answer).

RESOLUTION: Changed both distractors as suggested.

3 F 3 x S Bank.

4 F 2 X x E New. Distractor D is NOT plausible that the generator trip is to protect against excessive pressure in the main transformer.

RESOLUTION: Rewrote distractor D.

5 H 2 x S Bank.

Instructions

[Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts.]

1. Enter the level of knowledge (LOK) of each question as either (F)undamental or (H)igher cognitive level.

2. Enter the level of difficulty (LOD) of each question using a 1 - 5 (easy - difficult) rating scale (questions in the 2 - 4 range are acceptable).

3. Check the appropriate box if a psychometric flaw is identified:

@ The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information).

@ The stem or distractors contain cues (i.e., clues, specific determiners, phrasing, length, etc).

@ The answer choices are a collection of unrelated true/false statements.

@ One or more distractors is not credible.

@ One or more distractors is (are) partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem).

4. Check the appropriate box if a job content error is identified:

@ The question is not linked to the job requirements (i.e., the question has a valid K/A but, as written, is not operational in content).

@ The question requires the recall of knowledge that is too specific for the closed reference test mode (i.e., it is not required to be known from memory).

@ The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons).

@ The question requires reverse logic or application compared to the job requirements.

5. Check questions that are sampled for conformance with the approved K/A and those that are designated SRO-only (K/A and license level mismatches are unacceptable).

6. Based on the reviewers judgment, is the question as written (U)nacceptable (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory?

7. At a minimum, explain any U ratings (e.g., how the Appendix B psychometric attributes are not being met).

Note:First 20 in RO and first 10 in SRO for initial review. However, all questions were reviewed in detail. Due to noted quality of exam material 100% received independent review.

NUREG-1021, Draft Revision 9

ES-401 2 Form ES-401-9

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO U/E/S Explanation Focus Dist. Link units ward K/A Only 6 F 2 X x E New. Distractor C is NOT plausible that control of the Main Turbine would be available from the dedicated Shutdown Panel. Also, distractor C is NOT plausible because the question stem asks about the purpose of tripping the Main Turbine and distractor C discusses control of the Main Turbine.

RESOLUTION: Rewrote distractor C.

7 H 3 x S Bank.

8 F 2 x S Bank.

9 H 2 x S Bank.

10 H 1 X x U Bank. 1) Question K/A. The K/A is related to area radiation levels during a refueling accident, but the question is related to automatic actions on high radiation levels during a refueling accident. 2) LOD =1.

3) Distractors A and B are NOT plausible that the MSIVs would close or the EDGs would start on a high radiation level in the fuel pool building.

RESOLUTION: Rewrote question and distractors to apply correct K/A.

11 F 2 x S New.

12 H 3 X X x U Bank. Depending on how bad the SRV is leaking through, there could be NO correct answer. The leak could be small and tailpipe temperature could stabilize at 100 to 200 degF This question could be classified to be at the Higher cognitive level instead of at the Fundamental level, since one needs to interpret tailpipe temperature for a leaking SRV (from the steam tables) and also determine which SRV annunciator/light would be lit The steam tables should be available as a reference to answer this question.

RESOLUTION: Steam tables will be available as a reference during the written exam. Noted pressure condition in stem & changed temp to better meet steam tables. Clarified stem of question.

13 F 2 X x E Modified. 1) Based on the information provided with the Question 13 Details on the Previous Stem, this question should be categorized as a New question instead of a Bank question. 2) Distractor D is NOT plausible that turbine control valve closure would cause the reactor scram, since the question stem states that the turbine control valves have failed open.

RESOLUTION: Rewrote distractor D. Accept as modified.

14 F 2 x S New.

ES-401 3 Form ES-401-9

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO U/E/S Explanation Focus Dist. Link units ward K/A Only 15 H 1 x U Bank. First look did not know that a table would be provided. Given the table with the instructions on how to use the table the question is a direct look up. Remove the table descriptions, i.e., notes & cautions or otherwise delete the question.

RESOLUTION: Removed the table descriptions to allow use of the table.

16 F 2 X x U New. Distractors A and B are NOT plausible that either RCIC or HPCI would automatically switch suction to the torus on low torus level.

RESOLUTION: Distractors A and B show corrected on complete exam file (dated 9/7/04).

17 H 3 x S Bank.

18 F 2 x E Bank. The Question #18 Details worksheet lists the K/A as 295037 K3.01. This should be 295037 K2.04.

RESOLUTION: Noted & corrected.

19 F 2 x S Bank.

20 F 2 x S New.

21 H 2 X x U Bank. Distractors B and C are NOT plausible that an RHR pump would autostart on an RHR system overpressure condition and the resultant signal generated.

RESOLUTION: Distractors B and C rewritten.

22 H 3 x S Bank.

23 H 2 x E Bank. This question should be classified to be at the Higher cognitive level instead of at the Fundamental level, since one needs to review two parameters (i.e., RPV level and Recirc Pumps tripped) in order to determine which RPV level instrument provides the most accurate level reading. In addition, it appears similar to question # 15 on level instrument accuracy. Is this testing the same knowledge?

RESOLUTION: Not necessarily. The table in #15 does not apply to this question. The applicant must know the calibration requirements of each instrument and how the operation of the recirc pumps affect the instruments. Question is acceptable.

24 F 2 x U Bank. Question K/A. The K/A is related to determining suppression pool temperature as it applies to High Suppression Pool Temperature, whereas the question is related to determining suppression pool temperature as it applies to Low Suppression Pool Level condition.

RESOLUTION: Question rewritten to match K/A.

ES-401 4 Form ES-401-9

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO U/E/S Explanation Focus Dist. Link units ward K/A Only 25 F 2 X x E Bank. Distractor D is NOT plausible that operation of the SGTS is to ensure the secondary containment is maintained at a positive pressure.

RESOLUTION: Distractor D rewritten.

26 H 2 X x E Bank. Distractor A is NOT plausible that the emergency intake dampers would close on a high radiation signal.

RESOLUTION: Stem and distractors rewritten.

27 F 3 x S New.

28 H 2 x S Bank.

29 F 2 x S Bank.

30 H 3 X x E Bank. Distractor D is NOT plausible that the HPCI pump would trip on high flow.

RESOLUTION: Distractor D rewritten.

31 H 2 x S New.

32 H 3 X x E Bank. In the question stem, delete mention of RPV power and just say that the rods are full in.

RESOLUTION: Added 0% on the power info with rods full in.

33 H 2 X x E Bank. To provide emphasis on what the question is, fully capitalize the word next in the question stem.

RESOLUTION: Emphasis added.

34 F 2 x S New.

35 H 2 x S New.

36 F 3 x S Bank.

37 F 3 x S Bank.

38 F 3 x S Bank.

39 H 2 X x E New. Distractor D is NOT plausible that a failure of the RCIC inverter will have NO effect on RCIC.

RESOLUTION: Distractor D rewritten.

40 H 2 x S Bank.

41 H 2 x S Bank.

ES-401 5 Form ES-401-9

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO U/E/S Explanation Focus Dist. Link units ward K/A Only 42 F 2 X x E Bank. Distractor C is NOT plausible that the SRVs selected for use would be based on average torus temperature, since torus temperature indication would NOT provide a relative location/or any other discrimination for selection of the SRVs.

RESOLUTION: Distractor C rewritten.

43 H 1 x U New. 1) LOD = 1. Can easily determine that distractors A, B, and C are NOT correct, since none of these would cause RPV level to be rising.

2) Add the word exist to the question stem: The following conditions exist .... 3) In the question stem, add the word and as follows: RPV water level is 200 inches and slowly rising.

RESOLUTION: Stem and distractors rewritten to incorporate suggested changes.

44 H 2 X X x U New. 1) Distractors B and C are NOT plausible that the FWCS would lower the speed of the Reactor Feed Pump Turbine(s) on a feed line break. 2) Suggest changing the second part of distractor B to: ... and raise the speed of both Reactor Feed Pump Turbines. 3) Suggest changing the second part of distractor C to: ... and raise the speed of the A Reactor Feed Pump Turbine. 4) In the question stem, state that all plant systems are in their normal lineup, since this would imply that both Reactor Feed Pump Turbines are in AUTO control.

RESOLUTION: Distractors B and C rewritten.

45 F 3 x S Bank.

46 H 3 x E Bank. In the question stem, delete Reactor Power and just say that all rods are fully inserted.

RESOLUTION: Decided to insert 0% for power info and all rods fully in.

47 H 2 x S New.

48 F 3 X x E Bank. 1) Distractor B is NOT plausible that the governor valves would receive power from the Reactor Protection System. 2) Typo: In distractor A, change Unterruptible to Uninterruptible.

RESOLUTION: Stem and distractors rewritten to ask response on UPS deenergization.

49 F 3 x S Bank.

ES-401 6 Form ES-401-9

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO U/E/S Explanation Focus Dist. Link units ward K/A Only 50 H 1 X x U Bank. 1) Distractor B is NOT plausible that the EDGs would NOT eventually autostart with continued increasing drywell pressure and continued decreasing Reactor water level. 2) Distractor D is NOT plausible that the loads would be stripped and NOT sequence back on without a loss of offsite power (i.e., would have NO loading of the bus if offsite power was available).

RESOLUTION: Question replaced with new question.

51 H 3 x S New.

52 H 2 X x E New. In the question stem change was to is (i.e., The plant is operating ...), so as to NOT possibly imply that the plant would then be shutdown by the inadvertent transfer of MPU-3.

RESOLUTION: Suggested change incorporated.

53 H 3 x E Bank. To ensure the applicants fully understand the question, fully capitalize the word sequence in the question stem.

RESOLUTION: Emphasis added.

54 H 1 X x U Bank. LOD = 1. Distractor A is the only plausible answer.

RESOLUTION: Replaced question with new question.

55 H 2 x S Bank.

56 F 2 x S Bank.

57 H 3 x S Bank.

58 H 3 X x E Bank. Distractor D is NOT plausible that RHR Pump A would trip during the event.

RESOLUTION: Distractor D rewritten.

59 F 2 x E Bank. Editorial: In distractor D, correct the spelling of the word maintainted.

RESOLUTION: Typo corrected.

60 F 1 X x E New. Distractor C is NOT plausible that a loss of main steam to the West MSR would result in a loss of all steam to the LP turbines and reactor scram.

RESOLUTION: Distractor C rewritten.

ES-401 7 Form ES-401-9

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO U/E/S Explanation Focus Dist. Link units ward K/A Only 61 H 2 X X x E Bank. 1) Add to question stem that all systems are in their normal lineup. 2) Distractor C in NOT plausible that RPV level would be steady following a Reactor Feed Pump trip.

RESOLUTION: Distractor C rewritten.

62 H 3 x S New.

63 H 1 X x U New. LOD = 1, since even without knowing the details concerning the logic for MSIV closure on high radiation, the applicants should know that NO single failure would prevent the RPS from functioning properly.

Thus, distractors A, B, and C are NOT plausible.

RESOLUTION: Replaced Question and K/A with new question on fire protection.

64 H 3 x S New.

65 F 3 x S Bank.

66 F 2 x S Bank.

67 H 2 X x E Bank. Distractor B is NOT plausible that one should lower B MG set speed, since B Recirc System flow is less than A Recirc System flow.

RESOLUTION: Distractor B rewritten along with only minor editorial changes.

68 F 1 x U Bank. LOD = 1, since distractor D is obviously a correct answer.

RESOLUTION: Question resplaced with new question.

69 F 2 x S Bank.

70 F 2 x E Bank. 1) In the question stem, change the last few words to ..., as the Reactor Operator you IMMEDIATELY: 2) Re-word distractor A to:

direct the refuel floor to evacuate, since the RO is in the Control Room and does NOT evacuate the refuel floor.

RESOLUTION: Suggested changes incorporated.

71 F 3 x S Bank.

72 F 3 X x E Bank. Distractor D is NOT plausible because it is a subset of distractor A (i.e., if distractor A were correct, then distractor D would also be correct).

RESOLUTION: Distractors C and D rewritten to include the word Only at the beginning of each.

73 F 3 x S New.

ES-401 8 Form ES-401-9

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO U/E/S Explanation Focus Dist. Link units ward K/A Only 74 F 2 x S New.

75 H 3 x S Bank.

76 H 3 x X E New. The correct answer (distractor C) is associated with actions required in an administrative Conduct of Operations type procedure MOP 04. This answer could be misleading, since the other 3 distractors are associated with actions in AOPs. One would expect that an AOP would be effect and the operator would be following the applicable AOP.

RESOLUTION: Distractor C rewritten and other minor editorial changes to the stem.

77 H 3 x X U Bank. This question does NOT meet any of the criteria in 10CFR55.43(b) to be classified as an SRO level question. It is more of a system knowledge (RO level) type question.

RESOLUTION: Question replaced with new question.

78 H 3 x X S New.

79 H 3 x X E Bank. Need to see the Bank question to verify that this question is modified.

RESOLUTION: Modified to bank.

80 H 2 X x X U New. 1) This question is similar to Question 13 of RO exam. Replace question. 2) Distractor D is NOT plausible that the Turbine Control Valves are part of RPS.

RESOLUTION: Question replaced.

81 H 3 x X U Bank. LOD =1, given only one curve. Give more curves and more parameters to look at.

NOTE: A curve is supplied with the question as a reference.

RESOLUTION: Question rewritten to ask for Torus water temp. and only the original curve will be provided. Required appropriate reading of temp

& press to interpret the curve. Raised level of discrimination 82 H 3 x X S New.

83 F 1 x X U New. LOD = 1, since distractor C is obviously the correct answer.

RESOLUTION: Question replaced.

ES-401 9 Form ES-401-9

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO U/E/S Explanation Focus Dist. Link units ward K/A Only 84 F 2 x X E Bank. Editorial: In the question stem, change returns to return in the sentence associated with the APRMs.

RESOLUTION: Typo corrected.

85 H 2 x X S Modified.

86 H 2 x X S Bank.

87 H 3 x X S New.

88 H 3 x X S New.

89 H 1 x X U New. LOD = 1 with the distractors provided. RESOLUTION: Stem changed to specify CS Pump A failing the surveillance. Distractors B and C rewritten.

90 F 2 x X S Bank.

91 H 3 x X S Modified.

92 F 2 X x X E Bank. 1) Distractor C is NOT plausible that the RBM would be associated with a failure to scram. Suggest deleting the words should there be a failure to scram. 2) Editorial: In distractor C, change a anticipated transient to an anticipated transient. 3) Change distractor D to state: The RBM is designed ... to be similar to the other distractors.

RESOLUTION: Distractor C rewritten. The RBM is designed ... moved to stem.

93 H 2 x X S Bank.

94 F 2 x X S Bank.

95 F 2 x X S Bank.

96 F 2 x X S Bank.

97 F 3 x X S New.

98 F 2 X x X E New. Distractor D is NOT plausible that the bases for the 22 feet of water level over irradiated fuel is to slow a dropped load before it damages fuel assemblies in the RPV. RESOLUTION: Distractor D rewritten.

99 H 2 x X S Bank.

100 H 2 x X S Modified.

ES-401 BWR Examination Outline Form ES-401-1 Facility: Fermi 2 Date of Exam: 09/13/04 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G K A A G 1 2 3 4 5 6 1 2 3 4

• Total 2

• Total

1. 1 3 4 3 4 4 2 20 N/A N/A N/A N/A N/A Emergency

& 2 0 2 2 2 1 0 7 N/A N/A N/A N/A N/A Abnormal Plant Tier Evolutions 3 6 5 6 5 2 27 N/A N/A N/A N/A N/A Totals 1 3 2 3 3 2 2 2 2 3 2 2 26 N/A N/A N/A N/A N/A 2.

Plant 2 2 0 1 2 2 1 1 1 1 1 0 12 N/A N/A N/A N/A N/A Systems Tier 5 2 4 5 4 3 3 3 4 3 2 38 N/A N/A N/A N/A N/A Totals

3. Generic Knowledge and 1 2 3 4 1 2 3 4 Abilities Categories 10 N/A 3 2 2 3 N/A N/A N/A N/A Note: 1. Ensure that at least two topics from every K/A category are sampled within each tier of the RO Outline(i.e., the Tier Totals in each K/A category shall not be less than two). Refer to Section D.1.c for additional guidance regarding SRO sampling.

2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final exam must total 75 points and the SRO-only exam must total 25 points.

3. Select topics from many systems and evolutions; avoid selecting more than two K/A topics from a given system or evolution unless they relate to plant-specific priorities.

4. Systems/evolutions within each group are identified on the associated outline.

5. The shaded areas are not applicable to the category/tier.

6.* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. The SRO K/As must also be linked to 10CFR 55.43 or an SRO-level Learning objective.

7. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings (IR) for the applicable license level, and the point totals for each system and category. Enter the group and tier totals for each category in the table above; summarize all the SRO-only knowledge and non-A2 ability categories in the columns labeled K and A. Use duplicate pages for RO and SRO-only exams.

8. For Tier 3, enter the K/A numbers, descriptions, importance ratings, and point totals on Form ES-401-3.

9. Refer to ES-401, Attachment 2 for guidance regarding the elimination of inappropriate K/A statements.

17 of 34 NUREG-1021, Draft Revision 9

ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO)

E/APE # / Name / Safety Function K K K A A G K/A Topic IR #

1 2 3 1 2 295001 Partial or Complete Loss of Forced 6 Ability to determine and/or interpret the following as 3.2 1 Core Flow Circulation / 1 & 4 they apply to PARTIAL OR COMPLETE LOSS OF

(#1) FORCED CORE FLOW CIRCULATION :

(CFR: 41.10 / 43.5 / 45.13)

Nuclear boiler instrumentation 295003 Partial or Complete Loss of AC / 6 2 Knowledge of the interrelations between PARTIAL 4.1 2

(#2) OR COMPLETE LOSS OF A.C. POWER and the following: (CFR: 41.7 / 45.8)

Emergency generators 295004 Partial or Total Loss of DC Pwr / 6 1 Knowledge of the interrelations between PARTIAL 3.1 3

(#3) OR COMPLETE LOSS OF D.C. POWER and the following: (CFR: 41.7 / 45.8)

Battery charger 295005 Main Turbine Generator Trip / 3 4 Knowledge of the reasons for the following 3.2 4

(#4) responses as they apply to MAIN TURBINE GENERATOR TRIP: (CFR: 41.5 / 45.6)

Main generator trip 295006 SCRAM / 1 4 Ability to operate and/or monitor the following as 3.1 5

(#5) they apply to SCRAM :(CFR: 41.7 / 45.6)

Recirculation system 295016 Control Room Abandonment / 7 2 Knowledge of the reasons for the following 3.7 6

(#6) responses as they apply to CONTROL ROOM ABANDONMENT : (CFR: 41.5 / 45.6)

Turbine trip 295018 Partial or Total Loss of CCW / 8 1 Knowledge of the operational implications of the 3.5 7

(#7) following concepts as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER : (CFR: 41.8 to 41.10)

Effects on component/system operations 295019 Partial or Total Loss of Inst. Air / 8

• 2.1.27 Knowledge of system purpose and or 2.8 8

(#8) function.

295021 Loss of Shutdown Cooling / 4 1 Ability to operate and/or monitor the following as 3.4 9

(#9) they apply to LOSS OF SHUTDOWN COOLING :

(CFR: 41.7 / 45.6)

Reactor water cleanup system 295023 Refueling Acc Cooling Mode / 8 1 Ability to determine and/or interpret the following as 3.2 10

(#10) they apply to REFUELING ACCIDENTS :

(CFR: 41.10 / 43.5 / 45.13)

Area radiation levels 295024 High Drywell Pressure / 5 1 Knowledge of the operational implications of the 4.1 11

(#11) following concepts as they apply to HIGH DRYWELL PRESSURE : (CFR: 41.8 to 41.10)

Drywell integrity:

295025 High Reactor Pressure / 3 3 Ability to operate and/or monitor the following as 4.4 12

(#12) they apply to HIGH REACTOR PRESSURE: (CFR:

41.7 / 45.6)

Safety/relief valves:

NUREG-1021, Draft Revision 9 18 of 34

ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO)

E/APE # / Name / Safety Function K K K A A G K/A Topic IR #

1 2 3 1 2

(#13) 2 Ability to determine and/or interpret the following as 4.2 13 they apply to HIGH REACTOR PRESSURE:

(CFR: 41.10 / 43.5 / 45.13)

Reactor power 295026 Suppression Pool High Water

• 2.4.18 Knowledge of the specific bases for EOPs. 2.7 14 Temp. / 5 (#14) (CFR: 41.10 / 45.13) 295028 High Drywell Temperature / 5 1 Knowledge of the operational implications of the 3.5 15

(#15) following concepts as they apply to HIGH DRYWELL TEMPERATURE : (CFR: 41.8 to 41.10)

Reactor water level measurement 295030 Low Suppression Pool Wtr Lvl / 5 1 Ability to determine and/or interpret the following as 4.1 16

(#16) they apply to LOW SUPPRESSION POOL WATER LEVEL : (CFR: 41.10 / 43.5 / 45.13)

Suppression pool level 295031 Reactor Low Water Level / 2 8 Knowledge of the interrelations between REACTOR 4.2 17

(#17) LOW WATER LEVEL and the following:

(CFR: 41.7 / 45.8)

Automatic depressurization system 295037 SCRAM Condition Present and 4 Knowledge of the interrelations between SCRAM 4.4 18 Power Above APRM Downscale or CONDITION PRESENT AND REACTOR POWER Unknown / 1 ABOVE APRM DOWNSCALE OR UNKNOWN and

(#18) the following: (CFR: 41.7 / 45.8)

SBLC system 295038 High Off-site Release Rate / 9 1 Knowledge of the reasons for the following 3.6 19

(#19) responses as they apply to HIGH OFF-SITE RELEASE RATE: (CFR: 41.5 / 45.6)

Implementation of site emergency plan 600000 Plant Fire On Site / 8 5 Ability to operate and / or monitor the following as 3.0 20

(#20) they apply to PLANT FIRE ON SITE:

Plant and control room ventilation systems K/A Category Totals: 3 4 3 4 4 2 Group Point Total: 20 NUREG-1021, Draft Revision 9 18 of 34

ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO)

E/APE # / Name / Safety Function K K K A A G K/A Topic IR #

1 2 3 1 2 295002 Loss of Main Condenser Vac / 3 Not randomly selected 295007 High Reactor Pressure / 3 6 Knowledge of the interrelations between HIGH 3.5 21

(#21) REACTOR PRESSURE and the following:

(CFR: 41.7 / 45.8)

PCIS/NSSSS:

295008 High Reactor Water Level / 2 4 Ability to operate and/or monitor the following as 3.5 22

(#22) they apply to HIGH REACTOR WATER LEVEL :

(CFR: 41.7 / 45.6)

HPCI 295009 Low Reactor Water Level / 2 1 Knowledge of the interrelations between LOW 3.9 23

(#23) REACTOR WATER LEVEL and the following:

(CFR: 41.7 / 45.8)

Reactor water level indication 295010 High Drywell Pressure / 5 Not randomly selected 295011 High Containment Temperature / 5 Not randomly selected 295012 High Drywell Temperature / 5 Not randomly selected 295013 High Suppression Pool Temp. / 5 1 Ability to determine and/or interpret the following as 3.8 24

(#24) they apply to HIGH SUPPRESSION POOL TEMPERATURE :

(CFR: 41.10 / 43.5 / 45.13)

Suppression pool temperature 295014 Inadvertent Reactivity Addition / 1 Not randomly selected 295015 Incomplete SCRAM / 1 Not randomly selected 295017 High Off-site Release Rate / 9 2 Knowledge of the reasons for the following 3.3 25

(#25) responses as they apply to HIGH OFF-SITE RELEASE RATE :

(CFR: 41.5 / 45.6)

Plant ventilation 295020 Inadvertent Cont. Isolation / 5 & 7 Not randomly selected 295022 Loss of CRD Pumps / 1 Not randomly selected 295029 High Suppression Pool Wtr Lvl / 5 Not randomly selected 295032 High Secondary Containment Area Not randomly selected Temperature / 5 295033 High Secondary Containment Area 8 Ability to operate and/or monitor the following as 3.6 26 Radiation Levels / 9 they apply to HIGH SECONDARY CONTAINMENT

(#26) AREA RADIATION LEVELS : (CFR: 41.7 / 45.6)

Control room ventilation:

295034 Secondary Containment Not randomly selected Ventilation High Radiation / 9 295035 Secondary Containment High Not randomly selected Differential Pressure / 5 295036 Secondary Containment High Not randomly selected Sump/Area Water Level / 5 500000 High CNTMT Hydrogen Conc. / 5 4 Knowledge of the reasons for the following 3.1 27

(#27) responses as they apply to HIGH PRIMARY CONTAINMENT HYDROGEN CONCENTRATIONS:

(CFR: 41.5 / 45.6)

Emergency depressurization K/A Category Totals: 0 2 2 2 1 0 Group Point Total: 7 NUREG-1021, Draft Revision 9 19 of 34

ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 2/Group 1 (RO)

E/APE # / Name / Safety Function K K K K K K A A A A G K/A Topic IR #

1 2 3 4 5 6 1 2 3 4 203000 RHR/LPCI: Injection Mode 1 Ability to predict and/or monitor changes in 4.2 28

(#28) parameters associated with operating the RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) controls including: (CFR: 41.5 / 45.5)

Reactor water level 205000 Shutdown Cooling 3 Knowledge of the operational implications of the 2.8 29

(#29) following concepts as they apply to SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) : (CFR: 41.5 / 45.3)

Heat removal mechanisms 206000 HPC 1 Knowledge of the effect that a loss or malfunction of 4.0 30

(#30) the HIGH PRESSURE COOLANT INJECTION SYSTEM will have on following: (CFR: 41.7 / 45.4)

Reactor water level control:

(#31) 5 Ability to monitor automatic operations of the HIGH 4.3 31 PRESSURE COOLANT INJECTION SYSTEM including: (CFR: 41.7 / 45.7)

Reactor water level:

209001 LPCS 1 Ability to (a) predict the impacts of the following on 3.4 32

(#32) the LOW PRESSURE CORE SPRAY SYSTEM ;

and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR:

41.5 / 45.6)

Pump trips01+

211000 SLC 8 Ability to manually operate and/or monitor in the 4.2 33

(#33) control room: (CFR: 41.7 / 45.5 to 45.8)

System initiation:

212000 RPS 13 Knowledge of the physical connections and/or 3.5 34

(#34) cause effect relationships between REACTOR PROTECTION SYSTEM and the following: (CFR:

41.2 to 41.9 / 45.7 to 45.8)

Containment pressure

(#35) 9 Knowledge of REACTOR PROTECTION SYSTEM 3.8 35 design feature(s) and/or interlocks which provide for the following: (CFR: 41.7)

Control rod insertion following RPS system electrical failure 215003 IRM

• 2.2.2 Ability to manipulate the console controls as 4.0 36

(#36) required to operate the facility between shutdown and designated power levels. (CFR: 45.2) 215004 Source Range Monitor 2 Knowledge of the effect that a loss or malfunction of 3.1 37

(#37) the following will have on the SOURCE RANGE MONITOR (SRH) SYSTEM : (CFR: 41.7 / 45.7) 24/48 volt D.C. power 215005 APRM / LPRM 2 Knowledge of electrical power supplies to the 2.6 38

(#38) following: (CFR: 41.7)

APRM channels NUREG-1021, Draft Revision 9 20 of 34

ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 2/Group 1 (RO)

E/APE # / Name / Safety Function K K K K K K A A A A G K/A Topic IR #

1 2 3 4 5 6 1 2 3 4 217000 RCIC 10 Ability to (a) predict the impacts of the following on 3.1 39

(#39) the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR: 41.5 / 45.6)

Turbine control system failures 218000 ADS 1 Knowledge of the operational implications of the 3.8 40

(#40) following concepts as they apply to AUTOMATIC DEPRESSURIZATION SYSTEM : (CFR: 41.5 /

45.3)

ADS logic operation 223002 PCIS/Nuclear Steam Supply 2 Ability to predict and/or monitor changes in 3.7 41 Shutoff parameters associated with operating the

(#41) PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF controls including: (CFR: 41.5 / 45.5)

Valve closures 239002 SRVs 4 Knowledge of RELIEF/SAFETY VALVES design 3.4 42

(#42) feature(s) and/or interlocks which provide for the following: (CFR: 41.7)

Ensures even distribution of heat load to suppression pool, and adequate steam condensing 259002 Reactor Water Level Control 6 Knowledge of the physical connections and/or 3.0 43

(#43) cause effect relationships between REACTOR WATER LEVEL CONTROL SYSTEM and the following: (CFR: 41.2 to 41.9 / 45.7 to 45.8)

Plant air systems

(#44) 4 Ability to monitor automatic operations of the 3.2 44 REACTOR WATER LEVEL CONTROL SYSTEM including: (CFR: 41.7 / 45.7)

Changes in reactor feedwater flow 261000 SGTS 2 Knowledge of the effect that a loss or malfunction of 3.6 45

(#45) the STANDBY GAS TREATMENT SYSTEM will have on following: (CFR: 41.7 /45.6)

Off-site release rate 262001 AC Electrical Distribution 4 Knowledge of the effect that a loss or malfunction of 3.1 46

(#46) the A.C. ELECTRICAL DISTRIBUTION will have on following: (CFR: 41.7 / 45.4)

Uninterruptible power supply

(#47)

• 2.4.11 Knowledge of abnormal condition 3.4 47 procedures. (CFR: 41.10 / 43.5 / 45.13) 262002 UPS (AC/DC) 5 Knowledge of the physical connections and/or 2.7 48

(#48) cause effect relationships between UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

Reactor/turbine pressure control system control unit:

NUREG-1021, Draft Revision 9 20 of 34

ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 2/Group 1 (RO)

E/APE # / Name / Safety Function K K K K K K A A A A G K/A Topic IR #

1 2 3 4 5 6 1 2 3 4 263000 DC Electrical Distribution 1 Knowledge of D.C. ELECTRICAL DISTRIBUTION 3.1 49

(#49) design feature(s) and/or interlocks which provide for the following: (CFR: 41.7)

Manual/ automatic transfers of control:

264000 EDGs 5 Ability to monitor automatic operations of the 3.4 50

(#50) EMERGENCY GENERATORS (DIESEL/JET) including: (CFR: 41.7 / 45.7)

Load shedding and sequencing 300000 Instrument Air 1 Knowledge of electrical power supplies to the 2.8 51

(#51) following: (CFR: 41.7)

Instrument air compressor

(#52) 7 Knowledge of the effect that a loss or malfunction of 2.5 52 the following will have on the INSTRUMENT AIR SYSTEM: (CFR: 41.7 / 45.7)

Valves 400000 Component Cooling Water 1 Ability to manually operate and / or monitor in the 3.1 53

(#53) control room: (CFR: 41.7 / 45.5 to 45.8)

CCW indications and control K/A Category Totals: 3 2 3 3 2 2 2 2 3 2 2 Group Point Total: 26 NUREG-1021, Draft Revision 9 20 of 34

ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 2/Group 2 (RO)

E/APE # / Name / Safety Function K K K K K K A A A A G K/A Topic IR #

1 2 3 4 5 6 1 2 3 4 201001 CRD Hydraulic 1 Ability to (a) predict the impacts of the following on 3.2 54

(#54) the CONTROL ROD DRIVE HYDRAULIC SYSTEM

and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations

(CFR: 41.5 / 45.6)

Pumps trips 201002 RMCS Not randomly selected 201003 Control Rod and Drive 2 Ability to manually operate and/or monitor in the 3.5 55 Mechanism control room: (CFR: 41.7 / 45.5 to 45.8)

(#55)

CRD mechanism position:

201006 RWM Not randomly selected 202001 Recirculation 12 Knowledge of the physical connections and/or 3.6 56

(#56) cause effect relationships between RECIRCULATION SYSTEM and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

Recirculation system motor-generator sets:

202002 Recirculation Flow Control Not randomly selected 204000 RWCU Not randomly selected 214000 RPIS 1 Knowledge of ROD POSITION INFORMATION 3.0 57

(#57) SYSTEM design feature(s) and/or interlocks which provide for the following: (CFR: 41.7)

Reed switch locations 215001 Traversing In-core Probe Not randomly selected 215002 RBM Not randomly selected 216000 Nuclear Boiler Inst. Not randomly selected 219000 RHR/LPCI: Torus/Pool 2 Ability to predict and/or monitor changes in 3.5 58 Cooling Mode parameters associated with operating the

(#58) RHR/LPCI: TORUS/SUPPRESSION POOL COOLING MODE controls including: (CFR: 41.5 /

45.5)

System flow 223001 Primary CTMT and Aux. Not randomly selected 226001 RHR/LPCI: CTMT Spray 6 Knowledge of the operational implications of the 2.6 59 Mode following concepts as they apply to RHR/LPCI:

(#59) CONTAINMENT SPRAY SYSTEM MODE :(CFR:

41.5 / 45.3)

Vacuum breaker operation 230000 RHR/LPCI: Torus/Pool Not randomly selected Spray Mode 233000 Fuel Pool Cooling and Not randomly selected Cleanup 234000 Fuel Handling Equipment Not randomly selected NUREG-1021, Draft Revision 9 21 of 34

ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 2/Group 2 (RO)

E/APE # / Name / Safety Function K K K K K K A A A A G K/A Topic IR #

1 2 3 4 5 6 1 2 3 4 239001 Main and Reheat Steam 5 Knowledge of the physical connections and/or 2.8 60

(#60) cause effect relationships between MAIN AND REHEAT STEAM SYSTEM and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

Moisture separator reheaters:

239003 MSIV Leakage Control Not randomly selected 241000 Reactor/Turbine Pressure Not randomly selected Regulator 245000 Main Turbine Gen. and Not randomly selected Auxiliaries 256000 Reactor Condensate Not randomly selected 259001 Reactor Feedwater 1 Knowledge of the effect that a loss or malfunction of 3.9 61

(#61) the REACTOR FEEDWATER SYSTEM will have on following: (CFR: 41.7 / 45.4)

Reactor water level 268000 Radwaste Not randomly selected 271000 Offgas 4 Knowledge of the effect that a loss or malfunction of 2.8 62

(#62) the following will have on the OFFGAS SYSTEM :

(CFR: 41.7 / 45.7)

Dilution steam 272000 Radiation Monitoring 9 Ability to monitor automatic operations of the 3.6 63

(#63) RADIATION MONITORING SYSTEM including:

(CFR: 41.7 / 45.7)

Containment isolation indications 286000 Fire Protection Not randomly selected 288000 Plant Ventilation Not randomly selected 290001 Secondary CTMT Not randomly selected 290003 Control Room HVAC 1 Knowledge of CONTROL ROOM HVAC design 3.1 64

(#64) feature(s) and/or interlocks which provide for the following: (CFR: 41.7)

System initiations/reconfiguration:

290002 Reactor Vessel Internals 3 Knowledge of the operational implications of the 2.7 65

(#65) following concepts as they apply to REACTOR VESSEL INTERNALS : (CFR: 41.5 / 45.3)

Burnable poisons K/A Category Totals: 2 0 1 2 2 1 1 1 1 1 0 Group Point Total: 12 NUREG-1021, Draft Revision 9 21 of 34

NRC EXAM 2003 RO Retake Written Exam Questions Cog Direct Mod RO # Exam Bank # Exam Level Bank Bank New 1 EQ-OP-315-0121-000-B003-001 RO 2 X 2 EQ-OP-315-0165-000-C014-002 RO 2 X 3 EQ-OP-315-0164-000-A021-001 RO 1 X 4 EQ-OP-315-0155-000-A010-001 RO 1 X 5 EQ-OP-315-0104-000-B004-003 RO 2 X 6 EQ-OP-315-0099-000-A012-001 RO 1 X 7 EQ-OP-315-0167-000-B003-002 RO 2 X 8 EQ-OP-315-0171-000-A008-001 RO 1 X 9 EQ-OP-802-2001-000-R008-003 RO 2 X 10 EQ-OP-802-2001-000-R006-004 RO 2 X 11 EQ-OP-802-3002-000-0006-033 RO 1 X 12 EQ-OP-315-0105-000-B004-001 RO 1 X 13 EQ-OP-315-0127-000-A018-005 RO 1 X 14 EQ-OP-802-2001-000-R008-003 RO 1 X 15 EQ-OP-802-3002-000-0005-006 RO 2 X 16 EQ-OP-315-0139-000-B003-002 RO 1 X 17 EQ-OP-315-0142-000-A021-003 RO 3 X 18 EQ-OP-802-3002-000-0008-011 RO 1 X 19 EQ-OP-832-0001-000-0005-004 RO 1 X 20 EQ-OP-315-0172-000-C001-001 RO 1 X 21 EQ-OP-315-0141-000-A015-001 RO 2 X 22 EQ-OP-315-0139-000-C001-001 RO 2 X 23 EQ-OP-315-0121-000-A012-001 RO 1 X 24 EQ-OP-802-3002-000-0004-022 RO 1 X 25 EQ-OP-802-3005-000-0010-0010 RO 1 X 26 EQ-OP-315-0173-000-B003-001 RO 2 X 27 EQ-OP-802-3004-000-0013-004 RO 1 X 28 EQ-OP-315-0141-000-A021-011 RO 2 X 29 EQ-OP-315-0141-000-A013-001 RO 1 X 30 EQ-OP-315-0139-000-A021-004 RO 2 X 31 EQ-OP-315-0139-000-A021-003 RO 2 X 32 EQ-OP-315-0140-000-C005-001 RO 2 X 33 EQ-OP-315-0114-000-A021-001 RO 2 X 34 EQ-OP-315-0127-000-A002-001 RO 1 X 35 EQ-OP-315-0139-000-A021-004 RO 2 X 36 EQ-OP-315-0123-000-A011-001 RO 1 X 37 EQ-OP-315-0122-000-A013-002 RO 1 X 38 EQ-OP-315-0024-000-A013-001 RO 1 X 39 EQ-OP-315-0127-000-A002-001 RO 2 X 40 EQ-OP-315-0142-000-A021-004 RO 3 X 41 EQ-OP-315-0105-000-B003-002 RO 2 X 42 EQ-OP-315-0005-000-C005-001 RO 1 X 43 EQ-OP-315-0171-000-C005-002 RO 2 X 44 EQ-OP-315-0146-000-A015-004 RO 2 X 45 EQ-OP-315-0120-000-B006-001 RO 1 X 46 EQ-OP-315-0162-000-A006-001 RO 2 X 47 EQ-OP-802-2003-000-S002-001 RO 2 X 48 EQ-OP-315-0145-000-B007-001 RO 1 X 49 EQ-OP-315-0164-000-C002-001 RO 1 X 11/01/2004 1 of 2

NRC EXAM 2003 RO Retake Written Exam Questions Cog Direct Mod RO # Exam Bank # Exam Level Bank Bank New 50 EQ-OP-315-0165-000-A021-004 RO 2 X 51 EQ-OP-315-0171-000-A014-001 RO 2 X 52 EQ-OP-315-0171-000-A016-001 RO 2 X 53 EQ-OP-315-0167-000-B003-003 RO 2 X 54 EQ-OP-802-2001-000-R003-002 RO 3 X 55 EQ-OP-315-0109-000-C011-002 RO 2 X 56 EQ-OP-315-0104-000-A013-002 RO 1 X 57 EQ-OP-315-0111-000-A013-002 RO 2 X 58 EQ-OP-315-0141-000-A021-009 RO 2 X 59 EQ-OP-315-0116-000-A021-002 RO 1 X 60 EQ-OP-315-0105-000-A021-003 RO 1 X 61 EQ-OP-315-0107-000-B007-002 RO 2 X 62 EQ-OP-315-0135-000-A021-001 RO 2 X 63 EQ-OP-315-0105-000-A021-005 RO 2 X 64 EQ-OP-315-0173-000-B001-001 RO 2 X 65 EQ-OP-315-0103-000-A007-002 RO 1 X 66 EQ-OP-213-0041-000-B001-006 RO 1 X 67 EQ-OP-315-0104-000-C011-001 RO 2 X 68 EQ-OP-315-0133-000-A001-001 RO 1 X 69 EQ-OP-802-4101-000-0022-008 RO 1 X 70 EQ-OP-315-0190-000-C005-004 RO 1 X 71 EQ-OP-802-4101-000-0022-007 RO 1 X 72 EQ-OP-508-0001-000-A013-004 RO 1 X 73 EQ-OP-802-2001-000-R009-001 RO 1 X 74 EQ-OP-802-4101-000-0028-006 RO 1 X 75 EQ-OP-802-2004-000-0001-008 RO 2 X Questions 75 Direct Bank 53 Modified Bank 0 New 22 Cognitive Level 1 49%

Cognitive Level 2 and 3 51%

11/01/2004 2 of 2

Question #1 Details EQ-OP-315-0121-000-B003-001 2004 ILO NRC Exam Question Text The plant is operating at 53% power.

Preparations have been made to transition to single loop operations.

Conditions are as follows:

A MG set speed.....30%

B MG set speed.....73%

Total Core flow...57%

Which of the following describes how total core flow indication will respond when the A MG set is tripped?

Total core flow indication will:

Response A Rise due to less backpressure on Recirc Pump B Indication will not rise. Back pressure may change but is not why the indication changes.

Response B Rise due to flow through loop A being subtracted from loop B Indication will not rise, although loop A is subtracted from loop B.

Response C - Correct Answer Lower due to flow through loop A being subtracted from loop B Reference 1 Response D Lower due to less backpressure on Recirc Pump B Indication will lower. Back pressure may change but is not why the indication changes.

Author: BOLLINGER Keywords: RRS Not Archived Date Last Used: 2004 NRC RO Question Time: 0 Question ID: 35292 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 295001 A2.06 3.2 3.3 SRO o ESP o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

ST-OP-315-0021 o INO o Static

Question #2 Details EQ-OP-315-0165-000-C014-002 2004 RO NRC Exam Question Text Emergency Diesel Generator (EDG) 14 is paralleled to EDG Bus 14EA and is loaded to 1800kW. A lightning strike causes a loss of off-site power.

Which of the following describes the EDG System response?

Response A EDG 14 output breaker will trip, EDG 14 will shut down.

Although the output breaker will trip, the EDG will not shut down.

Response B - Correct Answer EDG 14 output breaker will trip, Load Shed will occur, and then EDG 14 output breaker will reclose.

Reference:

1 Response C EDG 14 output breaker will remain closed, EDG 14 will shutdown, and then restart in isochronous mode.

The EDG will remain running, and output breaker trips. The EDG will be in isochronous, but does not restart.

Response D EDG 14 output breaker will remain closed, EDG 14 will continue running and the governor will shift to isochronous mode.

Output breaker opens, other parts are correct.

Author: BOLLINGER Keywords: 120/345 kV Not Archived Date Last Used: SWITCHYARDS EDG Time: 3 2004 NRC RO Question Question ID: 35250 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 295003 K2.02 4.1 4.2 o SRO o ESP 264000 K1.01 3.8 4.1 o STAC o Part A 264000 A2.07 3.5 3.7 o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

ST-OP-315-0065 o INO o Static

RO Question #3 Details EQ-OP-315-0164-000-A021-001 2004 ILO NRC Exam Question Text The reactor has scrammed.

A Loss of Offsite Power has occurred.

Only EDGs 13 & 14 have started and loaded.

No other operator actions have occurred.

What is the source of power to the station DC loads?

Response A Div 1 DC loads - supplied by the Div 1 Batteries Div 2 DC loads - supplied by the Div 2 Battery Chargers Battery Chargers do not get reenergized by the Load Sequencer. Div 2 EDGs starting make this choice plausible if this not known.

Response B Div 1 DC loads - supplied by the Div 2 Battery Chargers Div 2 DC loads - supplied by the Div 2 Battery Chargers Battery Chargers do not get reenergized by the Load Sequencer. Div 2 EDGs starting and not knowing the DC system lineup make this choice plausible.

Response C Div 1 DC loads - supplied by the Div 1 Battery Chargers Div 2 DC loads - supplied by the Div 2 Batteries Battery Chargers do not get reenergized by the Load Sequencer. Not knowing the DC system lineup or EDG lineup make this choice plausible.

Response D - Correct Answer Div 1 DC loads - supplied by the Div 1 Batteries Div 2 DC loads - supplied by the Div 2 Batteries Battery Chargers do not get reenergized by the Load Sequencer.

References:

1, 2, 3 Author: BOLLINGER Keywords: 2004 NRC RO Question Not Archived Date Last Used:

Time: 0 Question ID: 35295 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 295004 K2.01 3.1 3.1 o SRO o ESP o STAC o Part A

References:

o STAI o Part B ST-OP-315-0064 o LOR o Open Ref.

20.300.OFFSITE Step AP o NOC Close Ref.

20.300.OFFSITE Bases o INO o Static

RO Question #4 Details EQ-OP-315-0055-000-A010-001 2004 ILO NRC Exam Question Text While operating at 100% power, the Generator Field Breaker 41Cs on COP H11-P804 opens, causing a generator trip.

The generator trip occurred to protect against which ONE of the following?

Response A Phase to phase faults in the stator windings.

Basis for the generator differential trip, not the loss of excitation trip.

Response B Phase to ground faults in the main transformer.

Basis for transformer over excitation trip Response C - Correct Answer Excessive current in the generator rotor.

Reference 1, 2 Response D Excessive pressure in the main transformer.

Basis for transformer over pressure trip.

Author: BOLLINGER Keywords: TURBINE STEAM Not Archived Date Last Used: RPS Time: 5 2004 NRC RO Question Question ID: 35284 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 295005 K3.04 3.2 3.2 o SRO o ESP o STAC o Part A

References:

o STAI o Part B 23.118 Step 3.11 o LOR o Open Ref.

ST-OP-315-0055 o NOC Close Ref.

o INO o Static

Question #5 Details EQ-OP-315-0104-000-B004-003 2004 ILO NRC Exam Question Text Following a Reactor Scram from full power total feedwater flow is 15%. The Operator checks the speed of the Recirculation Pumps.

What should the Recirculation Pumps speed be?

Response A - Correct Answer 30%

References 1, 2 Response B 37%

Close to Limiter #2/3 Response C 40%

Limiter #2/3, doesnt meet conditions for the limiter.

Response D 75%

Limiter #4, doesnt meet conditions for the limiter.

Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 0 Question ID: 35285 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 295006 AK3.06 3.2 3.3 SRO o ESP 295006 A1.04 3.1 3.2 o STAC o Part A o STAI o Part B

References:

o LOR o Open Ref.

o NOC Close Ref.

ST-OP-315-0004 o INO o Static

Question #6 Details EQ-OP-315-0099-000-A012-001 2004 ILO NRC Exam Question Text The Control Room (CR) has become uninhabitable. As a result, the plant has entered 20.000.19, Shutdown From Outside the Control Room. In accordance with the procedure, the Main Turbine has been tripped before exiting the Control Room.

What is the purpose of tripping the Main Turbine?

Response A Prevent MSIV isolation from low pressure.

Nothing states there would be lowering pressure. Preferred if MSIVs open to maintain pressure with bypass valves.

Response B - Correct Answer Allow bypass valves to control pressure and heat rejection.

This is preferred, but SRVs can do the same. Reference ST-OP-315-0099 (1), (2), 20.000.19 Response C Allow control of the Main Turbine from the dedicated Shutdown Panel.

There is no control of the turbine from the Panel.

Response D Prevent a high RPV level trip of the Main Turbine.

The SULCV should be maintaining level if the RFP are running, nonetheless, this is not the reason.

Author: BOLLINGER Keywords: DEDICATED S/D Not Archived Date Last Used:

Time: 3 Question ID: 35445 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 295016 K3.02 3.7 3.8 SRO o ESP o STAC o Part A o STAI o Part B

References:

o LOR o Open Ref.

20.000.19 o NOC Close Ref.

ST-OP-315-0099 o INO o Static

Question #7 Details EQ-OP-315-0167-000-B003-002 2004 ILO NRC Exam Question Text With the plant operating at full power, P4400-F603B, Div 2 EECW Supply Iso Vlv has failed closed.

Which ONE of the following must be taken to ensure cooling to the CRD pumps?

Response A

- Verify auto start of Div 2 EECW and EESW pumps Not completely correct. The pumps auto start, but further actions must be taken to ensure cooling to CRD pumps.

Response B - Correct Answer

- Verify auto start of Div 2 EECW and EESW pumps

- Depress Div. 2 EECW Iso Reset Switch

- Open P4400-F604, Div 2 EECW to CRD Sply Iso Vlv Closing P4400-F603B causes an auto start of EECW/EESW.

References:

ST-OP-315-0067(1), (2)

Response C

- Close P4400-F601B, Div 2 EECW Return Iso Vlv

- Start Div. 2 EECW and EESW pumps

- Open P4400-F604, Div 2 EECW to CRD SPLY Iso Vlv F601B will auto close, Div.2 EECW and EESW auto start.

Response D

- Place Div 2 EECW Iso Override Sw keylock switch in MANUAL OVERRD

- Depress Div 2 EECW Iso reset Switch

- Open P4400-F604, Div EECW to CRD Sply Iso Vlv Placing Div 2 EECW Iso Override Sw keylock switch in MANUAL OVERRD prevents all operation of EECW and EESW.

Author: BOLLINGER Keywords: 2004 NRC RO Question Not Archived Date Last Used:

Time: 3 Question ID: 35313 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 295018 K3.07 3.1 3.2 o SRO o ESP 295018 K1.01 3.5 3.6 o STAC o Part A o STAI o Part B

References:

o LOR o Open Ref.

ST-OP-315-0067 o NOC Close Ref.

o INO o Static

Question #8 Details EQ-OP-315-0171-000-A008-001 2004 ILO NRC Exam Question Text Which one of the following describes the operation and function of P50-F402, Station Air to Instrument Air Isolation Valve, during a loss of air event?

Response A - Correct Answer Closes to isolate the safety related control air from the station air supply The P50-F402 closes when station air drops to 72psig. Reference ST-OP-315-0071 Response B Closes to separate the two divisions of NIAS, from each other, to ensure redundancy.

P50-F440 and P50-F440 close to isolate NIAS, P50-F402.

Response C Opens to crosstie the Interruptible Air Supply to allow the Station Air Compressors to supply Division 2 NIAS.

The valve does not open, P50-F403 crossties Div 2 NIAS to IAS.

Response D Opens to allow the safety related Control Air Compressors to supply each division of NIAS.

The valve does not open, P50-F440 and P50-F440 actually close to isolate NIAS.

Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 3 Question ID: 35317 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 295019 K3.03 3.2 3.2 SRO o ESP 295019 2.1.27 2.8 2.9 o STAC o Part A o STAI o Part B

References:

o LOR o Open Ref.

ST-OP-315-0071 o NOC Close Ref.

o INO o Static

Question #9 Details EQ-OP-802-2001-000-R008-003 2004 ILO NRC Exam Question Text The plant is in extended maintenance shutdown in Mode 4 when a loss of shutdown cooling occurs. Shutdown cooling cannot be immediately restored to either loop of RHR.

The North Reactor Recirc pump is running.

Which ONE of the following is an allowable option for alternate shutdown cooling under these conditions?

Response A - Correct Answer RWCU Blowdown to the Main Condenser, makeup with a SBFW pump.

Reference : 23.800.04 Page 7 Response B Maximizing FPCCU flow and RBCCW Flow to the FPCCU Heat Exchangers.

RPV is not connected with the Fuel Pool.

Response C Bleed Steam via SRVs when pressure reaches 100 psig, makeup with Core Spray.

Only done when Recirc pumps are not available.

Response D Bleed Steam via Bypass Valves when pressure reaches 50 psig, makeup with SBFW.

Not an acceptable method per procedure.

Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 3 Question ID:

Points: 1 Parent ID:

Difficulty: 2 Child ID:

KA System KA Number RO Value SRO Value RO ILO 295021 A1.01 3.4 3.4 SRO o ESP o STAC o Part A o STAI o Part B

References:

o LOR o Open Ref.

20.800.04 o NOC Close Ref.

o INO o Static

Question #10 Details EQ-OP-802-2001-000-R006-004 2004 ILO NRC Exam Question Text An irradiated fuel bundle is being removed from the core. An adjacent bundle has been lifted along with the selected bundle. When noticed, fuel movement is stopped, and the non-selected bundle falls back into the core.

Bubbles come to the pool surface, and the local Continuous Air Monitor (CAM) alarms.

The Control Room has the following alarms:

16D1, Refueling Floor High Radiation 3D41, Fuel Pool Ventilation Exhaust Rad Monitor Upscale Trip What other actions would occur?

Response A MSIVs close.

MSIVs should already be closed based on these conditions.

Response B Emergency Diesel Generators start.

Doesnt meet the conditions for emergency start.

Response C CCHVAC System shifts to PURGE mode.

CCHVAC shifts to RECIRC mode.

Response D - Correct Answer Primary Containment Purge / Vent valves close.

Fuel Pool Exhaust Rad monitor will cause a secondary containment isolation.

Reference:

1, 2 Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 0 Question ID: 35409 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 295023 A2.01 3.6 4.0 SRO o ESP o STAC o Part A o STAI o Part B

References:

o LOR o Open Ref.

ST-OP-315-0048 o NOC Close Ref.

o INO o Static

Question #11 Details EQ-OP-802-3002-000-0006-033 2004 ILO NRC Exam Question Text Drywell sprays are initiated within the safe region of the Drywell Spray Initiation Limit Curve to preclude?

Response A - Correct Answer Primary containment failure due to differential pressure.

The negative pressure capability could be challenged.

Reference:

ST-OP-802-3002 Response B Excess hydrogen generation due to atomization of cooling water.

Although the cooling water is assumed to vaporized instantly, there is no hydrogen generation.

Response C An uncontrolled rise in drywell pressure due to the flashing of steam of the drywell spray water.

There could be an uncontrolled drop in pressure vs. rise in pressure.

Response D An uncontrolled pressure drop due to the displacement of Nitrogen from the drywell to the Torus.

Although there could be an uncontrolled pressure drop due to the deinerting of the drywell, the flow path is from the torus to the drywell.

Author: BOLLINGER Keywords: 2004 NRC RO Question Not Archived Date Last Used:

Time: 3 Question ID: 35381 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 295024 K1.01 4.1 4.0 SRO o ESP o STAC o Part A o STAI o Part B

References:

o LOR o Open Ref.

ST-OP-802-3002 o NOC Close Ref.

o INO o Static

Question #12 Details EQ-OP-315-0105-000-B004-001 2004 ILO NRC Exam Question Text A pressure transient has occurred with reactor pressure exceeding the reactor scram setpoint and initiating a reactor scram.

Which of the following describes the expected indications if this transient resulted in a leaking SRV?

Response A SRV Tailpipe temperature approximately 200°F; red SRV OPEN light ON.

0 Temperature alarm limit is 225 F, SRV OPEN light ON is for the SRV pushbutton.

Response B SRV Tailpipe temperature approximately 200°F; SRV OPEN Annunciator 1D61 ON.

0 Temperature alarm limit is 225 F, SRV OPEN Annunciator 1D61 ON is correct.

Response C SRV Tailpipe temperature approximately 225°F; red SRV OPEN light ON.

Temperature alarm limit is correct, SRV OPEN light ON is for the SRV pushbutton.

Response D - Correct Answer SRV Tailpipe temperature 225°F; SRV OPEN Annunciator 1D61 ON.

Temperature alarm limit is correct, causes Annunciator 1D61.

Reference:

ST-OP-315-0005(1) (2)

Author: BOLLINGER Keywords: 2004 NRC RO Question Not Archived Date Last Used:

Time: 3 Question ID: 35335 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 295025 K1.03 3.6 3.8 SRO o ESP 295025 A1.03 4.4 4.4 o STAC o Part A o STAI o Part B

References:

o LOR o Open Ref.

ARP 1D61 o NOC Close Ref.

ST-OP-315-0005 o INO o Static

Question #13 Details EQ-OP-315-0127-000-A018-005 2004 ILO NRC Exam Question Text The plant is operating at 100% power.

A failure of the governor/pressure regulator occurs which causes the turbine control valves to fully open.

Which one of the following RPS functions will scram the reactor?

Previous Stem: A failure of the governor/pressure regulator occurs which causes the turbine control valves to slowly close without a corresponding opening of the bypass valves.

Which one of the following RPS functions will scram the reactor to limit cladding temperatures?

Response A- Correct Answer Main Steam Isolation Valve Closure Provided to limit the amount of fission product release.

Reference:

ST-OP-315-0027 Response B APRM flux - Upscale The setpoints are selected to provide adequate margin for the Safety Limits.

Reference:

Response C Low RPV water level The reactor vessel water level trip setpoint was chosen far enough below the normal operating level to avoid spurious trips but high enough above the fuel to assure that there is adequate protection for the fuel and pressure limits.

Response D Turbine Control Valve Closure The turbine control valve fast closure trip anticipates the pressure, neutron flux, and heat flux increase that could result from fast closure of the turbine control valves due to load rejection with or without coincident failure of the turbine bypass valves.

Author: BOLLINGER Keywords: RPS Not Archived Date Last Used:

Time: 3 Question ID: 35370 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 212000 2.1.27 2.8 2.9 SRO o ESP 295025 A2.02 4.2 o STAC o Part A o STAI o Part B

References:

o LOR o Open Ref.

ST-OP-315-0027 o NOC Close Ref.

o INO o Static

Question #14 Details EQ-OP-802-3002-000-0006-032 2004 ILO NRC Exam Question Text During an ATWS, boron injection must be started before torus water temperature reaches a certain limit.

What is the reason for injecting before this temperature?

Response A - Correct Answer Ensure the reactor is shutdown before exceeding the torus water temperature upper limit.

Preclude exceeding the Heat Capacity Limit, which would require emergency depressurization.

Reference:

1 Response B Prevent opening torus to drywell vacuum breakers.

Higher temperature in the torus could cause the breakers to open, but its not the reason boron is injected.

Response C Allow continued RCIC operation.

Although torus temperature can limit RCIC operation, its not the specific reason boron is injected.

Response D Ensure adequate NPSH for LPCI.

Although there is a limit for NPSH, its not related to SLC injection.

Author: BOLLINGER Keywords: EOP TWT Not Archived Date Last Used:

Time: 3 Question ID: 35371 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 295026 2.4.18 2.7 3.6 SRO o ESP o STAC o Part A

References:

o STAI o Part B 29.100.01 Sh 6 o LOR o Open Ref.

ST-OP-802-3002 o NOC o Close Ref.

o INO o Static

Question #15 Details EQ-OP-802-3002-000-0005-006 2004 ILO NRC Exam Question Text A LOCA has occurred outside of the primary containment. Plant conditions are as follows:

Reactor Building Temperature (near all instrument runs) - 220oF and stable.

Reactor Pressure - 250 psig and stable.

Drywell Temperature - 155oF and stable.

Assuming the indicated level on each of the below instruments is 163 inches, which level instrument may be used for trending indication?

Response A Flood Up o

Minimum indicated level is 190 inches between 150 and 250 F Response B Narrow Range o

Maximum RB run temperature of 103 F Response C - Correct Answer Wide Range See Reference 29.100.01 Sheet 6 Caution 3.A Response D Core Level Maximum upper range is 50 inches.

Author: BOLLINGER Keywords: 2004 NRC RO Question Not Archived Date Last Used:

Time: 0 Question ID: 35417 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 295028 K1.01 3.5 3.7 SRO o ESP o STAC o Part A o STAI o Part B

References:

o LOR o Open Ref.

29-100-01 SH 6 o NOC Close Ref.

o INO o Static

Question #16 Details EQ-OP-315-0139-000-B003-002 2004 ILO NRC Exam Question Text Due to a valving error the torus water level has decreased to the EOP entry point. What is this level, and what automatic action is expected to occur at this point?

Response A This level is + 2 inches. RCIC suction will shift to the torus.

The level is wrong and RCIC switches from the CST to the Torus based on CST level, not Torus level.

Response B This level is + 2 inches. HPCI suction will shift to the torus.

The level is wrong and HPCI switches from the CST to the Torus based on CST level, not Torus level.

Response C - Correct Answer This level is - 2.0 inches. The Torus Water Management System (TWMS) pumps will trip.

Level is correct but action is wrong.

Response D This level is - 2.0 inches. The Torus Water Management System (TWMS) torus suction valves will close.

Reference ST-OP-315-0069 (1), (2)

Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 2 Question ID: 35375 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 295030 A2.1 4.1 4.2 SRO o ESP o STAC o Part A o STAI o Part B

References:

o LOR o Open Ref.

ST-OP-315-0069 o NOC Close Ref.

7D71 o INO o Static

Question #17 Details EQ-OP-315-0142-000-A021-003 2004 ILO NRC Exam Question Text While the plant was operating in the RUN mode, a LOCA and Loss of Offsite Power occurred and the following conditions exist :

RPV water level........................................+ 76 inches (lowering 4 inches/min)

DW pressure..............................................................17.5 psig (slowly rising)

EDGs..............................No. 14 ONLY running supplying associated ESF Bus Given the above parameters and assuming no operator action involving ADS, identify which of the following describe the expected response of the ADS System.

If the low pressure ECCS Systems function as designed, ADS will begin depressurizing the plant:

Response A - Correct Answer in approximately 13 minutes.

High DW pressure and L1 after 11 minutes plus 105 minutes ~ 13 minutes.

Reference:

ST-OP-315-0042 Figure 4 Response B in approximately 20 minutes.

Could be thought correct if the 7 minute wait on RPV level less than Level 1 is mistaken.

Response C 105 seconds following EDG 11 restart.

The logic has to satisfy high DW pressure AND L1 or L1 greater than 7 minutes, then 105 sec timer, then satisfy pumps running portion of logic.

Response D 525 seconds following EDG 12 restart.

The logic has to satisfy high DW pressure AND L1 or L1 greater than 7 minutes, then 105 sec timer, then satisfy pumps running portion of logic. 7 minutes and 105 seconds = 525 seconds.

Author: BOLLINGER Keywords: ADS Not Archived Date Last Used: 2004 NRC RO Question Time: 4 Question ID: 35376 Points: 1 Parent ID: 0 Difficulty: 3 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 218000 K5.01 3.8 3.8 SRO o ESP 218000 2.1.28 3.2 3.3 o STAC o Part A 295031 K2.08 4.2 4.3 o STAI o Part B

References:

o LOR o Open Ref.

23.201 o NOC Close Ref.

LP-OP-315-0142 o INO o Static

Question #18 Details EQ-OP-802-3002-000-0008-011 2004 ILO NRC Exam Question Text The plant has experienced an ATWS and SLC has been injected.

Which of the following items is assumed in determining the Hot Shutdown Boron Weight?

Response A RPV voids are at maximum.

No voids are assumed Response B No Xenon is present in the core.

No practical for after a power change.

Response C - Correct Answer RPV water level is at the high level trip setpoint.

Reference:

ST-OP-8002-3002 Response D RWCU is in normal operation.

Would be isolated when SLC is initiated.

Author: BOLLINGER Keywords: EOP RPV Power Not Archived Date Last Used: EOP Alt Boron Inj Time: 2 ATWS Question ID: 35475 Points: 1 SLC Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 295037 K3.01 4.4 4.5 SRO o ESP o STAC o Part A o STAI o Part B

References:

o LOR o Open Ref.

o NOC Close Ref.

o INO o Static Page: 1

Question #19 Details EQ-OP-832-0001-000-0005-004 2004 ILO NRC Exam Question Text An accident has happened at Fermi 2 that causes the Shift Manager to declare an UNUSUAL EVENT.

A short time later, radiation levels at the site boundary reach 11 mr/hr, and the Shift Manager declares an ALERT.

Which ONE of the following describes what happens at an ALERT that did not happen at UNUSUAL EVENT?

Response A Radiological Emergency and Personnel Monitoring Teams are activated.

Also done at an UNUSUAL EVENT Response B Offsite Protective Action Recommendations (PARS) are calculated.

Emergency Plan provides for protection of all members of the public Response C Joint Public Information Center (JPIC) is activated.

Done at Site Area Emergency.

Response D - Correct Answer Assembly and accountability is ordered in the Protected Area.

Reference : EP-103 Page 6 Author: BOLLINGER Keywords: 2004 NRC RO Question Not Archived Date Last Used:

Time: 3 Question ID: 35394 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 295038 K3.01 3.6 4.5 SRO o ESP o STAC o Part A o STAI o Part B

References:

o LOR o Open Ref.

EP-103 o NOC Close Ref.

o INO o Static

Question #20 Details EQ-OP-315-0172-000-C001-001 2004 ILO NRC Exam Question Text A fire has occurred in the plant. A smoke damper has isolated a HVAC system due to a suppression system initiation.

What must be done to re-open the smoke damper?

The damper is....

Response A reset locally, then opened.

Actually reset from the Control Room.

Response B reset locally, opens automatically.

Actually reset from the Control Room, no automatic opening.

Response C disassembled and the fusible link replaced.

This would be correct for a fire damper, not a smoke damper.

Response D - Correct Answer reset from the Control Room, then opened.

Reference:

ST-OP-315-0072 Author: BOLLINGER Keywords: FIRE PROT/DET Not Archived Date Last Used: 2004 NRC RO Question Time: 2 Question ID: 35378 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 600000 A1.05 3.0 3.5 SRO o ESP o STAC o Part A o STAI o Part B

References:

o LOR o Open Ref.

ST-OP-315-0072 o NOC Close Ref.

o INO o Static

Question #21 Details EQ-OP-315-0141-000-A015-001 2004 ILO NRC Exam Question Text The plant is in Mode 3 with RHR Div 1 in Shutdown Cooling operation.

RHR pump A is running.

Annunciator 1D33, RHR System Overpressure, is received.

Which one of the following describes the plant response to this condition?

Response A Group 1 isolation and RHR pump A trip.

Group 1 is MSIV isolation, RHR pump A trip is correct.

Response B Group 2 isolation and RHR pump B auto start.

Group 2 is reactor water sample isolation, there is no auto start of the RHR pump on overpressure.

Response C Group 3 isolation and RHR pump B auto start.

Group 3 is an RHR isolation, there is no auto start of the RHR pump on overpressure.

Response D - Correct Answer Group 4 isolation and RHR pump A trip.

Group 4 isolation is based on overpressure, pump trips due to low suction pressure.

Reference:

ST-OP-315-0048, ST-OP-315-0041.

Author: BOLLINGER Keywords: RHR - SDC Not Archived Date Last Used: PCIS Time: 2 2004 NRC RO Question Question ID: 35379 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 295007 K2.06 3.5 3.7 SRO o ESP o STAC o Part A o STAI o Part B

References:

o LOR o Open Ref.

ST-OP-315-0041 o NOC Close Ref.

ST-OP-315-0048 o INO o Static

Question #22 Details EQ-OP-315-0139-000-C001-001 2004 ILO NRC Exam Question Text HPCI and RCIC have automatically started following a loss of feedwater.

RPV level increases to 220 inches, and a short time later HPCI turbine speed is 0 RPM.

As RPV level begins to decrease below 160 inches the CRS directs HPCI to be restarted.

What action is taken to restart HPCI?

Response A Open E4150-F001 turbine steam supply isolation valve.

The trip logic is automatically reset at Level 2, wont be able to open this valve.

Response B Open E4150-F003 HPCI steam supply outboard isolation valve.

The trip logic is automatically reset at Level 2, wont be able to open this valve.

Response C Depress the HPCI initiation signal reset pushbutton and start the aux oil pump.

There is no initiation signal present, so resetting will have no effect.

Response D - Correct Answer Depress the reactor high water level signal reset pushbutton.

The trip logic is automatically reset at Level 2, to restart before Level 2, the trip signal must be reset.

Reference:

ST-OP-315-0039, 23.202 page 35.

Author: BOLLINGER Keywords: HPCI Not Archived Date Last Used: 2004 NRC RO Question Time: 0 Question ID: 35380 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 295008 A1.04 3.5 3.5 SRO o ESP o STAC o Part A o STAI o Part B

References:

o LOR o Open Ref.

23.202 o NOC Close Ref.

ST-OP-315-0039 o INO o Static

Question #23 Details EQ-OP-315-0121-000-A012-001 2004 ILO NRC Exam Question Text A plant transient has occurred. Plant conditions are :

Mode 3 RPV level is 170" RPV pressure is 950 psig.

Recirc Pumps A & B have tripped.

Which RPV level instrument would provide the most accurate level reading at this time based on its calibration conditions?

Response A Narrow Range Calibrated for best indication with jet pumps running.

Response B - Correct Answer Wide Range

Reference:

ST-OP-315-0021 Response C Floodup o

Calibrated for 0 Psig, 120 F, with no jet flow.

Response D Core Level Outside the calibrated level band of 150 to 50 inches.

Author: BOLLINGER Keywords: RPV INST Not Archived Date Last Used:

Time: 0 Question ID: 35453 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 295009 K2.01 3.9 4.0 SRO o ESP o STAC o Part A o STAI o Part B References o LOR o Open Ref.

ST-OP-315-0021 o NOC Close Ref.

o INO o Static

Question #24 Details EQ-OP-802-3002-000-0004-022 2004 ILO NRC Exam Question Text During a lowering torus water level event, what is the significance of torus water level dropping below -11"?

Response A Below -11" torus water level, operation of LPCI, CS, HPCI, or RCIC must be evaluated due to exceeding pump NPSH or vortex limits.

HPCI and RCIC do not have vortex limits, LPCI and CS vortex limits are about -90 inches.

Response B Below -11" torus water level, torus water temperatures must be obtained from the T23-R800, Suppression Chamber Bulk Water Temperature recorder, on the H11-P601 panel.

All of the thermocouples providing input to this recorder are uncovered and will indicate air temperature at this level.

Response C - Correct Answer Below -11" torus water level, torus water temperatures must be obtained from the T50-R800A/B, Primary Containment Air and Water Temperature recorders, on the H11-P601 / P602 panels.

Reference:

ST-OP-802-3002 Response D Below -11" torus water level, the Primary Containment Control EOPs (Sheet 2) must be entered.

EOPs are entered at -2 inches, not -11 inches.

Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 3 Question ID: 35385 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 295013 A2.01 3.8 4.0 SRO o ESP o STAC o Part A o STAI o Part B

References:

o LOR o Open Ref.

ST-OP-802-3002 o NOC Close Ref.

o INO o Static

Question #25 Details EQ-OP-802-3005-000-0010-0010 2004 ILO NRC Exam Question Text The first override statement in the Secondary Containment EOP states that if RB HVAC or fuel pool vent exhaust radiation levels exceeds certain limits, then the operator shall confirm isolation of RB HVAC and initiation of SGTS.

Which of the following best describes why the above must be confirmed or manually initiated?

Response A Confirming isolation of RBHVAC subsequent to receipt of a high radiation signal terminates any further release of radioactivity to the Reactor Building from this system.

RBHVAC actually exhausts air from the Reactor Building, not the other way around.

Response B - Correct Answer SGTS is the normal mechanism employed under post-transient conditions to maintain Reactor Building Pressure negative with respect to the atmosphere.

Reference:

ST-OP-8002-3005 Response C Exhaust from SGTS is processed and directed to an elevated release point before being discharged to the Reactor Building.

Exhaust from the SGTS is discharged to atmosphere.

Response D Operation of SGTS will ensure that the Secondary Containment is maintained at a positive pressure.

SGTS designed to maintain negative pressure in the Reactor Building.

Author: BOLLINGER Keywords: Archived Date Last Used:

Time: 3 Question ID: 28725 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 295017 K3.02 3.3 3.5 SRO o ESP o STAC o Part A o STAI o Part B

References:

o LOR o Open Ref.

ST-OP-802-3005 o NOC Close Ref.

o INO o Static

Question #26 Details EQ-OP-315-0173-000-B003-001 2004 ILO NRC Exam Question Text The plant is operating at 100% power when the following alarms occur:

3D32, Div I/II RB Vent Exh Radn Monitor Upscale 3D36, Div I/II RB Vent Exh Radn Monitor Upscale Trip How should the Control Center Heating, Ventilation and Air Conditioning (CCHVAC)

System Respond?

Response A The Emergency Intake Control dampers close.

Emergency dampers open.

Response B - Correct Answer The Normal Intake and Exhaust Dampers close.

Reference ST-OP-315-0027 Response C The Return Dampers close and the Recirculation Filter Train starts.

Return fans stay open, but the filter train starts.

Response D The Return fans start drawing air through the Emergency Make-up filter.

The fans in the emergency makeup filter train draw air through the filter.

Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 5 Question ID: 35387 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 295033 A1.08 3.6 3.8 SRO o ESP o STAC o Part A o STAI o Part B

References:

o LOR o Open Ref.

LP-OP-315-0173 o NOC Close Ref.

3D36 o INO o Static

Question #27 Details EQ-OP-802-3004-000-0013-004 2004 ILO NRC Exam Question Text The plant has experienced a transient that requires emergency depressurization due to high drywell hydrogen and oxygen levels.

Why would the crew perform this emergency depressurization?

Response A - Correct Answer Burning of these gasses may damage equipment important to the safe shutdown of the plant.

Reference:

ST-OP-802-3002 Response B Hydrogen and oxygen concentrations can be prevented from exceeding explosive limits.

The ED happens at explosive limits, so the limits have been exceeded.

Response C Hydrogen and oxygen concentrations are outside the limits for safe operation of the recombiners.

Although this is true for the recombiners, its not true for the reason for ED.

Response D Spraying the drywell is ineffective at these levels of hydrogen and oxygen.

Spraying is not ineffective, has nothing to do with ED.

Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 0 Question ID: 35224 Points: 1 Parent ID: 34091 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 500000 K3.04 3.1 3.9 SRO o ESP o STAC o Part A o STAI o Part B

References:

o LOR o Open Ref.

ST-OP-802-3002 o NOC Close Ref.

o INO o Static

Question #28 Details EQ-OP-315-0141-000-A021-011 2004 ILO NRC Exam Question Text The plant has experienced a LOCA with the following conditions:

EDG................................................13 not running RPV Level1.....................................25 inches RPV Pressure..................................425 psig Drywell Pressure..............................2.5 psig Torus Water Temperature................128°F A Reactor Recirc MG set.................tripped B Reactor Recirc MG set.................tripped B3105-F031A, Recirc Loop A discharge isolation valve, is shut.

What is the current status of the RHR system?

Response A RHR pumps A, C & D are running, injecting into Loop A No injection until about 300 psig, theres been no LOOP, so EDG 13 not running doesnt matter.

Response B All RHR pumps are running, injecting into Loop A All pumps are running, but no injection because of the RPV pressure.

Response C RHR pumps A, C & D are running and not injecting All pumps are running, since theres been no LOOP Response D - Correct Answer All RHR pumps are running and not injecting

Reference:

ST-OP-315-0041 Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 3 Question ID: 35443 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 203000 A1.01 4.2 4.3 SRO o ESP o STAC o Part A

References:

o STAI o Part B o LOR o Open Ref.

ST-OP-315-0041 o NOC Close Ref.

o INO o Static

Question #29 Details EQ-OP-315-0141-000-A013-001 2004 RO NRC Exam Question Text The General Operating Procedure for reactor shutdown and cooldown directs the operator to raise RPV water level to above 220" prior to entering Shutdown Cooling (SDC).

What is the reason for raising water level above the normal level?

Response A Ensures adequate NPSH for RHR pumps.

Incorrect because NPSH for RHR pumps is a function of Torus Temp and RPV level.

Response B Satisfies the interlock required for opening RHR SDC valves.

Incorrect because RHR SDC valve interlock is >L3.

Response C Provides additional inventory for RHR system warmup in preparation for SDC.

Incorrect because 220 has nothing to do with inventory for piping warmup Response D - Correct Answer Provides adequate natural circulation to minimize temperature stratification during SDC.

Reference:

22.000.04 Reactor shutdown procedure, page 37, ST-OP-315-0141 Author: CADDEN Keywords: RHR - SDC Not Archived Date Last Used: 10/23/2000 2004 NRC RO Question Time: 3 Question ID: 35386 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 295009 K1.05 3.3 3.4 SRO o ESP 205000 K5.03 2.8 3.1 o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

22.000.04 Reactor shutdown procedure, page 37 o INO o Static ST-OP-315-0141

Question #30 Details EQ-OP-315-0139-000-A021-004 2004 ILO NRC Exam Question Text During an AUTOMATIC initiation of HPCI, the HPCI Pump flow is 5200 GPM. Five minutes later the E4150-F012 Pump Min Flow Valve fails open.

The HPCI system will respond by:

Response A - Correct Answer Raising HPCI turbine speed.

Reference:

ST-OP-315-0039 Response B Lowering HPCI turbine speed.

The HPCI controller is attempting to maintain 5200 gpm going to the RPV, so speed will not be lowered.

Response C Indicated HPCI flow rising above 5200 GPM.

Indicated flow will stay at 5200 gpm, since the controller senses flow going to the vessel.

Response D Tripping HPCI at a flow in excess of 5200 GPM.

There is no high flow trip of HPCI.

Author: BOLLINGER Keywords: HPCI Not Archived Date Last Used:

Time: 2 Question ID: 30766 Points: 1 Parent ID: 29955 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 206000 K3.01 4.0 4.0 SRO o ESP o STAC o Part A o STAI o Part B

References:

o LOR o Open Ref.

ST-OP-315-0039 o NOC Close Ref.

o INO o Static

Question #31 Details EQ-OP-315-0139-000-A021-003 2004 RO NRC Exam Question Text High Pressure Coolant Injection (HPCI) has automatically initiated with the following indications:

Reactor water level.............................................+40" on WR level instrument HPCI Barometric condenser condensate pump.....................................running HPCI Barometric condenser vacuum pump..........................................running HPCI Auxiliary Oil pump................................................................not running HPCI flow......................................................................................5,000 gpm RPV level subsequently drops to +20 inches on WR level indication. How should HPCI respond?

Response A HPCI auxiliary oil pump will auto start Incorrect because the aux oil pump is not required while HPCI is at rated speed Response B HPCI flow will increase to 5,200 gpm Incorrect because the flow controller has not been changed Response C - Correct Answer HPCI Barometric condenser condensate pump will trip

Reference:

ST-OP-315-0039 Response D HPCI will continue to operate in it's current configuration Incorrect because the barometric condenser condensate and vacuum pumps trip at 31 RPV level Author: CADDEN Keywords: HPCI Not Archived Date Last Used: LOCA Time: 2 2004 NRC RO Question Question ID: 35384 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 206000 K5.02 2.8 2.9 SRO o ESP 206000 A3.05 4.3 4.3 o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

ST-OP-315-0039 o INO o Static

Question #32 Details EQ-OP-315-0140-000-C005-001 2004 RO NRC Exam Question Text During operation at 100% power a LOCA occurs and the following conditions exist :

RPV power............................................... ...rods full in RPV pressure......................................... .......100 psig RPV water level....................+ 25 inches (slowly rising)

RHR System..................both divisions injecting to RPV Core Spray System........both divisions injecting to RPV An electrical fault in Core Spray Pump B motor windings causes the pump breaker to trip on overcurrent relays.

Given the above conditions, identify which one of the following actions are required by the operating crew.

Response A Throttle closed E2150-F005A to avoid pump runout on pump A.

Incorrect because no Division one pumps tripped Response B - Correct Answer Throttle closed E2150-F005B to avoid pump runout on pump D.

Reference:

23.203, precautions and limitations Response C Throttle open E2150-F005A to maintain division one flow >3175 gpm.

Incorrect because Division one flow should not have changed Response D Throttle open E2150-F005B to maintain division two flow >3175 gpm.

Incorrect because Division two flow can not achieve >3175gpm with only one pump Author: CADDEN Keywords: CSS Not Archived Date Last Used: 2004 NRC RO Question Time: 2 Question ID: 35383 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 209001 A2.01 3.4 3.4 SRO o ESP o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

23.203, precautions and limitations o INO o Static ST-OP-3115-0140

Question #33 Details EQ-OP-315-0114-000-A021-001 2004 ILO NRC Exam Question Text SLC injection becomes necessary. The Operator places the initiation switch to PUMP A and the following occurs:

Squib continuity lights go out.

SLC Ignition Continuity Loss annunciator alarms.

SLC Pump A fails to start.

The operator places the initiation switch to PUMP B and SLC Pump B starts. Which one of the following actions should be taken next?

Response A Attempt to start SLC Pump A a second time.

If the B pump is running, ther is no need to start the A pump.

Response B Direct an Operator to isolate SLC Pump A.

There is no need to isolate the pump if Pump B is running with no indication of a leak.

Response C Determine if the B explosive valve fired.

The only indication is the loss of continuity, then other indications such as power, tank level.

Response D - Correct Answer Check for indications of SLC flow to the RPV.

Reference ST-OP-315-0014 (1), (2)

Author: BOLLINGER Keywords: SLC Not Archived Date Last Used:

Time: 2 Question ID: 35465 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 211000 A1.02 3.8 3.9 SRO o ESP 211000 A4.08 4.2 4.2 o STAC o Part A o STAI o Part B

References:

o LOR o Open Ref.

ST-OP-315-0014 o NOC Close Ref.

o INO o Static

Question #34 Details EQ-OP-315-0127-000-A002-001 2004 RO NRC Exam Question Text Which one of the following statements describes the basis for automatic scrams associated with High Containment Pressure?

Response A to limit the fission product release from the fuel into containment Incorrect because this is the basis for the Hi Main Steam Line Radiation Scram Response B to counteract the pressure increase by rapidly reducing core power Incorrect because this is the basis for the Hi RPV Pressure Scram Response C to anticipate the rise in containment pressure and prevent exceeding the containment design pressure Incorrect because the Hi DW pressure scram is not based on containment pressure limits Response D - Correct Answer to minimize the possibility of fuel damage and to reduce the amount of energy being added to the coolant and the containment

Reference:

ST-OP-315-0127 Author: CADDEN Keywords: RPS Not Archived Date Last Used: CONTAINMENT Time: 2 2004 NRC RO Question Question ID: 35382 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 212000 K1.13 3.5 3.6 SRO o ESP o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

ST-OP-315-0127 o INO o Static

Question #35 Details EQ-OP-315-0127-000-A018-006 2004 RO NRC Exam Question Text The plant was operating at 65% power when RPS Motor Generator Set "A" tripped.

Shortly after, a plant transient caused RPV level to drop to 165".

How will the RPS system respond to this event?

Response A - Correct Answer Full Reactor Scram

Reference:

ST-OP-315-0027(1), (2)

Response B Half Scram on RPS A Incorrect because RPS will get 1/2 Scram on A due to loss of power, and a full scram when level goes <L3.

Response C Half Scram RPS B Incorrect because RPS will get 1/2 Scram on A due to loss of power, and a full scram when level goes <L3.

Response D No SCRAM will occur Incorrect because RPS will get 1/2 Scram on A due to loss of power, and a full scram when level goes <L3.

Author: CADDEN Keywords: RPS Not Archived Date Last Used: 2004 NRC RO Question Time: 0 Question ID: 35374 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 212000 K4.09 3.8 3.9 SRO o ESP o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

ST-OP-315-0027 o INO o Static

Question #36 Details EQ-OP-315-0123-000-A011-001 2004 RO NRC Exam Question Text The RETRACT PERMIT light for IRM G is NOT lit. Which of the following describes the effect on IRM G?

Response A IRM will NOT retract.

Incorrect because the IRM will retract Response B - Correct Answer The IRM can be retracted. Retracting it will cause a Rod Block.

Reference:

ST-OP-315-0023 Response C The IRM can be retracted ONLY if IRM G is on Range 1. Retracting it will cause a Rod Block Incorrect because the IRM will retract on all ranges Response D The IRM can be retracted ONLY if IRM G is on Range 1. Retracting it will NOT cause a Rod Block.

Incorrect because the IRM will retract on all ranges and will cause a rod block Author: CADDEN Keywords: IRM Not Archived Date Last Used: 2004 NRC RO Question Time: 0 Question ID: 35372 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 215003 K4.05 2.9 3.0 SRO o ESP Generic 2.2.2 4.0 3.5 o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

ST-OP-315-0023 o INO o Static

Question #37 Details EQ-OP-315-0122-000-A013-002 2004 RO NRC Exam Question Text The plant was operating at 60% power when a loss of 24/48 VDC power occurred? How will this loss impact the plant?

Response A Main Turbine Trip Incorrect because MT trip logic powered from BOP battery Response B Loss of HPCI logic Incorrect because HPCI logic powered from ESF battery Response C - Correct Answer Loss of SRMs and IRMs

Reference:

ST-OP-315-0022 Response D Loss of Feedwater Level Control Incorrect because FW Level Control powered from UPS A Author: CADDEN Keywords: DC ELEC Not Archived Date Last Used: 2004 NRC RO Question Time: 3 SRM Question ID: 35369 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 215004 K6.02 3.1 3.3 SRO o ESP o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

ST-OP-315-0064 o INO o Static ST-OP-315-0022

Question #38 Details EQ-OP-315-0024-000-A013-001 2004 RO NRC Exam Question Text The power supply for the APRMs is which one of the following?

Response A H11-P908A & B, 120 VAC instrument and control power.

Response B R3100S009A & B (UPS) Circuit 9.

Response C 2PA-1 and 2PB-1 via static inverters.

Response D - Correct Answer C71-P001A & B via QLVPS.

Reference:

ST OP-315-0024-001 (Table 2, PRNM Power Supplies)

This is a power supply question. The distractors are just wrong.

Author: BOLLINGER Keywords: PRNM Not Archived Date Last Used: APRM/OPRM Time: 2 Question ID: 33478 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 215005 K2.02 2.6 2.8 o SRO o ESP o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

ST OP-315-0024-001 (Table 2, PRNM Power Supplies) o INO o Static

Question #39 with Details EQ-OP-315-0143-000-A016-001 2004 RO NRC Exam Question Text The plant experienced a LOCA. RCIC is running and discharging to the RPV when 1D60, RCIC INVERTER FAILURE, alarms.

Which one of the following would describe (1) the impact on RCIC and (2) what actions should be taken?

Response A

1) Loss of indication on E51-R613, RCIC Pump Flow Indicator.

2) Manually control discharge flow using E51-F013, RCIC Pump Inboard Isolation Valve.

Incorrect because the correct action is to trip RCIC per ARP 1D60 Response B

1) Loss of indication on E51-K615, RCIC Discharge Flow Controller.

2) Manually control discharge flow using E51-F045, RCIC Turbine Steam Inlet Valve.

Incorrect because the correct action is to trip RCIC per ARP 1D60 Response C - Correct Answer

1) Loss of indication on E51-K615, RCIC Discharge Flow Controller.

2) Manually trip the RCIC turbine and supply the RPV with an alternate source.

Reference:

1D60 Response D

1) No impact.

2) Monitor RPV level.

Incorrect because there will be loss of indications and power to the flow controller Author: BOLLINGER Keywords: RCIC Not Archived Date Last Used: _RO retake 2001 Time: 2 Question ID: 35389 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 217000 A2.10 3.1 3.1 o SRO o ESP o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

ST-OP-315-0043 o INO o Static 1D60

Question #40 Details EQ-OP-315-0142-000-A021-004 2004 RO NRC Exam Question Text A LOCA concurrent with a loss of offsite power has occurred and the following conditions exist :

RPV water level..................................42 inches (slowly lowering)

RPV pressure.................................................................670 psig Drywell pressure.................................................2.5 psig (rising)

EDGs 11 and 12..................................................... failed to start EDGs 13 and 14......................................tripped (will not restart)

Given the above conditions and assuming no ADS related operator actions are taken, how will the ADS system respond?

When the RPV water level drops below RPV Level-1, the 105-second timer will:

Response A Start, time out, then ADS will initiate.

Incorrect because the system does not meet the Low Pressure ECCS pump running permissive Response B - Correct Answer Start and time out but ADS will not initiate.

Correct because it will start due to the Hi DW and L1 signals, but not initiate because the low-pressure ECCS pump permissive will not be met (ADS Logic)

Response C NOT start and ADS will NOT initiate.

Incorrect because it will start based on L1 and Hi DW signals Response D Start after the 7 minute timer times out, then ADS will initiate.

Incorrect because the system does not meet the Low Pressure ECCS pump running permissive Author: BOLLINGER Keywords: ADS Not Archived Date Last Used: 2 _RO retake 2001 Time: 3 Question ID: 34823 Points: 1 Parent ID: 0 Difficulty: 3 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 218000 K5.01 3.8 3.8 o SRO o ESP 218000 K3.02 4.5 4.6 o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC o Close Ref.

ST-OP-315-0042 o INO o Static

Question #41 details EQ-OP-315-0105-000-B003-002 2004 RO NRC Exam Question Text How are open MSIVs affected when NSSS Isolation logic channels B and D trip, assuming logic channels A and C are NOT tripped?

Response A Inboard MSIVs, F022A-D close Response B All MSIVs close Response C Outboard MSIVs, F028A-D close Response D - Correct Answer All MSIVs remain open

Reference:

23.601, Enclosure G The justification for this answer is that MSIV isolation logic requires a one out two, taken twice logic to actuate. Since only division 2 logic is tripped, no isolation signal will be sent. The logic is half cocked.

Author: BOLLINGER Keywords: NUC BLR Not Archived Date Last Used:

Time: 3 Question ID: 25517 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 223002 A1.02 3.7 3.7 o SRO o ESP o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

ST-OP-315-0005-001 o INO o Static 23.601

Question #42 Details EQ-OP-315-0005-000-C005-001 Question Text When controlling pressure using SRVs, it is expected SRVs for use will be selected based on the:

Response A SRV pressure setpoint Incorrect because only SRVs A and G have pressure control setpoints, otherwise they have safety pressure limits Response B - Correct Answer SRV position on the matrix

Reference:

23.201, Precautions and Limitations Response C indicated average torus temperature Incorrect because you can not determine torus water temperature at the discharge of the individual SRVs Response D Main Steam Line to which they are attached Incorrect because it does not matter where the steam comes from.

Author: BOLLINGER Keywords: SRVs Not Archived Date Last Used:

Time: 1 Question ID: 30075 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 239002 K4.04 3.4 3.6 o SRO o ESP o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

23.201, Precautions and Limitations o INO o Static

Question #43 Details EQ-OP-315-0171-000-C005-002 2004 RO NRC Exam Question Text The following conditions during a plant startup :

Reactor power is 15%

RPV water level is 200 inches slowly rising The following annunciators are in alarm:

7D54 Interruptible Control Air Header Pressure Low 7D55 Interruptible Control Air Isolation Valve Closed 7D69 Station Air Compressor Auto Start Based on the above conditions, what has happened and how is the plant responding?

Response A Loss of Div II NIAS which has caused the Reactor Feed Pump Minimum Flow Valves to start opening.

Incorrect because the indications do not show Div II NIAS as being lost Response B Loss of Div I NIAS which has caused the Reactor Feed Pump Seal Water Valves to start closing.

Incorrect because the indications do not show Div I NIAS as being lost Response C Loss of Station Air which has caused the Reactor Feed Pump Discharge Valves to start closing.

Incorrect because the indications do not show Station Air as being lost (Station Air hdr press low)

Response D - Correct Answer Loss of IAS which has caused the Startup Level Control Valve to start opening.

Reference:

ST-OP-315-0071, 20.129.01, Page 2 Author: CADDEN Keywords: COMPRESSED AIR Not Archived Date Last Used: 8/7/2000 2004 NRC RO Question Time: 0 Question ID: 35363 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 259002 K1.06 3.0 3.1 SRO o ESP o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

ST-OP-315-0071 o INO o Static 20.129.01, Page 2

Question #44 Details EQ-OP-315-0146-000-A015-004 2004 ILO NRC Exam Question Text The plant is operating at 100% power with the Feedwater Control System (FWCS) in 3 element control.

Which ONE of the following describes the response of the FWCS to a feed line rupture in the A feedwater line?

FWCS will....

Response A - Correct Answer shift to single element control and raise the speed of both Reactor Feed Pump Turbines.

Digital Control System will sense a greater that 0.5 mlbm/hr difference and shift to single element.

Because RPV level is going down, FWCS will attempt to raise the speed of the pumps.

Response B stay in 3 element control and lower the speed of the A Reactor Feed Pump Turbine.

Digital Control System will sense a greater that 0.5 mlbm/hr difference and shift to single element.

Because RPV level is going down, FWCS will attempt to raise the speed of both pumps.

Response C shift to single element control and lower the speed of both Reactor Feed Pump Turbines.

Digital Control System will sense a greater that 0.5 mlbm/hr difference and shift to single element.

Because RPV level is going down, FWCS will attempt to raise, not lower, the speed of the pumps.

Response D stay in 3 element control and raise the speed of the A Reactor Feed Pump Turbine.

Digital Control System will sense a greater that 0.5 mlbm/hr difference and shift to single element.

Because RPV level is going down, FWCS will attempt to raise the speed of both pumps.

Author: BOLLINGER Keywords: FEEDWATER CTRL Not Archived Date Last Used: FEEDWATER Time: 3 Question ID: 35441 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 259002 K6.05 3.5 3.5 o SRO o ESP 259002 A3.04 3.2 3.2 o STAC o Part A o STAI o Part B

References:

o LOR o Open Ref.

ST-OP-315-0064 o NOC Close Ref.

o INO o Static

Question #45 Details EQ-OP-315-0120-000-B006-001 2004 RO NRC Exam Question Text Following a Loss of Coolant Accident, the Standby Gas Treatment System has been in service for several hours venting the drywell and torus IAW 29.ESP.07, Primary Containment Venting. Chemistry reports that stack release rates have begun to rise.

Which of the following situations could explain the rise in release rates?

Response A SGTS total flow decrease to 2500 scfm Incorrect because less flow would not, by itself, cause release rates to rise.

Response B After Heater air temperature increase to 200°F Incorrect because the After Heater range is from 150-225°F.

Response C - Correct Answer Charcoal Adsorber temperature increase to 290°F.

Reference:

ST-OP-315-0020 Response D Moisture Separator differential pressure decrease to 0.4 inches water.

Incorrect because the Moisture Separator range is from 0-1 inches of water.

Author: CADDEN Keywords: SGTS Not Archived Date Last Used: 2004 NRC RO Question Time: 3 Question ID: 35362 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 261000 K1.07 3.1 3.2 SRO o ESP 261000 K3,02 3.6 3.9 o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

ST-OP-315-0020 o INO o Static

Question #46 Details EQ-OP-315-0162-000-A006-001 2004 RO NRC Exam Question Text While the reactor was operating in the RUN mode a loss of offsite power occurred and the following conditions now exist:

Reactor power................................................all rods fully inserted EDGs 11, 12 & 13...........................................failed to initiate EDG 14............................................operating and carrying its ESF Bus 480V AC Bus 72R..........................................energized What is the current status of the UPS system?

Response A Loads on Unit B are supplied from the UPS battery though the Inverter.

Incorrect because Loads are not being supplied from the battery Response B - Correct Answer Loads on Unit A are supplied from the Unit B Rectifier through the Unit A Inverter.

Reference:

ST-OP-315-0062-001(1), (2), Figure 2 Response C Loads on Unit A are supplied from its Alternate Source through the Static Transfer Switch.

Incorrect because Loads are not being supplied from the Alternate source Response D Loads on Unit B are supplied from its Alternate Source through the Static Transfer Switch.

Incorrect because Unit B Loads are being supplied from the Normal source Author: CADDEN Keywords: UPS Not Archived Date Last Used: 9/3/1997 2004 NRC RO Question Time: 1 Question ID: 35359 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 262002 K4.02 3.1 3.4 SRO o ESP 262001 K3.04 3.1 3.4 o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

ST-OP-315-0062-001, Figure 2 o INO o Static

Question #47 Details EQ-OP-802-2003-000-S002-001 2004 RO NRC Exam Question Text The plant was operating at 25% power when Bus 65G was lost due to an electrical fault.

What action(s) is/are the Operating Crew required by AOP to perform immediately:

Response A - Correct Answer Place the Reactor Mode Switch to SHUTDOWN.

Reference:

20.138.01, Rev. 35 (Immediate Actions)

Response B Verify there are no thermal hydraulic instability oscillations.

Incorrect because the Immediate Action is to place the mode switch in S/D due to loss of both Recirc Pumps Response C Insert the Cram control rods and monitor for reactor core thermal hydraulic instabilities.

Incorrect because the Immediate Action is to place the mode switch in S/D due to loss of both Recirc Pumps Response D Raise reactor water level to raise natural circulation rate and commence inserting control rods.

Incorrect because the Immediate Action is to place the mode switch in S/D due to loss of both Recirc Pumps Author: CADDEN Keywords: AOP Not Archived Date Last Used: RRS Time: 1 2004 NRC RO Question Question ID: 35360 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO Generic 2.4.11 3.4 3.6 SRO o ESP Generic 2.4.49 4.0 4.0 o STAC o Part A o STAI o Part B o LOR o Open Ref.

o NOC Close Ref o INO o Static

References:

20.138.01, Rev. 35 (Immediate Actions)

Question #48 with Details EQ-OP-315-0145-000-B007-001 2004 RO NRC Exam Question Text Where do the Governor Control Cubicles in the H11-P633 Panel receive their power from?

Response A - Correct Answer Unterruptible Power Supply

Reference:

ST-OP-315-0062 Response B Reactor Protection System Incorrect Response C 120VAC Instrument & Control Incorrect Response D DC Distribution Incorrect Author: CADDEN Keywords: AOP Not Archived Date Last Used: RRS Time: 1 2004 NRC RO Question Question ID: 35360 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 262002 K1.05 2.7 o SRO o ESP o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

ST-OP-315-0062 o INO o Static

Question #49 Details EQ-OP-315-0164-000-C002-001 2004 ILO NRC Exam Question Text What is the impact of a Loss of Division II ESF 130V/260V Battery on bus 72CF?

Response A Bus 72 CF will deenergize 72CF is an AC bus. It will not deenergize.

Response B There will be NO impact on bus 72CF 72CF will lose automatic throwover capability.

Response C - Correct Answer Automatic throwover capability for 72CF will be lost

Reference:

AOP 20.300.260ESF, Page 6 Response D Bus 72CF will automatically transfer to its alternate power supply Automatic throwover capability for 72CF will be lost Author: CADDEN Keywords: DC ELEC Not Archived Date Last Used: 2004 NRC RO Question Time: 3 Question ID: 35345 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO G2.4.11 3.4 3.6 SRO o ESP 263000 K4.01 3.1 3.4 o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

AOP 20.300.260ESF o INO o Static

Question #50 Details EQ-OP-315-0165-000-A021-004 2004 ILO NRC Exam Question Text The following conditions exist:

Reactor power.........................................98%

Drywell Pressure.....................................1.1 psig, raising slowly Reactor water level..................................185 inches, lowering slowly All other systems are functioning as designed.

If the pressure and level trends continue, what can the operator expect to happen to the Emergency Diesel Generators (EDG), and what action should be taken?

Response A EDG will auto start, EDG output breaker will close, and loads will be sequenced onto the EDG.

Dispatch operator to verify proper operation of the EDG.

Loads wont sequence without a loss of power Response B EDG will not auto start.

Dispatch operator to start the EDG.

EDG will auto start.

Response C - Correct Answer EDG will auto start.

Run the EDG loaded for at least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> before stopping.

Reference:

ST-OP-315-0065, 23.307 Precaution 3.7 Response D EDG auto starts, load sequencer strips loads.

Dispatch operator to verify proper operation of the EDG.

Loads wont sequence without a loss of power Author: BOLLINGER Keywords: EDG Not Archived Date Last Used:

Time: 3 Question ID: 34766 Points: 1 Parent ID: 0 Cognitive Level: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 264000 A3.05 3.4 3.5 SRO ¨ ESP

References:

¨ STAC ¨ Part A ST-OP-315-0065 ¨ STAI ¨ Part B 23.307 ¨ LOR ¨ Open Ref.

¨ NOC Close Ref.

¨ INO ¨ Static

Question #51 with Details EQ-OP-315-0171-000-A014-001 2004 RO NRC Exam Question Text The plant is operating at 100% power with the following auxiliary equipment lineup:

West Station Air Compressor running; Center in AUTO South Reactor Feedwater Pump Turbine East Lube Oil Pump running; West in AUTO North Reactor Feedwater Pump Turbine West Lube Oil Pump running; East in AUTO North Main Turbine Lube Oil Pump running; South in AUTO South and Center TBCCW pumps running Bus 64A is lost due to an internal electrical fault. What is your response to this event?

Response A Perform a rapid power reduction Incorrect because Loss of 64A says put the mode switch in Shutdown Response B Start both SBFW pumps and inject at 1200 gpm Incorrect because the RFPT Emergency LO Pumps are sufficient to supply the RFPTs, therefore RFPs will not trip.

Response C Verify the North TBCCW pump has started automatically Incorrect because 64A is the power supply to N. TBCCW pump Response D - Correct Answer Verify the Center Station Air Compressor has automatically started

Reference:

ST-OP-315-0171-001, 20.300.64A Page 5 Author: CADDEN Keywords: 4160/480 ELEC Not Archived Date Last Used: COMPRESSED AIR Time: 5 2004 NRC RO Question Question ID: 35341 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 300000 K2.01 2.8 2.8 SRO o ESP o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

20.300.64A o INO o Static ST-OP-315-0171-001

Question #52 with Details EQ-OP-315-0171-000-A016-001 2004 RO NRC Exam Question Text The plant was operating at 85% power when maintenance activities resulted in an inadvertent transfer of MPU-3. Which of the following is the expected plant response with no operator action?

Response A - Correct Answer Outboard MSIVs will go shut

Reference:

20.129.01 Page 2 and 8 Response B TBCCW TCV will remain in its current position Incorrect because the valve will fail OPEN Response C Condensate Polishing Demineralizers effluent valves will go full open Incorrect because the valve is supplied by Station Air Response D LP Hood Spray pressure and temperature control valves will go shut Incorrect because the valves will fail OPEN Author: CADDEN Keywords: COMPRESSED AIR Not Archived Date Last Used: 2004 NRC RO Question Time: 2 Question ID: 35340 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 300000 K6.07 2.5 2.6 SRO o ESP o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

o INO o Static 20.129.01 Page 2 and 8

Question #53 Details EQ-OP-315-0167-000-B003-003 2004 RO NRC Exam Question Text Concerning the RBCCW/EECW System, which ONE of the following describes the sequence of events that will occur when there is a Loss of Off-Site Power (LOP)?

Response A - Correct Answer White Emergency Mode Light comes on, EDG Output Breakers close, Supply and Return Header Isolation Valves close, EECW Pumps start.

Reference:

ST-OP-315-0067-001, (2)

Response B RBCCW Pumps trip, EDG Output Breakers close, EECW Make-Up Tank Isolation Valves close, EECW Pumps start.

Incorrect because the EECW Make-up tank isolation valve OPENS Response C White Emergency Mode Light comes on, EECW Make-Up Tank Isolation Valves open, EDG Output Breakers close, EECW Pumps start.

Incorrect because the EDG output breakers close before the make-up tank isolation opens Response D RBCCW Pumps trip, Supply and Return Header Isolation Valves close, EDG Output Breakers close, EECW Pumps start.

Incorrect because the EDG output breakers close before the Supply and Return Isolation valves close Author: CADDEN Keywords: RBCCW/EECW Not Archived Date Last Used:

Time: 3 Question ID: 34534 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 400000 A4.01 3.1 3.0 o SRO o ESP o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

ST-OP-315-0067-001 o INO o Static

Question #54 Details EQ-OP-802-2001-000-R003-002 2004 RO NRC Exam Question Text The reactor is operating at 100% power when the following conditions exist :

Annunciator 3D5, CRD Charging H20 Pressure Low........................activated Annunciator 3D10, CRD Accumulator Trouble.................................activated E41-R609, HPCI Pump Suction Pressure Indicator............................20 psig C11-PDIS-N002, CRD Drive Water Filter Differential Pressure............0 psig C11-R603, Cooling Water to reactor Differential Pressure Indicator.....0 psid C11-R800, CRD Hydraulic Flow Ind..................................................1 gpm Which of the following is the reason annunciators 3D5 and 3D10 are activated?

Response A - Correct Answer The operating CRD pump has tripped.

Reference:

ST-OP-315-0010-001 Response B The in-service CRD flow control valve has failed closed.

Incorrect because the flow control valves have a mechanical block to allow 15 gpm flow when they are shut, therefore flow could not be 1 gpm.

Response C C11-F034, Charging Header Isolation Valve, has been closed.

Incorrect because the drive water filters is upstream of this valve, therefore the Drive water filter D/P can not be 0 if it is shut.

Response D C11-F003, CRD Drive/Cooling Water PCV, has been closed.

Incorrect because the drive water connection is upstream of this valve, therefore the Drive water filter D/P can not be 0 if it is shut.

Author: CADDEN Keywords: CRDH Archived Date Last Used: AOP Time: 3 LOR 00-04 Question ID: 32645 Points: 1 Parent ID: 30789 Difficulty: 3 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 201001 A2.01 3.2 3.3 o SRO o ESP o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

20.106.01 o INO o Static ST-OP-315-0010-001

Question #55 Details EQ-OP-315-0109-000-C011-002 2004 RO NRC Exam Question Text During a plant startup, Control Rod 26-35 was withdrawn to position 48. During the coupling check:

Position indication was lost 3D76 CONTROL ROD OVERTRAVEL alarmed 3D80 CONTROL ROD DRIFT alarmed (1) What is the status of Control Rod 26-35 and (2) what procedure should the Control Room Staff enter and execute?

Response A (1) stuck (2) AOP 20.106.05 STUCK CONTROL ROD Incorrect because these are indications of an uncoupled control rod Response B (1) uncoupled (2) AOP 20.106.1 CRD HYDRAULIC SYSTEM FAILURE.

Incorrect because the crew should enter 20.106.02 Response C - Correct Answer (1) uncoupled (2) AOP 20.106.02 UNCOUPLED/DROPPED CONTROL ROD (FROM REACTOR CORE)

Reference:

20.106.02, page 7 Response D (1) stuck (2) SOP 23.106 CONTROL ROD DRIVE HYDRAULIC SYSTEM, difficult rod movement section.

Incorrect because these are indications of an uncoupled control rod Author: CADDEN Keywords: CRDM Not Archived Date Last Used: 2004 NRC RO Question Time: 2 Question ID: 35339 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 201003 A2.02 3.7 3.8 SRO o ESP 201003 A4.02 3.5 3.5 o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

20.106.02, page 7 o INO o Static

Question #56 Details EQ-OP-315-0104-000-A013-002 2004 RO NRC Exam Question Text The "A" Reactor Recirc Pump has been given a signal to increase speed. What is occurring in the fluid drive coupling?

The scoop tube positioner is changing position to _________ the amount of oil in the working circuit of the coupler thus _________ the coupling between the Reactor Recirc Motor and Generator.

Response A reduce, reducing Incorrect because this will be the case when lower speed is desired Response B reduce, increasing Incorrect because less oil in the working speed will lower the coupling Response C increase, reducing Incorrect because increasing the amount of oil will increase the coupling Response D - Correct Answer increase, increasing

Reference:

ST-OP-315-0004-001 Author: PRE-EXISTING Keywords: RRS Not Archived Date Last Used: 3/16/2001 Time: 2 Question ID: 33031 Points: 1 Parent ID: 25453 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 202001 K1.12 3.6 3.6 o SRO o ESP o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

ST-OP-315-0004-001 o INO o Static

Question #57 with Details EQ-OP-315-0111-000-A013-002 2004 RO NRC Exam Question Text A reactor startup is in progress with the following conditions:

Rod Select Power Switch........................................ON Select button for rod 26-31......................................ON 3D80, Control Rod Drift...........................................ON What is the cause of the Control Rod Drift Alarm?

Rod 26-31 at position..

Response A - Correct Answer 35 with the Rod Control Movement Switch in OFF

Reference:

ST-OP-315-011 Response B 35 with the Rod Control Movement Switch in OUT NOTCH Incorrect because RMCS still thinks the rod is moving Response C 34 with the Rod Control Movement Switch in OFF there will be no rod drift if the rod settles on an even position Response D 34 with the Rod Control Movement Switch in OUT NOTCH Incorrect because RMCS still thinks the rod is moving and there will be no rod drift if the rod settles on an even position Author: BOLLINGER Keywords: Not Archived Date Last Used:

Time: 0 Question ID: 35393 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 214000 K4.01 3.0 3.1 o SRO o ESP o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

ST-OP-315-011 o INO o Static

Question #58 Details EQ-OP-315-0141-000-A021-009 2004 RO NRC Exam Question Text Division 1 of RHR was operating in torus cooling mode with "A" RHR pump in service to support an upcoming HPCI surveillance. The plant experienced a seismic event, which resulted in a failure to SCRAM and a LOCA. The following conditions exist:

RPV Level................................-2" on Core Level Reactor Power.............................0%

RPV Pressure..............................650 psig Drywell Pressure........................ 12 psig Torus Pressure.............................10.2 psig (1) How would RHR respond to this event, and (2) What minimum operator action is necessary to realign RHR Pump "A" back to torus cooling?

Response A (1) Division 1 RHR will continue to operate in Torus Cooling.

(2) No action required.

Incorrect because RHR Torus cooling will isolate on Hi Drywell Pressure and L1 Response B (1) E11-F024A, Div 1 RHR Torus Clg Iso.and E11-F028A, Div 1 RHR Torus Iso Vlv. will automatically close.

(2) Place Containment Spray Mode Select switch in MANUAL, and reopen the E11-F024A and E11-F028A valves.

Incorrect because must use 2/3 Core Height Override due to Level <0 Response C - Correct Answer (1) E11-F024A, Div 1 RHR Torus Clg Iso. and E11-F028A, Div 1 RHR Torus Iso Vlv. will automatically close.

(2) Place Containment Spray Mode Select switch in MANUAL and Containment Spray 2/3 Core Height Override keylock switch in MANUAL OVERRIDE and reopen the E11-F024A and E11-F028A valves.

Reference:

ST-OP-315-0041(1). (2); 23.205, page 103 Response D (1) E11-F024A, Div 1 RHR Torus Clg Iso.and E11-F028A, Div 1 RHR Torus Iso Vlv. will automatically close and RHR pump "A" will trip.

(2) Place Containment Spray Mode Select switch in MANUAL, restart RHR Pump "A" and reopen the E11-F024A and E11-F028A valves.

Incorrect because RHR Pump A will not trip.

Author: CADDEN Keywords: RHR - TOR CLNG Not Archived Date Last Used: RHR - LPCI Time: 5 RHR - GENERAL Question ID: 35338 Points: 1 2004 NRC RO Question Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 219000 A4.06 3.9 3.7 SRO o ESP 219000 A1.02 3.5 3.5 o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

23.205, page 103 o INO o Static ST-OP-315-0041

Question #59 Details EQ-OP-315-0116-000-A021-002 2004 RO NRC Exam Question Text During a Design Bases Loss of Coolant Accident the Drywell Spray Mode of RHR is initiated. How will the Containment System respond?

Response A - Correct Answer Suppression Chamber to Drywell Vacuum Breakers will open to ensure Drywell to Torus d/p is maintained within limits.

Reference:

ST-OP-315-0016(1), (2)

Response B Suppression Chamber to Drywell Vacuum Breakers will open to ensure Drywell pressure is maintainted lower than Torus pressure.

The vacuum breakers prevent damage to the containment from d/p. DW pressure is usually higher than torus pressure.

Response C Reactor Building to Suppression Chamber Vacuum Breakers will open to ensure Reactor Building to Torus d/p is maintained within limits.

The RB Vacuum breakers are for inadvertent initiation of Torus Sprays.

Response D Reactor Building to Suppression Chamber Vacuum Breakers will open to ensure Torus pressure is maintained higher Reactor Building Pressure.

Right reason, but wrong cause. RB Vacuum breakers not for DW sprays after a DBA LOCA.

Author: CADDEN Keywords: CONTAINMENT Not Archived Date Last Used:

Time: 3 Question ID: 35337 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 226001 A1.01 3.6 3.8 SRO o ESP 226001 K5.06 2.6 2.8 o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

ST-OP-315-0016 o INO o Static

Question #60 Details EQ-OP-315-0105-000-A021-003 2004 RO NRC Exam Question Text The plant was operating at 85% power when Main Steam was lost to the West Moisture Separator Reheater. Which of the following describes the effect of this loss?

Loss of Main Steam to the Moisture Separator Reheater would cause the:

Response A HP Turbine to experience a significant increase in windage losses and become less efficient The HP turbine is upstream of the MSR, therefore there is no effect.

Response B - Correct Answer LP Turbines to experience more damage to the first stage blading and to become less efficient

Reference:

ST-OP-315-0005 Response C LP Turbines to lose all their steam flow and scram the Rx on closure of the LP Stop and Intercept valves The LP turbines will not lose all of their steam flow and the Rx will not scram.

Response D HP Turbine to pick up more load and therefore the thrust on the HP Turbine would be above its Maximum Normal Range.

The HP turbine is upstream of the MSR, therefore there is no effect.

Author: CADDEN Keywords: NUC BLR Not Archived Date Last Used: 2004 NRC RO Question Time: 0 Question ID: 35336 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 239001 K1.05 2.8 2.8 SRO o ESP o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

ST-OP-315-0005 o INO o Static

Question #61 Details EQ-OP-315-0107-000-B007-002 2004 RO NRC Exam Question Text The plant was operating at 100% power when the South RFP tripped.

Which of the following describes the expected plant response?

(Assume no operator action).

Response A - Correct Answer RPV level - Lowers, then stabilizes Recirc speed - Lowers Rx Power - Lowers

Reference:

ST-OP-315-007 Response B RPV level - Lowers Recirc speed - Lowers Rx Power - 0% (SCRAM)

Incorrect because the Reactor will not SCRAM on Level 3 Response C RPV level - Steady Recirc speed - Raises Rx Power - Steady Incorrect because the Level will go down and the Recirc pumps will run back on limiter #4 Response D RPV level - Lowers, then stabilizes Recirc speed - Steady Rx Power - Lowers Incorrect because Recirc pumps will run back on limiter #4 Author: CADDEN Keywords: RX FEEDWATER Not Archived Date Last Used:

Time: 3 Question ID: 35334 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 259001 K3.01 3.9 3.9 SRO o ESP o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

ST-OP-315-007 o INO o Static

Question #62 Details EQ-OP-315-0135-000-A021-001 2004 RO NRC Exam Question Text The plant is operating at 75% power. The Dilution Steam controller for the operating off-gas train fails and admits 100% dilution steam to the 18" manifold.

Select from below the expected off-gas system response:

Response A Total off-gas flow will decrease Incorrect because total off gas flow will increase due to increased steam supply Response B Hydrogen concentration will increase Incorrect because hydrogen concentration will decrease due to increased steam supply (recombining of O2/H2 into water vapor)

Response C Off-gas after cooler temperature will increase Incorrect because after cooler will decrease due to lowered recombiner outlet temperature Response D - Correct Answer Thermal recombiner outlet temperature will decrease

Reference:

ST-OP-315-0035-001 Author: CADDEN Keywords: OFF GAS Not Archived Date Last Used:

Time: 2 Question ID: 35333 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 271000 K6.04 2.8 2.8 SRO o ESP o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

ST-OP-315-0035-001 o INO o Static

Question #63 with Details EQ-OP-315-0105-000-A021-005 2004 RO NRC Exam Question Text The 'A' Main Steam Line Rad Monitor has failed downscale.

A gross fuel failure occurs at 85% power. All other Main Steam Line rad monitors detect the fuel failure and trip.

How do the MSIVs and RPS respond?

Response A Inboard MSIVs close Half Scram Incorrect because MSIVs will go closed and a full scram will be initiated Response B Outboard MSIVs close Half Scram Incorrect because MSIVs will go closed and a full scram will be initiated Response C MSIVs remain open Full Scram Incorrect because MSIVs will go closed Response D - Correct Answer All MSIVs close Full Scram

Reference:

ST-OP-315-0005-001, 23.601 (page 46) (Correct because logic says 1 out of 2 taken twice)

Author: CADDEN Keywords: NUC BLR Not Archived Date Last Used: 2004 NRC RO Question Time: 0 Question ID: 35419 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 272000 A3.09 3.6 3.5 o SRO o ESP o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

ST-OP-315-0005-001 o INO o Static

Question #64 Details EQ-OP-315-0173-000-B001-001 2004 RO NRC Exam Question Text Division I CCHVAC was operating in Purge mode due to a fire in the Relay Room. Annunciator 3D35, DIV I/II FP VENT EXH RADN MONITOR UPSCALE TRIP, alarms due to high radiation in the Fuel Pool exhaust. What will happen to the CCHVAC configuration?

Div I CCHVAC will:

Response A continue to operate in Purge mode.

Incorrect because recirculation mode overrides all other modes.

Response B - Correct Answer transfer from Purge mode to Recirculation mode.

Reference:

ST-OP-315-0073-001 (1), (2), ARP 3D35 Response C trip and will have to be started manually in Recirculation mode.

Incorrect because CCHVAC will automatically shift to recirculation mode Response D trip and Div II CCHVAC will start and operate in Recirculation mode.

Incorrect because CCHVAC will automatically shift to recirculation mode Author: CADDEN Keywords: CCHVAC Not Archived Date Last Used: 2004 NRC RO Question Time: 0 Question ID: 35326 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 290003 K4.01 3.1 3.2 SRO o ESP o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

ST-OP-315-0073-001 o INO o Static ARP 3D35

Question #65 Details EQ-OP-315-0103-000-A007-002 2004 RO NRC Exam Question Text Which of the following are two advantages of loading burnable poisons into the fuel?

Response A Radial power shaping and allow lower power fuel bundles to be used.

Incorrect because water rods help with radial power shaping. Reference Response B Longer control rod life and smoother reactivity control.

Incorrect. This is a description of using a control cell core Reference Response C - Correct Answer Longer fuel cycles and axial power shaping.

Reference:

ST-OP-315-0003-001 Response D Wider margin to thermal limits and allow lower power fuel bundles to be used.

Incorrect. This is a description of using a ring of fire. Reference Author: CADDEN Keywords: CORE & FUEL Not Archived Date Last Used: 2004 NRC RO Question Time: 0 Question ID: 35324 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 234000 G2.1.28 3.2 3.3 SRO o ESP 290002 K5.03 2.7 3.0 o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

ST-OP-315-0003 o INO o Static

Question #66 Details EQ-OP-213-0041-000-B001-006 2004 RO NRC Exam Question Text In accordance with MOP09, "Locked Valve", a ____________________ padlock should be used on a locked closed position valve.

Response A Red Incorrect because red is open Response B Green Incorrect because green is not used for padlock locked valves Response C red with black dot Incorrect because red with black dot is throttled Response D - Correct Answer no color identification

Reference:

MOP09, section 3.8 Author: BOLLINGER Keywords: ADMIN Archived Date Last Used:

Time: 2 Question ID: 32576 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO Generic 2.1.1 3.7 3.8 o SRO o ESP o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

MOP09 o INO o Static

Question #67 Details EQ-OP-315-0104-000-C011-001 2004 RO NRC Exam Question Text The plant was operating at 95% power when the following indications were observed:

Generator megawatt output - 1095MWe, lowering slowly Reactor power - 88%, lowering slowly RPV level - 197 inches, steady RPV pressure - 1015 psig, lowering slowly Total core flow lowered and stabilized at 83 Mlbm/hr A Recirc System: B Recirc System:

recirc loop flow - 55000 gpm recirc loop flow - 40000 gpm jet pump loop flow - 22 Mlbm/hr jet pump loop flow - 61 Mlbm/hr Based on the given conditions what action should be taken?

Response A Place the mode switch in shutdown and enter 20.000.21 Reactor Scram Incorrect because indications are of a jet pump failure. You would commence a plant shutdown, not scram.

Response B Lower 'B' MG set speed to match recirc flows Incorrect because these are the actions for uncontrolled recirc flow change.

Response C Enter 20.138.03, Uncontrolled Recirc Flow Change Incorrect because there is no indication that RRS MG speed has changed.

Response D - Correct Answer Enter 20.138.02, Jet Pump Failure

Reference:

20.138.02, page 5 Author: DOUCET Keywords: RRS Not Archived Date Last Used: 8/27/2002 _RO retake 2001 Time: 2 Question ID: 34691 Points: 1 Parent ID: 33560 Difficulty: 3 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO generic 2.1.7 3.7 4.4 o SRO o ESP o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

ST-OP-315-0004-001 o INO o Static 20.138.02

Question #68 Details EQ-OP-315-0133-000-A001-001 2004 RO NRC Exam Question Text Which one of the following describes the purpose of the Circulating Water system?

Response A Deaerates the water in the Cooling Towers.

Incorrect because deaeration is not a function of Circ Water.

Response B Transfers heat to the atmosphere via the CW Reservoir.

Incorrect because transfers heat via the cooling towers.

Response C Heats the water in the cooling towers to prevent marine growth.

Incorrect because marine growth is prevented using chemical treatment.

Response D - Correct Answer Removes heat rejected to the Condenser from the Low Pressure Turbines.

Reference:

ST-OP-315-0033-001 Author: CADDEN Keywords: CIRC WATER Not Archived Date Last Used:

Time: 3 Question ID: 35395 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO Generic 2.1.27 2.8 2.9 SRO o ESP o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

ST-OP-315-0033-001 o INO o Static

Question #69 Details EQ-OP-802-4101-000-0022-008 2004 RO NRC Exam Question Text Which one of the following is required when a non-visible break must be used to disconnect a piece of equipment from its power supply?

Response A Independent verification of the caution tag.

Incorrect because you would not use a caution tag for personal protection.

Response B An approved grounding device installed on the load side.

Incorrect because you may or may not use a grounding device, depending on the load.

Response C - Correct Answer An approved blocking device and a method for determining that power is removed.

Reference:

MOP12, section 3.2.11 Response D A safety observer is stationed for all work performed on the equipment.

Incorrect because the work will be considered deenergized, therefor no safety observer required. Also, safety observers may be used at the Operating Authorities discretion.

Author: BOLLINGER Keywords: ADMIN Not Archived Date Last Used:

Time: 3 Question ID: 34573 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO Generic 2.2.13 3.6 3.8 o SRO o ESP o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

MOP12 o INO o Static

Question #70 Details EQ-OP-315-0190-000-C005-004 2004 RO NRC Exam Question Text Refueling is in progress. As a once burned fuel bundle is being placed in the core SRM counts on one of the 2 operable SRM detectors begin increasing with a steady positive period. In accordance with procedure MOP13, Refueling Operations, you IMMEDIATELY:

Response A evacuate the refuel floor.

Incorrect because you would evacuate based on hi monitored radiation levels Response B - Correct Answer direct the refuel floor to stop fuel movement.

Reference:

MOP13, section 3.3 Response C inform the refuel floor to remove the fuel bundle and try again.

Incorrect because the RO would not direct the refuel floor to do anything. SRO job.

Response D declare the improperly responding SRM INOP and insert all insertable control rods within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Incorrect because MOP13 states you should believe all instrument indications (section 3.3.1)

Author: BARRETT Keywords: Not Archived Date Last Used: 2/7/2000 Time: 0 Question ID: 34502 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO Generic 2.2.30 3.5 3.3 o SRO o ESP 295023 K1.03 3.7 4.0 o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

MOP13, Conduct of Refueling and Core Alterations o INO o Static

Question #71 Details EQ-OP-802-4101-000-0022-007 2004 ILO NRC Exam Question Text An operator is conducting a normal day to day rounds inspection of equipment which is located in a high radiation area. In accordance with MOP04, Shift Operations, and MRP05 , ALARA/RWPs, the operator must:

Response A preplan the inspection during turnover.

Not in accordance with the references Response B - Correct Answer conduct the inspection from the barrier to the area.

Reference : MRP05, MOP4 Response C obtain Radiation Protection supervisor approval.

Not in accordance with the references Response D enter the area with a hand held monitoring device.

Not in accordance with the references Author: BOLLINGER Keywords: ADMIN Not Archived Date Last Used:

Time: 3 Question ID: 35422 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO Generic 2.3.2 2.5 2.9 SRO o ESP o STAC o Part A

References:

o STAI o Part B MOP4 o LOR o Open Ref.

MRP05 o NOC Close Ref.

o INO o Static

Question #72 Details EQ-OP-508-0001-000-A013-004 2004 RO NRC Exam Question Text A fully qualified Radiation Worker was escorting a male visitor with no previous exposure through the Reactor Building when they inadvertently walked through a high radiation area. Assuming no previous exposure, RP personnel read the dosimeters for the individuals and calculated that they received the following radiation exposure:

Chest 800 mrem Hands 1060 mrem Eye Lens 510 mrem Internal 550 mrem Which, if any, exposure limit has been exceeded?

Response A Both exceeded Federal TEDE limits.

Incorrect because the fully qualified Radiation Worker did not exceed Federal TEDE limits Response B Both exceeded Fermi administrative TEDE limits.

Incorrect because the fully qualified Radiation Worker did not exceed Fermi TEDE limits Response C - Correct Answer The male visitor exceeded the federal TEDE limit

Reference:

ST-GN-508 Response D The fully qualified Radiation Worker exceeded the federal TEDE limit Incorrect because the fully qualified Radiation Worker did not exceed Federal TEDE limits Author: CADDEN Keywords: 2004 NRC SRO Question Not Archived Date Last Used: ADMIN Time: 2 Question ID: 35322 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO generic 2.3.4 2.5 3.1 SRO o ESP o STAC o Part A

References:

o STAI o Part B 10 CFR 20 o LOR o Open Ref.

ST-GN-508 o NOC Close Ref.

o INO o Static

Question #73 Details EQ-OP-802-2001-000-R009-001 2004 RO NRC Exam Question Text When does ODE-03, Communications, allow relaxing of the 3-way communications requirement?

Response A When communicating face-to-face during peer checks Incorrect because 3-way communications are expected to be used during peer checks.

Response B When transferring information important to plant safety to the CRS.

Incorrect because 3-way communications are expected to be used when transferring plant information.

Response C - Correct Answer During transients when the CRS requests frequent updates of a certain parameter.

Reference:

ODE-03, Communications, page 2 Response D During testing evolutions between the Control Room Operator and the technician in the field.

Incorrect because 3-way communications are expected to be used during testing and maintenance activities.

Author: CADDEN Keywords: 2004 NRC SRO Question Not Archived Date Last Used: ADMIN Time: 2 Human Performance Question ID: 35319 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO Generic 2.4.15 3.0 3.5 SRO o ESP o STAC o Part A

References:

o STAI o Part B ODE-03, Communications o LOR o Open Ref.

MOP03 NOC o Close Ref.

o INO o Static

Question #74 Details EQ-OP-802-4101-000-0028-006 2004 RO NRC Exam Question Text In accordance with MOP10, "Fire Brigade", which one of the following individuals could be assigned to the fire brigade with the plant operating in mode one?

Assume each individual has met the physical and training requirements.

Response A Reactor Operator - assigned as Safe Shutdown Incorrect because required to be available for Safe Shutdown Response B Radwaste Operator -assigned as shift communicator Incorrect because required to be available to act as shift communicator Response C Senior Reactor Operator - assigned as the shift manager Incorrect because required to be available to act as Shift Manager Response D - Correct Answer Nuclear Operator - assigned as Turbine Building Rounds

Reference:

MOP 10, section 3.1 Author: CADDEN Keywords: FIRE PROT/DET Not Archived Date Last Used: 2004 NRC RO Question Time: 2 Question ID: 35318 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO 286000 2.4.26 2.9 3.3 o SRO o ESP Generic 2.4.25 2.9 3.4 o STAC o Part A o STAI o Part B

References:

o LOR o Open Ref.

MOP10 o NOC Close Ref.

o INO o Static

Question #75 Details 2004 RO NRC Exam EQ-OP-802-2004-000-0001-008 Question Text During a reactor startup the following conditions exist :

RPV Pressure.................................................680 psig RPV water level...........................................193 inches RWCU System.....................in Blowdown Mode If the operating CRD Pump trips followed by Annunciator 3D10,CRD ACCUMULATOR TROUBLE (in alarm for one withdrawn rod), the Operating Crew is required by AOP to immediately:

Response A Start the standby CRD pump.

Incorrect because pressure is <900 psig and 3D10 in alarm for a withdrawn control rod Response B - Correct Answer Place the Reactor Mode Switch to SHUTDOWN.

Reference:

20.106.01, (Immediate Actions)

Response C Have a Nuclear Operator check the local alarm panel.

Incorrect because the reactor must be scrammed and then a lot of alarms will come in on the local control panel.

Response D Monitor for the second control rod DRIFT alarm to activate, then manually scram the reactor.

Incorrect because this is the immediate actions for Control Rod drift. There are no drifting control rods given in the stem.

Author: BOLLINGER Keywords: AOP Archived Date Last Used: CRDH Time: 1 LOR 00-04 Question ID: 30908 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value RO ILO Generic 2.4.11 3.4 3.6 o SRO o ESP Generic 2.4.49 4.0 4.0 o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

20.106.01, (Immediate Actions) o INO o Static

Question #1 Details EQ-OP-802-2001-000-S001-001 2004 SRO NRC Exam Question Text A Loss of Power Event has occurred. The CRNSO reports the following:

• 345KV mat power indicating lights........................off

• EDG 13...................................................NOT running

• EDG 14............................................carrying 65F Bus

• 65E, 72E, 13EC, and 72EC...................................off

• E6 and E8 breakers...........................................tripped What actions should be directed?

Response A Start CTG 11-1 in accordance with 23.324.

Incorrect because CTG 11-1 is not required for operation with a loss of 345Kv.

Response B Perform Rapid Power Reduction in accordance with 23.623.

Incorrect because Loss of 345Kv Immediate Actions direct placing mode switch in Shutdown.

Response C - Correct Answer Investigate cause of Bus Failure in accordance with MOP 04.

Reference:

1 Response D Perform Emergency Diesel Generator Failure in accordance with 20.307.01.

Incorrect because EDG13 is not supposed to start with bus 65E locked out.

Author: CADDEN Keywords: 4160/480V ELEC Not Archived Date Last Used: AOP Time: 4 EDG Question ID: 35280 Points: 1 2004 NRC SRO Question Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value o RO ILO 295003 AA2.01 3.4 3.7 SRO o ESP 295003 AA2.04 3.7 o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC o Close Ref.

20.300.65E o INO o Static MOP04 20.307.01 Page: 1

Question #2 with Details EQ-OP-802-2001-000-S001-002 2004 ILO NRC Exam Question Text The reactor is shutdown due to a lockout on bus 72F during an earthquake. All systems operated normally during the shutdown.

An aftershock occurs which trips all remaining RBCCW pumps. Considering all remaining systems operate normally, which one of the following actions must be directed in accordance with plant procedures?

Response A - Correct Answer Trip the south recirc MG set

Reference:

20.127.01, override statement. There will be no cooling to Div II DW penetrations due to the loss of 72F (resulted in loss of Div II EECW)

Response B Trip the north recirc MG set Incorrect because the North recirc MG will still be cooled by Div I EECW Response C Take local manual control of the south recirc MG Incorrect because the South recirc MG will have to be tripped. Plausible distractor because Scoop tube is powered by 72F, which is lost.

Response D Take local manual control of the north recirc MG Incorrect because the North recirc MG will still have power to its scoop tube.

Author: CADDEN Keywords: RBCCW/EECW Not Archived Date Last Used:

Time: 4 Question ID: 35473 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value o RO ILO 400000 K1.02 3.2 3.4 SRO o ESP 295018 A2.04 2.9 o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

ST-OP-315-0067-001 o INO o Static 20.127.01

Question #3 Details EQ-OP-315-0141-000-C005-002 2004 SRO NRC Exam Question Text The plant is in mode 4 with Shutdown Cooling in operation. Plant conditions are as follows:

• E1150-F008, SDC Outboard Iso. vlv is shut

• E1150-F009, SDC Inboard Iso. vlv is shut

• RPV Level is 184 inches

• RPV Pressure is 95 psig Based on the information above, what action would the SRO direct and why?

Response A Condition C of 20.205.01, Loss of SDC for level, to mitigate a Loss of Coolant Accident.

Incorrect because Level isolation is <173.4 Response B Condition C of 20.205.01, Loss of SDC for level, to prevent temperature stratification.

Incorrect because Level isolation is <173.4 Response C Condition D of 20.205.01, Loss of SDC for pressure, to maintain adequate NPSH to operating RHR pumps.

Incorrect because the pressure isolation is based on high pressure, not low pressure.

Response D - Correct Answer Condition D of 20.205.01, Loss of SDC for pressure, to prevent over-pressurization of SDC piping.

Reference:

ST-OP-315-0041-001 Author: CADDEN Keywords: RHR - SDC Not Archived Date Last Used: 2004 NRC SRO Question Time: 0 Question ID: 35281 Points: 1 Parent ID: 0 Difficulty: 3 Child ID: 0 KA System KA Number RO Value SRO Value o RO ILO 295021 A2.06 3.3 SRO o ESP o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

20.205.01, Loss of Shutdown Cooling o INO o Static 23.205, RHR System ST-OP-315-0041-001

Question #4 Details EQ-OP-802-3004-000-0109-010 2004 SRO NRC Exam Question Text A major plant transient has occurred causing the following plant conditions:

• Drywell pressure is 8 psig and rising slowly

• Torus pressure is 7.5 psig and rising slowly

• Drywell temperature is 153°F and rising slowly

• Torus temperature is 102°F and rising slowly

• Torus water level is 18 inches Based on the information above, which of the following would be the next action to take, AND what is the basis for taking this action?

Response A - Correct Answer Initiate Torus sprays to prevent "chugging".

Reference:

ST-OP-802-3004-001, EOP Primary Containment Control Response B Initiate Primary Containment Vent to prevent "chugging".

The stated conditions do not warrant venting the containment Response C Initiate Torus sprays to decrease the percentage of non-condensibles in the Drywell.

The Torus Spray Initiation Pressure is defined to be the lowest torus pressure which can occur when 95%

of the non-condensibles in the drywell have been transferred to the airspace of the torus.

Response D Initiate Primary Containment Vent to decrease the percentage of non-condensibles in the Drywell.

The stated conditions do not warrant venting the containment Author: CADDEN Keywords: 2004 NRC SRO Question Not Archived Date Last Used: EOP PCP Time: 0 Question ID: 35282 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value o RO ILO 295024 A2.01 4.4 SRO o ESP o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC o Close Ref.

ST-OP-802-3004-001, EOP Primary Containment Control o INO o Static 29.100.01, Sh 2

Question #5 with Details EQ-OP-315-0127-000-0009-005 2004 SRO NRC Exam Question Text The plant is operating at 100% power.

A failure of the governor/pressure regulator system causes the turbine control valves to slowly close without a corresponding opening of the bypass valves.

(1) Which RPS function will scram the reactor and (2) what is the basis for that trip?

Response A - Correct Answer (1) APRM flux - Upscale (2) to prevent fuel damage or excessive reactor pressure.

Reference:

ITS Bases Response B (1) Main Steam Isolation Valve Closure (2) to anticipate the complete loss of the normal heat sink Incorrect because MSIVs will not go closed in this situation. Reference for basis Response C (1) Low RPV water level (2) to substantially reduce the heat generated in the fuel from fission.

Incorrect because a RPV L3 Scram will not occur prior to the APRM trip. Reference for basis Response D (1) Turbine Control Valve Closure (2) to anticipate the transient that will result from full valve closure.

Incorrect because the trip function is for Turbine Stop Valves. Reference for basis.

Author: CADDEN Keywords: RPS Not Archived Date Last Used: 2004 NRC SRO Question Time: 2 Question ID: 35283 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value o RO ILO 295025 A2.02 4.2 SRO o ESP o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

ST-OP-315-0027 o INO o Static ITS bases

Question #6 Details EQ-OP-802-3002-000-0007-040 2004 SRO NRC Exam Question Text A plant transient has occurred which has resulted in the following conditions:

• Torus level is -20 inches and lowering

• Torus temperature is 174°F and steady (1) Given these conditions, what is the maximum RPV pressure allowed without Emergency Depressurizing?

(2) The basis for maintaining RPV pressure below this limit is to ensure that a Blowdown will not result in exceeding the.....

Response A - Correct Answer (1) 800 psig (2) Torus design temperature

Reference:

ST-OP-802-3002-001 Response B (1) 1000 psig (2) Torus design temperature Incorrect because you must you the next highest pressure CURVE Response C (1) 800 psig (2) Drywell design temperature Incorrect because the limit is based on Torus temperature Response D (1) 1000 psig (2) Drywell design temperature Incorrect because you must you the next highest pressure CURVE Author: CADDEN Keywords: EOP TWT Not Archived

Date Last Used: 2004 NRC SRO Question Time: 0 Question ID: 35286 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value o RO ILO 295030 A2.03 3.9 SRO o ESP o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

29.100.01 Sh 6 o INO o Static ST-OP-802-3002-001 Page: 1

Question #7 Details EQ-OP-802-3003-000-0019-011 2004 ILO NRC Exam Question Text A valid Reactor Scram signal was received and the rods failed to insert. The following are the current plant conditions:

• Reactor Power is 9%

• Torus temperature is 102°F and slowly rising

• Drywell pressure is 0.75 psig and slowly rising

• Reactor water level is 45 inches on the Wide Range level indicator

• Standby Liquid Control has been started and is injecting to the RPV

• SRVs are controlling RPV pressure

• Terminate and Prevent for level has been performed What level band should be directed per the EOPs, AND what is the basis for the bands upper limit?

Response A

-28 to 50 inches. Sufficiently preheats incoming feedwater 50 inches does not sufficiently preheat feedwater.

Response B

-28 to 50 inches. Suppresses Reactor power to the lowest practical level T&P for level, not power because still <BIIT.

Response C - Correct Answer

-28 to 114 inches. Sufficiently preheats incoming feedwater

Reference:

ST-OP-802-3003 Response D

-28 to 114 inches. Suppresses Reactor power to the lowest practical level 114 inches does not suppress reactor power Author: CADDEN Keywords: ATWS Not Archived Date Last Used: EOP RPV Level Time: 2 2004 NRC SRO Question Question ID: 35287 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value o RO ILO generic 2.1.6 4.3 SRO o ESP o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

ST-OP-802-3003 o INO o Static

Question #8 with Details EQ-OP-802-3005-000-0001-020 2004 SRO NRC Exam Question Text A severe plant transient has occurred, resulting in RPV water level remaining below TAF for several minutes. A release is in progress with D1 & D2 CHRRMS indicating 20,000 R/hr.

No emergency operating facilities have been activated. Which of the following SM responsibilities are listed in the correct order of performance?

Response A Determine offsite protective action recommendations, complete emergency notifications to the NRC, complete emergency notifications to offsite authorities, and classify the event.

Incorrect because an event must be classified before a PAR is determined to be required.

Response B Classify the event, complete emergency notifications to offsite authorities, complete emergency notifications to the NRC, determine offsite protective action recommendations.

Incorrect because a PAR, if required, must be formulated before notification of Offsite Authorities.

Response C - Correct Answer Classify the event, determine offsite protective action recommendations, complete emergency notifications to offsite authorities, complete emergency notifications to the NRC.

An event must be classified to determine if a PAR is required. Notifications are completed in accordance with the specified time limits.

Response D Determine offsite protective action recommendations, classify the event, complete emergency notifications to the NRC, and complete emergency notifications to offsite authorities.

Incorrect because an event must be classified before a PAR is determined to be required.

Author: BARKER Keywords: Not Archived Date Last Used:

Time: 3 Question ID: 35442 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value o RO ILO 295038 K2.05 4.7 SRO o ESP o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

EP-290 Emergency Notifications o INO o Static EP-105 General Emergency, Attachment 1 Checklist

Question #9 Details EQ-OP-315-0127-000-A007-001 2004 SRO NRC Exam Question Text While the reactor is operating in normal two-loop operation at 85% power and 80% flow, a Main Steam Isolation Valve disc becomes separated from the stem and rapidly shuts.

During the transient the following indications are observed:

• APRMs spike to 113.5% and returns to 100%

• Reactor Pressure spikes to 1120 psig and returns to 1000 psig

• Reactor water level lowers to 182" and returns to 216 inches What Technical Specification allowable value has been exceeded?

Response A Reactor water level Not > Safety system setting per ITS Response B ARPM fixed neutron flux Not > Safety system setting per ITS Response C - Correct Answer Reactor steam dome pressure

Reference:

ITS 3.3.1.1 Response D APRM simulated thermal power Not > Safety system setting per ITS Author: CADDEN Keywords: 2004 NRC SRO Question Not Archived Date Last Used: TECH SPECS Time: 0 Question ID: 35289 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value o RO ILO 295007 A2.01 4.1 SRO o ESP o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

ITS 3.3.1.1 o INO o Static

Question #10 Details EQ-OP-802-3004-000-0004-005 2004 SRO NRC Exam Question Text The plant was operating at 100% when, due to an operator error, the Drywell (DW) Fan Master CMC switch for Division 1 DW Cooling fans was placed in All Stop.

The following conditions exist:

• Alarm 8D41 "Div 1 High Drywell Temperature".......lit

• Alarm 17D41 "Div 2 High Drywell Temperature".....lit

• Confirmed Average Drywell Temperature............149°F

• Drywell Pressure...................................................0.68 psig What actions should the CRS direct?

Response A - Correct Answer Enter 29.100.01 Sheet 2, Primary Containment Control, and operate all available DW cooling

Reference:

29.100.01 Sheet 2, ST-OP-802-3004-001, ST-OP-802-3004-001(2)

Response B Enter 29.100.01 Sheet 2, Primary Containment Control, and shutdown Reactor Recirc pumps Incorrect because this step is taken when DW pressure is >1.68 psig Response C Place RBCCW supplemental cooling in service per 23.127.01, and monitor DW temperature and pressure Incorrect because this action is directed by ARPs. The conditions listed are EOP entry conditions.

Response D Lower DW pressure per 23.406, Primary Containment Nitrogen Inerting and Purge, and monitor DW temperature and pressure Incorrect because DW pressure is still within allowable limits Author: CADDEN Keywords: DW COOLING Not Archived Date Last Used: 2004 NRC SRO Question Time: 0 Question ID: 35290 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value o RO ILO 295010 A2.06 3.6 3.6 SRO o ESP 295010 K3.02 3.4 3.4 o STAC o Part A 2.1.6 2.1 4.3 o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

ST-OP-802-3004-001 o INO o Static 29.100.01 Sheet 2

Question #11 with Details EQ-OP-802-3004-000-0009-025 2004 SRO NRC Exam Question Text The CRS is evaluating the need for drywell sprays during implementation of the EOPs.

Which one of the following states the significance of reaching +50 inches Torus water level?

Response A Torus level increasing to this point following the LOCA will compress the non-condensables exhausted from the drywell to the torus, resulting in opening the vacuum breakers.

Incorrect because torus water level is >vacuum breakers, so they will not open Response B Torus venting cannot be performed above this level if it becomes necessary to vent the Primary Containment.

Incorrect because Torus Venting limit is >570 ft in containment, which is Top of Torus area.

Response C - Correct Answer Vacuum Breakers will be covered with water and unable to relieve torus pressure to the drywell.

Reference:

29.100.01, sheet 2, ST-OP-802-3004-0001 Response D Above this level there is insufficient free volume to accommodate the non-condensable gases driven into the torus by the LOCA.

Incorrect because no steps in the Torus Water Level EOP is based on Non-condensable gases.

Author: CADDEN Keywords: 2004 NRC SRO Question Not Archived Date Last Used: 10/22/1999 EOP TWL Time: 0 Question ID: 35291 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value o RO ILO 295029 A2.01 3.9 SRO o ESP o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

29.100.01, sheet 2 o INO o Static ST-OP-802-3004-0001

Question #12 with Details EQ-OP-802-3004-000-0009-026 2004 SRO NRC Exam Question Text The reactor was operating at 100 % power when a LOCA occurred which caused RPV water level to initially lower below TAF. RPV water level has been raised above TAF and the following conditions exist :

RPV pressure.......................................................................600 psig RPV water level.......................................+ 5 inches (slowly rising)

Drywell pressure................................................7 psig (slowly rising)

Drywell temperature..................................................185°F (rising)

Torus H2 concentration.............................................................6.5 %

Torus O2 concentration................................................................6 %

RHR System.........In Torus Cooling/Torus Sprays on Division one Rx is Shutdown..................................................all rods are inserted Given the above parameters, select which of the following actions the CRS would direct the operating crew to execute:

Response A Initiate Drywell sprays.

Can not initiate Drywell sprays until >9 psig in the Torus per PCP-6 Response B - Correct Answer Emergency depressurize the RPV.

Reference:

29.100.01 SH 4, Rev. 7 (CC)

Response C Place the Thermal Recombiners in service.

Can not place thermal recombiners in service with H2 concentration >6%

Response D Vent the drywell irrespective of radioactivity release rate.

No Drywell O2/H2 parameters given, therefore no basis to vent the drywell Author: CADDEN Keywords: EOP PC H2/O2 Not Archived Date Last Used: 2004 NRC SRO Question Time: 5 Question ID: 35294 Points: 1 Parent ID: 0 Difficulty: 3 Child ID: 0 KA System KA Number RO Value SRO Value o RO ILO 500000 A2.04 3.3 SRO o ESP o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

29.100.01 SH 4, Rev. 7 (CC) o INO o Static

Question #13 with Details EQ-OP-315-0141-000-A021-010 2004 SRO NRC Exam Question Text The plant was operating at 65% power. A seismic event occurred which resulted in a loss of offsite power and a feedwater rupture outside of containment.

The following conditions exist:

EDGs 11 and 12 are tripped.

EDGs 13 and 14 are running loaded.

RPV Level 155" RPV pressure 650 psig (1) What RHR piping system flowpaths are available for use and (2) what is the earliest you can direct opening the RHR LPCI injection valve to mitigate the loss of coolant event?

Response A - Correct Answer (1) Both Divisions for LPCI injection mode. Only Division 2 for Torus Cooling/Spray and DW Spray (2) 461 psig

Reference:

ST-OP-315-0141, 23.205 (page 202)

Response B (1) Only Division 2 for LPCI injection mode. Both Divisions for Torus Cooling/Spray and DW Spray (2) 461 psig Incorrect because Division 1 Torus cooling/spray and DW spray valves have no power.

Response C (1) Both Divisions for LPCI injection mode. Only Division 2 for Torus Cooling/Spray and DW Spray (2) 295 psig Incorrect because 461 psig is the injection valve permissive pressure Response D (1) Only Division 2 for LPCI injection mode. Both Divisions for Torus Cooling/Spray and DW Spray (2) 295 psig Incorrect because 461 psig is the injection valve permissive pressure Author: CADDEN Keywords: RHR - LPCI Not Archived Date Last Used: 2004 NRC SRO Question Time: 2 Question ID: 35412 Points: 1 Parent ID: 0 Difficulty: 3 Child ID: 0 KA System KA Number RO Value SRO Value o RO ILO 203000 A2.04 3.5 3.6 SRO o ESP o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

ST-OP-315-0141 o INO o Static 23.205

Question #14 with Details EQ-OP-315-0140-000-C013-001 2004 SRO NRC Exam Question Text The plant is operating at 28% power during a startup. Division one (1) Core Spray is declared inoperable due to failing Surveillance Requirement 3.5.1.8, Core Spray flow test.

Which one of the following components if subsequently declared inoperable would cause the most limiting condition in accordance with technical specifications with Division one (1) Core Spray already out of service?

Response A - Correct Answer Core Spray - Pump B

Reference:

Tech Specs Response B Any one (1) ADS Valve Incorrect because would be 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> action statement. ADS would be limiting if HPCI were inop.

Response C Reactor Core Isolation Cooling (RCIC)

Incorrect because RCIC is not a limiting factor for Core Spray tech specs.

Response D High Pressure Coolant Injection (HPCI)

Incorrect because would be 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> action statement. HPCI would be limiting if ADS were inop.

Author: CADDEN Keywords: HPCI Not Archived Date Last Used: RCIC Time: 2 TECH SPECS Question ID: 35406 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value o RO ILO 209001 2.1.12 4.0 SRO o ESP o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

Tech Specs o INO o Static

Question #15 with Details EQ-OP-802-3003-000-0002-012 2004 SRO NRC Exam Question Text While performing RPV Control - ATWS, step FSL-2 directs automatic initiation of ADS to be inhibited.

Which of the following best describes why this action is directed?

Response A The conditions assumed in the design of the ADS actuation logic could not exist if the RPV is experiencing an ATWS.

Incorrect since ADS logic design has nothing to do with ATWS and the conditions could exist during an ATWS.

Response B - Correct Answer Rapid and uncontrolled injection of relatively cold, unborated water would dilute in-core boron concentration.

Reference:

ST-OP-802-3003-001 Response C ADS actuation with the RPV in an ATWS condition imposes a severe mechanical transient on the SRV tailpipes which could lead to primary containment failure.

Although ADS actuation does impose severe mechanical stress, that is not the basis for FSL-2.

Response D ADS actuation with the RPV at pressure imposes a severe thermal transient on the drywell and may significantly complicate efforts to maintain drywell temperature as specified.

The thermal transient will be felt on the Torus. Also, this is not the basis for FSL-2.

Author: CADDEN Keywords: ATWS Not Archived Date Last Used: ADS Time: 2 2004 NRC SRO Question Question ID: 35297 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value o RO ILO Generic 2.4.7 3.8 SRO o ESP o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

ST-OP-802-3003-001 o INO o Static

Question #16 with Details EQ-OP-802-3003-000-0111-001 2004 SRO NRC Exam Question Text The plant was operating at 100% power when a LOCA occurred. The following plant conditions exist:

RPV pressure...................................................900 psig RPV level................................155 inches and lowering Heater Feed Pumps............................................tripped The STA reports that the leak is 2.6 million Lbm/hr. In accordance with RPV Control EOP table 1, What is the MINIMUM combination of available systems the CRS should direct be used to maintain RPV water level? (8 lbm/gal)

Response A HPCI Incorrect since (2.6 Mlbm/hr at 1lbm/hr = 8 gpm, => 2.6x106/(8*60) = 5,416.7 gpm. The design flowrate of HPCI is 5000 gpm Response B - Correct Answer HPCI and RCIC Correct since need 5,416.7 gpm. HPCI (5,000 gpm) + RCIC (650 gpm) = 5,650 gpm Response C HPCI, RCIC and one SBFW pump Incorrect since question asks MINIMUM combination and SBFW is not needed.

Response D HPCI, RCIC and both SBFW pumps Incorrect since question asks MINIMUM combination and SBFW is not needed.

Author: CADDEN Keywords: LOCA Not Archived Date Last Used: EOP RPV Level Time: 0 2004 NRC SRO Question Question ID: 35298 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value o RO ILO 259002 2.4.48 3.8 SRO o ESP o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC o Close Ref.

ST-OP-802-3003-001 o INO o Static ST-OP-315-0039-001, ST-OP-315-0043, ST-OP-315-0018 29.100.01, Sheet 1, Table 1

Question #17 with Details EQ-OP-315-0124-000-A002-001 2004 SRO NRC Exam Question Text Which of the following best describes the basis for the Limiting Condition of Operation (LCO) for the Rod Block Monitor (RBM)?

Response A - Correct Answer The RBM is designed to automatically prevent fuel damage in the event of erroneous rod withdrawal from locations of high power density during high power operation.

Reference:

Technical Specifications Response B The RBM is designed to provide automatic supervision to assure that out-of -sequence rods will not be withdrawn or inserted to limit the effects of a rod drop accident.

Incorrect since this is the function of the Rod Worth Minimizer Response C The RBM is designed to enforce a control rod pattern which will limit fuel temperature should there be a failure to scram during a anticipated plant transient.

Incorrect since RBM does not enforce control rod patterns Response D The RBM setpoints are designed to provide adequate margin for the Safety Limits and yet allow operating margin that reduces the possibility of unnecessary shutdown.

Incorrect because this answer references the setpoints, not the LCO for the RBM.

Author: CADDEN Keywords: RBM Not Archived Date Last Used: 2004 NRC SRO Question Time: 0 Question ID: 35299 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value o RO ILO 215002 2.2.25 3.7 SRO o ESP o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

Technical Specifications o INO o Static ST-OP-315-0124-001

Question #18 with Details EQ-OP-315-0190-000-A017-002 2004 SRO NRC Exam Question Text The plant is in a refueling outage with the mode switch in REFUEL and all rods inserted.

The refuel crew has used the grapple to pick up a fuel bundle. They start to move towards the core when the control room operator withdraws a rod.

What is the expected response when the bridge reaches the core?

Response A - Correct Answer stop and a hoist block will be generated

Reference:

ST-OP-315-0190-001(1), ST-OP-315-0190-001 (2)

Response B stop and the hoist will remain operable Incorrect because a hoist block is generated Response C continue moving and a hoist block will be generated Incorrect because the bridge will stop moving Response D continue moving and the hoist will remain operable Incorrect because a hoist block is generated Author: CADDEN Keywords: Not Archived Date Last Used: 2/7/2000 Time: 0 Question ID: 35300 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value o RO ILO 234000 2.2.27 2.6 3.5 SRO o ESP o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

Technical Specification Basis 3.9.1-1 o INO o Static ST-OP-315-0190-001 Page: 1

Question #19 with Details EQ-OP-315-0141-000-A021-008 2004 SRO NRC Exam Question Text Two minutes after a small steam leak develops inside the drywell, the following conditions exist:

• Drywell pressure.................................................3.0 psig.

• Reactor pressure............................................750 psig and lowering.

• RPV level........................................................170 inches and rising.

• HX A Bypass Cont E11-F048A.......................white Sealed In light

• E11-F015A, E11-F017A..................................white Close light

• HX B Bypass Cont E11-F048B.......................white Sealed In light Based on these conditions, which loop is selected for injection, and which Division of RHR should be used for Primary Containment (PC) control?

Response A A loop selected for injection, Division 1 RHR for PC control.

Incorrect since B Loop selected for injection (15A and 17A are closed)

Response B - Correct Answer B loop selected for injection, Division 1 RHR for PC control.

Reference:

ST-OP-315-041-001, also the Non-selected loop is used for PC control Response C A loop selected for injection, Division 2 RHR for PC control.

Incorrect since B Loop selected for injection (15A and 17A are closed)

Response D B loop selected for injection, Division 2 RHR for PC control.

Incorrect since the Non-selected loop is used for PC Control.

Author: CADDEN Keywords: RHR - LPCI Not Archived Date Last Used: 5/16/2002 Time: 5 Question ID: 34591 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value o RO ILO Generic 2.1.7 3.7 4.4 SRO o ESP 203000 A3.06 3.7 3.6 o STAC o Part A 203000 K4.01 4.2 4.2 o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

ST-OP-315-041-001 o INO o Static 23.205 23.601

Question #20 with Details EQ-OP-804-0001-000-0008-006 2004 SRO NRC Exam Question Text Which one of the following describes a Fermi 2 technical specification safety limit?

Response A Water level in the spent fuel pool shall be greater than the top of active irradiated fuel.

Incorrect since there is no safety limit for fuel pool water level Response B Reactor vessel water level shall be greater than 31" above the top of active irradiated fuel.

Incorrect since the safety limit is > top of active fuel Response C - Correct Answer MCPR shall be >1.07 for two recirculation loop operation or >1.09 for single recirculation loop operation

Reference:

Technical Specifications and bases Response D With the reactor steam dome pressure < 785 psig or core flow < 10% rated core flow, core thermal power is limited to 50%

Incorrect since the safety limit is limited to 25% thermal power Author: CADDEN Keywords: 2004 NRC SRO Question Not Archived Date Last Used: Thermal Limits Time: 2 Question ID: 35306 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value o RO ILO 295009 2.2.22 3.4 4.1 SRO o ESP o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

Technical Specifications and bases o INO o Static

Question #21 with Details EQ-OP-802-4101-000-0030-010 2004 SRO NRC Exam Question Text During refueling operations a Refuel Floor Log is maintained. Who has the shared responsibility for maintaining this log in accordance with procedure MOP13, Conduct of Refueling and Core Alterations?

Response A - Correct Answer Refuel Floor Coordinator and Refuel Floor Supervisor

Reference:

MOP13 Conduct of Refueling and Core Alterations, Page 6 Response B Station Nuclear Engineer and Fuel Movement Verifier Incorrect because Neither SNE nor Fuel Movement Verifier maintains the log.

Response C Supervisor Reactor Engineering and Station Nuclear Engineer Incorrect because Neither Supervisor Reactor Engineering nor SNE maintains the log.

Response D Refuel Floor Supervisor and Supervisor Reactor Engineering Incorrect because Supervisor Reactor Engineering does not maintain the log.

Author: CADDEN Keywords: REFUELING Not Archived Date Last Used: 2/7/2000 2004 NRC SRO Question Time: 3 Question ID: 35310 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value o RO ILO 2.2.29 3.8 SRO o ESP o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

MOP13 Conduct of Refueling and Core Alterations o INO o Static

Question #22 with Details EQ-OP-315-0019-000-C005-001 2004 SRO NRC Exam Question Text The plant was operating at 100% power with the operating crew making preparations to vent the Drywell for pressure control in accordance with 23.406, Primary Containment Nitrogen Inerting and Purge System, using Division I SGTS as a vent path. The CRNSO reports that Division I SGTS has failed to start.

What action should the CRS direct?

Response A - Correct Answer Line-up and vent through RBHVAC

Reference:

23.406, page 17 (pre-requisites)

Response B Start Division II SGTS and vent the Torus Incorrect because precautions and limitations (P/L 3.4, pg 5) state both divisions of SGTS should be functionally capable if using SGTS to vent the DW.

Response C Start Division II SGTS and vent the Drywell Incorrect because precautions and limitations (P/L 3.4, pg 5) state both divisions of SGTS should be functionally capable if using SGTS to vent the DW. Also, venting the DW, not the Torus.

Response D Line-up and vent containment through the Torus Hardened Vents Incorrect because venting through the Torus Hardened Vent is only done in emergencies.

Author: CADDEN Keywords: 2004 NRC RO Question Not Archived Date Last Used: CONTAINMENT Time: 5 NITROGEN Question ID: 35311 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value o RO ILO Generic 2.3.8 3.2 SRO o ESP o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

ST-OP-315-0019-001 o INO o Static 23.406

Question #23 with Details EQ-OP-315-0115-000-C005-001 2004 SRO NRC Exam Question Text While in the Refueling Mode, Technical Specification 3.7.7 requires a minimum of 22 feet of water over the irradiated fuel assemblies. What is the basis for this requirement?

Response A Adequate Net Positive Suction Head is available for a running RHR pump while in the Fuel Pool Cooling Assist Mode of operation.

Incorrect RHR pumps take suction on Fuel Pool Skimmer Surge Tanks.

Response B - Correct Answer Sufficient volume is available to remove 99% of the assumed 10% iodine gap activity released from a damaged fuel assembly.

Reference:

ST-OP-315-0015-001, Tech Spec Basis 3.7.7 Response C Background radiation levels at the surface of the water are less than or equal to 5 mr/hr while refueling operations are in progress.

Incorrect because rad levels at the water surface are not in the design for minimum water level.

Response D The free-fall of an 1100-pound load dropped over the vessel will be sufficiently slowed so as not to cause damage to the fuel assemblies in the RPV.

There is no basis to support this answer.

Author: CADDEN Keywords: FPC&C Not Archived Date Last Used:

Time: 0 Question ID: 35312 Points: 1 Parent ID: 0 Difficulty: 1 Child ID: 0 KA System KA Number RO Value SRO Value o RO ILO Generic 2.3.10 3.3 SRO o ESP o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

ST-OP-315-0015-001 o INO o Static Tech Spec Basis 3.7.7

Question #24 with Details EQ-OP-315-0141-000-0003-012 2004 SRO NRC Exam Question Text The plant is shutdown for a refueling outage.

RPV temperature is 140°F.

Division 2 RHR is operating in the shutdown cooling mode.

RHR pump B is running.

The following alarms and indications are noted:

• 3D156 REACTOR WATER LEVEL LOW

• 3D79 REAC VESSEL WATER LEVEL L3 CHANNEL TRIP RPV water level 160" and steady on narrow range level indicators.

RPV water level 135" and lowering slowly on wide range level indicators.

Based on these conditions what action is taken in accordance with plant procedures?

Response A Enter 20.205.01 Loss of Shutdown Cooling and restore shutdown cooling using B RHR pump.

Incorrect because SDC will not be restored until level is >L3. The plant is experiencing a LOCA.

Response B Enter 20.205.01 Loss of Shutdown Cooling and re-open E1150-F015B, LPCI Inbd Iso Vlv.

Incorrect because E1150-F015B can not be opened until level is >L3.

Response C - Correct Answer Enter 29.100.01 sheet 1 RPV control and restore level as directed using Table 1 systems.

Reference:

29.100.01 sht 1 RPV control Response D Enter 29.100.01 sheet 1 RPV control and restore level per RPV flooding due to level indication discrepancies.

Incorrect because there is no level discrepancy. NR level stops indicating at 160.

Author: CADDEN Keywords: RHR - SDC Not Archived Date Last Used: 2004 NRC SRO Question Time: 3 Question ID: 35314 Points: 1 Parent ID: 0 Difficulty: 3 Child ID: 0 KA System KA Number RO Value SRO Value o RO ILO 295031 2.4.1 4.3 4.6 SRO o ESP 295031 2.4.9 3.9 o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

ST-OP-315-0041-001 o INO o Static ST-OP-802-3002,3003

29.100.01 sht 1 RPV control Question #25 with Details EQ-OP-802-3003-000-0008-008 2004 SRO NRC Exam Question Text Which of the following set of conditions would allow the CRS/SM to exit the ATWS section of the EOPs?

Response A All control rods inserted to position 02; SLC injecting with tank level at 14 inches.

Incorrect because Maximum Sub-critical Banked Withdrawal Position is 0.

Response B One rod inserted to position 30 and all other control rods inserted to position 02; SLC injecting with tank level at 45 inches.

Incorrect because Maximum Sub-critical Banked Withdrawal Position is 0.

Response C Three rods inserted to position 04 while all others inserted to position 00; SLC injecting with tank level at 34 inches.

Incorrect because Maximum Sub-critical Banked Withdrawal Position is 0.

Response D - Correct Answer One rod inserted to position 46 and all others inserted to position 0; SLC injecting with tank level at 58 inches.

Reference:

ST-OP-802-3003-001, EPG Appendix B, Contingency 5, Tech Spec Bases, Shutdown Margin Author: CADDEN Keywords: ATWS Not Archived Date Last Used: 3/9/2001 EOP RPV Power Time: 2 2004 NRC RO Question Question ID: 35315 Points: 1 Parent ID: 0 Difficulty: 2 Child ID: 0 KA System KA Number RO Value SRO Value o RO ILO Generic 2.4 2.4.21 3.7 4.3 SRO o ESP 295006 A2.01 4.5 4.6 o STAC o Part A o STAI o Part B o LOR o Open Ref.

References:

o NOC Close Ref.

ST-OP-802-3003-001 o INO o Static EPG Appendix B, Contingency 5 Tech Spec Bases, Shutdown Margin