ML103080007

2010-10-Draft Written Exam Comments

ML103080007
Person / Time
Site:	Waterford
Issue date:	11/04/2010
From:	Apger G Operations Branch IV
To:	Entergy Operations
References
50-382/10-302, ES-401, ES-401-9 50-382/10-302
Download: ML103080007 (168)

Text

ES-401 WT-2010-10 Written Examination Review Worksheet Form ES-401-9 ALL RO MARKUPS ATTACHED AT END OF THIS FORM Some comments state Attach original question. The originals were attached at the end of the file containing the question references. Disregard this comment.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 1 H 2 N S D, CR, 41.3 A, CR, 41.5 - If the applicant recognizes that the minimum flow isnt achieved with 2 F 2 X N S single loop flow, then distracters B and C are the same. Changed distracters, Answer now B.

B, CR, 41.7 - Question: Is there significance to the 28 gpm letdown flow vice it 3 H 3 B S lowering to a new level? OK as is. Min letdown.

4 H 3 M S A, CR, 41.10 Minor Edit to stem.

B, CR, 41.5 - Question: Do power supplies 314A and 315A supply LPSI/ECCS 5 F 2 M S loads? From the references, I cant tell. This affects whether these are plausible distracters. Also, the question references OP-901-313 Attachment 2, and Attachment 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 B 5 (easy B difficult) rating scale (questions in the 2 B 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.

$ The distractors are not credible; single implausible distractors should be repaired, more than one is unacceptable.

$ 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. Enter question source: (B)ank, (M)odified, or (N)ew. Check that (M)odified questions meet criteria of ES-401 Section D.2.f.

7. Based on the reviewer=s judgment, is the question as written (U)nsatisfactory (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory?

8. At a minimum, explain any AU@ ratings (e.g., how the Appendix B psychometric attributes are not being met). Page 1 of 7 OBDI 202 - IOLE Process

ES-401 WT-2010-10 2 Form ES-401-9

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 1 is provided. OK as is. References updated.

6 H 3 N S A, CR, 41.10 7 F 3 M S A, CR, 41.8 8 H 3 M S C, CR, 41.5 9 H 2 M S D, CR, 41.10 10 H 3 N S C, OR, 41.5 11 H 3 N S B, CR, 41.7 A, CR, 41.7 - It appears that loads are restored with either a UV condition or not according to the sequencer. There appears to be no situation when loads will be 12 F 3 X N S restored immediately. Therefore, if it isnt possible for loads to start immediately, the applicant can eliminate distracters B and D based on knowing that isnt possible.

Changed ESFAS loads to the HPSI pump. Times would be minutia.

13 F 2 N S A, CR, 41.7 14 F 3 N S D, CR, 41.9 15 H 4 M S D,CR, 41.1 D, CR, 41.4 - It is assumed that steam from S/G B can supply both SGFP A and B, but steam from S/G A can only supply SGFP A, based on the question. The 16 F 2 B S reference materials do not provide the information to support this. Please confirm if this is the intent of the question, and review reference materials to see if additional information is needed. OK as is. B side supplies both pumps.

B, CR, 41.7 - The references dont show the details of DEH control stated in support 17 H 3 N S to two of the distracters. Added additional reference.

18 H 2 M S A, CR, 41.7 19 H 3 B S B, CR, 41.7 20 F 3 B S C, CR, 41.7 A, CR, 41.7 - Reference OP-500-004, Section 4.114, SUPS SA Trouble, says that the there are no Control Room indications of this alarm. However, the nature of the question indicates that there is a loss of indication for affected components in the 21 F 3 N S Control Room.

The references provided show that the valve indications stated in the question will be part of a Loss of SUPS A. The list of items that give a SUPS SA Trouble condition Page 2 of 7 OBDI 202 - IOLE Process

ES-401 WT-2010-10 3 Form ES-401-9

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only does not include the Loss of SUPS A. Clarify how the two interface so the source of the correct answer can be understood. OK as is. Enhanced references.

C, CR, 41.7 - Will the applicant be able to determine the correct answer, not by knowing the power supply lists, but by eliminating distracters based power supply 22 F 2 M S naming conventions? Do you know that A-DC and B-DC are incorrect because neither are associated with safety equipment, per their X-DC naming convention, vice YY-DC, for example? OK as is.

D, CR, 41.7 - Based on reviewing the reference material, there does not appear to be a trigger point in the automatic loading sequence at 7 seconds for anything.

Clarify why this distracter is plausible.

23 H 4 X B S As an observation, stating that all of the wrong answers are wrong because the right answer is right doesnt prove why the distracters are plausible. Additional detail on the justification would be beneficial. This has been observed in other places as well.

Added another bullet. No overlap with Q12.

24 H 2 N S A, CR, 41.12 25 F 2 X B S B, CR, 41.4 - OK as is.

26 H 3 N S D41.5 Need to fix punctuation in first sentence after bullets. Question OK.

27 F 2 N S D41.8 28 F 2 N S C41.9 Remove ONE DONE 29 F 2 N S D41.5 See markup. Edits fixed.

30 F 1 B S C41.7 [none] Too easy. See markup. OK as is.

U 31 H 3 U M B41.2 KA Mismatch Question replaced.

S 32 H 2 N S B41.10 33 F 3 N S C41.10 See markup Fixed 34 H 2 N S B41.5 See markup for change to stem. Fixed.

35 H 3 N S B41.5 See markups. Fixed.

36 F 2 E N S D41.10 See markup. Stem focus needs to be enhanced. OK as is.

37 H 3 N S D41.5 See markup. Fixed. Page 3 of 7 OBDI 202 - IOLE Process

ES-401 WT-2010-10 4 Form ES-401-9

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 38 F 2 N S D41.8 Minor edit. Fixed.

39 H 2 N S A41.10 See markup. Fixed.

40 H 3 N S B41.14 41 H 2 N S A41.5 42 H 3 N S B41.10 See markup. Fixed.

43 H 3 M S A41.10 See markup. Fixed.

44 H 3 E N S D41.10 Fix non-credible distractor. Fixed.

45 H 3 N S B41.5 See markup. Fixed.

46 F 3 M S C41.5, 10 See markup for change to stem. Fixed.

47 F 2 E B S D41.10 Fix credible distractor. Fixed.

48 F 2 N S A41.10 49 H 3 N S D41.10 See markup. Fixed.

50 H 4 M S C41.10 Need original. See markup. Please explain. Question OK. Fixed.

51 F 2 B S A41.10 [none] Revised stem for clarity.

C41.5 See Markup. Need original. Replace KA and question for this or Q56.

52 H 3 M S Revised Q56. This is OK question.

53 H 2 M S A41.5 See markup. Fixed.

54 F 3 N S C41.10 55 F 2 N S B41.5 See markup. Fixed.

A41.5 Please revise the question as indicated on markup. Closer tie to KA. Question 56 H 2 N S revised.

57 H 3 N S D41.6 See Markups. Fixed.

58 F 2 B S B41.5 [2006 NRC]See markups. Fixed.

59 H 2 N S D41.5 60 F 2 B S C41.10 [none] Minor edit: Space between stem and answers. Fixed.

61 H 3 U U N U B41.10 See markup. The original question had little focus and it wasnt clear what Page 4 of 7 OBDI 202 - IOLE Process

ES-401 WT-2010-10 5 Form ES-401-9

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only S was being asked. Question replaced.

U 62 H 2 U N D41.10 Replace question. Does not meet KA. Question replaced.

S 63 H 3 N S C41.9 See markup. Fixed.

64 H 2 N S B41.10 See Markup. Fixed.

65 H 3 B S D41.10 [none] Note: this is borderline SRO Only, but there are no RO applicants.

66 H 3 N S A41.10 See Markup. Fixed.

67 F 2 N S D41.5 See markup. Fixed.

U 68 F 2 U N B41.10 See markup. Replaced question.

S 69 F 2 M S C41.2 70 H 3 B S A41.4 [none]

71 H 2 M S B41.12 See Markup. Fixed.

72 H 3 M S D41.12 [2000 NRC] See markup. Fixed.

U C41.10 This is too easy. SIAS is in the stem, and anyone who wouldnt know the 73 F 1 U U U N answer would guess SIAS as the answer and be correct. Does not match KA. See S markup for possible generic question. Question replaced.

74 F 3 N S C41.10 U A41.10 See comment on mark-up attached. Fixed B so there are not 2 correct 75 H 3 U N S answers.

U 1 H X N A/43.5 Question does not address RCS pressure limits. Question Replaced.

S 2 H 4 M S A/43.6 B/43.2 Administrative - move and cascading Tech Specs to stem since in all 3 F 3 N S answers. Fixed.

D/43.6 Im not sure what establish reactive load < 0.1 MW real load means and 4 F 3 X N S how that action could affect first part of answers . Changed to 1MVAR. Page 5 of 7 OBDI 202 - IOLE Process

ES-401 WT-2010-10 6 Form ES-401-9

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 5 H 4 M S B/43.5 6 H 3 N S B/43.5 7 H 2 X N S C/43.5 8 H 3 M S D/43.5 OPEN REFERENCE. Add Primary to Delta T header in answers. Fixed.

A/43.5 OP-901-110 step E0.2 directs entry into OP-901-112 if a problem with 9 H 3 X N S letdown. Therefore, C could be correct also. Question OK. Revised Distractors.

C/43.5 Stem states both CCW pumps are running therefore distractors A and B to 10 H 3 X N S use sub-section E2 for Loss of CCW Pumps are not credible. Changed E2 to E3 to remove ambiguity. Question OK.

11 H 2 X M S C/43.5 OPEN REFERENCE.

12 H 3 N S D/43.2 13 H 4 N S B/43.5 Revised procedure titles.

14 F 3 M S C/43.5 15 H 3 X N S A/43.2 OPEN REFERENCE.

D/43.5 B and C are not credible since part (1) and part (2) of the answers U contradict each other. For C, part (1) says pressurizer level controller failed with 16 H 3 X N S part (2) saying to enter procedure for letdown malfunction. Replaced question due to overlap with Q9.

17 F 4 N S A/43.5 A/43.6 Modified from 2004 W3 SRO Exam. B is also correct per procedure.

18 H 3 X B S Answer A is based on an assumption that applicant will deem 2ft per minute level drop too fast to re-grapple and move assembly. Subjective . Revised stem for clarity.

19 H 3 N S B/43.5 20 F 3  ? N S A/43.2 U D/43.2 Although TS 3.03 does have a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> element, this question is testing 21 H 2 X N S knowledge of cold shutdown requirements (37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br />). Question replaced.

22 F 3 N S D/43.2 23 F 4 B S C/43.5 FROM 2009 NRC EXAM. Page 6 of 7 OBDI 202 - IOLE Process

ES-401 WT-2010-10 7 Form ES-401-9

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 24 H 3 N S C/43.5 OPEN REFERENCE 25 H 3 B S B/43.4 OPEN REFERENCE; From 2009 NRC EXAM B= F= E=

RO TOTALS: M= H= U= Additional Notes:

N=

B= F= E=

SRO TOTALS: M= H= U= Additional Notes:

N=

GENERAL COMMENT

S:

1. Chief Examiner comments are indicated in blue. Page 7 of 7 OBDI 202 - IOLE Process

ES-401 WT-2010-10 Written Examination Review Worksheet Form ES-401-9 ALL RO MARKUPS ATTACHED AT END OF THIS FORM

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 1 H 2 N S D, CR, 41.3 A, CR, 41.5 - If the applicant recognizes that the minimum flow isnt achieved with 2 F 2 X N E single loop flow, then distracters B and C are the same.

B, CR, 41.7 - Question: Is there significance to the 28 gpm letdown flow vice it 3 H 3 B S lowering to a new level?

4 H 3 M S A, CR, 41.10 B, CR, 41.5 - Question: Do power supplies 314A and 315A supply LPSI/ECCS loads? From the references, I cant tell. This affects whether these are plausible 5 F 2 M E distracters. Also, the question references OP-901-313 Attachment 2, and Attachment 1 is provided.

6 H 3 N S A, CR, 41.10 7 F 3 M S A, CR, 41.8 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 B 5 (easy B difficult) rating scale (questions in the 2 B 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.

$ The distractors are not credible; single implausible distractors should be repaired, more than one is unacceptable.

$ 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. Enter question source: (B)ank, (M)odified, or (N)ew. Check that (M)odified questions meet criteria of ES-401 Section D.2.f.

7. Based on the reviewer=s judgment, is the question as written (U)nsatisfactory (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory?

8. At a minimum, explain any AU@ ratings (e.g., how the Appendix B psychometric attributes are not being met). Page 1 of 7 OBDI 202 - IOLE Process

ES-401 WT-2010-10 2 Form ES-401-9

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 8 H 3 M S C, CR, 41.5 9 H 2 M S D, CR, 41.10 10 H 3 N S C, OR, 41.5 11 H 3 N S B, CR, 41.7 A, CR, 41.7 - It appears that loads are restored with either a UV condition or not according to the sequencer. There appears to be no situation when loads will be 12 F 3 X N E restored immediately. Therefore, if it isnt possible for loads to start immediately, the applicant can eliminate distracters B and D based on knowing that isnt possible.

13 F 2 N S A, CR, 41.7 14 F 3 N S D, CR, 41.9 15 H 4 M S D,CR, 41.1 D, CR, 41.4 - It is assumed that steam from S/G B can supply both SGFP A and B, but steam from S/G A can only supply SGFP A, based on the question. The 16 F 2 B S reference materials do not provide the information to support this. Please confirm if this is the intent of the question, and review reference materials to see if additional information is needed.

B, CR, 41.7 - The references dont show the details of DEH control stated in support 17 H 3 N S to two of the distracters.

18 H 2 M S A, CR, 41.7 19 H 3 B S B, CR, 41.7 20 F 3 B S C, CR, 41.7 A, CR, 41.7 - Reference OP-500-004, Section 4.114, SUPS SA Trouble, says that the there are no Control Room indications of this alarm. However, the nature of the question indicates that there is a loss of indication for affected components in the Control Room.

21 F 3 N E The references provided show that the valve indications stated in the question will be part of a Loss of SUPS A. The list of items that give a SUPS SA Trouble condition does not include the Loss of SUPS A. Clarify how the two interface so the source of the correct answer can be understood.

C, CR, 41.7 - Will the applicant be able to determine the correct answer, not by 22 F 2 M E knowing the power supply lists, but by eliminating distracters based power supply naming conventions? Do you know that A-DC and B-DC are incorrect because Page 2 of 7 OBDI 202 - IOLE Process

ES-401 WT-2010-10 3 Form ES-401-9

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only neither are associated with safety equipment, per their X-DC naming convention, vice YY-DC, for example?

D, CR, 41.7 - Based on reviewing the reference material, there does not appear to be a trigger point in the automatic loading sequence at 7 seconds for anything.

Clarify why this distracter is plausible.

23 H 4 X B E As an observation, stating that all of the wrong answers are wrong because the right answer is right doesnt prove why the distracters are plausible. Additional detail on the justification would be beneficial. This has been observed in other places as well.

24 H 2 N S A, CR, 41.12 B, CR, 41.4 - The K/A aims at determining where parameters will go with the system and/or what if any control operations would be needed in response. The question as 25 F 2 X B U stated tells the applicant that controls will be operated, and that temperatures and pressures will change. The applicant should be given conditions and tested on what he/she expects to happen, and what actions if any are needed.

26 H 3 N E D41.5 Add a period at end of last sentence.

27 F 2 N S D41.8 28 F 2 N E C41.9 Remove ONE 29 F 2 N E D41.5 See markup.

30 F 1 B U C41.7 [none] Too easy. See markup.

31 H 3 U M U B41.2 KA Mismatch 32 H 2 N S B41.10 33 F 3 N E C41.10 See markup 34 H 2 N E B41.5 See markup for change to stem.

35 H 3 N E B41.5 See markups.

36 F 2 E N E D41.10 See markup. Stem focus needs to be enhanced.

37 H 3 N E D41.5 See markup.

38 F 2 N E D41.8 Minor edit 39 H 2 N E A41.10 See markup.

40 H 3 N S B41.14 Page 3 of 7 OBDI 202 - IOLE Process

ES-401 WT-2010-10 4 Form ES-401-9

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 41 H 2 N S A41.5 42 H 3 N E B41.10 See markup.

43 H 3 M E A41.10 See markup 44 H 3 E N E D41.10 Fix non-credible distractor.

45 H 3 N E B41.5 See markup 46 F 3 M E C41.5, 10 See markup for change to stem.

47 F 2 E B E D41.10 Fix credible distractor.

48 F 2 U N U A41.10 Fix focus of question to operational implication.

49 H 3 N E D41.10 See markup.

50 H 4 M E C41.10 Need original. See markup. Please explain.

51 F 2 U B U A41.10 [none] See markup. Why ask what was previously in a procedure?

52 H 3 M E C41.5 See Markup. Need original. Replace KA and question for this or Q56.

53 H 2 M E A41.5 See markup 54 F 3 N S C41.10 55 F 2 N E B41.5 See markup 56 H 2 N E A41.5 Please revise the question as indicated on markup. Closer tie to KA.

57 H 3 N E D41.6 See Markups 58 F 2 B E B41.5 [2006 NRC]See markups 59 H 2 N S D41.5 60 F 2 B E C41.10 [none] Minor edit: Space between stem and answers.

61 H 3 U U N U B41.10 See markup.

62 H 2 U N U D41.10 Replace question. Does not meet KA.

63 H 3 N E C41.9 See markup 64 H 2 N E B41.10 See Markup 65 H 3 B S D41.10 [none] Note: this is borderline SRO Only, but there are no RO applicants. Page 4 of 7 OBDI 202 - IOLE Process

ES-401 WT-2010-10 5 Form ES-401-9

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 66 H 3 N E A41.10 See Markup.

67 F 2 N E D41.5 See markup.

68 F 2 U N U B41.10 See markup 69 F 2 M S C41.2 Need original Q 70 H 3 B S A41.4 [none]

71 H 2 M E B41.12 See Markup. Need original Q.

72 H 3 M E D41.12 [2000 NRC] See markup. Need original Q.

C41.10 This is too easy. SIAS is in the stem, and anyone who wouldnt know the 73 F 1 U U U N U answer would guess SIAS as the answer and be correct. Does not match KA. See markup for possible generic question.

74 F 3 N S C41.10 75 H 3 U N U A41.10 See comment on mark-up attached.

1 H X N U A/43.5 Question does not address RCS pressure limits 2 H 4 X M E A/43.6 Would SRO be expected to know this from memory?

B/43.2 Administrative - move and cascading Tech Specs to stem since in all 3 F 3 N E answers D/43.6 Im not sure what establish reactive load < 0.1 MW real load means and 4 F 3 X N E how that action could affect first part of answers 5 H 4 M S B/43.5 6 H 3 N S B/43.5 C/43.5 Part (1) distractors referencing CCW system malfunction not credible with 7 H 2 X N U information provided in stem. The stem contains no evidence of anything wrong with CCW.

8 H 3 M S D/43.5 OPEN REFERENCE. Add Primary to Delta T header in answers.

A/43.5 OP-901-110 step E0.2 directs entry into OP-901-112 if a problem with 9 H 3 X N U letdown. Therefore, C could be correct also C/43.5 Stem states both CCW pumps are running therefore distractors A and B to 10 H 3 X N U use sub-section E2 for Loss of CCW Pumps are not credible Page 5 of 7 OBDI 202 - IOLE Process

ES-401 WT-2010-10 6 Form ES-401-9

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only C/43.5 OPEN REFERENCE. Answer D not credible based on stem since no release 11 H 2 X M E or core damage indicated. Also, 32A and 32B supply breakers should be renamed to SST A32 FEEDER and SST B32 FEEDER BREAKERS 12 H 3 N S D/43.2 13 H 4 N S B/43.5 14 F 3 M S C/43.5 A/43.2 OPEN REFERENCE. Asking tech spec knowledge vice indications of a 15 H 3 X N U dropped rod D/43.5 B and C are not credible since part (1) and part (2) of the answers 16 H 3 X N U contradict each other. For C, part (1) says pressurizer level controller failed with part (2) saying to enter procedure for letdown malfunction.

A/43.5 Is knowledge of RAB-7C Fire Area something SROs should know from 17 F 4 N E memory?

A/43.6 Modified from 2004 W3 SRO Exam. B is also correct per procedure.

18 H 3 X B E Answer A is based on an assumption that applicant will deem 2ft per minute level drop too fast to re-grapple and move assembly. Subjective B/43.5 Is there an assumption that insertion limits are being met due to absence of 19 H 3 N E Insertion Limit alarm?

A/43.2 Would SRO be expected to know the testing requirements for CVAS 20 F 3  ? N S/E boundary door? Possibly minutia.

D/43.2 Although TS 3.03 does have a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> element, this question is testing 21 H 2 X N U knowledge of cold shutdown requirements (37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br />) 22 F 3 N S D/43.2 23 F 4 B S C/43.5 FROM 2009 NRC EXAM.

24 H 3 N S C/43.5 OPEN REFERENCE 25 H 3 B S B/43.4 OPEN REFERENCE; From 2009 NRC EXAM B= F= E=

RO TOTALS: M= H= U= Additional Notes:

N=

SRO TOTALS: B= F= E= Additional Notes: Page 6 of 7 OBDI 202 - IOLE Process

ES-401 WT-2010-10 7 Form ES-401-9 M= H= U=

N=

GENERAL COMMENT

S:

1. Bank questions are indicated by B; Modified are indicated by M; New questions are indicated by N

2. Chief Examiner comments are indicated in blue.

3. Average difficulty is __ ___ on the RO exam and ___ on the SRO exam.

4. The 10CFR55.41/43 distribution is: RO / SRO 41.1 = 43.1 =

41.2 = 43.2 =

41.3 = 43.3 =

41.4 = 43.4 =

41.5 = 43.5 =

41.6 = 43.6 =

41.7 = 43.7 =

41.8 =

41.9 =

41.10 =

41.11 =

41.12 =

41.13 =

41.14 =

5. The answer distribution is: RO / SRO A = 13 (17%) / 6 (24%)

B = 16 (22%) / 7 (28%)

C = 21 (28%) / 5 (20%)

D = 25 (33%) / 7 (28%)

6. There are questions with attachments provided. Page 7 of 7 OBDI 202 - IOLE Process

Examination Outline Cross- Level RO SRO reference:

Tier # 2 Group # 1 K/A # 003 K3.01 Importance Rating 3.7 K/A Statement Knowledge of the effect that a loss or malfunction of the RCPS will have on the following:

RCS Proposed Question: RO 1 Rev: 0 The following conditions exist:

The plant is in Mode 3 with a cooldown in progress with 3 RCPs running.

RCP 2A was secured 2 minutes ago.

Which ONE of the following conditions would result in a TOTAL loss of RCS flow?

A. RCP 1B Oil Pressure is LOW.

B. RCP 1A Oil Reservoir level is LOW.

C. RCP 2B Bearing Temperature is HIGH.

D. RCP 2A has Reverse Rotation Detected.

Proposed Answer: D Explanation (Optional):

A. INCORRECT: Low oil pressure condition requires stopping the affected pump ONLY.

B. INCORRECT: Low oil level condition may require stopping the affected pump ONLY.

C. INCORRECT: High temperature condition requires stopping the affected pump ONLY.

D. CORRECT: Anti-Reverse Rotation Device is defective and the RCP 2A is running in reverse which requires securing ALL running RCPs - Loss of RCS flow.

1 Exam Submittal

Technical Reference(s) SD-RCS Table 2 (Attach if not previously OP-901-130 E5 provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-RCP00 Obj 7 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 3 Comments:

2 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 2 Group # 1 K/A # 003 K5.05 Importance Rating 2.8 K/A Statement Knowledge of the operational implications of the following concepts as they apply to the RCPS: The dependency of RCS flow rates upon the number of operating RCPs Proposed Question: RO 2 Rev: 0 The following plant conditions exist:

Cooldown to Mode 5 is in progress Boration to Refuel Boron requirements is in progress All RCPs are running Which ONE of the following RCP pump combinations describes the minimum required RCS flow alignment for RCS flow to ensure proper boron concentration is reached in both loops?

A. 1B and 2B are running B. 1A and 1B are running Since this is essentially the same as C, the applicant can easily eliminate both. Change this to one RCP in one loop.

C. 2A and 2B are running D. All 4 RCPs are required Proposed Answer: A Explanation (Optional):

A. CORRECT: This configuration has a RCP in each loop running. Procedure prefers one RCP in each loop remain running for equalization of flow through each SG to ensure proper cooldown and boron mixing.

B. INCORRECT: Procedure prefers one RCP in each loop remain running for equalization of flow through each SG to ensure proper cooldown and boron mixing.

C. INCORRECT: Procedure prefers one RCP in each loop remain running for equalization of flow through each SG to ensure proper cooldown and boron mixing.

D. INCORRECT: This would be optimum but is not the minimum requirement.

Procedure prefers one RCP in each loop remain running during cooldown for equalization of flow through each SG to ensure proper cooldown and boron mixing.

3 Exam Submittal

Technical Reference(s) OP-010-005 pg 35 & Att (Attach if not previously 9.15 provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-RCP00 Obj 10 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5 Comments:

4 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 2 Group # 1 K/A # 004 A3.14 Importance Rating 3.4 K/A Statement Ability to monitor automatic operation of the CVCS, including: Letdown and charging flows Proposed Question: RO 3 Rev: 0 The following plant conditions exist:

Reactor power is 100%

Charging Pump B is running Charging Pump A and AB control switches are in AUTO Standby Pump Selector switch is in the AB - A position Which ONE of the following describes the Letdown flow response following a trip of the running Charging Pump?

A. Lowers to 28 GPM and stabilizes Is there something significant about 28.

B. Isolates upstream of the Regenerative Heat Exchanger C. Lowers to a new value and bypasses the in-service CVCS ion exchanger D. Lowers to a new value until the standby pump starts, then returns to normal flow Proposed Answer: B Explanation (Optional):

A. INCORRECT: Letdown will no longer be cooled and will isolate on a high temperature a short time later producing NO flow condition.

B. CORRECT: Letdown will no longer be cooled and will isolate on a high temperature a short time later producing NO flow condition.

C. INCORRECT: Letdown will no longer be cooled but will bypass Ion Exchanger flow for the in-service ion exchanger a short time later.

D. INCORRECT: Letdown will no longer be cooled and will isolate on a high temperature a short time later producing NO flow condition.

5 Exam Submittal

(Attach if not previously Technical Reference(s) SD-CVC pg 10 provided)

(including version/revision OP-500-007 A-1 number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-CVC00 Obj 2 (As available)

Question Source: Bank # X 08390 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2007 RO/SRO Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 Comments:

6 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 2 Group # 1 K/A # 005 K1.06 Importance Rating 3.5 K/A Statement Knowledge of the physical connections and/or cause effect relationships between the RHRS and the following systems: ECCS Proposed Question: RO 4 Rev: 0 The following plant conditions exist:

Shutdown Cooling Train A is in service at 4000 gpm RCS pressure is 125 PSIA with depressurization in progress for Crud Burst cleanup As RCS pressure is lowered, Which which ONE of the following valves is required to be CLOSED and CAUTION tagged to prevent inadvertent makeup to the RCS from the RWSP as RCS pressure is lowered?

A. SI-109A, LPSI Pump A Suction Isolation B. SI-116A, LPSI Pump A Minimum Flow Recirculation Stop Check C. CVC-1661, Purification Ion Exchanger Outlet Header Isolation D. SI-138A, LPSI Header to RXC Loop 2A Control Proposed Answer: A Explanation (Optional):

A. CORRECT: NOTE prior to Step 5.3.14 requires SI-109A to be CLOSED and CAUTION tagged during the lineup to prevent makeup to RCS from RWSP.

B. INCORRECT: Step 5.3.11 requires SI-116A to be CLOSED to prevent loss of inventory from the RCS in the SDC lineup..

C. INCORRECT: CVC-1661 is required to be closed to prevent a loss of RCS inventory during SDC purification operations.

D. INCORRECT: SI-138A is required to be throttled closed during RCS mid-loop operation to prevent LPSI Pump vortexing.

7 Exam Submittal

(Attach if not previously Technical Reference(s) OP-009-005 Sec 5.3 provided)

(including version/revision SD-SDC Fig 1 number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-SDC00 Obj 3 (As available)

Question Source: Bank # 07906 Modified (Note changes or attach Bank # X parent)

New Question History: Last NRC Exam 2006 RO Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 10 Comments:

8 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 2 Group # 1 K/A # 006 K2.04 Importance Rating 3.6 K/A Statement Knowledge of bus power supplies to the following: ESFAS-operated valves Proposed Question: RO 5 Rev: 0 What is the power supply to SI-138 A, LPSI Header to RC Loop 2A Control Isolation?

A. Bus 213 A B. Bus 311 A C. Bus 314 A Does this and 315A exist, and are they plausible? Cant find them in references.

D. Bus 315 A Proposed Answer: B Explanation (Optional):

A. INCORRECT: SI-138 A is not powered from Bus 213A B. CORRECT: SI-138 A is powered from Bus 311A C. INCORRECT: SI-138 A is not powered from Bus 314A D. INCORRECT: SI-138 A is not powered from Bus 315A 9

Exam Submittal

(Attach if not previously Technical Reference(s) OP-901-313 Att 2 (pg 42) provided)

(including version/revision SD-SDC Table 4 number)

Proposed references to be provided to applicants during examination: NONE Learning Objective: WLP-OPS-SDC00 Obj: 2 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach X parent)

New Question History: Last NRC Exam 2009 RO/SRO Q# 31 Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5 Comments:

10 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 2 Group # 1 K/A # 007 A2.01 Importance Rating 3.9 K/A Statement Ability to (a) predict the impacts of the following malfunctions or operations on the PRTS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Stuck-open PORV or code safety Proposed Question: RO 6 Rev: 0 The following annunciator alarms are LIT on CP-2:

• Pressurizer Relief Line Temp HIGH

• Quench Tank Level HI/LO

• Quench Tank Temperature Hi Which ONE of the following conditions and corrective actions would address these alarms?

A. Leaking Pressurizer Safety Valve; Fill and Drain the Quench Tank to reduce temperature.

B. Leaking Quench Tank Drain Valve; Fill and Drain the Quench Tank to reduce temperature.

C. Leaking Reactor Vessel Vent To Quench Tank, enter Containment and isolate the leaking solenoid valve.

D. Stuck Closed Quench Tank Drain Valve; Perform a Reactor Coolant Drain Tank Leakage Diagnostic to determine the source of in-leakage.

Proposed Answer: A Explanation (Optional):

A. CORRECT: All alarms can be related to a leaking Safety Valve which requires action to maintain Quench Tank level and temperature by fill and drain method.

B. INCORRECT: Quench Tank LOW level would indicate a problem with the Quench Tank Drain Valve, but does NOT relate to Pressurizer Relief Line or Quench Tank HIGH Temp.

C. INCORRECT: A leaking Head vent would not cause a PZR Relief Line Temperature High alarm but would give the remaining alarms.

D. INCORRECT: Quench Tank HIGH level would NOT indicate a problem with the Quench Tank Drain Valve since it does NOT function in AUTO.

11 Exam Submittal

Technical Reference(s) OP-901-111 (Attach if not previously OP-500-008 A-2, D-2, F-1 provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: NONE Learning Objective: WLP-OPS-RCS00 Obj 2 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 10 Comments:

12 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 2 Group # 1 K/A # 008 K4.09 Importance Rating 2.7 K/A Statement Knowledge of CCWS design feature(s) and/or interlock(s) which provide for the following:

The standby feature for the CCW pumps Proposed Question: RO 7 Rev: 0 Which ONE of the following conditions will send an automatic start signal to ACCW Pump A?

A. Low ACCW system pressure B. High ACCW system temperature C. Dry Cooling Tower A bypass opens D. Low Component Cooling Water flow Proposed Answer: A Explanation (Optional):

A. CORRECT: ACCW pumps start on system low pressure.

B. INCORRECT: ACCW pumps start on high CCW temperature.

C. INCORRECT: ACCW pumps are NOT started on DCT in bypass.

D. INCORRECT: ACCW pumps are NOT started on Low CCW flow.

13 Exam Submittal

Technical Reference(s) SD-CC pg 45-46 and Table (Attach if not previously 1.28 provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: NONE Learning Objective: WLP-OPS-CC00 Obj 3 (As available)

Question Source: Bank # 2136-A Modified Bank # (Note changes or attach X parent)

New Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 8 Comments:

14 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 2 Group # 1 K/A # 008 A3.04 Importance Rating 2.9 K/A Statement Ability to monitor automatic operation of the CCWS, including: Requirements on and for the CCWS for different conditions of the power plant Proposed Question: RO 8 Rev: 0 The following plant conditions exist:

• Dry Cooling Tower Fans 1 - 5 A are running in SLOW.

• Component Cooling Water Heat Exchanger A Outlet temperature rose to 93.

• 15 minutes later, CCW Heat Exchanger A Outlet Temperature drops from 92 °F to 91° F and stabilizes.

Which ONE of the following conditions identifies the number of Train A Dry Cooling Tower Fans that will be running and their respective speed(s) at the 15 minute point?

(Assume ALL DCT Fans are operable and will function as designed)

FANS SPEED A. 1 thru 15 SLOW B. 1 thru 15 FAST C. 1 thru 5; 6 thru 15 FAST; SLOW D. 1 thru 5; 6 thru 15 SLOW; FAST Proposed Answer: C 15 Exam Submittal

Explanation (Optional):

A. INCORRECT: DCT fans cycle on 1 thru 15 every 60 seconds in SLOW until ALL fans are running, BUT continue to cycle on 1 thru 15 every 60 seconds in FAST until temperature is less than 92° F.

B. INCORRECT: DCT fans cycle on 1 thru 15 every 60 seconds in SLOW until ALL fans are running, THEN cycle on 1 thru 15 every 60 seconds in FAST until temperature is less than 92° F.

C. CORRECT: DCT fans cycle on 1 thru 15 every 60 seconds in SLOW until ALL fans are running, THEN cycle on 1 thru 15 every 60 seconds in FAST until temperature is less than 92° F.

D. INCORRECT: DCT fans cycle on 1 thru 15 every 60 seconds in SLOW until ALL fans are running, BUT cycle on 1 thru 15 every 60 seconds in FAST until temperature is less than 92° F.

(Attach if not previously Technical Reference(s) SD-CC pg 19-20 and 73 provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: NONE Learning Objective: WLP-OPS-CC00 Obj 3 (As available)

Question Source: Bank # 6065A Modified Bank # (Note changes or attach X parent)

New Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 5 Comments:

16 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 2 Group # 1 K/A # 010 A1.06 Importance Rating 3.1 K/A Statement Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PZR PCS controls including: RCS heatup and cooldown effect on pressure Proposed Question: RO 9 Rev: 0 Plant conditions are as follows:

• RCS pressure is 160 psia

• Pressurizer level is 98% and lowering

• The crew is drawing a Pressurizer bubble in accordance with OP-001-001, Reactor Coolant System Fill and Vent Which of the following describes how the operator knows that a bubble has been formed in the Pressurizer during this evolution?

A. Pressurizer Backup heaters cycle off.

B. Pressurizer water temperature reaches 212 °F.

C. Pressurizer water temperature reaches saturation temperature for RCS pressure.

D. Pressurizer Pressure no longer drops while Pressurizer level is being lowered.

Proposed Answer: D Explanation (Optional):

A. Incorrect: Pressurizer pressure will not be rising during this evolution.

B. Incorrect: The Pressurizer bubble does not form at 212 °F for the conditions given.

C. Incorrect: OP-001-001 directs raising Pressurizer temperature to this point, and then directs lowering Pressurizer level while monitoring Pressurizer pressure.

D. Correct: OP-001-001 has a note with this information. While raising Letdown flow and lowering Pressurizer level, pressure will stop dropping when the Pressurizer bubble is formed.

17 Exam Submittal

(Attach if not previously Technical Reference(s) OP-001-001 Step 6.6 provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: (As available)

Question Source: Bank # 1452-A Modified (Note changes or attach Bank # X parent)

New Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 10 Comments:

18 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 2 Group # 1 K/A # 010 G2.1.25 Importance Rating 3.9 K/A Statement Pressurizer Pressure Control System: Ability to interpret reference materials, such as graphs, curves, tables, etc.

Proposed Question: RO 10 Rev: 0 The plant is performing a Cooldown to Cold Shutdown in accordance with OP-010-005 using Att 9.4, Cooldown to Cold Shutdown (Mode 4 to Mode 5). The CRS has directed you to monitor the Pressurizer Cooldown evolution using Att. 9.5, Pressurizer Saturation

& Psat + 100 PSIA curve.

Which ONE of the following data points indicates an excessive pressure condition requiring operator action?

Press (PSIA) Temp (°F)

A. 167 308 B. 216 347 C. 319 386 D. 348 415 Proposed Answer: C Explanation (Optional):

A. INCORRECT: :Pressure/Temperature conditions are met on the Psat + 100 PSIA curve with NO entry into the NOT allowed region on Att 9.5.

B. INCORRECT: :Pressure/Temperature conditions are met on the Psat + 100 PSIA curve with NO entry into the NOT allowed region on Att 9.5.

C. CORRECT: Pressure/Temperature condition exceeds the Psat + 100 PSIA curve with entry into the NOT allowed region on Att 9.5.

D. INCORRECT: :Pressure/Temperature conditions are met on the Psat + 100 PSIA curve with NO entry into the NOT allowed region on Att 9.5.l 19 Exam Submittal

OP-010-005 Step 3.2.29 (Attach if not previously Technical Reference(s) and Att 9.5 provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: OP-010-005 Att 9.5 Learning Objective: WLP-OPS-PLC00 Obj 3 (As available)

Question Source: Bank #

Modified (Note changes or attach Bank # parent)

New X Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 5 Comments:

20 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 2 Group # 1 K/A # 012 A1.01 Importance Rating 2.9 K/A Statement Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RPS controls including: Trip setpoint adjustment Proposed Question: RO 11 Rev: 0 The following plant conditions exist:

The plant is operating at 100% with NOT and NOP Performance of OP-903-107, Plant Protection System Channel A Functional Test, is in progress The NPO reports that he inadvertently depressed the LOW PZR PRESS Setpoint Reset pushbutton.

Which of the following pressures (PSIA) indicates the approximate value at which Channel A would generate a low Pressurizer pressure trip?

A. 1850 B. 1684 C. 1484 D. 1284 Proposed Answer: B 21 Exam Submittal

Explanation (Optional):

A. INCORRECT: The manual RESET pushbutton will only lower the existing setpoint of a maximum of 400 PSIA below existing RCS pressure. The setpoint has a ceiling of 1684 PSIA. This number would be plausible if the candidate does not realize that there is an upper ceiling on the setpoint.

B. CORRECT: The manual RESET pushbutton will only lower the existing setpoint of a maximum of 400 PSIA below existing RCS pressure. The setpoint has a ceiling of 1684 PSIA.

C. INCORRECT: The manual RESET pushbutton will only lower the existing setpoint of a maximum of 400 PSIA below existing RCS pressure. The setpoint has a ceiling of 1684 PSIA. This number is 200 psia below existing setpoint and would be plausible if the candidate believes that it works like the Steam Pressure Lo setpoint which is 200 psia and uses the setpoint instead of process pressure to determine the new setpoint.

D. INCORRECT: The manual RESET pushbutton will only lower the existing setpoint of a maximum of 400 PSIA below existing RCS pressure. The setpoint has a ceiling of 1684 PSIA. This number is 400 psia below given setpoint and is plausible if the candidate uses the setpoint vs. process pressure to determine the new setpoint.

(Attach if not previously Technical Reference(s) SD-PPS pg 33 & Fig 30 provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: NONE Learning Objective: WLP-OPS-PPS00 Obj 3 (As available)

Question Source: Bank #

Modified (Note changes or attach Bank # parent)

New X Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 Comments:

22 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 2 Group # 1 K/A # 013 K1.12 Importance Rating 4.1 K/A Statement Knowledge of the physical connections and/or cause effect relationships between the ESFAS and the following systems: ED/G Proposed Question: RO 12 Rev: 0 The following plant conditions exist:

• EDG A is running paralleled in TEST mode for surveillance OP-903-068

• A SIAS actuation occurred with NO Loss of Offsite Power condition The EDG output breaker will (1) and the ESFAS loads will be Started (2) .

after Change (2) to sequencer times for UV and no UV.

(1) (2)

A. OPEN by the sequencer xx seconds B. OPEN Immediately yy seconds C. stay CLOSED by the sequencer D. stay CLOSED Immediately Proposed Answer: A Explanation (Optional):

A. CORRECT: EDG output breaker OPENs and after 2 seconds the sequencer loading begins since NO undervoltage conditions existed on the safety bus.

B. INCORRECT: EDG output breaker OPENs and after 2 seconds the sequencer loading begins since NO undervoltage conditions existed on the safety bus to ensure NO excess loading if IMMEDIATELY started.

C. INCORRECT: EDG output breaker OPENs and after 2 seconds the sequencer loading begins since NO undervoltage conditions existed on the safety bus.

D. INCORRECT: EDG output breaker OPENs and after 2 seconds the sequencer loading begins since NO undervoltage conditions existed on the safety bus to ensure NO excess loading if IMMEDIATELY started..

23 Exam Submittal

(Attach if not previously Technical Reference(s) SD-EDG pg 44 - 45 provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: NONE Learning Objective: WLP-OPS-EDG00 Obj 3 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 Comments:

24 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 2 Group # 1 K/A # 013 K6.01 Importance Rating 2.7 K/A Statement Knowledge of the effect of a loss or malfunction on the following will have on the ESFAS:

Sensors and detectors Proposed Question: RO 13 Rev: 0 Regarding a single channel of Plant Protection System, which ONE of the following PPS sensor failures would cause a Reactor Trip signal but NO ESFAS signal from the channel if it failed to ZERO?

A. RCP 1A Speed B. S/G 1 Level C. S/G 1 Pressure D. Wide Range Pressurizer Pressure Proposed Answer: A Explanation (Optional):

RPS and ESFAS channels share the same sensors A. CORRECT: Loss of the 1A RCP speed output (zero speed) signal will cause a reactor trip signal but is not an input to ESFAS.

B. INCORRECT: Loss of the S/G 1 Level output signal will cause a reactor trip and ESFAS (EFAS-1) signal C. INCORRECT: Loss of the S/G 1 Pressure output signal will cause a reactor trip and ESFAS (MSIS) signal D. INCORRECT: Loss of the WR Pressurizer pressure output signal will cause a reactor trip and ESFAS (SIAS/CIAS) signal.

25 Exam Submittal

(Attach if not previously Technical Reference(s) SD-PPS Fig 15 & 32 provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: NONE Learning Objective: WLP-OPS-PPS00 Obj 3 (As available)

Question Source: Bank #

Modified (Note changes or attach Bank # parent)

New X Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 Comments:

26 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 2 Group # 1 K/A # 022 A4.03 Importance Rating 3.2 K/A Statement Ability to manually operate and/or monitor in the control room: Dampers in the CCS Proposed Question: RO 14 Rev: 0 Which ONE of the following methods will OPEN the CCS-102 A(B), Emergency Discharge Damper(s)?

A. Place CCS-102 A(B) control switch to OPEN at CP-18 B. Start Containment Fan Cooler in FAST at CP-18 C. Start Containment Fan Cooler in SLOW at CP-18 D. SIAS Proposed Answer: D Explanation (Optional):

A. INCORRECT: NO control switch available B. INCORRECT: NO function tied to fan operation C. INCORRECT: NO function tied to fan operation D. CORRECT: Designed to OPEN on SIAS to direct cool air to top of containment following a LOCA or MSLB event.

27 Exam Submittal

(Attach if not previously Technical Reference(s) SD-CCS pg 10 and Fig 2 provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: NONE Learning Objective: WLP-OPS-CCS00 Obj 5 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 9 Comments:

28 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 2 Group # 1 K/A # 026 K3.02 Importance Rating 4.2 K/A Statement Knowledge of the effect that a loss or malfunction of the CSS will have on the following:

Recirculation spray system Proposed Question: RO 15 Rev: 0 The following plant conditions exist:

• A large break LOCA occurred

• Containment Spray Line A pipe failure occurred in the -35 Wing Area Which ONE of the following conditions describes the operational concern for the Safety Injection system following RAS initiation?

The ___(1)___ will not have adequate water inventory for automatic operation of the

___(2)___ pumps.

(1) (2)

A. RWSP LPSI B. RWSP HPSI C. SIS sump LPSI D. SIS sump HPSI Proposed Answer: D Explanation (Optional):

A. INCORRECT: RWSP is NOT available once RAS is initiated B. INCORRECT: RWSP is NOT available once RAS is initiated C. INCORRECT: SIS sump water will spray into -35 wing area which will cause a loss of inventory until the break can be isolated and loss of inventory for pump suction.

D. CORRECT: SIS sump water will spray into -35 wing area which will cause a loss of inventory until the break can be isolated and loss of inventory for pump suction.

29 Exam Submittal

SD-CS pg 7 (Attach if not previously Technical Reference(s) OP-902-008 pg 30 (IC-2: SI) provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: NONE Learning Objective: WLP-OPS-CS00 Obj.5 (As available)

Question Source: Bank # 6504A Modified (Note changes or attach Bank # X parent)

New Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 1 Comments:

30 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 2 Group # 1 K/A # 039 K1.08 Importance Rating 2.7 K/A Statement Knowledge of the physical connections and/or cause-effect relationships between the MRSS and the following systems: MFW Proposed Question: RO 16 Rev: 0 Steam supply to both Steam Generator Feedwater pump turbines comes from _______

and ________ .

Does steam for both turbines come from B side?? References dont make this clear.

A. Main Steam Header A; MSR A header.

B. Main Steam Header A; MSR B header.

C. Main Steam Header B; MSR A header.

D. Main Steam Header B; MSR B header.

Proposed Answer: D Explanation (Optional):

A. INCORRECT: The SGFP does NOT receive steam from the A Main Steam or the A MSR headers.

B. INCORRECT: The SGFP does NOT receive steam from the A Main Steam but does receive steam from the B MSR headers.

C. INCORRECT: The SGFP does receive steam from the B Main Steam but does NOT receive steam from the A MSR headers.

D. CORRECT: The SGFP does receive steam from both the B Main Steam and the B MSR headers based upon plant power.

31 Exam Submittal

(Attach if not previously Technical Reference(s) SD-FWP Fig 4A & pg 33 provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: NONE Learning Objective: WLP-OPS-FWP Obj 1 (As available)

Question Source: Bank # X 1871A Modified (Note changes or attach Bank # parent)

New Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 4 Comments:

32 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 2 Group # 1 K/A # 039 A2.04 Importance Rating 3.4 K/A Statement Ability to (a) predict the impacts of the following malfunctions or operations on the MRSS; and (b) based on predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Malfunctioning steam dump Proposed Question: RO 17 Rev: 0 The following plant conditions exist:

Plant is operating at 92% following Main Turbine testing MS-319A, Main Steam Bypass 1A valve, fails OPEN Which ONE of the following conditions states the initial plant response and the required operator action?

A. Turbine Governor Valve position will lower; lower turbine loading to maintain reactor power 100% and TAVG stable.

B. Reactor power will rise; lower turbine loading to maintain reactor power 100%

and TAVG stable.

C. Turbine Governor Valve position will lower; manually initiate Reactor Power Cutback.

D. Reactor power will rise; manually initiate Reactor Power Cutback.

Proposed Answer: B 33 Exam Submittal

Explanation (Optional):

A. INCORRECT: If DEH feedback loops are in service the Governor valves will open to try and compensate for the loss of MW or impulse pressure. If they are not in service the Governor valves will remain as is. The additional steam flow will cause a rise in reactor power which requires operator action to reduce main steam flow to the main turbine.

B. CORRECT: The additional steam flow will cause a rise in reactor power which requires operator action to reduce main steam flow to the main turbine.

C. INCORRECT: If DEH feedback loops are in service the Governor valves will open to try and compensate for the loss of MW or impulse pressure. If they are not in service the Governor valves will remain as is. The additional steam flow will cause a rise in reactor power which requires operator action to reduce main steam flow to the main turbine.

D. INCORRECT: The additional steam flow will cause a rise in reactor power which requires operator action to reduce main steam flow to the main turbine.

(Attach if not previously Technical Reference(s) SD-SBC pg 27-28 provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: NONE Learning Objective: WLP-OPS-SBC00 Obj 8 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam New Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 Comments:

34 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 2 Group # 1 K/A # 059 K4.05 Importance Rating 2.5 K/A Statement Knowledge of MFW design feature(s) and/or interlock(s) which provide for the following:

Control of speed of MFW pump turbine Proposed Question: RO 18 Rev: 0 Which ONE of the following signals or conditions will result in a SG Feedwater Pump A speed reduction to approximately 3900 RPM?

A. Reactor Trip Override B. SG1 High Level Override C. One of two Feedwater Flow Demand output signals fails LOW D. One of two Speed Pickup units to GE Microprocessor fails Proposed Answer: A Explanation (Optional):

A. CORRECT: A Rector Trip Override (RTO) signal is initiated on a Reactor Trip to ensure minimum SGFP output to the Steam Generators.

B. INCORRECT: High Level Override (HLO) generates a zero flow demand to close both FWRVs and a zero flow demand to SGFP control but HIGH select circuit is used and the higher of the two signal controls FWCS to non effected SG level.

C. INCORRECT: Feedwater Flow Demand controls operate on a HIGH select circuit that uses the higher of the two signal to control FWCS.

D. INCORRECT: GE Microprocessor uses two shaft speed pickup units and uses the high select for speed input.

35 Exam Submittal

(Attach if not previously Technical Reference(s) SD-FWC Figs 22 - 24 provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: NONE Learning Objective: WLP-OPS-FW00 Obj. 4 (As available)

Question Source: Bank # 3163A Modified (Note changes or attach Bank # X parent)

New Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 Comments:

36 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 2 Group # 1 K/A # 061 K6.02 Importance Rating 2.6 K/A Statement Knowledge of the effect of a loss or malfunction of the following will have on the AFW components: Pumps Proposed Question: RO 19 Rev: 0 The AB EFW pump has tripped on OVERSPEED. The NPO was directed to take the Turbine Stop Valve (MS-416) control switch to the OPEN position.

Which ONE of the following reasons would explain why the valve position did NOT change position following this action?

A. The control switch must be taken to the CLOSE position prior to going to the OPEN position.

B. The mechanical overspeed tappet nut and linkage must be locally reset.

C. The emergency steam line drain valve (MS-407) must be closed first D. The steam supply valves (MS-401 A & B) must be closed first.

Proposed Answer: B Explanation (Optional):

A. INCORRECT: A mechanical overspeed trip locks out MS-416 from opening in the control room until the mechanical overspeed tappet nut and linkage have been reset.

B. CORRECT: A mechanical overspeed trip locks out MS-416 from opening in the control room until the mechanical overspeed tappet nut and linkage have been reset.

C. INCORRECT: The valve must be reclosed after a high level condition has cleared but is NOT linked to the overspeed function.

D. INCORRECT: Not closing MS-401 A & B will not prevent MS-416 from operating.

However, the valves must be closed to reset the ramp generator to prevent another overspeed condition when restoring the pump.

37 Exam Submittal

(Attach if not previously Technical Reference(s) SD-EFW pg 16 provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: NONE Learning Objective: WLP-OPS-EFW00 Obj 5 (As available)

Question Source: Bank # X 139A Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 Comments:

38 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 2 Group # 1 K/A # 061 G2.1.28 Importance Rating 4.1 K/A Statement Auxiliary / Emergency Feedwater System: Knowledge of the purpose and function of major system components and controls.

Proposed Question: RO 20 Rev: 0 Which ONE of the following states the purpose of the bypass lines that are provided from Main Feedwater to the piping downstream of the Emergency Feedwater Pumps?

A. Provide a cleanup path for the emergency feedwater system.

B. Provide a means to test the EFW system check valves in Modes 4 - 6.

C. Keep the EFW lines filled and pressurized to prevent water hammer on EFAS initiation.

D. Keep the EFW discharge lines warm to prevent thermal shock to the SG Feedwater ring.

Proposed Answer: C Explanation (Optional):

A. INCORRECT: This is a keep filled line with NO cleanup feature provided.

B. INCORRECT: While this line contains a check valve for prevention of backflow, no test feature is provided.

C. CORRECT: Bypass line is provided to ensure the EFW piping is full of water at all times. This feature prevents a water hammer even upon actuation. In addition, the line has a check valve to prevent backflow into the Main Feedwater system D. INCORRECT: This is a keep filled line with NO warming feature provided 39 Exam Submittal

Technical Reference(s): OP-003-033 3.2.2 (Attach if not previously SD-EFW pg 29 provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: NONE Learning Objective: WLP-OPS-EFW00 Obj 7 (As available)

Question Source: Bank # X 108A Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 Comments:

40 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 2 Group # 1 K/A # 062 G2.4.46 Importance Rating 4.2 K/A Statement A.C. Electrical Distribution: Ability to verify that the alarms are consistent with the plant conditions.

Proposed Question: RO 21 Rev: 0 Please explain. The references arent clear.

The ATC reports that indication has been lost on the following CP-4 components:

CVC-101, Letdown to Regen HX from RCS Loop 2B CVC-109, Letdown HX Inlet Header Isolation CVC-510, Borated Water to VCT Header Isolation All 3 components indicate closed on the PMC.

Which ONE of the following SUPS Trouble alarms would be expected for the CVC system indications?

A. SA B. SB C. SAB D. SMD Proposed Answer: A Explanation (Optional):

A. CORRECT: A loss of SUPS SA power supply will cause the CVC valves to reposition and CC-636 should AUTO close when CVC-109 goes close but that does NOT occur on loss of AC power.

B. INCORRECT: A loss of SUPS SB does not affect these valves.

C. INCORRECT: A loss of SUPS SAB does not affect these valves.

D. INCORRECT: A loss of SUPS SMD does not affect these valves.

41 Exam Submittal

(Attach if not previously Technical Reference(s): OP-500-004 Att 4.114 provided)

(including version/revision OP-901-312 B2.8 number)

Proposed references to be provided to applicants during examination: NONE Learning Objective: WLP-OPS-PPO30 Obj 4 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 Comments:

42 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 2 Group # 1 K/A # 063 K2.01 Importance Rating 2.9 K/A Statement Knowledge of bus power supplies to the following: Major DC loads Proposed Question: RO 22 Rev: 0 Ensure plausibility of incorrect answers.

Loss of which DC bus will cause a failure of MS-401A, EFW Pump AB Turbine Steam Supply valve, to perform its AUTO function?

A. A-DC B. B-DC C. AB-DC D. TGB-DC Proposed Answer: C Explanation (Optional):

A. INCORRECT: MS-401A(B) motor operated valves receive power from the AB-DC bus.

B. INCORRECT: MS-401A(B) motor operated valves receive power from the AB-DC bus.

C. CORRECT: MS-401A(B) motor operated valves receive power from the AB-DC bus.

D. INCORRECT: MS-401A(B) motor operated valves receive power from the AB-DC bus.

43 Exam Submittal

(Attach if not previously Technical Reference(s) SD-DC pg 28 provided)

(including version/revision OP-901-313 Att 5 (pg 50) number)

Proposed references to be provided to applicants during examination: NONE Learning Objective: WLP-OPS-DC Obj. 8 (As available)

WLP-OPS-GEN Obj. 10 Question Source: Bank # 3297-A Modified (Note changes or attach Bank # X parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 Comments:

44 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 2 Group # 1 K/A # 064 A3.07 Importance Rating 3.6 K/A Statement Ability to monitor automatic operation of the ED/G system, including: Load sequencing Proposed Question: RO 23 Rev: 0 This tests same knowledge as Q12. Fix this or 12 or resample one of the KAs.

The following plant conditions exist:

EDG A & B have started due to a Loss of Offsite Power event Transformer input to MCC-315A developed a direct short to ground upon being re-energized by the Sequencer 1 second Load Block (S1 relay)

An undervoltage condition exists on 4160 Volt Bus 3A Which ONE of the following conditions describes the Sequencer response?

A. Immediately stops the automatic loading process due to Under Voltage Override (UVO) condition.

B. Immediately stops the automatic loading process due to Sequencer Lockout (SLO) condition.

C. Stops the automatic loading process when the 7 second Load Block (S3 relay) is reached.

D. Stops the automatic loading process when the 17 second Load Block (S4 relay) is reached.

Proposed Answer: D Explanation (Optional):

A. INCORRECT: : A SLO condition will occur at Load Block S4 due to the undervoltage condition on Bus 3A B. INCORRECT: : A SLO condition will occur at Load Block S4 due to the undervoltage condition on Bus 3A C. INCORRECT: : A SLO condition will occur at Load Block S4 due to the undervoltage condition on Bus 3A D. CORRECT: A SLO condition will occur at Load Block S4 due to the undervoltage condition on Bus 3A Need better explainations.

45 Exam Submittal

(Attach if not previously Technical Reference(s) SD-EDG pg 46 provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: NONE Learning Objective: WLP-OPS-EDG Obj 3 (As available)

Question Source: Bank # X 2226-A Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 Comments:

46 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 2 Group # 1 K/A # 073 K5.03 Importance Rating 2.9 K/A Statement Knowledge of the operational implications as they apply to concepts as they apply to the PRM system: Relationship between radiation intensity and exposure limits Proposed Question: RO 24 Rev: 0 The CROAI Radiation monitors isolate the Control Room Ventilation (HVC) on a high radiation level to prevent Control Room staff from receiving a maximum dose of

___(1)___ for the ___(2)___ of the event.

(1) (2)

A. 5 rem duration B. 5 rem first 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> C. 2 rem duration D. 2 rem first 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Proposed Answer: A Explanation (Optional):

A. CORRECT: The isolation of the Control Room for the duration of the event ensures no one individual will exceed the Federal Limit of 5 rem.

B. INCORRECT: Wrong duration. The isolation of the Control Room for the duration of the event ensures no one individual will exceed the Federal Limit of 5 rem.

C. INCORRECT: Wrong dose. The isolation of the Control Room for the duration of the event ensures no one individual will exceed the Federal Limit of 5 rem.

D. INCORRECT: Wrong dose, wrong duration. The isolation of the Control Room for the duration of the event ensures no one individual will exceed the Federal Limit of 5 rem.

47 Exam Submittal

(Attach if not previously Technical Reference(s) FSAR 6.4.1 provided)

(including version/revision 10 CFR 50.67(b)(iii) number)

Proposed references to be provided to applicants during examination: NONE Learning Objective: WLP-OPS-RAD02 Obj 12 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 12 Comments:

48 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 2 Group # 1 K/A # 076 A1.02 Importance Rating 2.6 K/A Statement Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the SWS controls including: Reactor and turbine building closed cooling water temperatures Proposed Question: RO 25 Rev: 0 KA mismatch.

The plant is currently producing 500 MWe output with all systems operating per design.

Which ONE of the following MANUAL operator actions is required as the plant ramps to 1100 MWe output in order to maintain Turbine Cooling Water system temperature and pressure constant?Focus this question such that the applicant must determine that temperature and pressure will be affected on TBCCW, and that throttling valves will be required. This would fit the PREDICT and/or MONITOR portion of KA better than telling them they will adjust temp and press.

Throttle the TCW Temperature Control Valve (TC-147) in the ________ direction and throttle the TCW Pressure Control Valve (TC-135) in the _________ direction.

A. OPEN  ; OPEN B. OPEN  ; CLOSED C. CLOSED ; OPEN D. CLOSED ; CLOSED Proposed Answer: B Explanation (Optional):

A. INCORRECT: Need more cooling as heat input rises during power escalation and less pressure control to maintain system in a balanced condition.

B. CORRECT: Need more cooling as heat input rises during power escalation and less pressure control to maintain system operation in a balanced condition.

C. INCORRECT: Need more cooling as heat input rises during power escalation and less pressure control to maintain system in a balanced condition.

D. INCORRECT: Need more cooling as heat input rises during power escalation and less pressure control to maintain system in a balanced condition.

49 Exam Submittal

OP-901-512 E3 (Attach if not previously Technical Reference(s) SD-TCW pg 11 provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: NONE Learning Objective: WLP-OPS-TC00 Obj 4 (As available)

Question Source: Bank # X 7045A Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 4 Comments:

50 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 2 Group # 1 K/A # 078 K3.02 Importance Rating 3.4 K/A Statement Knowledge of the effect that a loss or malfunction of the IAS will have on the following:

Systems having pneumatic valves and controls Proposed Question: RO 26 Rev: 0 Plant conditions are as follows:

• The plant is in day 18 of a refueling outage

• Shutdown Cooling Train B is in service and Train A is in standby

• SI-129 B, LPSI Pump B Flow Control, is closed

• SI-415 B, Shutdown Cooling HX B Temperature Control, is 50% open

• CC-963B, SDC HX B TCV is full open

• SI Train B flow is 3000 gpm An Instrument Air line ruptures in the RCA, causing Instrument Air pressure to drop to 20 psig. (assume pressure drop duration depletes any accumulator capacity)

Based on these conditions, Safety Injection Train B flow will (1) and RCS temperature will (2) .

(1) (2)

A. drop drop B. drop rise C. rise drop D. rise rise Proposed Answer: D 51 Exam Submittal

Explanation (Optional):

A. INCORRECT: SI-129 B fails OPEN on a loss of air and SI-415 will not respond to air leak causing SDC flow to rise but the flow is bypassing the Heat Exchanger.

B. INCORRECT: SI-129 B fails OPEN on a loss of air and SI-415 will not respond to air leak causing SDC flow to rise but the flow is bypassing the Heat Exchanger.

C. INCORRECT SI-129 B fails OPEN on a loss of air and SI-415 will not respond to air leak causing SDC flow to rise but the flow is bypassing the Heat Exchanger.

D. CORRECT: SI-129 B fails OPEN on a loss of air and SI-415 will not respond to air leak causing SDC flow to rise but the flow is bypassing the Heat Exchanger.

(Attach if not previously Technical Reference(s) SD-SDC Pages 9 & 13 provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: NONE Learning Objective: WLP-OPS-AIR Obj. 5 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 10 Comments:

52 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 2 Group # 1 K/A # 064 A4.01 Importance Rating 4.0 K/A Statement Ability to manually operate and/or monitor in the control room: Local and remote operation of the EDG Proposed Question: RO 27 Rev: 0 SAT The following plant conditions exist:

Plant was operating at 100% when a LOOP event occurred EDG B started as designed Which of the following conditions will cause an EDG B trip?

A. BOP presses the Diesel Generator B Trip pushbutton on CP-1 B. EDG B Oil Pressure drops to less than 20 psig C. EDG B Jacket Water Temperature is 210° F D. EDG B Speed rises to greater than 680 rpm Proposed Answer: D Explanation (Optional):

A. INCORRECT: Diesel Generator B Trip pushbutton on CP-1 is NOT functional during LOOP event B. INCORRECT: Engine Lube Oil pressure trip limit is 30 PSIG but NOT functional during LOOP event C. INCORRECT: Jacket Water Temperature trip limit is 205 °F but NOT functional during LOOP event D. CORRECT: Overspeed condition exist above 660 rpm to TRIP the EDG 53 Exam Submittal

OP-009-002 Section 8.8 (Attach if not previously Technical Reference(s) provided)

(including version/revision SD-EDG Table 2 & Fig 17 number)

Proposed references to be provided to applicants during examination: NONE Learning Objective: WLP-OPS-EDG00 Obj 2 (As available)

Question Source: Bank #

Modified (Note changes or attach Bank # parent)

New X Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 8 Comments:

54 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 2 Group # 1 K/A # 103 K4.01 Importance Rating 3.0 K/A Statement Knowledge of containment system design feature(s) and/or interlock(s) which provide for the following: Vacuum breaker protection Proposed Question: RO 28 Rev: 0 Which ONE of the following conditions describes the setpoint and design basis for the Containment Vacuum Relief valve operation?

At ___(1)___ INWD Containment to Annulus differential pressure, CVR-101(201) open to ensure Containment internal pressure does not become more ____(2)____ than the Containment design limit.

(1) (2)

A. 5.5 negative B. 5.5 positive C. 8.5 negative D. 8.5 positive Proposed Answer: C Explanation (Optional):

A. INCORRECT: Containment Vacuum Relief valve operation does not occur at 5.5 INWD to ensure the design Containment negative pressure is not exceeded.

B. INCORRECT: Containment Vacuum Relief valve operation does not occur at 5.5 INWD to ensure the design Containment negative pressure is not exceeded.

C. CORRECT: Containment Vacuum Relief valve auto operation occurs at 8.5 INWD to ensure the design Containment negative pressure is not exceeded.

D. INCORRECT: Containment Vacuum Relief valve auto operation occurs at 8.5 INWD to ensure the design Containment negative pressure is not exceeded.

55 Exam Submittal

OP-008-005 Section 8.1 & (Attach if not previously Technical Reference(s) 9.0 provided)

(including version/revision FSAR 6.2.3 number)

Proposed references to be provided to applicants during examination: NONE Learning Objective: WLP-OPS-CB Obj. 2 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 Comments:

56 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 2 Group # 2 K/A # 001 K1.05 Importance Rating 4.5 K/A Statement Knowledge of the physical connections and/or cause effect relationships between the CRDS and the following systems: NIS and RPS Proposed Question: RO 29 Rev: 0 Which ONE of the following output signals is used as an input (direct or calculated) signal to prohibit ALL automatic CEA movement below 15% reactor power?

A. RCS Average Temperature B. Pressurizer Pressure C. RCS Cold Leg Temperature (Subset of A. Replace this with Tref.)

D. Reactor Power (control channel)

Proposed Answer: D Explanation (Optional): Change explanations when corrections made above.

A. INCORRECT: Average Reactor Coolant Temperature output to SBCS for quick opening permissive.

B. INCORRECT: Pressurizer Pressure output to the Summed Error calculation.

C. INCORRECT: RCS Cold Leg Temperature output to Tave Loop calculation.

D. CORRECT: Power Range Control Channel output is used to produce the reactor power error calculation which prohibits auto CEA movement below 15% reactor power.

57 Exam Submittal

(Attach if not previously Technical Reference(s) SD-RR Fig 2 and pg 22 provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: NONE Learning Objective: WLP-OPS-RR00 Obj 3 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 6 Comments:

58 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 2 Group # 2 K/A # 016 K4.03 Importance Rating 2.8 K/A Statement Knowledge of NNIS design feature(s) and/or interlock(s) which provide for the following:

Input to control systems Proposed Question: RO 30 Rev: 0 Too easy. Change this to Pressurizer level control or pressure control.

RCS Reference Temperature (Tref) signal is generated in the ____(1)_____ system as a function of the ___(2)____ input.

(1) (2)

A. Reactor Regulating Main Steam Crossover Header pressure B. Steam Bypass Control Turbine First Stage pressure C. Reactor Regulating Turbine First Stage pressure D. Steam Bypass Control Main Steam Crossover Header pressure Proposed Answer: C Explanation (Optional):

A. INCORRECT: : Reactor Regulating System takes input from Turbine First Stage Pressure to calculate the current Tref but does not use MS Crossover Header Pressure.

B. INCORRECT: Steam Bypass Control uses Turbine First Stage Pressure as an input to the AMI circuitry but it does not calculate Tref in Steam Bypass Control.

C. CORRECT: Reactor Regulating System take input from Turbine First Stage Pressure to calculate the current Tref.

D. INCORRECT: Steam Bypass Control input from Main Steam Crossover Header pressure for Master Controller permissive input is NOT part of RR.

59 Exam Submittal

SD-RR Fig 02 (Attach if not previously Technical Reference(s) SD-SBC Fig 02 provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: NONE Learning Objective: WLP-OPS-RR00 Obj 2 (As available)

Question Source: Bank # X 1267B Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 Comments:

60 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 2 Group # 2 K/A # 017 A3.01 Importance Rating 3.6 K/A Statement Ability to monitor automatic operation of the ITM system including: Indications of normal, natural, and interrupted circulation of RCS Proposed Question: RO 31 Rev: 0 Need to write this to compare/contrast/recognize indications for normal natural interrupted RCS flow. As written, this is a heatup calculation and doesnt test the ability of the applicant to monitor changes in ITM based on different flow conditions.

The plant has been operating for 100 days when a shutdown was performed to repair a Reactor Coolant Pump seal. The shutdown was completed on January 4th at 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br />. All RCPs are secured and the drain down to replace the seal has been completed.

At 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> on January 8th a total loss of Shutdown Cooling occurs.

Representative Core Exit Thermocouple temperature is 123 degrees °F at the start of the event.

Due to the loss of Shutdown Cooling flow, the RCS temperature will rise to 212 °F by

______ hours on January 8th. (ASSUME: NO operator action.)

A. 2010 B. 2015 C. 2020 D. 2025 Proposed Answer: B Explanation (Optional):

A. INCORRECT: IF the plant has been shutdown 3 days which equals a value of 6.5 deg F per minute. (10 mins X 6.5 deg F/min) + 123 deg F = 188 deg F final temp.

B. CORRECT: The plant has been shutdown 4 days which equals a value of 6 deg F per minute. (15 mins X 6 deg F/min) + 123 deg F = 212 deg F final temp.

C. INCORRECT: IF the plant has been shutdown 5 days which equals a value of 5.5 deg F per minute. (20 mins X 5.5 deg F/min) + 123 deg F = 233 deg F final temp.

D. INCORRECT: IF the plant has been shutdown 6 days which equals a value of 5 deg F per minute. (25 mins X 5 deg F/min) + 123 deg F = 248 deg F final temp.

61 Exam Submittal

(Attach if not previously Technical Reference(s) OP-901-131 Att 2 provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: OP-901-131 Att 2 Learning Objective: WLP-OPS-INI00 Obj 8 (As available)

WLP-OPS-REQ21 Obj 1 Question Source: Bank # 3500A Modified Bank # X (Note changes or attach parent)

New Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 5 Comments:

62 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 2 Group # 2 K/A # 028 A2.03 Importance Rating 3.4 K/A Statement Malfunctions or operations on the HRPS; and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those malfunctions or operations: The hydrogen air concentration in excess of limit flame propagation or detonation with resulting equipment damage in containment Proposed Question: RO 32 Rev: 0 The following plant conditions exist:

Plant tripped due to a Large Break LOCA event and TSC directed that both Hydrogen Recombiners were to be placed in service Hydrogen Recombiner A failed and was removed from service Hydrogen Recombiner B is operating with a setting of 25 KW output Hydrogen Analyzers indicate Containment H2 concentration of 4.2% and rising slowly.

The CRS directs you to raise Hydrogen Recombiner B output in accordance with OP-008-006 using Attachment 11.2 to reduce Hydrogen concentration.

Post-LOCA Containment pressure is 17.7 PSIA and Pre-LOCA Containment Temperature was 105° F.

The final setting on the B potentiometer will be ____ KW to establish the required value.

A. 53 B. 55 C. 57 D. 59 Proposed Answer: B 63 Exam Submittal

Explanation (Optional):

A. INCORRECT: Using Att 11.2 and 11.4, multiply 48 KW by pressure factor (Cp) to get final value: 48 X 1.10 = 53 for (16.7 and 120)

B. CORRECT: Using Att 11.2 and 11.4, multiply 48 KW by pressure factor (Cp) to get final value: 48 X 1.15 = 55 for (17.7 and 105)

C. INCORRECT: Using Att 11.2 and 11.4, multiply 48 KW by pressure factor (Cp) to get final value: 48 X 1.19 = 57 for (18.0 and 90)

D. INCORRECT: Using Att 11.2 and 11.4, multiply 48 KW by pressure factor (Cp) to get final value: 48 X 1.23 = 59 for (18.0 and 60)

OP-902-002 Step 13 (Attach if not previously Technical Reference(s) OP-008-006 Step 6.1.9 provided)

(including version/revision OP-008-006 Att 11.2 & 11.4 number)

Proposed references to be provided to applicants during OP-008-006 Att 11.2 examination: & 11.4 Learning Objective: WLP-OPS-HRA00 Obj 3 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 8 Comments:

64 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 2 Group # 2 K/A # 029 G 2.4.30 Importance Rating 2.7 K/A Statement Containment Purge System: Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.

Proposed Question: RO 33 Rev: 0 With the plant in Mode 1, which of the following conditions would require a 60 day LER for failure to comply with Tech Specs if the condition was not corrected?

A. Pressurizer level stable rose and stabilized at 61%. WHAT?? Please fix this.

B. Containment pressure dropped and stabilized at 14.57 psia.

C. Containment Purge Isolations remained open for 95 hours0.0011 days <br />0.0264 hours <br />1.570767e-4 weeks <br />3.61475e-5 months <br /> in a 365 day period.

D. RWSP boron concentration sample results are reported as 2150 ppm.

Proposed Answer: C Explanation (Optional):

A. INCORRECT: The Tech Spec 3.4.3.1 limit for Pressurizer level is < 62.5 %.

B. INCORRECT: The Tech Spec 3.6.1.4 limit for containment pressure is 14.275 psia.

C. CORRECT: The Tech Spec 3.6.1.7 limit for a Containment Purge Isolation Valve is 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> in the previous 365 days.

D. INCORRECT: The Tech Spec 3.5.4 limit for RWSP boron concentration is 2050 ppm.

65 Exam Submittal

Tech Spec 3.4.3.1, 3.5.4, (Attach if not previously Technical Reference(s) 3.6.1.4, 3.6.1.7. provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: NONE Learning Objective: WLP-OPS-TS04 Obj 1 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 Comments:

66 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 2 Group # 2 K/A # 035 K3.01 Importance Rating 4.4 K/A Statement Knowledge of the effect that a loss or malfunction of the S/GS will have on the following:

RCS Proposed Question: RO 34 Rev: 0 The following plant conditions exist:

• Mode 3 following a Reactor Trip due to an Excess Steam Demand event in the TGB

• Both ADVs were maintaining SG pressure at 991 psig in AUTO

• Subsequently, both ADVs failed to the CLOSE position Which ONE of the following temperature (°F) RISES corresponds to the MINIMUM RCS temperature rise to reach saturation pressure for the LOWEST lift setpoint for the SG Safety Valves?If both ADVs were to fail CLOSED, how far must RCS temperature rise in order to start lifting the FIRST SG Safety Valve?

A. 12°F B. 9°F C. 6°F D. 3°F Proposed Answer: B Explanation (Optional):

A. INCORRECT: The 2nd safety lifts at 1085 psig (1100 PSIA) which corresponds to 556 °F; therefore a change of 11 °F is required.

B. CORRECT: Current pressure is 991 psig (1006 PSIA) which corresponds to 545 °F and the First safety lifts at 1070 psig (1085 PSIA) which corresponds to 554 °F; therefore a change of 9 °F is required.

C. INCORRECT: The First safety lifts at 1070 psig (1085 PSIA) which corresponds to 554 °F; therefore a 6 °F change is insufficient D. INCORRECT: The First safety lifts at 1070 psig (1085 PSIA) which corresponds to 554 °F; therefore a 3 °F change is insufficient 67 Exam Submittal

(Attach if not previously Technical Reference(s) SD-MS Table 1 pg 34 provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: Steam Tables Learning Objective: WLP-OPS-MS00 Obj 4 (As available)

Question Source: Bank # X 07717 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 1 Comments:

68 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 2 Group # 2 K/A # 041 G2.4.2 Importance Rating 4.5 K/A Statement Steam Dump System (SDS) and Turbine Bypass Control: Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.

Proposed Question: RO 35 Rev: 0 The following plant conditions exist:

Plant is operating at 100%

RCS Tavg is 573° F RCS pressure is 2250 PSIA Reactor Cutback is Out of Service Reactor Trip on Turbine Trip is ENABLED Which ONE of the following describes the response of the Steam Bypass Control System immediately following a Turbine Trip?Following a Turbine Trip, the Steam Bypass Control System will quick open _______ Bypass Valves.

Valve(s) _______ will quick open.

A. ONLY 1 through 3 B. ONLY 1 through 5 C. 1 through 6 D. NoneONLY 2 through 6 Proposed Answer: B 69 Exam Submittal

Explanation (Optional):

A. INCORRECT: With RXC out of service and Reactor Power at 100% the Reactor Trip on Turbine Trip is enabled. When the turbine trips the reactor then trips. The reactor trip automatically blocks Quick Open on steam bypass valve 6 With Tavg >

561°F Valves 1,2,3,4,5 will receive quick open signals. Valves 1-3 is plausible because the valves open together on a QO1 signal.

B. CORRECT: With RXC out of service and Reactor Power at 100% the Reactor Trip on Turbine Trip is enabled. When the turbine trips the reactor then trips. The reactor trip automatically blocks Quick Open on steam bypass valve 6 With Tavg >

561°F Valves 1,2,3,4,5 will receive quick open signals. INCORRECT: Valves 1,2,3,4,5 ONLY receive quick open signal with RXC signal OOS and a Reactor Trip is generated.

C. INCORRECT: Valves 1-6 is plausible if the candidate does not know that valve 6 is blocked on a reactor trip.

D. None would be plausible if the candidate misapplies the QO blocks generated by RXC when .a feed pump trips. All 6 valves are blocked from QO in that case.

However, this is generated by the RXC system which is out of service. And the event is wrong.

(Attach if not previously Technical Reference(s) SD-SBC Fig 11 & 21 provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: NONE Learning Objective: WLP-OPS-SBC00 Obj: 5 (As available)

Question Source: Bank # X 07938 Modified (Note changes or attach Bank # parent)

New Question History: Last NRC Exam 2006 RO Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 Comments:

70 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 2 Group # 2 K/A # 055 K1.06 Importance Rating 2.6 K/A Statement Knowledge of the physical connections and/or cause effect relationships between the CARS and the following systems: PRM system Proposed Question: RO 36 Rev: 0 Per the procedure, this is only true when checking for condenser air in-leakage (which may be true during normal ops, but is not explained in the references). Set this up in the stem.

OP-003-001, Condenser Air Evacuation System, requires Condenser Vacuum Pumps (1) be operating to provide a suction path for the (2)

(1) (2)

A. A or B Condenser Air Evacuation WRGM B. A or B Condenser Air Evacuation PIG Rad Monitor C. B or C Condenser Air Evacuation WRGM D. B or C Condenser Air Evacuation PIG Rad Monitor Proposed Answer: D Explanation (Optional):

Condenser Air Evacuation Wide Range Was Monitor takes a suction from the common discharge of all 3 Air Evacuation Pumps. The Condenser Air Evacuation PIG Radiation Monitor takes a suction from B and C Air Evacuation Pumps. OP-003-001 specifies that either B or C Pumps must be running to ensure the discharge is monitored by the Condenser Air Evacuation PIG.

71 Exam Submittal

SD-AE Fig 1 (Attach if not previously Technical Reference(s) SD-RMS Table 4 & 5 provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: NONE Learning Objective: WLP-OPS-AE00 Obj 1 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 Comments:

72 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 2 Group # 2 K/A # 011 A2.04 Importance Rating 3.5 K/A Statement Ability to (a) predict the impacts of the following malfunctions or operations on the PZR LCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of one, two or three charging pumps Proposed Question: RO 37 Rev: 0 Plant conditions are as follows:

• Power is 100%

• Charging Pump A is running

• CVC-ILT-0227 (NAME)fails to 0%

The crew secured Charging Pump A and closed CVC-101 in accordance with OP-901-113, Volume Control Tank Makeup Control Malfunction.

Based on these conditions, the first backup Charging Pump will start when Pressurizer level drops (1) below Pressurizer level setpoint and the crew will be required to (2) after the Charging Pump starts.

(1) (2)

A. 3.9% makeup to the VCT B. 3.9% reduce Main Turbine load C. 2.5% makeup to the VCT D. 2.5% reduce Main Turbine load Proposed Answer: D Explanation (Optional):

A. INCORRECT: The first Pump will start at -2.5% below program but the second pump will NOT start until -3.9% below program; Initial operator action is to reduce Main Turbine load due to the boration that occurs.

B. INCORRECT: The first Pump will start at -2.5% below program but the second pump will NOT start until -3.9% below program.

C. INCORRECT: The Initial operator action is to reduce Main Turbine load due to the boration that occurs.

D. CORRECT: The first Pump will start at -2.5% below program; Initial operator action is to reduce Main Turbine load due to the boration that occurs.

73 Exam Submittal

(Attach if not previously Technical Reference(s) SD-CVC pg 23 provided)

(including version/revision OP-901-112 C & E0 number)

Proposed references to be provided to applicants during examination: NONE Learning Objective: WLP-OPS-CVC Obj 6 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 Comments:

74 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 2 Group # 2 K/A # 086 A4.05 Importance Rating 3.0 K/A Statement Ability to manually operate and/or monitor in the control room: Deluge valves Proposed Question: RO 38 Rev: 0 Which of the following is the only air filtration unit that has a Fire Protection Deluge system which that can be operated from the Control Room?

A. RAB Normal Exhaust Unit B. CVAS Emergency Filtration Unit C. Shield Building Ventilation Filter Unit D. Airborne Radioactivity Removal Unit Proposed Answer: D Explanation (Optional):

A. INCORRECT: RAB Normal Unit has a manual deluge actuation operated locally in the RAB B. INCORRECT: CVAS Emergency Unit has a manual deluge actuation operated locally in the RAB C. INCORRECT: SBV Unit has a manual deluge actuation operated locally in the RAB D. CORRECT: The ARR Unit has a manual deluge actuation operated from the Control Room.

75 Exam Submittal

OP-009-004 Step 8.10 (Attach if not previously Technical Reference(s) SD-FP Table 5 provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: NONE Learning Objective: WLP-OPS-FP00 Obj 2 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 Comments:

76 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 1 Group # 1 K/A # E02 EA2.2 Importance Rating 3.0 K/A Statement Ability to determine and interpret the following as they apply to the (Reactor Trip Recovery): Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.

Proposed Question: RO 39 Rev: 0 A reactor trip has just occurred.

Which of the following support entry into OP-902-001, Reactor Trip Recovery?

(Assume components and parameters that are not described listed below operate as designedare as designed)

A. Two (2) CEAs fully withdrawn, with, with emergency boration in progress.

B. Pressurizer level is 25% and lowering with three (3) charging pumps running.

C. S/G 1 and 2 levels are 45% NR and lowering after an inadvertent MSIS.

D. Containment pressure is 16.5 psia and stable with the Containment PIG in alert.

Proposed Answer: A 77 Exam Submittal

Explanation (Optional):

A. CORRECT. With all other parameters normal as stated in the stem this condition supports entry into OP-902-001.

B. Incorrect. This indicates a condition where an RCS leak is greater than charging capacity and would not support entry into OP-902-001 C. Incorrect. The conditions given would not support entry into OP-902-001 because MSIS closes the MFIVs and therefore a loss of main feedwater has occurred.

D. Incorrect. Containment pressure and rising activity in containment would drive you to OP-902-002 or OP-902-008.

Technical Reference(s) OP-902-001, Rev 011 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE01 Obj: 12 Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41(b) 10 Comments:

78 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 1 Group # 1 K/A # 008 AK1.01 Importance Rating 3.2 K/A Statement Knowledge of the operational implications of the following concepts as they apply to a Pressurizer Vapor Space Accident: Thermodynamics and flow characteristics of open or leaking valves Proposed Question: RO 40 Rev: 0 The plant was at 100% power when Pressurizer Safety Valve, RC-317A, failed open.

The crew tripped the reactor and initiated SIAS and CIAS.

The following conditions exist:

• RCS pressure - 1250 PSIA

• RCS Thot temperature - 552 °F

• Quench Tank pressure - 41 PSIG What is the expected temperature indication of the Pressurizer Relief Line?

A. 267 °F B. 288 °F C. 552 °F D. 572 °F Proposed Answer: B 79 Exam Submittal

Explanation (Optional):

A. Incorrect. Value is equal to the given pressure if the candidate does not convert to psia from psig which is the normal units for Quench Tank Pressure indication on CP-2.

B. CORRECT. This value corresponds to the value that can be obtained from a Molliere diagram for 56 psia, assuming that the throttling process across the open relief valve is isenthalpic C. Incorrect. This value is equal to the Hot Leg temperature given, which could be selected if the candidate does not realize that the throttling process is isenthalpic and assumes that an in-surge from the Hot Leg has lowered PZR Temperature to Hot Leg Temperature.

D. Incorrect. This value is equal to the saturation temperature for the RCS pressure given and could be selected if the candidate realizes the RCS is still subcooled, and therefore no significant in-surge has occurred to the PZR, but does not realize that the throttling process is isenthalpic.

Technical Reference(s) Steam Tables - Properties of Saturated and Superheated Steam Proposed references to be provided to applicants during examination: Steam Tables Learning Objective: WLP-OPS-RCS00 Obj: 2 WLP-OPS-RCS00 Obj: 5 Question Source: Bank # WF3-OPS-7177-A Modified Bank #

New Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41(b) 14 Comments:

80 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 1 Group # 1 K/A # 009 EK3.12 Importance Rating 3.4 K/A Statement Knowledge of the interrelations between the small break LOCA and the following: Letdown Isolation Proposed Question: RO 41 Rev: 0 The plant was operating at 100% power when a double ended shear of the Letdown line occurs at the weld on the outlet of the Regenerative Heat Exchanger. Given the following timeline:

• T1 - PZR Pressure 1900 psia, Containment Pressure = 16.5 psia

• T2 - PZR Pressure 1800 psia, Containment Pressure = 17.0 psia

• T3 - PZR Pressure 1700 psia, Containment Pressure = 17.5 psia

• T4 - PZR Pressure 1600 psia, Containment Pressure = 18.0 psia Letdown initially isolated due to _______ Pressure. At the end of the timeline the break is isolated from the RCS by a total of __________ automatic isolation valves.

A. Containment; two B. PZR; two C. Containment; three D. PZR; three Proposed Answer: A 81 Exam Submittal

Explanation (Optional):

A. CORRECT. The timeline indicates that the setpoint is met for the High Containment Pressure (SIAS) (17.1 psia) prior to exceeding any ESFAS setpoint (PZR Press (SIAS) (1684 psia). The break is located inside containment on the outlet of the Regenerative HX upstream of the containment isolation that is outside containment. Therefore, the break is isolated from the RCS by two valves (CVC-101, CVC-103).

B. Incorrect. Wrong isolation parameter, correct number of valves. See explanation A.

C. Incorrect. Correct isolation parameter, wrong number of valves. See explanation A.

D. Incorrect. Wrong isolation parameter, wrong number of valves. See explanation A.

Technical Reference(s) OP-002-005, Chemical and Volume Control, Rev. 32 OP-902-009, Standard Appendices, Rev. 301 OP-902-000, Standard Post Trip Actions, Rev. 10 G-168, Chemical and Volume Control Sheet 1, Rev. 43 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-CVS00 Obj. 11 WLP-OPS-CVC00 Obj.3 Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41(b) 7 Comments:

82 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 1 Group # 1 K/A # 015 AA2.10 Importance Rating 3.7 K/A Statement Ability to determine and interpret the following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): When to secure RCPs on loss of cooling or seal injection Proposed Question: RO 42 Rev: 0 Given the Following:

• The Reactor is operating at 100% RTP

• At 1445 the following alarms and indications are noted in the Control Room o Panel M, CCW Surge Tank Level Lo-Lo A o Panel N, CCW Surge Tank Level Lo-Lo B o Panel N, CCW Surge Tank Level Hi-Lo o All Automatic Actions have occurred What is the latest time that CCW flow can be restored to the Reactor Coolant Pumps without requiring they be tripped per OP-901-510, Component Cooling Water System Malfunction?In accordance with OP-901-510, CCW Malfunction, CCW flow must be restored to the Reactor Coolant Pumps by ________ or all RCPs must be tripped.

A. 1447 B. 1448 C. 1450 D. 1455 Proposed Answer: B Explanation (Optional):

A. Incorrect. See B. This was previously a good answer at Waterford 3.

B. CORRECT. OP-901-510, Section E1 states that if CCW flow is lost to the AB header and cannot be restored within 3 minutes, trip the reactor and trip all RCPs. The conditions in the stem provide indication that flow is lost to the AB header.

C. Incorrect. See B.

D. Incorrect. See B. 10 minutes, as mentioned in OP-901-510 Section E1, CAUTION 1 is the time that if exceeded could cause damage to RCP Seals if CCW flow is then restored to an affected RCP.

83 Exam Submittal

Technical Reference(s) OP-901-510, Component Cooling Water System Malfunction Rev 300 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPO05 Obj.06 Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41(b) 10 Comments 84 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 1 Group # 1 K/A # 022 AA1.01 Importance Rating 3.4 K/A Statement Ability to operate and/or monitor the following as they apply to the Loss of Reactor Coolant Makeup: CVCS letdown and charging Proposed Question: RO 43 Rev: 0 Given the following:

• The plant is performing a heatup to NOP/NOT

• RCS Pressure is 1300 psia

• RCS temperature is 440ºF

• Charging Pump B is the Lead Pump

• Charging pump AB is OOS

• Charging pump A is the first backup pump and in standby Charging Pump B trips on overcurrent. The direction provided in OP-901-112, Charging or Letdown Malfunction, would be to firstinitially directs the operator to____:.

SPACE A. vVerify a suction path aligned and manually start Charging Pump A.

B. vVerify a suction path aligned and verify Charging Pump A cycles on PZR level.

C. mManually close CVC-101, Letdown Stop Valve.

D. vVerify auto closure of CVC-101, Letdown Stop Valve.

Proposed Answer: A 85 Exam Submittal

Explanation (Optional):

A. CORRECT. OP-901-112 has the Operator verify either the VCT or RWST suction valve open and attempt to restart a charging pump if a charging pump trips and letdown has not isolated.

B. Incorrect. OP-901-112 manually restarts a charging pump vice allowing the auto start to occur. Plausible if candidate realizes that the given conditions will not result in an auto isolation of letdown.

C. Incorrect. This action is performed if a charging pump can not be restarted and letdown is still in service.

D. Incorrect. The auto isolation will not occur since the temperature of the RCS is currently below the auto isolation setpoint of 470ºF.

Technical Reference(s) OP-901-112, Charging and Letdown Malfunction, Rev. 3 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPO10 Obj. 3 WLP-OPS-PPO10 Obj. 4 Question Source: Bank #

Modified Bank # WF3-OPS-4273-B New Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41(b) 7 / 10 Comments:

86 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 1 Group # 1 K/A # 025 G2.2.38 Importance Rating 3.6 K/A Statement Knowledge of conditions and limitations in the facility license.

Proposed Question: RO 44 Rev: 0 Given the following:

• The plant is in MODE 6 with core shuffle in progress

• Cavity level is 44 MSL

• LPSI Pump A is OOS

• LPSI Pump B is OPERABLE and in operation LPSI Pump B trips. Which of the following is prohibited per Technical Specifications?

A. Shuffling CEAs within the core using the CEA Mast.

B. Loading a new fuel assembly into the core from the Spent Fuel Pool.

C. Adding 200 gallons of Boric Acid to the RCS from an OPERABLE BAM Tank.

Not credible.

D. Loading a twice burned fuel assembly into the core from the Spent Fuel Pool.

Proposed Answer: D Explanation (Optional):

A. Incorrect. Shuffling CEAs within the vessel does not increase decay heat load or constitute an operation that would lower boron concentration below that required by TS 3.9.1.

B. Incorrect. Loading new fuel assemblies does not increase decay heat load or constitute an operation that would lower boron concentration below that required by TS 3.9.1.

C. Incorrect. Adding boric acid to the RCS does not increase decay heat load or constitute an operation that would lower boron concentration below that required by TS 3.9.1.

D. CORRECT. Loading a previously burned fuel assembly into the core increases decay heat load and is prohibited by TS 3.9.8.1 when the LCO is not met 87 Exam Submittal

Technical Reference(s) TS 3/4.9.8.1, Amendment 185 B3/4.9.8, Change 19 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-REQ04 Obj. 2 Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41(b) 10 Comments:

88 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 1 Group # 1 K/A # 026 AA2.01 Importance Rating 2.9 K/A Statement Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: Location of a leak in the CCW system Proposed Question: RO 45 Rev: 0 Given the following

• A leak is occurring in the Component Cooling Water System

• Initially CCW Surge Tank Level A and B lowered to 0%

• CCW Surge Tank level A remains at 0%

• CCW Surge Tank level B recovered to ~ 55% and stabilized Which of the following is potentially the a potential location of the leak?

A. Supply pipe to Waste Gas Compressor A B. Supply pipe to Shutdown Cooling HX A C. Return pipe from Spent Fuel Pool HX A D. Return pipe from CEDM Fan Cooler A Proposed Answer: B Explanation (Optional):

A. Incorrect. The Waste Gas compressor is an NNS Loop load. This pipe would have been automatically isolated by the AB loop isolation valves and level in both sides of the CCW surge tank would have recovered.

B. CORRECT. Shutdown HX A is a Safety Loop A load. Safety Loops A and B would be split out such that the leak no longer affects Loop B until CCW Surge Tank Level B exceeds 55% which is the top of the baffle separating A and B sides of the CCW surge tank.

C. Incorrect. SFP HX A is an AB Loop load. This pipe would have been automatically isolated by the AB Loop isolation valves and level in both sides of the CCW surge tank would have recovered.

D. Incorrect. CEDM Fan Cooler A is an AB Loop load. This pipe would have been automatically isolated by the AB Loop isolation valves and level in both sides of the CCW surge tank would have recovered.

89 Exam Submittal

Technical Reference(s) OP-901-510, Component Cooling Water Malfunction, Rev. 4 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-CC00 Obj. 7 Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41(b) 7 Comments:

90 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 1 Group # 1 K/A # 027 AK3.03 Importance Rating 3.7 K/A Statement Knowledge of the reasons for the following responses as they apply to the Pressurizer Pressure Control Malfunctions: Actions contained in EOP for PZR PCS malfunction Proposed Question: RO 46 Rev: 0 GIVEN:

• Mode 1

• A loss of all PZR heaters has occurred

• Crew entered OP-901-120, Title

• The decision is made to reduce power While reducing power, the crew must _________ in order to ________.

During a loss of all pressurizer heaters, OP-901-120, Pressurizer Pressure Control Malfunction, provides steps to (1) during power reduction to (2) .

A. (1) maintain PZR level constant (2) maintain PZR pressure constant B. (1) raise PZR level (2) maintain PZR pressure constant C. (1) maintain PZR level constant (2) conserve PZR inventory and enthalpy D. (1) raise PZR level (2) conserve PZR inventory and enthalpy Proposed Answer: C 91 Exam Submittal

Explanation (Optional):

A. Incorrect. The methodology used is correct per OP-901-120; however, even if you maintain PZR level constant RCS pressure will lower due to charging water into the PZR via the surge line that is at Hot Leg temperature, the effects of PZR Spray bypass flow into the PZR steam space, and ambient heat losses from the PZR. If the candidate does not have a good grasp on fundamentals this is an attractive answer.

B. Incorrect. Both the methodology and procedure bases are wrong. OP-901-120 has steps to take local control of PZR level controller setpoint and then set the setpoint to current PZR level before starting a down power. The basis is also wrong (see explanation in A).

C. CORRECT. Per OP-901-120 this is the correct approved methodology and the correct bases (See note prior to step for setting up PZR level controller).

D. Incorrect. Per OP-901-120 the methodology for PZR level control is wrong,;

however, this could be a viable way to control pressure during the down power.

The Bases is correct per OP-901-120.

Technical Reference(s) OP-901-120, Pressurizer Pressure Control Malfunction Rev. 301 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPO10 Obj. 4 Question Source: Bank #

Modified Bank # WF3-OPS-5995-A New Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41(b) 10 Comments:

92 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 1 Group # 1 K/A # 029 G2.4.11 Importance Rating 4.0 K/A Statement Knowledge of abnormal condition procedures.

Proposed Question: RO 47 Rev: 0 The basis for re-closing the A32 and B32 feeder breakers 5 seconds after opening during an ATWS is to restore power to the:

SPACE A. CEDMCS in order to verify that all CEAs have fully inserted.

B. A32 and B32 busses before UV relays strip loads from the busses. Not Credible C. CEDM cooling fans to protect CEDM coils from overheating.

D. pressurizer heaters to maintain RCS pressure control.

Proposed Answer: D Explanation (Optional):

A. Incorrect. Power for rod position indication is independent of power from A32 and B32 to CEDM MG Sets.

B. Incorrect. The associated UV relays would have already operated by this point and all loads on the Bus that strip on UV would have already have been stripped.

C. Incorrect. CEDM cooling fans are powered from A31 and B31.

D. CORRECT. Re-closing the A32 and B32 feeder breakers allows for maintaining RCS pressure control via the pressurizer heaters. This is in accordance with the basis for Step 1 of OP-902-000, Standard Post Trip Actions as listed in TGOP-902-000, Technical Guide for Standard Post Trip Actions.

93 Exam Submittal

Technical Reference(s) TGOP-902-000, Technical Guide for Standard Post Trip Actions, Rev. 9 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE01 Obj 11 (As available)

Question Source: Bank # WF3-OPS-1704-A Modified Bank #

New Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41(b) 10 Comments:

94 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 1 Group # 1 K/A # 038 EK1.02 Importance Rating 3.2 K/A Statement Knowledge of the operational implications of the following concepts as they apply to the SGTR: Leak rate vs. pressure drop Proposed Question: RO 48 Rev: 0 KA mismatch. Need to focus on operational implication (i.e. throttling SI during depressurizing, overfilling SG due to high DP etc). We can discuss this one.

With a Steam Generator Tube Rupture in progress it is ultimately desired to depressurize the RCS to within ___(1)___ psid of the ruptured Steam Generator to

___(2)___ and minimize the potential for Steam Generator overfill.

(1) (2)

A. 50 minimize the potential release to the environment B. 50 prevent loss of subcooled margin C. 100 minimize the potential release to the environment D. 100 prevent loss of subcooled margin Proposed Answer: A Explanation (Optional):

A. CORRECT. Per step 12 of OP-902-007 and TG-OP-902-007 this is the correct pressure differential. Per TG-OP-902-007 this minimizes pri-to-sec leakage which minimizes release magnitude and helps to prevent S/G overfill.

B. Incorrect. Right D/P, wrong bases. The substep within step 12 that provides instructions for maintaining RCS pressure within the P/T curve limits prevents loss of subcooled margin and allows continued operation of RCPs.

C. Incorrect. Wrong D/P; right bases.

D. Incorrect. Wrong D/P, wrong bases.

95 Exam Submittal

Technical Reference(s) OPO-902-007, Steam Generator Tube Rupture Recovery, Rev. 012 TG-OP-902-007, Rev. 302 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE07 Obj 3 (As available)

Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41(b) 14 Comments:

96 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 1 Group # 1 K/A # E05 EK2.2 Importance Rating 3.7 K/A Statement Knowledge of the interrelations between the (Excess Steam Demand) and the following:

Facilitys heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.

Proposed Question: RO 49 Rev: 0 An Excess Steam Demand event is in progress and OP-902-004, Excess Steam Demand Recovery is being implemented.

• RCS Subcool Margin 80ºF and stable

• SG 1 pressure is 540 psia and lowering

• SG 2 pressure is 670 psia and stable

• SG 1 level 45% WR and lowering

• SG 2 level 60% WR and lowering slowly

• Containment Pressure 25 psia and rising

• Containment Spray Pump A is tagged out with CS-125A gagged shut

• Containment Spray Header B flow is 1000 gpm

• CVC-103, Letdown Inside Containment Isolation Valve stuck open

• EFW-228A, Emergency Feedwater Isolation SG 1 Primary is tagged closed

• All other systems and components are operating as designed Which Safety Function is not being met as a result of these failures?

Based on this, which Safety Function is NOT being met?

A. RCS Pressure Control B. RCS Heat Removal C. Containment Isolation D. Containment Temperature and Pressure Control Proposed Answer: D 97 Exam Submittal

Explanation (Optional):

A. Incorrect. RCS pressure Control can be met by LPSI and HPSI pumps providing flow > OP-902-009 Appendix 2 curves. This is implied by the last bullet in the conditions given.

B. RCS Heat Removal. Although S/G 2 level is lowering the final bullet implies that that EFAS-2 actuated per design and EFW is operating per design. The level given would not be low enough yet for EFW to feed S/G 2. Operators are trained to evaluate this safety function as SAT if EFW is automatic and working as designed. Tc can also be implied to be lowering during the blowdown phase of an excess steam demand. The conditions given imply that information.

C. Incorrect. Both CVC containment isolation valves would have to fail to jeopardize the Containment Isolation safety function. The last bullet implies that this is not the case.

D. CORRECT. At least one Containment Spray pump must be providing > 1750 gpm of flow to meet the CT&PC safety function.

Technical Reference(s) OP-902-004, Excess Steam Demand Recovery, Rev. 11 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE04 Obj. 6 (As available)

Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41(b) 10 Comments:

98 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 1 Group # 1 K/A # E06 G2.1.7 Importance Rating 4.4 K/A Statement Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

Proposed Question: RO 50 Rev: 0 The plant has tripped due to a loss of both Main Feedwater Pumps. The crew has diagnosed to OP-902-006 and taken all required actions. The plant will be cooled down to SDC entry conditions. The plant conditions are as follows:

• RCPs 1B and 2B are running

• CSP Level = 50%

• DWST Level = 70%

• RCS Thot = 550 degrees F

• Plant Shutdown = 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> The approximate maximum time remaining to place SDC in service is:

A. 29 hours3.356481e-4 days <br />0.00806 hours <br />4.794974e-5 weeks <br />1.10345e-5 months <br /> B. 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> C. 19 hours2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br /> D. 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> Proposed Answer: C Explanation (Optional):

A. Incorrect. This is the value that would be obtained if the no RCPs operating curve were used (OP-902-009 Att. 2-J).

B. Incorrect. This is the value that would be obtained if the correct attachment were used but the candidate did not take into account the water needed to remove the sensible heat between Thot of 550ºF and SDC entry conditions of 350ºF.

C. CORRECT. This is the value that should be obtained if the candidate calculates available feedwater and selects and correctly reads the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> curve on Att. 2-I of OP-902-009.

D. Incorrect. This is the value obtained using the 4 RCP operating curve of OP-902-009 (Att. 2-H).

99 Exam Submittal

Technical Reference(s) OP-902-009, Standard Appendices, Rev. 301 Proposed references to be provided to applicants during OP-902-009 Att. 2-G examination: thru 2-J Learning Objective: WLP-OPS-PPE06 Obj. 4 WLP-OPS-PPE06 Obj. 9 Question Source: Bank #

Modified Bank # WF3-OPS-6908-A New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41(b) 5 / 10 Comments:

100 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 1 Group # 1 K/A # 055 EA1.06 Importance Rating 4.1 K/A Statement Ability to operate and monitor the following as they apply to a Station Blackout:

Restoration of power with one ED/G Proposed Question: RO 51 Rev: 0 Given the following:

• The plant is implementing OP-902-005, Station Blackout Recovery.

• Attachments 7-A(B)(C), Switchgear Room A(B)(AB) Removable Loads have been completed as required by OP-902-005.

• Emergency Diesel Generator A has become available to restore power.

OP-902-005, previously (WHAT??? Are we testing on what a procedure previously stated?) directed the Operators to place both Containment Spray Pump control switches to OFF if Containment pressure is < 17.7 psia to prevent A. an inadvertent spray of containment B. actuating a Sequencer UV Lockout C. operating CS Pumps at shutoff head D. overloading an Emergency Diesel Generator Proposed Answer: A Explanation (Optional):

A. CORRECT. Due to de-energizing ESFAS relays as part of the Attachment given in the stem a CSAS signal is generated. Restoration of EDG A will result in a start of CS Pump A and initiation of flow through the Train A Spray Header nozzles.

B. Incorrect. Although the restoration of EDG A will start various ESFAS A loads, the Sequencer should still function to start the loads in the prescribed order without initiating a sequencer lockout.

C. Incorrect. Although CS Pump A will start on the restoration of EDG A, the CS A header isolation valve should be open due to the load stripping that occurs in the Attachments given in the stem as complete.

D. Incorrect. The operation of the sequencer on the start of EDG A should prevent an overload condition on EDG A.

101 Exam Submittal

Technical Reference(s) OP-902-005, Station Blackout Recovery, Rev. 13 OP-902-009, Standard Appendices, Rev. 301, Attachments 7-A, 7-B, and 7-C TG-OP-902-005, Technical Guide for Station Blackout, Rev. 302 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE05 Obj. 7 Question Source: Bank # WF3-OPS-2469-A Modified Bank #

New Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41(b) 10 Comments:

102 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 1 Group # 1 K/A # 056 AA1.37 Importance Rating 3.4 K/A Statement Ability to operate and / or monitor the following as they apply to the Loss of Offsite Power:

Instrument air Proposed Question: RO 52 Rev: 0 Replace this or question 56 (replace KA topic) because testing IA cross-connecting knowledge again.

Given the following initial conditions:

• The plant is at 100% power

• EDG A is OOS

• IA compressor A is running; IA compressor B is in standby

• Combined Instrument Air and Station Air usage is within the capacity of one air compressor

• The plant is operating at 100% with all systems aligned normally, except as noted, when aA reactor trip and Loss of Offsite Power occurs

• All Automatic Actions occur as designed Which of the following is correct?

A. IA pressure drops until IA compressor B starts automatically, then IA pressure recovers.

B. IA pressure drops until action is taken to manually cross-connect Instrument AirIA and Station Air, then IA pressure recovers.

C. IA pressure continues to drop until alternate cooling is aligned to IA compressor B and the compressor is started manually, then IA pressure recovers.

D. IA pressure drops until Station Air and Instrument airIA are automatically cross-connected, then IA pressure varies around the setpoint of the automatic valve.

Proposed Answer: C 103 Exam Submittal

Explanation (Optional):

A. Incorrect. IA Compressor B will not automatically start (see explanation in B).

B. Incorrect. The conditions given in the stem indicate a Loss of Offsite Power has occurred. Train A is lost due to the 87STA actuation which isolates SUT A.

Train B is lost due to the Generator Output Breaker B failing to open which then opens the feeder breakers from the grid feeding Offsite power to Train B. This results in loss of all Station Air Compressors and Instrument Air Compressor A.

IA compressor B is interlocked such that it will not auto start when the normal power supply is unavailable to Bus B3. Bus B3 which is currently energized by EDG B. Even if the IA and SA systems are manually cross-connected pressure would not recover because no SA air compressors are available.

C. CORRECT. IA compressor B can be manually started. This would require alternate cooling be aligned due to the loss of normal cooling (TCW, CW). OP-902-003 contains steps to align potable water to the air compressors and start all available air compressors. In this case, the only available air compressor is IA compressor B (see explanation in A).

D. Incorrect. See explanation A. Even if the IA to SA cross-connect automatically opens without air compressors running pressure is going to continue to lower.

Technical Reference(s) OP-902-003, Loss of Offsite Power/Loss of Forced Circulation, Rev.006 OP-902-009, Standard Appendices, Rev 301 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-AIR00 Obj. 1 Question Source: Bank #

Modified Bank # WF3-OPS-6737-A New Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41(b) 4 Comments:

104 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 1 Group # 1 K/A # 057 AA2.19 Importance Rating 4.0 K/A Statement Ability to determine and interpret the following as they apply to the Loss of Vital AC Instrument Bus: The plant automatic actions that will occur on the loss of a vital ac electrical instrument bus.

Proposed Question: RO 53 Rev: 0 ATTACH ORIGINAL QUESTION Given the following

• The plant is at 100%

On the a loss of SUPS MA, Reactor Trip breakers _____________ open and the reactor A. 1, 2, 5, and 6; remains at 100%

B. 1, 2 ,5, and 6; trips C. 3, 4, 7, and 8; remains at 100%

D. 3, 4, 7, and 8; trips Proposed Answer: A Explanation (Optional):

A. CORRECT. This is the correct combination of trip breakers that will open on a loss of SUPS MA. These breakers opening will only eliminate one of two paths for power to the CEAs and the reactor does not trip.

B. Incorrect. Correct breakers, wrong effect. See explanation for A.

C. Incorrect. Wrong breaker combination. See explanation A.

D. Incorrect. Wrong breaker combination, wrong effect. See explanation A 105 Exam Submittal

Technical Reference(s) OP-901-312, Rev. 2 SD-PPS, Fig. 1, Rev. 0 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPO30 Obj. 1 Question Source: Bank #

Modified Bank # WF3-OPS-3316-A New Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41(b) 7 Comments:

106 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 1 Group # 1 K/A # 058 AK3.02 Importance Rating 4.0 K/A Statement Knowledge of the reasons for the following responses as they apply to the Loss of DC Power: Actions contained in EOP for loss of dc power Proposed Question: RO 54 Rev: 0 On a Loss of TGB-DC Bus, the reactor will be manually tripped when Instrument Air Header Pressure lowers to ____________ due to loss of power to _______________.

A. 80 psig; IA and SA compressor unloader valves B. 80 psig; Instrument Air Dryers C. 65 psig; IA and SA compressor unloader valves D. 65 psig; Instrument Air Dryers Proposed Answer: C Explanation (Optional):

A. Incorrect. The reactor will not be tripped until 65 psig per OP-901-313. the basis is correct per a note in OP-901-313.

B. Incorrect. Wrong pressure. Wrong bases, however, IA dryer malfunctions can significantly affect IA pressure making it plausible.

C. CORRECT. Per the step and associated note in OP-901-313 this is the correct value and bases.

D. Incorrect. Correct pressure. Wrong Bases.

Technical Reference(s) OP-901-313, Loss of a 125 DC Bus, Rev. 301 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPO03 Obj. 4 107 Exam Submittal

Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41(b) 10 Comments:

108 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 1 Group # 1 K/A # 062 G2.4.21 Importance Rating 4.0 K/A Statement Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

Proposed Question: RO 55 Rev: 0 Given the following

• A loss of main feedwater event has occurred

• No Wet Cooling Tower Basin is available for alignment to EFW due to loss of both ACCW Pumps.

In accordance with TG-OP-902-009, Technical Guide for Standard Appendices, at which Condensate Storage Pool level will the RCS and Core Heat Removal Safety Function start to be impacted by EFW pump cavitation?

Which of the following is the level in the Condensate Storage Pool at which the RCS and Core Heat Removal safety function is impacted by the potential loss of the EFW pumps due to cavitation, per TG-OP-902-009, Technical Guide for Standard Appendices?

A. 5%

B. 11%

C. 13%

D. 25%

Proposed Answer: B Explanation (Optional):

A. Incorrect. This is an old value from a previous revision that does not take level uncertainties into account.

B. CORRECT. This is the value stated in TGOP-902-009.

C. Incorrect. This is the value that Operators should wait for to complete the lineup to the Wet Tower Basin to ensure that unnecessary depletion of the Wet Tower Basin does not occur.

D. Incorrect. This is the level at which the CRS should notify personnel outside of the Control Room to start the lineup to the Wet Tower Basin. This allows 20 minutes to complete the lineup.

109 Exam Submittal

110 Exam Submittal

Technical Reference(s): TGOP-902-009, Technical Guide for Standard Appendices, Rev. 301 OP-902-009, Standard Appendices, Rev. 301 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE06 Obj. 9 Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41(b) 10 Comments:

111 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 1 Group # 1 K/A # 065 AK3.04 Importance Rating 3.0 K/A Statement Ability to determine and interpret the following as they apply to the Loss of Instrument Air:

Cross-over to backup air supplies Proposed Question: RO 56 Rev: 0 Given:

• A leak in the Instrument Air system is in progress

• IA header pressure is 100psig and slowly lowering Which of the following valves have repositioned?

N2/Instrument Air Accumulator Outlet Valves (Correct)SA System crossover valves xxxx IA Dryer Bypass Valves xxxx

The following alarm is received in the Control Room on Annunciator Panel L:

• Valve Operators Nitrogen Backup Actuated/Trouble Which of the following is a potential cause of this alarm?

A. A Nitrogen Accumulator Outlet Valve is open.

B. An Essential Air Nitrogen Station has been aligned.

C. An Essential Air Nitrogen bottle pressure is less than 715 psig.

D. A Nitrogen Tube Trailer has been aligned.

Proposed Answer: A Explanation (Optional):

A. CORRECT. Per Annunciator Response Procedure OP-500-010, any one of eight Nitrogen Accumulator Outlet Valve limit switches indicating that the valve is not fully closed actuates the alarm.

B. Incorrect. None of the 3 inputs to the alarm is associated with the Essential Air Accumulators. However, the Essential Air system is a valid backup source of 112 Exam Submittal

motive air that is aligned on a loss of IA and valve position is a parameter used as an input to the alarm.

C. Incorrect. None of the 3 inputs to the alarm is associated with the Essential Air Accumulators. However, the Essential Air system is a valid backup source of motive air that is aligned on a loss of IA. 715 psig is the setpoint for the nitrogen accumulator pressure that is an input to the alarm D. Incorrect. The tube trailer is a backup source of nitrogen but is not an input to the alarm. However, valve position is used as an input to the alarm, but the source is from the nitrogen accumulator outlet valves.

113 Exam Submittal

Technical Reference(s) OP-500-010, Control Room Cabinet L, Rev 020 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-AIR00 Obj. 4 Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41(b) 7 Comments:

114 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 1 Group # 2 K/A # 001 AK2.08 Importance Rating 3.1 K/A Statement Knowledge of the interrelations between the Continuous Rod Withdrawal and the following: Individual rod display lights and indications Proposed Question: RO 57 Rev: 0 Given the following:

• Reactor Power is 12% with power ascension in progress

• Reg Group 6 is being withdrawn manually in MS mode to raise power to 15%

• Individual Reg Group 6 CEAs have a 0.0 deviation from the Group

• No deviation exists between Pulse Counters and RSPTs for Group 6

• The ATC releases the IN-HOLD-OUT switch at 135 and Reg Group 6 continues out due to a switch contact failurefailure of the OUT contacts in the switch Assuming a 0.0 deviation between individual CEAs in Reg Group 6 and 0.0 deviation between the Pulse Counters and RSPTs for Reg Group 6 answer the following:Assuming the reactor does not trip:

(1) What will stop CEA motion for Reg Group 6?

(2) What will be the approximate reading of the Pulse Counters on CP-2?

(3) What will be the status of the Red indicators for Reg Group 6 CEAs on the CEDMCS Control Panel on CP-2?

A. (1) Upper Electrical Limit (2) 150 (3) Illuminated B. (1) Upper Electrical Limit (2) 145.5 (3) Extinguished C. (1) Upper Group Stop (2) 150 (3) Illuminated D. (1) Upper Group Stop (2) 145.5 (3) Extinguished 115 Exam Submittal

Proposed Answer: D 116 Exam Submittal

Explanation (Optional):

A. Incorrect. Upper Group Stop would occur, not the Upper Electrical Limit. This would occur at 145.5 on the pulse counters, not 150. The red lights would be extinguished because they are actuated by the Upper Electrical Limit for the individual rod, not the Upper Group Stop.

B. Incorrect. Upper Group Stop would occur, not the Upper Electrical Limit. This would occur at 145.5 on the pulse counters as stated. The red lights would be extinguished as stated because they are actuated by the Upper Electrical Limit for the individual rod, not the Upper Group Stop.

C. Incorrect. Upper Group Stop would occur as stated; however, this would occur at 145.5 on the pulse counters, not 150. The red lights would be extinguished because they are actuated by the Upper Electrical Limit for the individual rod, not the Upper Group Stop.

D. CORRECT. Upper Group Stop would occur as stated. This would occur at 145.5 on the pulse counters as stated. The red lights would be extinguished as stated because they are actuated by the Upper Electrical Limit for the individual rod, not the Upper Group Stop.

Technical Reference(s) OP-004-004, Rev. 16 Proposed references to be provided to applicants during examination:

Learning Objective: WLP-OPS-CED00 Obj. 1 Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41(b) 6 Comments:

117 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 1 Group # 2 K/A # 036 AA1.02 Importance Rating 3.1 K/A Statement Ability to operate and / or monitor the following as they apply to the Fuel Handling Incidents: ARM system Proposed Question: RO 58 Rev: 0 Given the following:

• The plant is in MODE 6 with fuel shuffle in progress in both the Fuel Handling Building and Containment.

• Containment Purge is in the Refueling Mode.

• Containment equipment hatch and airlock doors are closed and no containment penetrations are impaired.

• A fuel bundle is dropped from the Refueling Machine Fuel Hoist. Is this on the

+46 elevation of containment?

Which of the following radiation monitors can detect the event ANDwill terminateautomatically terminate the radioactive gas release to the environment?

A. Containment Atmosphere Hi Range Area Radiation Monitor, ARM-IRE-5400AS.

B. Containment Purge Area Radiation Monitor, ARM-IRE-5024.

C. Refueling Machine Area Radiation Monitor, ARM-IRE-5013.

D. Containment PIG Process RMRadiation Monitor, PRM-IRE-0100S.

Proposed Answer: B Explanation (Optional):

A. Incorrect. No automatic functions are associated with this Rad Monitor.

However, the RM detectors are in containment and could see the radiation from the fuel handling incident.

B. CORRECT. ARM 5024 provides isolation of Containment Purge on Hi Rad and is in the general area of fuel handling on the +46 elevation of Containment.

C. Incorrect. This rad monitor is in the general area of the Refueling Cavity; however, it has indication and alarm functions only.

D. Incorrect. The containment PIG monitors containment atmosphere but does not have Containment Purge isolation functions.

118 Exam Submittal

Technical Reference(s) OP-901-405, Fuel Handling Incident, Rev.

2 Proposed references to be provided to applicants during examination:

None Learning Objective: WLP-OPS-RMS00 Obj. 2 Question Source: Bank # WF3-OPS-07922 Modified Bank #

New Question History: Last NRC Exam 2006 W3 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41(b) 11 Comments:

119 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 1 Group # 2 K/A # 037 AK1.01 Importance Rating 2.9 K/A Statement Knowledge of the operational implications of the following concepts as they apply to Steam Generator Tube Leak: Use of steam tables Proposed Question: RO 59 Rev: 0 Given the following:

• A cooldown is being performed to MODE 5 per OP-901-202, Steam Generator Tube Leakage or High Activity due to a leak on SG 2.

• All RCPs are secured

• CET Temp is 382ºF

• Th Loop1 is 375ºF

• Th Loop1 is 378ºF

• Tc Loop 1 is 350ºF

• Tc Loop 2 is 382ºF

• The CRS has placed a lower limit of 30ºF on Subcool Margin Determine the minimum value of RCS pressure that supports the requested RCS Subcool Margin.

A. 196 psia B. 262 psia C. 270 psia D. 283 psia Proposed Answer: D 120 Exam Submittal

Explanation (Optional):

A. Incorrect. This is the value associated with Cold leg 1 temperature. The hottest RCS temperature should be used to determine subcool margin. This would also lower RCS pressure below the isolated S/G pressure.

B. Incorrect. This is the value associated with Hot Leg Loop 1 temperature. The hottest RCS temperature should be used to determine subcool margin.

C. Incorrect. This is the value associated with Hot Leg Loop 2 temperature. The hottest RCS temperature should be used to determine subcool margin.

D. CORRECT. This is the value associated with CET and Cold Leg 2 temperatures.

The hottest RCS temperature should be used to determine subcool margin. OI-038-000 has guidance to use CET temperatures on natural circulation Technical Reference(s) Steam Tables - Properties of Saturated and Superheated Steam Proposed references to be provided to applicants during examination: Steam Tables Learning Objective: WLP-OPS-PPO20 Obj. 3 Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41(b) 10 / 14 Comments:

121 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 1 Group # 2 K/A # 051 AA2.02 Importance Rating 3.9 K/A Statement Ability to determine and interpret the following as they apply to the Loss of Condenser Vacuum: Conditions requiring reactor and/or turbine trip Proposed Question: RO 60 Rev: 0 In accordance with OP-901-220, Loss of Condenser Vacuum, a reactor trip is first required when condenser vacuum is approaching _________ inches Hg and not stabilized.

[SPACE]

A. 25 B. 23 C. 20 D. 14 Proposed Answer: C Explanation (Optional):

A. Incorrect. This is the point at which a power reduction is required.

B. Incorrect. This is the point at which the Condenser Vacuum Pumps go into the Hogging mode of operation.

C. CORRECT. This is the requirement stated in OP-901-220.

D. Incorrect. This is the point at which the main feedwater pumps would trip and OP-901-220 requires action to be performed to protect the Main Condenser from high pressure.

122 Exam Submittal

Technical Reference(s) OP-901-220, Loss of Condenser Vacuum, Rev. 2 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPO02 Obj. 3 (As available)

Question Source: Bank # WF3-OPS-5789-A Modified Bank #

New Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41(b) 10 Comments:

123 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 1 Group # 2 K/A # CE/E09 EK2.1 Importance Rating 3.6 K/A Statement Knowledge of the interrelations between the Functional Recovery and the following:

Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Proposed Question: RO 61 Rev: 0 Given the following:

• A large break LOCA concurrent with aoccurred while in Mode 1

• S/G 2 Safety Valve XXXX failed open after the trip secondary safety on S/G 2 has occurred

• RCS Pressure is 100 psia and stable

• RWSP Level is 60% and lowering

• HPSI Pump A/B is OOS for a pump coupling replacement

• HPSI Pump A tripped on overcurrent upon its initial start signal 15 minutes later, MCC 311B feeder breaker trips on overcurrent.

With no Operator action taken to mitigate this condition, which of the following would interrupt Safety Injection flow FIRST? WHAT is being asked??? Clear this up.

Flow will not be lost until RWSP outlet valves are closed?

A. Injecting from the RWSP prior to RAS. Not credible. The question asks what terminates injection.

B. Injecting from the SIS Sump after RAS. This contradicts the question because no injection will occur after RAS.

C. Isolating the SI Pump recircs after RAS. After RAS, injection flow is lost. Can be argued as correct.

D. Isolating the RWSP from the SI Pump suction after RAS. After RAS, injection flow is lost. Can be argued as correct.

Proposed Answer: B.

124 Exam Submittal

Explanation (Optional):

A. Incorrect. Per conditions given, (RWSP level has dropped at least 23%

assuming minimum required volume was available, RCS pressure well below SIAS setpoint) the SI system should be in its SIAS alignment. The flow path should be unaffected by the loss of 311B which would cause loss of power to LPSI and HPSI Loop FCV MOVs and SI-120B which is also an MOV. This would fail them in their SIAS position.

B. CORRECT. The loss of MCC 311B causes loss of power to SI-602B which is the MOV suction isolation to the Train B ECCS pumps from the SIS Sump. This valve would normally automatically open at 10% level in the RWSP to provide a suction source to the pumps from the alternate source prior to emptying the RWSP. Since only HPSI Pump B is available to inject this would result in SI flow being interrupted after RAS when the RWSP empties.

C. Incorrect. Only one of two pump recirc isolation valves in series has lost power due to the malfunction given (SI-120B). SI-121B is powered from MCC 312B and would still be available to isolate the recirc flow path.

D. Incorrect. While SI-106B (Train B RWSP isolation) can not be isolated until SI-602B is open, this would not be the reason flow would be lost. Flow will be lost as a result of not aligning the alternate source of suction (SIS Sump) prior to primary source (RWSP) depletion. The act of aligning the alternate source would in itself allow isolation of the primary source after RAS.

Technical Reference(s) OP-009-008, Safety Injection, Rev. 29 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-SI00 Obj. 3 WLP-OPS-SI00 Obj. 8 Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41(b) 7 Comments:

125 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 1 Group # 2 K/A # 074 EK3.04 Importance Rating 3.9 K/A Statement Knowledge of the reasons for the following responses as they apply to the Inadequate Core Cooling: Tripping RCPs Proposed Question: RO 62 Rev: 0 As written, the question does not discriminate against the KA topic (tripping criteria). The question fails to meet the 1 of 2 taken twice, therefore, only one item is needed to answer the question (when to trip, not the reason to trip).

Suggested question:

While operating at 100% power:

• A Small Break LOCA occurred

• All feedwater is lost

• SIAS initiated

• SPTAs are completed and the crew is in OP-902-008, Functional Recovery What action is required and why?

(Correct answer) Secure all RCPs to reduce heat input to the RCS.

Secure all RCPs to prevent RCP damage.

Under what circumstances does OP-902-008, Safety Function Recovery:

(1) require securing all RCPs for a potential inadequate core cooling condition?

AND (2) What is the basis for this action.action?

A. (1) Containment Spray Actuation Signal (CSAS)

(2) Prevent RCP Damage B. (1) Loss of NPSH requirements for RCPs (2) Prevent RCP Damage C. (1) Loss of Main Feedwater > 30 minutes, only EFW AB operable (2) Eliminate RCP heat input to RCS D. (1) Loss of all Feedwater Only need to know this to get D.

(2) Eliminate RCP heat input to RCS This is not discriminated against.

126 Exam Submittal

Proposed Answer: D 127 Exam Submittal

Explanation (Optional):

A. Incorrect. CSAS by itself does not indicate a condition that could lead to inadequate core cooling; however, it is a valid reason to secure the RCP and is addressed in Section 4.0 of OP-902-008 prior to entering any Safety Function Success Path for the reason stated.

B. Incorrect. NPSH requirements for the RCP by itself does not indicate an inadequate core cooling condition; however, it is a valid reason to secure the RCP and is addressed in Section 4.0 of OP-902-008 prior to entering any Safety Function Success Path for the reason stated.

C. Incorrect. Inadequate feedwater can lead to an inadequate core cooling condition. However, all RCPs would only be secured in this circumstance if only one motor driven EFW Pump is available. EFW Pump AB has 100% capacity D. CORRECT. Inadequate feedwater can lead to an inadequate core cooling condition. The RCPs are required to be secured for this reason. With no feedwater the RCPs are secured to eliminate the heat input into the RCS from the RCPs that must be removed by steaming the S/Gs.

Technical Reference(s) OP-902-008, Safety Function (Attach if not previously Recovery, Rev. 15 provided)

TG-OP-902-008, Technical (including version/revision Guide for Safety Function number)

Recovery, Rev.302 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE08 Obj.9 WLP-OPS-PPE08 Obj. 4 Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41(b) 10 Comments:

128 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 1 Group # 2 K/A # 069 AA1.01 Importance Rating 3.5 K/A Statement Ability to operate and/or monitor the following as they apply to the Loss of Containment Integrity: Isolation valves, dampers, and electro-pneumatic devices Proposed Question: RO 63 Rev: 0 Given the following:

• A Loss of Coolant Accident has occurred

• Containment pressure is 17.2 psia and slowly rising

• Equipment lineups were normal at the start of the event and aAll systems operate as designed and equipment lineups were normal at the start of the event Which of the following pipe breaks would constitute result in a loss of containment integrity at the current conditions?

A. on the downstream weld of CVC-101, Letdown Stop Valve. Third question testing knowledge of location of CVC-101 and -103 (change this).

B. just upstream of CS-128B, Containment Spray Riser B Check Valve.

C. on the supply line of Containment Fan Cooler C at the cooling coils.

D. just downstream of CVC-216B, Pressurizer Auxiliary Spray Valve B Proposed Answer: C A. Incorrect. A leak at this location would be upstream of the Containment Isolation valves CVC-103 and CVC-109. Both of these valves closed on a CIAS at 17.1 psia in the containment.

B. Incorrect. CS-125B, Containment Spray Header B Isolation Valve would still be closed until pressure reaches 17.7 psia.

C. CORRECT. On an SIAS all flow control valves for CC flow through CFC C would be open due to the containment pressure providing a path outside containment.

A Keyswitch allows override of the valves to isolate the leak.

D. Incorrect. Although CVC-216B does not get any automatic isolation signals it is normally closed and conditions indicate that the valve is in its normal position.

129 Exam Submittal

Technical Reference(s) G-160 Sht 4, Rev. 16 SD-CC00, Rev. 12 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-CC00 Obj. 7 Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41(b) 9 Comments:

130 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 1 Group # 2 K/A # 076 G2.1.25 Importance Rating 3.9 K/A Statement Ability to interpret reference materials, such as graphs, curves, tables, etc.

Proposed Question: RO 64 Rev: 0 Given the following:

• Reactor power is 100%

• OP-901-410, High Activity in Reactor Coolant System, was entered today at 0230 due to the Isotopic Analysis for DEQDose Equivalent I-131 sample reading 3.0 ci/gm.

• The last sample taken for Isotopic Analysis for Iodine activity was taken today at 0400.

A reactor trip occurs at 0430. Using TS Table 4.4-4, determine the LATEST time possible to perform the next sample for Isotopic Analysis for IodineIodine isotopic analysis.

A. 0630 today B. 0800 today C. 1030 today D. 0400 in 14 days Proposed Answer: B Explanation (Optional):

A. Incorrect. Even though the reactor tripped, the sample is not required to be taken due to the power change until 1030. A sample at two hours is not required.

B. CORRECT. The table requires a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> sample be taken as long as Iodine activity is exceeding 1.0 ci/gm.

C. Incorrect. If the plant was not already in a 4 hr sampling requirement this would be the required time to take the sample post trip due to the power change.

Waiting until this point would however, violate the 4 hr requirement.

D. Incorrect. The increased Iodine sampling requirements must continue on a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> basis until Iodine activity is less than 1.0 ci/gm.

131 Exam Submittal

Technical Reference(s) TS Table 4.4-4, Amendment 184 OP-901-410, High Activity in Reactor Coolant System, Rev.

3 Proposed references to be provided to applicants during TS 3.4.7 and Table examination: 4.4-4 Learning Objective: WLP-OPS-PPO40 Obj. 3 WLP-OPS-PPO40 Obj. 5 Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41(b) 10 Comments:

132 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 1 Group # 2 K/A # CE/A16 AA2.1 Importance Rating 2.7 K/A Statement Ability to determine and interpret the following as they apply to the (Excess RCS Leakage)

Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

Proposed Question: RO 65 Rev: 0 Given the following conditions:

• Letdown is secured to determine the location of an RCS leak

• RCS Tavg is 575 degrees and steady

• Current RCS leakage is 86 gpm

• AB Charging pump is out of service

• Charging pumps A and B are running Which of the following is the appropriate action to be performed?

[SPACE]

A. Remain in OP-901-111, Reactor Coolant System Leak, and attempt to locate the leak.

B. Commence a normal shutdown in accordance with OP-010-005, Plant Shutdown.

C. Commence a rapid plant shutdown in accordance with OP-901-212, Rapid Plant Power Reduction.

D. Initiate a manual reactor trip, SIAS/CIAS, and go to OP-902-000, Standard Post Trip Actions.

Proposed Answer: D 133 Exam Submittal

Explanation (Optional):

A. Incorrect. The RCS leakage and the 4-6 gpm RCP controlled bleedoff that normally exists exceeds the capacity of two charging pumps. This is an option if pressurizer level can be maintained.

B. Incorrect. The RCS leakage and the 4-6 gpm RCP controlled bleedoff that normally exists exceeds the capacity of two charging pumps. This is an option if pressurizer level can be maintained and a shutdown is required.

C. Incorrect. The RCS leakage with the 4-6 gpm RCP controlled bleedoff that normally exists exceeds the capacity of two charging pumps. This is a valid shutdown option; however, OP-901-111 specifically ignores this option based on the possible inability to control pressurizer level on the shutdown.

D. CORRECT. Based on the total inventory loss from the RCS (RCS leakage +

RCP controlled bleedoff) exceeding Charging pump capacity, Pressurizer level can not be maintained. OP-901-111 requires that answer D be performed per step 2 when this is the case.

Technical Reference(s) OP-901-111, Reactor Coolant System Leak, Rev.

301 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPO10 Obj. 3 Question Source: Bank # WF3-OPS-5199-A Modified Bank #

New Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41(b) 8 / 10 Comments:

134 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 3 Group # 1 K/A # G 2.1.40 Importance Rating 2.8 K/A Statement Conduct of Operations: Knowledge of refueling administrative requirements.

Proposed Question: RO 66 Rev: 0 The reactor was operating at 100% power at EOC. The following sequence of events occurs:

• At 1330 on 10/4 the reactor trips

• At 1245 on 10/9 the cause of the trip has been corrected and the crew has commenced withdrawing the Shutdown Banks.

• At 1315 on 10/9 with Shutdown Bank B at 50, the reactor trip breakers open due to low S/G levels

• At 1700 on 10/9, the decision is made to enter the refueling outage early A decision is made to enter the Refueling outage early. At what minimum point in time does theIn accordance with TS 3.9.3, Decay Time, the plant will meet meet (met) the minimum time requirements to remove irradiated fuel from the reactor per TS 3.9.3, Decay Time at ______?

A. 1330 on 10/7 B. 1730 on 10/8 C. 1315 on 10/12 D. 1715 on 10/13 Proposed Answer: A 135 Exam Submittal

Explanation (Optional):

A. CORRECT. The conditions given for the startup indicate that the reactor did not obtain criticality prior to the trip. Therefore, the 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> starts from the first reactor trip time. The time limit is based on allowing the decay of short lived fission products.

B. Incorrect. The base time used is correct but a minimum subcriticality time of 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> is used. This time is common in Tech Specs in the industry.

C. Incorrect. This is 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from the second trip. Based on the conditions given in the stem the reactor never achieved criticality prior to second trip.

D. Incorrect. This is 100 hrs from the second trip. This is the wrong duration after shutdown and also would not apply since we did not reach criticality prior to the second trip.

Technical Reference(s) TS 3/4.9.3, Decay Time, Amendment 0 B3/4.9.3, Decay Time, Change 21 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-FHS00 Obj. 5 Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41(b) 1 / 10 Comments:

136 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 3 Group # 1 K/A # G 2.1.19 Importance Rating 3.9 K/A Statement Conduct of Operations: Ability to use plant computers to evaluate system or component status.

Proposed Question: RO 67 Rev: 0 Which of the following control board annunciator would be if the Plant Monitoring Computer fails?WHAT?? This is not a complete sentence!

A. CEA DISABLED B. CEDMCS TIMER FAILURE C. CEDMCS MAINTENANCE ERROR D. POWER DEPENDENT INSERTION LIMIT Suggested replacement:

Some alarming condition is present, or abnormal system status.

While using the Plant Monitoring Computer to evaluate the [some system or component status], the operator must ________.

Steps to accomplish this on the PMC.

Proposed Answer: D Explanation (Optional):

A. Incorrect. This alarm is generated by contacts for CEA Circuit Breakers in OFF.

B. Incorrect. This alarm is generated by ACTM Micro-processer Card.

C. Incorrect. This alarm is generated by CEDMCS when trying to place more than one subgroup on hold bus.

D. CORRECT. This alarm is generated by the PMC.

137 Exam Submittal

Technical Reference(s) SD-PMC, Rev. 7 OP-500-00, Control Room Cabinet H, Rev. 26 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PMC00 Obj. 3 Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41(b) 4 Comments:

138 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 3 Group # 2 K/A # G 2.1.37 Importance Rating 4.3 K/A Statement Equipment Control: Knowledge of procedures, guidelines, or limitations associated with reactivity management.

Proposed Question: RO 68 Rev: 0 True/False Please fix the distracters so they are not stand-alone statements.

Which of the following accurately describes the procedure requirement regarding reactivity management?

A. Planned Primary Makeup additions less than 100 gallons are exempt from peer checks in Modes 3, 4, and 5.

B. Positive reactivity additions may be made by two methods simultaneously if in accordance with an approved reactivity plan.

C. An approved reactivity plan is only needed for planned reactor power changes of greater than 5%.

D. During approach to criticality the designated Reactor Engineer gives permission to continue rod withdrawal after verifying 1/M plots do not predict criticality.

Proposed Answer: B Explanation (Optional):

A. Incorrect. EN-OP-115, Conduct of Operations requires that all planned reactivity manipulations are verified/peer checked.

B. CORRECT. Per EN-OP-103 and EN-OP-115, Conduct of Operations it is permissible to add positive reactivity to the reactor by more than one means with an approved reactivity plan.

C. Incorrect. EN-OP-115 guidance is to develop a written reactivity plan for power changes of greater than 2%.

D. Incorrect. EN-OP-115 specifically requires direction that affects reactivity to come through the individual holding Command and Control to the Control Room Operators.

139 Exam Submittal

Technical Reference(s) EN-OP-103, Reactivity Management Program, Rev.

4 EN-OP-115, Conduct of Operations, Rev. 9 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-EXP00 Obj. 15 WLP-OPS-PPA00 Obj. 3 Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41(b) 10 Comments:

140 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 3 Group # 2 K/A # G 2.2.38 Importance Rating 3.6 K/A Statement Equipment Control: Knowledge of conditions and limitations in the facility license.

Proposed Question: RO 69 Rev: 0 Per the Waterford 3 Operating License, Entergy Operations Inc. is authorized to operate the Waterford 3 reactor core at power levels not to exceed:

A. 3441 MWt B. 3461 MWt C. 3716 MWt D. 3739 MWt Proposed Answer: C Explanation (Optional):

A. Incorrect. This value is equal to the intermediate power uprate value.

B. Incorrect. This value is equal to the intermediate power uprate value + the old estimated RCP heat contribution.

C. CORRECT. This is the value listed in the current Operating License post power uprate.

D. Incorrect. This is the value listed in the current Operating License post power uprate + the most recent evaluation of RCP heat contribution.

141 Exam Submittal

Technical Reference(s) Waterford 3 Operating License, Amendment 225 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-TS00 Obj. 2 Question Source: Bank #

Modified Bank # WF3-OPS-06762 New Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41(b) 2 Comments:

142 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 3 Group # 2 K/A # G 2.2.41 Importance Rating 3.5 K/A Statement Equipment Control: Ability to obtain and interpret station electrical and mechanical drawings.

Proposed Question: RO 70 Rev: 0 Given the following:

• Main Steam Drip Pot MS-ILS-0313A has detected a high level

• MS Drain Valve, MS-127A has automatically opened MS-127A will close:

A. when the high level condition clears and the control switch is taken to close.

B. if valve limit switch contact (bo) indicates the valve did not stroke fully open.

C. when the white Water Detected lights on the control switch extinguishes.

D. when the high level condition clears and relay LSX de-energizes.

Proposed Answer: A Explanation:

A. CORRECT. The high level condition must be cleared and then the operator can manually close the valve.

B. Incorrect. This valve does not have an auto close feature if the valve does not fully stroke.

C. Incorrect. The white lights will extinguish when the high level condition clears but it will not cause closure of the valve.

D. Incorrect. The LSX relay disables closure of the valve with a high level condition but does not provide auto closure when the high condition clears.

143 Exam Submittal

Technical Reference(s) CWD B424-1648, Rev. 8 Proposed references to be provided to applicants during CWDs B424-1648 examination:

Learning Objective: WLP-OPS-CD00 Obj. 3 Question Source: Bank # WF3-OPS-2357-A Modified Bank #

New Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41(b) 4 Comments:

144 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 3 Group # 3 K/A # G 2.3.15 Importance Rating 2.9 K/A Statement Radiation Control: Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

Proposed Question: RO 71 Rev: 0 The _____(1)_________ Radiation Monitor(s) is(are) susceptible to Thermally Induced Currents (TIC) during a LOCA/Steam Line Break and will initially read erroneously

_____(2)______ with rising temperatures in Containment.During a LOCA or Steam Line Break in Containment, the ____(1)____ Radiation Monitor(s) will read erroneously (2) while Containment temperature is rising.

A. (1) Containment High Range (2) low B. (1) Containment High Range (2) high C. (1) Containment PIG (2) low D. (1) Containment PIG (2) high Proposed Answer: B Explanation:

A. Incorrect. Correct rad monitors, wrong indication effect.

B. CORRECT. The Containment High Range Radiation Monitors have been determined to be susceptible to TIC post accident which will cause erroneously high readings for at least 15 minutes from the time containment temperature stabilizes.

C. Incorrect. Wrong rad monitor, wrong effect.

D. Incorrect. Wrong rad monitor, correct effect.

145 Exam Submittal

Technical Reference(s) WLP-OPS-MCD06, Radiation Monitoring, Rev. 4 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-MCD06 Obj.3 Question Source: Bank #

Modified WF3-OPS-Bank # 5638-A New Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41(b) 11 Comments:

146 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 3 Group # 3 K/A # G 2.3.12 Importance Rating 3.2 K/A Statement Radiation Control: Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

Proposed Question: RO 72 Rev: 0 Given the following:

• The plant is at 10% Power

• A containment entry is desired During a containment entry, Wwhich of the following areas inside containment is forbidden to enterare forbidden from being entered?

A. Pressurizer Cubicle below +21 elevation B. +46 elevation at the Quench Tank C. Main Steam Line Crossovers on the +46 elevation D. 1A Cold Leg penetration through the D Ring Wall Proposed Answer: D A. Incorrect. This is an area known to have high radiation levels, but is not listed in HP-001-213 as being forbidden in MODE 1. Not an area listed as needing RP Manager approval to enter.

B. Incorrect. This area is in close proximity to the Reactor Cavity but is a sufficient distance away that it is not forbidden, or need RP Manager approval to enter.

C. Incorrect. This is an exception to the requirement for obtaining RP Manager approval for going above the actual +46 elevation in Containment. It is not listed as forbidden.

D. CORRECT. Per HP-001-213, Step 5.2.2 and Attachment 7.1, this is a forbidden area in MODE 1. (> 5% RTP).

147 Exam Submittal

Technical Reference(s) HP-001-213, Control of Containment Building Power Entries, Rev. 301 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPA00 Obj. 3 Question Source: Bank #

Modified Bank # WF3-NRC-5770-A New Question History: Last NRC Exam 2000 W3 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41(b) 12 Comments:

148 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 3 Group # 3 K/A # G 2.4.50 Importance Rating 4.2 K/A Statement Emergency Procedures / Plan:. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

Proposed Question: RO 73 Rev: 0 XXXX is in alarm. Which of the following would be acceptable to verify the validity of the alarm per xxx-xxx-xxx alarm response procedure?

Which of the following alarms/status is used to verify a SIAS has occurred during Standard Post Trip Action verification, per OI-038-000, Emergency Operations Procedures Operations Expectations/ Guidance?

A. RPS Channel Trip PZR Pressure Lo - illuminated B. Train A(B) ESF Valves Overload Override - extinguished C. SIAS Train A(B) Logic initiated - illuminated D. LPSI/HPSI Pump A(B) Pump unavailable - extinguished A.

Proposed Answer: C Explanation (Optional):

A. Incorrect. This alarm does come in when SIAS occurs but is not used by OI-038-000 and would be in if only one RPS channel has tripped.

B. Incorrect. This alarm actually comes in when SIAS occurs.

C. CORRECT. These are the alarms called out in OI-038-000 to support verifying a SIAS.

D. Incorrect. These alarms, if extinguished > 47 seconds after an SIAS, occurs would tell the Operator that the breakers for the associated pumps closed.

However, OI-038-000 does not use them for verification of an SIAS.

Technical Reference(s) OI-038-000, Rev. 11 Proposed references to be provided to applicants during examination: None 149 Exam Submittal

Learning Objective: WLP-OPS-PPE01 Obj. 4 Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41(b) 5 / 7 / 10 Comments:

150 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 3 Group # 4 K/A # G 2.4.30 Importance Rating 2.7 K/A Statement Emergency Procedures/Plan: Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator Proposed Question: RO 74 Rev: 0 Which of the following is the lowest classification that requires notification of the Coast Guard and Union Pacific Railroad to establish Exclusion Area Boundary Controls?

A. Unusual Event B. Alert C. Site Area Emergency D. General Emergency Proposed Answer: C Explanation (Optional):

A. Incorrect. Per EP-002-010, Notifications and Communications the USCG and Union Pacific Railroad will be notified at a Site Area Emergency or General Emergency.

B. Incorrect. Per EP-002-010, Notifications and Communications the USCG and Union Pacific Railroad will be notified at a Site Area Emergency or General Emergency.

C. CORRECT. Per EP-002-010, Notifications and Communications the USCG and Union Pacific Railroad will be first be notified at a Site Area Emergency.

D. Incorrect. Per EP-002-010, Notifications and Communications the USCG and Union Pacific Railroad will first be notified at a Site Area Emergency.

151 Exam Submittal

Technical Reference(s) EP-002-010, Notifications and Communications, Rev.

304 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-EP00 Obj. 12 Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41(b) 10 Comments:

152 Exam Submittal

Examination Outline Cross- Level RO SRO reference:

Tier # 3 Group # 4 K/A # G 2.4.21 Importance Rating 4.0 K/A Statement Emergency Procedures / Plan: Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

Proposed Question: RO 75 Rev: 0 Which of the following would indicate failure to meet a Safety Function acceptance criteria for Containment Isolation per OP-902-008, Safety Function Functional Recovery?

A. S/G 1 activity rising without explanation, Control Room is commencing rapid cooldown to Thot < 520ºF per HR-2 of OP-902-008.

B. Containment pressure is 16.5 psia and Containment Area Radiation Monitors are rising without explanation, and no containment isolation. Based on OP-902-008, CI-1 Condition 1.c., would this also be correct??

C. Containment Pressure is 17.5 psia and only RC-606, RCP Controlled Bleedoff Inside Isolation Valve closes on the associated penetration.

D. MSL 2 Radiation Monitor is in high alarm, S/G 2 isolation has been completed, S/G 2 pressure is 945 psia, no steam is issuing from ADV 2.

Proposed Answer: A Explanation:

A. CORRECT. Conditions given in the answer indicate that the S/G has not been isolated yet per procedure.

B. Incorrect. Containment isolation is not required until Containment Pressure is >

17.1 psia. Therefore, at this time no containment isolation valve is required to be closed.

C. Incorrect. OP-902-008 only requires one valve per penetration to be closed to meet the acceptance criteria.

D. Incorrect. All acceptance criteria for OP-902-008 are met as long as the S/G is isolated and the ADV is not steaming.

153 Exam Submittal

Technical Reference(s) OP-902-008, Safety Function Recovery, Rev.15 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE08 Obj. 8 Question Source: Bank #

Modified Bank #

New X Question History: Last NRC Exam N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41(b) 10 Comments:

154 Exam Submittal