ML080170187
| ML080170187 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 01/17/2008 |
| From: | Division of Reactor Safety IV |
| To: | |
| References | |
| Download: ML080170187 (86) | |
Text
ES-401 Waterford 3 Written Examination Form ES-401-9 Review Worksheet (TAC#: X02356)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only
- 6.
U/E/S
- 7.
Explanation 1
H 2
S D, 41.10, CR 2
H 3
X U
D, 41.10, CR - This question does not test on the effect of losing seal water to an RCP as required by the KA, but instead tests on diagnosis and operator actions in response to a loss of seal water.
3 H
3 S
D, 41.7, CR 4
H 2
S B, 41.5, CR 5
H 3
S B, 41.10, CR 6N03 H
3 X
U A, 41.4, CR - The question does not test on how a loss or malfunction of the PRTS will affect containment as required by the KA.
7 H
2 S
B, 41.4, CR 8
F 3
S A, 41.10, CR 9
H 2
S D, 41.5, CR Instructions
[Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts.]
- 1.
Enter the level of knowledge (LOK) of each question as either (F)undamental or (H)igher cognitive level.
- 2.
Enter the level of difficulty (LOD) of each question using a 1 - 5 (easy - difficult) rating scale (questions in the 2 - 4 range are acceptable).
- 3.
Check the appropriate box if a psychometric flaw is identified:
The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information).
The stem or distractors contain cues (i.e., clues, specific determiners, phrasing, length, etc).
The answer choices are a collection of unrelated true/false statements.
One or more distractors is (are) not credible.
One or more distractors is (are) partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem).
- 4.
Check the appropriate box if a job content error is identified:
The question is not linked to the job requirements (i.e., the question has a valid K/A but, as written, is not operational in content).
The question requires the recall of knowledge that is too specific for the closed reference test mode (i.e., it is not required to be known from memory).
The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons).
The question requires reverse logic or application compared to the job requirements.
- 5.
Check questions that are sampled for conformance with the approved K/A and those that are designated SRO-only (K/A and license level mismatches are unacceptable).
- 6.
Based on the reviewer=s judgment, is the question as written (U)nacceptable (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory?
- 7.
At a minimum, explain any AU@ ratings (e.g., how the Appendix B psychometric attributes are not being met).
33 of 34 NUREG-1021, Draft Revision 9
ES-401 2
Form ES-401-9
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
Stem Focus Cues T/F CredDist Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only
- 6.
U/E/S
- 7.
Explanation 10 F
3 S
B, 41.7, CR 11 F
2 S
B, 41.7, CR 12 H
3 S
D, 41.7, CR 13 H
3 S
B, 41.7, CR 14 F
2 S
C, 41.7, CR 15 H
3 S
A, 41.7, CR 16 H
3 S
C, 41.7, CR 17 H
3 S
B, 41.7, CR 18 H
3 S
D. 41.10, CR 19 H
3 S
A, 41.7, CR 20 H
3 S
A, 41.7, CR 21 F
3 X
E D, 41.10, CR - It could be argued all four answers are correct in that distractors A-C are subsets of D. Recommend adding Only to distractors A-C.
22 F
4 X
E D, 41.7, CR - Typically, setpoints for non-critical alarms are not are required to be memorized.
Recommend checking with the facility.
23 F
4 X
E B, 41.7, CR - Typically, setpoints for non-critical alarms are not are required to be memorized.
Recommend checking with the facility.
24 F
3 S
B, 41.10, CR 25 F
3 S
B, 41.11, CR 26 F
3 X
U A, 41.10, CR - This question does not address the predict the impacts part of the KA.
27 F
3 X
U A, 41.4, CR - The four distractors are all true /
false statements.
28 H
3 S
B, 41.10, CR 29 H
3 S
D, 41.5, CR 30 H
3 S
C, 41.5, OR
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
Stem Focus Cues T/F CredDist Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only
- 6.
U/E/S
- 7.
Explanation 31 H
4 X
U C, 41.10, CR - This question tests on the subsequent actions in the ONP. Generally, candidates are not expected to have subsequent actions memorized.
32 F
3 S
C, 41.6, CR 33 F
3 S
C, 41.5, CR 34 F
3 S
A, 41.8, CR 35 H
3 X
?
D, 41.10, CR - This question tests on the subsequent actions in the ONP. Generally, candidates are not expected to have subsequent actions memorized. DISCUSS W/ LICENSEE.
36 F
3 S
D, 41.4, CR 37 H
3 X
U B, 41.7, CR - It can be argued both B and C are correct since B is a subset of C.
38 F
3 S
C, 41.10, CR 39 F
2 X
U D, 41.10, CR - There appears to be no correct answer.
40 H
2 S
C, 41.5, CR 41 H
3 S
C, 41.7, CR 42N03 H
3 X
U D, 41.10, CR - The KA selected tests on a specific system procedure or an integrated procedure (e.g. startup). The question tests on an emergency procedure.
43 H
3 X
X U
C, 41.10, OR - Distractors C and D are correct as D is a subset of C. Second, the reference provided does not contain a requirement to trip the reactor.
44 H
3 S
C, 41.10, CR 45 H
4 X
X X
U A, 43.2, CR - This is an SRO only question as it is testing on the application of tech specs.
Second it is a KA mismatch in that it does not test on tech spec entry conditions. Last, the tech spec is not provided as an attachment and candidates are generally not expected to have tech spec actions memorized unless less the LCO is less than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
46 H
3 S
D, 41.5, CR
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
Stem Focus Cues T/F CredDist Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only
- 6.
U/E/S
- 7.
Explanation 47 F
3 S
D, 41.5, CR 48 H
3 S
D, 41.10, CR ES-401 2
Form ES-401-9
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only
- 6.
U/E/S
- 7.
Explanation 49 F
3 S
B, 41.10, CR 50 H
3 S
A, 41.10, CR 51 H
3 X
U C, 41.10, CR - The KA requires testing on EOP actions and the question tests on ONP actions.
52 F
3 X
U C, 41.10, CR - The KA requires testing on EOP actions and the question tests on ONP actions.
53 H
3 S
B, 41.10, CR 54 H
3 S
C, 41.10, CR 55 F
3 S
C, 41.10, CR 56 H
3 X
U B, 41.10, CR - The KA tests on loss of FW and interrelations with other systems (signals, interlocks, etc) and the question is focused on operator EOP actions.
57 H
3 S
B, 41.5, CR 58 F
2 S
A, 41.6, CR 59 H
3 X
U D, 41.7, CR - The KA requires testing of the reasons for terminating a release and the question tests on system response.
60 H
3 S
D, 41.7, CR 61 F
3 X
E D, 41.10, CR - Recommend changing stem to read SG atmospheric dump valve has spuriously opened to match the procedure and revise distractor D accordingly.
62 F
4 X
X X
X U
C, 43.2, CR - This question tests on TS LCO actions making it an SRO Only question.
Second, the TS is not provided and the applicable
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only
- 6.
U/E/S
- 7.
Explanation LCO is a 54 or 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> action statement (not required to be memorized) and the stem does not explain which limit was exceeded.
63 F
3 X
U B, 43.2, CR - The answer for this question is found in the TS bases making it an SRO Only question.
64 F
2 X
X U
D, 41.10, CR - Distractors A and B are not credible. The question does not involve natural circulation as required by the KA.
65 H
2 S
A, 41.10, CR 66 F
2 X
X U
C, 41.5, CR - There is more than one variable to be met in order to be in Mode 6 that are not addressed in the stem. Distractor B could be argued to be correct.
34 of 34 NUREG-1021, Draft Revision 9
ES-401 2
Form ES-401-9
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
Stem Focus Cues T/F Cred Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only
- 6.
U/E/S
- 7.
Explanation 67 H
4 X
U B, 41.5, CR - This TS requires three LCOs be memorized that are greater than one hour action statements and are not required to be memorized.
68 F
3 S
B, 41.10, CR 69 H
2 S
D, 41.10, CR 70 F
1 U
D, 41.10, CR - The level of difficulty is too low (easy) to be a discriminating question.
71 F
3 S
B, 41.10, CR 72 H
2 S
A, 41.12, CR 73 F
2 S
C, 41.10, CR 74 H
3 X
U A, 41.10, CR - The KA tests on setpoints, interlocks, and automatic actions and the question tests on required operator actions.
75 F
2 S
A, 41.10, CR
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
Stem Focus Cues T/F Cred Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only
- 6.
U/E/S
- 7.
Explanation RO B= 37 (49%)
M=1 (1%)
N= 37 (49%)
H = 43 (75%)
F = 32 (43%)
U = 21 (28%)
E = 2 (3%)
S = 52 (69%)
(%)
M=
N=
(%)
H =
F =
U =
E =
SRO TOTALS
GENERAL COMMENT
S:
- 1.
This exam review was performed by S. Garchow the week of 10/01/2007.
- 2.
Bank questions are indicated by B; Modified are indicated by M; New questions are indicated by N.
- 3.
Comment resolution is indicated in blue.
- 4.
Average difficulty is 3.0 on the RO exam. This value is within the 2.75 - 3.00 difficulty band typically seen on an average exam by this reviewer.
- 5.
The 10CFR55.41/43 question distribution is (see general comment 10):
41.1 =
0 43.1 =
0 41.2 =
0 43.2 =
3 41.3 =
0 43.3 =
0 41.4 =
4 43.4 =
0 41.5 =
11 43.5 =
0 41.6 =
2 43.6 =
0 41.7 =
16 43.7 =
0 41.8 =
1 41.9 =
0 41.10 = 35 41.11 = 1 41.12 = 1 41.13 = 0 41.14 = 0
- 6.
The answer distribution is:
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
Stem Focus Cues T/F Cred Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only
- 6.
U/E/S
- 7.
Explanation A = 15 / 75 (20%).
B = 20 / 75 (27%).
C = 18 / 75 (24%).
D = 22 / 75 (29%).
- 7.
There are 3 questions with attachments provided.
- 8.
The RO portion of the exam is well outside the 50 - 60 % band for higher cognitive questions as required by the Written Exam Quality Checklist (ES-401-6). As graded by this reviewer, there are 57 (76%) higher cognitive questions. Recommend the Chief Examiner review these and have the facility licensee reduce the number as deemed appropriate so the exam is in compliance with the checklist. (See general comment 9.)
- 9.
There are over 60 questions that are scenario based. This is much higher than normal and directly contributes to the high number of cognitive questions.
- 10.
The exam is heavily skewed toward questions involving 10 CFR 55.41.10 (procedure based questions). The exam has about 35 questions focused on procedures which is significantly over-sampled when compared to a typical exam value of approximately 22 questions as seen by this reviewer. Recommend reducing the number of 41.10 focused questions by at least 10.
- 11.
There are several questions that test on subsequent actions contained in procedures. Typically, candidates are not expected to have questions of this type as memory questions unless supported by an objective. Historically, these questions are likely to be deleted from an exam during the appeal process if not supported by an objective.
Note that not all the questions of this type were flagged as needing review. Recommend the facility licensee review the exam in general to ensure the questions are supported by a learning objective.
- 12.
In general, this exam is poorly written and based on this review, will require a significant amount of rework. It is estimated that based on both the general comments above and the number of unsatisfactory questions, one-half to two-thirds of the questions will require some amount of rework to make the exam acceptable. It is also recommended the Chief Examiner follow up with the facility licensee on how the exam was reviewed and validated.
34 of 34 NUREG-1021, Draft Revision 9
NRC comments from Tom Stetka 10/4/2007 ES-401-9 form to follow General Overview:
10CFR55.41 distribution as follows:
41.10 35 twice number accustomed to seeing 41.7 16 41.5 11 41.2 0
41.3 0
41.13 0 41.14 0 41.9 0
41.8 1
Reevaluate CFR55.41 ties and redistribute to cover 0 covered items Cognitive level is high in band (This makes for overall more difficult exam), when revising questions slant more towards lower end, will result in easier test.
60 questions appear to be scenario based need to slant more towards systems based.
Generally speaking make the exam a little more fundamental.
Questions that are now considered Cognitive level 1 8, 10, 11, 21, 24, 26, 32, 33, 34, 36, 38, 39, 47, 49, 52, 58, 61, 62, 63, 64, 66, 68, 70, 71, 73, 75, and some others Comments on questions:
2, 6, 21, 22, 23, 26, 27, 35, 37, 39, 42, 43, 45, 51, 52, 56, 59, 61, 62, 63, 64, 66, 67, 70, 74
Examination Outline Cross-reference:
2 Group #
1 K/A #
003 K6.02 Importance Rating 2.7 Knowledge of the effect of a loss or malfunction on the following will have on the RCPS: RCP seals and seal water supply Proposed Question:
Common 2 OP-902-005, Station Blackout Recovery, directs the operator to verify closed the CCW non safety header containment isolation valves, CC-641, CC-710, ad CC-713 to isolate CCW to Containment. What is the reason for this?
A. To prevent thermal shocking the CEDM coolers when restarting the CCW pumps.
B. To prevent water hammer in Cntmt Bldg piping when restarting the CCW pumps.
C. To prevent thermal shocking the RCPs when restarting the CCW pumps.
D. To prevent running out the CCW pumps when restarting.
Proposed Answer:
C Explanation (Optional):
A.
Incorrect. CCW valves are isolated to prevent thermal shocking RCP upon CCW pump restart and readmission to RCPs after extended loss of cooling.
B.
Incorrect. CCW valves are isolated to prevent thermal shocking RCP upon CCW pump restart and readmission to RCPs after extended loss of cooling C.
Correct.
D.
Incorrect. CCW valves are isolated to prevent thermal shocking RCP upon CCW pump restart and readmission to RCPs after extended loss of cooling Technical Reference(s)
OP-902-005 step 6 TGOP-902-005 Step 6 (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPO10 Obj 01 (As available)
Question Source:
Bank #
X
Modified Bank #
(Note changes or attach parent)
New Question History:
Last NRC Exam Waterford 2004 Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis 10 CFR Part 55 Content:
55.41 7
Comments:
Need to look at parameters and reference NRC Comments:
KA mismatch does not meet seal water supply tie New Question
Examination Outline Cross-reference:
2 Group #
1 K/A #
007 K3.01 Importance Rating 3.3 Knowledge of the effect that a loss or malfunction of the PRTS will have on the following: Containment Proposed Question:
Common 6 A Steam Generator Tube Rupture has occurred that resulted in an automatic SIAS/CIAS.
Which ONE of the following would result in rising containment pressure, due to automatic alignment to the Quench Tank?
A. RCP Control Bleedoff B. RCP Vapor Seal Leak Off C. Reactor Head Vent Header D. Pressurizer Vent Header Proposed Answer:
A Explanation (Optional):
A is correct because RC-606, RCP Control Bleedoff Inside Containment Isolation Valve closes on a CIAS, redirecting RCP control bleedoff to the quench tank through a relief valve. Containment pressure would rise when quench tank rupture disc relieves.
B is incorrect because RCP vapor seal leakoff is directed to the Reactor Drain Tank at all times.
C is incorrect because the Reactor head vent must be aligned to the quench tank manually.
D is incorrect because the Pressurizer vent must be aligned to the quench tank manually.
Technical Reference(s)
WLP-OPS-RCS00 (Attach if not previously provided)
Proposed references to be provided to applicants during None
examination:
Learning Objective:
WLP-OPS-RCS00 obj 2 (As available)
Question Source:
Bank #
X Modified Bank #
(Note changes or attach parent)
New Question History:
Last NRC Exam 2003 NRC #32 Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
10 CFR Part 55 Content:
55.41 X
Comments:
NRC Comments:
KA mismatch Reworded question
Examination Outline Cross-reference:
2 Group #
1 K/A #
062 G2.4.6 Importance Rating 3.1 Emergency Procedures/Plan: Knowledge of symptom based EOP mitigation strategies Proposed Question:
Common 21 Given the Following:
- At 0930 the reactor was manually tripped due to loss of both Main Feedwater pumps
- Tavg is 547°F.
- EFAS-1 and EFAS-2 actuated one minute after the trip.
- EFW Pump B is running normally.
- OP-902-006, Loss of Main Feedwater Recovery Procedure has been entered.
- The time is now 1010.
Based on given plant conditions, how many RCPs must be secured?
A. Only 1 B. Only 2 C. Only 3 D. All 4 Proposed Answer:
D Explanation (Optional):
A.
Incorrect.
B.
Incorrect.
C.
Incorrect.
D.
Correct.
Technical Reference(s)
OP-902-006 (Attach if not previously
provided)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPE06 obj 4 (As available)
Question Source:
Bank #
X Modified Bank #
(Note changes or attach 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 10 Comments:
NRC Comments:
Editorial Could be argued all 4 answers correct If have to secure 4 then have to secure 1,2,3 Add only to distractors A,B and C 1only 2 only 3 only all 4 Reworded question per recommendation
Examination Outline Cross-reference:
2 Group #
1 K/A #
063 K4.04 Importance Rating 2.6 Knowledge of dc electrical system design feature(s) and/or interlock(s) which provide for the following: Trips Proposed Question:
Common 22 The following conditions exist in the plant:
- The BATTERY CHGR SA1 TROUBLE annunciator comes in on CP-35 in the Control Room
- The RAB Watch is sent to the A Switchgear to investigate Which ONE of the following has caused the alarm?
A. A Low Voltage Shutdown occurred at 129 VDC.
B. A Low Voltage Shutdown occurred at 134 VDC.
C. A High Voltage Shutdown occurred at 139 VDC.
D. A High Voltage Shutdown occurred at 144 VDC.
Proposed Answer:
D Explanation (Optional):
A.
Incorrect. Low voltage alarm at 129 VDC but not shutdown B.
Incorrect. 134 VDC is a typical float charge C.
Incorrect. 139 VDC is a typical equalizing charge D.
Correct. High voltage shutdown occurs at 144 VDC Technical Reference(s)
OP-006-003 (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-DC00, #6 (As available)
Question Source:
Bank #
WF3-
NRC-82-B Modified Bank #
(Note changes or attach 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:
NRC Comments:
Editorial Memorization of alarm setpoints When resubmit final include copy of learning objective OBJECTIVES:
STATE the purpose of the DC Distribution system. [1]
STATE the design basis of the system. [2]
STATE the purpose of the major components: [3]
- Battery Chargers
- Battery
- Distribution Panels EXPLAIN how a battery charger operates. [4]
Given a one line diagram of the system, LABEL the components, buses, and PDPs. [5]
IDENTIFY the causes of alarms associated with the system. [6]
Examination Outline Cross-reference:
2 Group #
1 K/A #
064 K6.08 Importance Rating 3.2 Knowledge of the effect of a loss or malfunction of the following will have on the ED/G system: Fuel oil storage tanks Proposed Question:
Common 23 Given the following conditions:
- Emergency Diesel Generator B is operating at 4.4 kW for OP-903-068 surveillance testing.
- The following alarm is received:
EDG B FUEL OIL XFER PUMP PWR LOST
- Fuel Oil Feed Tank B indicates 100 percent on CP-1
- The RAB watch reports that the breaker for Fuel Oil Transfer Pump B breaker is tripped, and the motor is too hot to touch.
Based on these conditions, what is the MAXIMUM time Emergency Diesel Generator B continue to operate with no additional actions?
A. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> B. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> C. 1 day D. 7 days Proposed Answer:
B Explanation (Optional):
A.
Incorrect. The auto start setpoint of the Fuel Oil Transfer pump is -30 inches which corresponds to a 1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> run time plus 10 %
B.
Correct. The feed tank holds a two-hour supply of fuel based on 600 gal capacity
and 307 gal/hr consumption.
C.
Incorrect.
D.
Incorrect. The Storage tank holds about a seven-day supply of fuel Technical Reference(s)
SD EDG Page 16 (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-EDG obj 7 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis 10 CFR Part 55 Content:
55.41 X
55.43 2
Comments:
NRC Comments:
Editorial Memorization of alarm setpoints When resubmit final include copy of learning objective New question
SYSTEM DESCRIPTION EDG FUEL OIL FEED TANK This vertical, cylindrical, carbon steel tank is designed for 15 psig and 125°F. Its capacity is sufficient to maintain at least 60 minutes of operation at 100% load plus 10%
margin at the level where oil is added automatically. This amounts to 339 gallons based on usage of 307.8 gallons/hour plus 10%. The tank's overflow volume is 613 gallons. It is filled from the Fuel Oil Storage Tank by the Fuel Oil Transfer Pump. The Fuel Oil Transfer Pump will start at a feed tank level of -30 inches (EGF-ILS-6907A (B)) below the overflow centerline, and stop at a feed tank level of -6 inches (EGF-ILS-6908A (B)).
The Fuel Oil Transfer Pump can also be operated in manual at the local control panel.
The storage tank is normally filled by trucks. An emergency fill connection is provided for use during flooding of the area and can be filled from a barge. The transfer pumps are required for operability but can be cross-connected if necessary for transferring oil.
The following tank levels are referenced from the overflow line except for EGF-ILS-6903A (B), which is referenced from the bottom tangent of the tank. Level indication is available in the Control Room on EGF-ILI-6903-1A (B) over a range of 0-100% and locally on EGF-ILI-6903A (B) over a range of 0-6 feet. Low and high level alarms are provided locally by EGF-ILS-6906A(B) at -34 in. and by EGF-ILS-6903A (B) at 70 in., respectively. A FUEL OIL DAY TANK HI/LO alarm is provided at G2 and G4 on Cabinet D in the Control Room with high and low setpoints of -32 in. (EGF-ILS-6906A (B)) and -4 in. (EGF-ILS-6908A (B)), respectively. At -34 in. level, an EDG UNAVAILABLE alarm will annunciate at G1 and G3 on Cabinet D in the Control Room.
The tank's UNID is EGF-MTNK-0002A (B).
FUEL OIL STORAGE TANK This vertical, cylindrical, carbon steel, atmospheric tank has a useable volume of 40,747 gallons of fuel oil and an overflow volume of 41,579 gallons. Its design temperature is 125°F. It is designed to hold enough fuel oil to supply its diesel engine for seven days based on calculations done in support of the safety analyses. The Technical Specification requirement to have at least 39,300 gallons of fuel oil stored in the tank is based on the time dependent loads of the EDG following a loss of offsite power (LOOP) and a design bases accident.
Tank level is provided locally in the Fuel Oil Storage Tank Room on EGF-ILI-6994.1A (B) over a range of 0-100%. High and low levels are annunciated in the Control Room at K2 and K4 on Cabinet D at 98.8%. and 93.5%, respectively, as sensed by EGF-IAA-6994A (B). The high level alarm is intended to prevent overflowing the storage tank weir wall, and the low level is intended to prevent going below the Tech Spec limit (5 day limit plus two hours consumption). The tank's UNID is EGF-MTNK-0001A (B).
Page 61
Examination Outline Cross-reference:
2 Group #
1 K/A #
076 A2.01 Importance Rating 3.5 Ability to (a) predict the impacts of the following malfunctions or operations on the SWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of SWS Proposed Question:
Common 26 Given the following:
- The plant is at 100% power.
- TCW Pump B is in service.
- TCW Pump A is tagged for repair.
- The following alarms are received in the control room:
o TURB CLNG WTR PUMP B TRIP/TROUBLE o TURB CLNG WATER DISCH HDR PRESS LO
- Operator actions fail to restore TCW flow.
Which ONE of the following describes the impact AND the actions required IAW OP-901-512 for these conditions?
A. Generator Winding damage, Trip the reactor.
B. Loss of Generator Hydrogen, Trip the reactor.
C. Generator Winding damage, Initiate a plant shutdown to remove the main generator from service.
D. Loss of Generator Hydrogen, Initiate a plant shutdown to remove the main generator from service.
Proposed Answer:
A Explanation (Optional):
A.
Correct. Section E1 of AOP B.
Incorrect. Main Generator will be damaged if operating for 2-3 minutes with no TCW. Generator H2 will be maintained by air side and hydrogen side seal oil.
C.
Incorrect. A reactor trip is required because the Main Generator will be damaged if operating for 2-3 minutes with no TCW D.
Incorrect. A reactor trip is required because the Main Generator will be damaged if operating for 2-3 minutes with no TCW Technical Reference(s)
OP-901-512, E1 (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPO50 obj 3 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis 10 CFR Part 55 Content:
55.41 10 Comments:
NRC Comments:
Unacceptable KA mismatch New question
Examination Outline Cross-reference:
2 Group #
1 K/A #
078 A3.01 Importance Rating 3.1 Ability to monitor automatic operation of the IAS, including: Air pressure Proposed Question:
Common 27 Given the following conditions:
100 percent power Instrument Air Header pressure is 120 psig An air leak occurs, causing Instrument Air Header pressure to drop to 100 psig.
Which of the following describes the status of the instrument air system?
A. SA-125 Station Air Backup is OPEN, SA-123 Air dryer Bypass is OPEN B. SA-125 Station Air Backup is CLOSED, SA-123 Air dryer Bypass is OPEN C. SA-125 Station Air Backup is OPEN, SA-123 Air dryer Bypass is CLOSED D. SA-125 Station Air Backup is CLOSED, SA-123 Air dryer Bypass is CLOSED Proposed Answer:
C Explanation (Optional):
A.
Incorrect. SA-125 opens at 105 psig SA-123 opens at 95 psig B.
Incorrect. SA-125 opens at 105 psig SA-123 opens at 95 psig C.
Correct D.
Incorrect. SA-125 opens at 105 psig SA-123 opens at 95 psig Technical Reference(s)
SD AIR, R7, pg 8 OP-003-016 (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-AIR00 obj. 01 (As available)
Question Source:
Bank #
X Modified Bank #
(Note changes or attach 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 5
Comments:
NRC Comments:
Unacceptable True false statements New question
Examination Outline Cross-reference:
2 Group #
2 K/A #
033 A2.03 Importance Rating 3.1 Ability to (a) predict the impacts of the following malfunctions or operations on the Spent Fuel Pool Cooling System ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Abnormal Spent Fuel Pool water level or loss of water level Proposed Question:
Common 35 Given the following:
The RAB watch has just completed opening the Fuel Transfer Tube Gate Valve in the FHB.
The RAB Watch reports that SFP level dropped to 41 feet when he was opening the valve.
Which of the following is true for this situation?
A. Low Spent Fuel Pool level Alarm only, fill from Primary Makeup.
B. Low Spent Fuel Pool Level Alarm and CMU Auto makeup Valve Opens to refill the SFP C. Low Spent Fuel Pool Level Alarm and running SFP Cooling Pump trips, fill from Condensate Storage Pool.
D. Low Spent Fuel Pool Alarm and FHB Isolation Actuation occurs, fill form the Refueling Water Storage Pool.
Proposed Answer:
C Explanation (Optional):
A.
Incorrect. SFP cooling pumps trips at 41.6 feet. Primary makeup is not used to fill SFP B.
Incorrect. SFP cooling pumps trips at 41.6 feet, CMU makeup is aligned manually C.
Correct. SFP Cooling pumps trip at 41 6. SFP is filled from CSP or RWSP D.
Incorrect. SFP Cooling pumps trip at 41 6. Alarm at 43 9. Do not isolate FHB vent, just check it Technical Reference(s)
OP-901-513 (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-FS00 obj 3 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis 10 CFR Part 55 Content:
55.41 10 Comments:
NRC Comments:
Unacceptable Memorize Subsequent actions from memory Will need objective to support if we require from memory New question system knowledge of SFP pump trips and systems available for filling SFP
Examination Outline Cross-reference:
2 Group #
2 K/A #
045 K4.43 Importance Rating 2.8 Knowledge of MT/G system design feature(s) and/or inter-lock(s) which provide for the following: T-ave. program, in relation to SDS controller Proposed Question:
Common 37 Given the following:
- The plant is operating at 100% power.
- Tavg and PZR level are on program.
- A Main Turbine Governor Valve fails closed.
- Generator load drops by approximately 30%.
Which ONE of the following describes the operation of the SBCS for this condition?
A. All 6 SBCS valves are available to modulate, Quick Open is blocked for all 6 valves B. All 6 SBCS valves are available to modulate and for Quick Open.
C. SBCS valves 1 through 5 are available for Quick Open, Valve 6 is blocked.
D. SBCS valves 1 through 5 are available to modulate, Valve 6 is blocked.
Proposed Answer:
B Explanation (Optional):
A Incorrect. Valves will quick open, modulation also available B Correct. Quick open blocked by Tavg <562 on reactor trip. #6 valve blocked on any reactor trip. Quick open is available to all valves to maintain steam pressure during a load rejection C Incorrect. Credible because conditions could exist with reactor trip that would result in this function D Incorrect. Quick open would only be blocked for 1 valve if a trip occurred, modulation is available
Technical Reference(s)
WLP-OPS-SBC00 (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-SBC obj 4 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
10 CFR Part 55 Content:
55.41 7
Comments:
NRC Comments:
B and c could both be argued to be correct b subset of c Modify c and d only 5 will open Reworded question
Examination Outline Cross-reference:
1 Group #
1 K/A #
007 EA2.02 Importance Rating 4.3 Ability to determine or interpret the following as they apply to a reactor trip: Proper actions to be taken if the automatic safety functions have not taken place Proposed Question:
Common 39 Given the following:
- The plant was at 100% power.
- A reactor trip occurred.
- The crew is performing Standard Post Trip Actions.
- BOTH Generator Output Breakers remain closed.
- The Generator Exciter Field Breaker remains closed.
Which of the following will the BOP perform in response to the generator not being tripped?
A. Manually OPEN all 3 breakers from CP-1.
B. Transfer BOTH electrical busses from the UAT to the SUT.
C. Manually trip the Main Generator using EITHER GENERATOR EMERG TRIP pushbutton.
D. Manually trip the Main Generator using BOTH GENERATOR EMERG TRIP pushbuttons.
Proposed Answer:
D Explanation (Optional):
A. Incorrect. Busses must be transferred first B. Incorrect. After bus transfer, breakers must be opened C. Incorrect. Not enough action. BOTH pushbuttons must be depressed D. Correct.
Technical Reference(s)
OP-902-000, step 2.b contingency (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPE01 obj. 09 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis 10 CFR Part 55 Content:
55.41 10 Comments:
NRC Comments:
No correct answer Stem says what actions will bop perform first Modify stem to say which of the following BOP will perform to response to generator not being tripped Will make fundamental question Reworded per recommendation
Examination Outline Cross-reference:
1 Group #
1 K/A #
011 G2.1.23 Importance Rating 3.9 Conduct of Operations: Ability to perform specific system and integrated plant procedures during all modes of plant operation.
Proposed Question:
Common 42 Given the following:
- A Small Break LOCA is in progress.
- The crew has diagnosed into OP-902-002, LOCA Recovery Procedure and performed all required steps.
- Containment Temperature is 205°F and slowly lowering.
Which of the following criteria would preclude transitioning into OP-009-005, Shutdown Cooling System procedure and placing a Shutdown Cooling Train in service.?
A. RCS Subcooling is 28°F and slowly rising.
B. Pressurizer Pressure is 420 psia and stable.
C. RCS Thot is 345°F and stable.
D. Pressurizer Level 33% and steady.
Proposed Answer:
B Explanation (Optional):
A.
Incorrect. Minimum subcooling requirement is met.
B.
Correct. Less than 392 psia required.
C.
Incorrect. Thot required to be less than 350°F.
D.
Incorrect. Pressurizer Level is required to be greater than 33%.
Technical Reference(s)
LOCA OP-902-002 OP-009-005, SDC System Procedure Precautions and Limitations.
(Attach if not previously provided)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPE02 obj 17 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis 10 CFR Part 55 Content:
55.41 10 55.43 Comments:
NRC Comments:
Unacceptable KA mismatch Test EOP not integrated or normal procedure or system op Meant to be NOP or SOP not EOP actions New question OP-902-002 and OP-009-005 SDC entry conditions
Examination Outline Cross-reference:
1 Group #
1 K/A #
022 AK1.03 Importance Rating 3.0 Knowledge of the operational implications of the following concepts as they apply to Loss of Reactor Coolant Pump Makeup: Relationship between charging flow and PZR level Proposed Question:
Common 43 Plant status is as follows:
- Reactor power is 70%.
- The operating Charging Pump trips.
- The backup Charging Pumps cannot be started.
SELECT the highest Pressurizer level at which the reactor should be manually tripped.
A. 48%
B. 40%
C. 37%
D. 33%
Proposed Answer:
C Explanation (Optional):
A.
Incorrect. Trip not required this corresponds to program level plausible if wrong curve used B.
Incorrect. Trip not required C.
Correct. OP-901-112 Attachment A D.
Incorrect. Trip should occur prior to this level Technical Reference(s)
OP-901-112 (Attach if not previously provided)
Proposed references to be provided to applicants during OP-901-112, Att 1,
examination:
PDB RCS Temp band vs power Learning Objective:
WLP-OPS-PPO10 obj. 03 (As available)
Question Source:
Bank #
X Modified Bank #
(Note changes or attach 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 10 Comments:
D subset of c 2 right answers if have to trip at 37 also have to trip at 33
Reference:
doesnt show where trip needed Sent 110 should be 112 reference needs to direct tripping Reworded based on recommendations included correct documentation reference
Examination Outline Cross-reference:
1 Group #
1 K/A #
026 G2.1.33 Importance Rating 3.4 Conduct of Operations: Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications.
Proposed Question:
Common 45 Given the following conditions:
The unit is at 100% power.
1200 CCW Pump "A" declared INOPERABLE due to a failed surveillance.
1227 CCW Pump "B" also declared INOPERABLE due to the results of a common cause failure analysis.
1254 Plant Shutdown to Mode 3 commenced.
1319 CCW Pump "A" returned to OPERABLE status.
1338 CCW Pump "B" returned to OPERABLE status.
Which ONE (1) of the following describes the Technical Specification requirements for operation of the plant?
Plant conditions...
A. allowed the plant shutdown to be terminated no earlier than 1319.
B. allowed the plant shutdown to be terminated no earlier than 1327.
C. require that the Shutdown to Mode 3 is completed by 1827.
D. require that the Shutdown to Mode 3 is completed by 1927.
Proposed Answer:
A Explanation (Optional):
A.
Correct. CSP minimum pool level is 92%
B.
Incorrect. SIT pressure is 600-677 psig C.
Incorrect. RWSP boron concentration spec 2050-2900 ppm D.
Incorrect. CS riser surveillance is >149.5 MSL TS logs = > 182 ft
Technical Reference(s)
TS 3.0.3, TS section 3.7 (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-TS04 obj. 1,2 (As available)
Question Source:
Bank #
X Modified Bank #
(Note changes or attach parent)
New Question History:
Last NRC Exam Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
10 CFR Part 55 Content:
55.41 10 2
Comments:
WTSI Bank NRC Comments:
SRO only question RO which of the following require entering ts Control room display look at it require ts entry KA mismatch Stem gives you that your in an LCO Take something out of tech spec logs give numbers ask which one is outside TS limit We would like to discuss this question.
An alternate question has been proposed
Plant conditions are as follows:
Plant is in Mode 1 at 100% power following a refueling outage.
Dry Bulb Temperature is 92°F.
Wet Bulb Temperature is 88°F.
Auxiliary Component Cooling Water (ACCW) Trains A & B are in service with flow at 2000 GPM per train.
The RAB watch calls and reports that ACC-132A, ACC HEADER A TO WET CLG TOWER INLET ISOL is Locked Closed, and should be Locked Open.
Based upon these conditions determine the appropriate action?
A. No action required, Wet Cooling Tower is OPERABLE with other three valves verified Locked Open.
B. ACCW Train A is INOPERABLE, enter T.S. 3.7.3 for ACCW Train A and cascading Tech Specs.
C. Wet Cooling Tower A is INOPERABLE, enter T.S. 3.7.4 for Ultimate Heat Sink Only.
D. ACCW Train A is OPERABLE, but Wet Cooling Tower A is INOPERABLE, enter T.S. 3.7.4 for Ultimate Heat Sink and cascading Tech Specs.
Proposed answer: B A. Incorrect, all valves required to be open for Operability of ACCW Train per OP-100-014.
B. Correct. The ACCW Train is declared inoperable, and cascading TS are entered per OP-100-014 C. Incorrect. Cascading Tech Specs must be entered for this condition.
D. Incorrect. The ACCW Train cannot be Operable with the Ultimate Heat Sink Inoperable.
Technical
Reference:
OP-100-014 T.S. 3.7.3 & 3.7.4
Examination Outline Cross-reference:
1 Group #
1 K/A #
057 AK3.01 Importance Rating 4.1 Knowledge of the reasons for the following responses as they apply to the Loss of Vital AC Instrument Bus: Actions contained in EOP for loss of vital ac electrical instrument bus Proposed Question:
Common 51 Given the following:
- The plant is at 70% power.
- Auxiliary Component Cooling Water Pump A is running.
- A loss of bus MA has occurred.
Which ONE (1) of the following the action that will be required to control Component Cooling Water temperature, and reason for the action?
A. Manually control dry cooling tower and wet cooling tower train A fans because CC HX A ACC Outlet TCV (ACC-126A) fails closed, resulting in loss of temperature control.
B. Manually throttle cooling tower wet basin M/U valve (CMU-410A) to maintain wet basin level because CC HX A ACC Outlet TCV (ACC-126A) fails closed, resulting in loss of Wet Basin level control..
C. Manually control dry cooling tower and wet cooling tower train A fans because CC HX A ACC Outlet TCV (ACC-126A) fails open, resulting in loss of temperature control.
D. Manually isolate cooling tower wet basin M/U valve (CMU-410A) to prevent a high wet basin level because CC HX A ACC Outlet TCV (ACC-126A) fails open.
Proposed Answer:
C Explanation (Optional):
A.
Incorrect. Valve fails open, but actions correct B.
Incorrect. Valve fails open, actions not correct C.
Correct. Part of action for manually controlling CCW temperature with A ACCW in
service.
D.
Incorrect. Would throttle M/U valve, would not isolate it.
Technical Reference(s)
OP-901-312 (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-CC00 obj. 03, 04 WLP-OPS-PPE30 obj. 03 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
10 CFR Part 55 Content:
55.41 10 Comments:
NRC Comments:
KA mismatch Reasons for response not asking why is it Reworded question
Examination Outline Cross-reference:
1 Group #
1 K/A #
058 AK3.02 Importance Rating 4.0 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:
Common 52 Given the following:
- Emergency Diesel Generator 'A' is running loaded.
- A loss of DC control power occurs.
Which of the following describes the effect of the loss of DC control power on the EDG and its auxiliaries?
A. The EDG fuel racks will trip and the EDG must be declared inoperable.
B. The lube oil cooler temperature control valve will fail to the full cooling position.
C. Fuel oil transfer pump starts and must be secured to prevent overfilling the feed tank.
D. Jacket cooling water valves fail open and the jacket water heater loses power.
Proposed Answer:
C Explanation (Optional):
A.
Incorrect. Loss of DC will not trip fuel racks B.
Incorrect.
C.
Correct.
D.
Incorrect.
Technical Reference(s)
OP-901-313 (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
None
Learning Objective:
WLP-OPS-PPO30 obj 3 (As available)
Question Source:
Bank #
X Modified Bank #
(Note changes or attach parent)
New Question History:
Last NRC Exam Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
10 CFR Part 55 Content:
55.41 10 Comments:
NRC Comments:
KA mismatch Reasons for response not asking why is it Asking what happens Basis Interlocks functions What is the basis for Loss of dc take some actions why does the operator do this Reason for action We would like to discuss this question
Examination Outline Cross-reference:
1 Group #
1 K/A #
E06 EK2.1 Importance Rating 3.3 Knowledge of the interrelations between the (Loss of Feedwater) and the following: Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
Proposed Question:
Common 56 Given the following:
- The reactor has tripped due to a loss of Main Feedwater.
- Standard Post Trip Actions have been carried out in accordance with OP-902-000
- Diagnostics has directed the crew to OP-902-006, Loss of Main Feedwater Recovery.
Which ONE of the following describes when and how the crew will align EFW Pump suction to ACCW in accordance with OP-902-006 and Appendix 10?
A. At 25% CSP level, EFW Pump suctions must be aligned to their respective train of ACCW.
B. At 25% CSP level, EFW Pump suctions must be aligned to one operating train of ACCW.
C. At 11% CSP level, EFW Pump suctions must be aligned to their respective train of ACCW.
D. At 11% CSP level, EFW Pump suctions must be aligned to one operating train of ACCW.
Proposed Answer:
B Explanation (Optional):
A.
Incorrect. Not required to be aligned by train.
B.
Correct.
C.
Incorrect. Wrong level and not required to be train-specific. 11% credible because it is the minimum level for CSP to supply EFW D.
Incorrect. Wrong level
Technical Reference(s)
OP-902-006 (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPE06 obj 9 (As available)
Question Source:
Bank #
WF3-OPS-5662-A Modified Bank #
(Note changes or attach parent)
New Question History:
Last NRC Exam Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
10 CFR Part 55 Content:
55.41 10 Comments:
KA mismatch Loss of feedwater Feed pump turbine fails because of that Instrument fails as a result interlock failure modes auto manual actions Systems questions not procedure We would like to discuss this question.
Examination Outline Cross-reference:
1 Group #
2 K/A #
059 AK3.01 Importance Rating 3.5 Knowledge of the reasons for the following responses as they apply to the Accidental Liquid Radwaste Release:
Termination of release of radioactive liquid Proposed Question:
Common 59 Given the following:
- Waste Condensate Tank B is being discharged to the Circ Water system.
- The following indications are observed in the Control Room:
o WASTE LIQUID DISCH ACTIVITY HI annunciator in alarm on CP-4 o EFFLUENT RAD MONITORING SYS ACTIVITY HI-HI annunciator in alarm on CP-36 Based on the above conditions, which ONE of the following describes plant response?
A. ONLY BM-547, Boron Management Discharge to Circ Water Auto Isolation Valve, closes.
B. ONLY LWM-441, Liquid Waste to Circ Water Shutoff Valve, closes.
C. BM-547, Boron Management Discharge to Circ Water Auto Isolation Valve, closes.
BM-549, Boron Management Discharge to Circ Water Flow Control Valve closes.
D. LWM-441, Liquid Waste to Circ Water Shutoff Valve, closes.
LWM-442, Liquid Waste to Circ Water Control Valve, closes.
Proposed Answer:
D Explanation (Optional):
A.
Incorrect. Valve does not close for this alarm B.
Incorrect. Valve closes, but the flow control valve also closes C.
Incorrect. Both of these valves are initiated from a different rad monitor alarm D.
Correct.
Technical Reference(s)
WLP-OPS-PPO40 (Attach if not previously provided)
OP-901-414 Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-LWM obj 5 (As available)
Question Source:
Bank #
X Modified Bank #
(Note changes or attach 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 Comments:
WF3-OPS-4222B KA mismatch Basis or reason System question We see no credible way to test the reason behind why we terminate an inadvertent liquid radioactive release. This is very basic fundamental knowledge of protecting the safety and health of the public.
Examination Outline Cross-reference:
1 Group #
2 K/A #
068 AA1.01 Importance Rating 4.3 Ability to operate and / or monitor the following as they apply to the Control Room Evacuation:: S/G atmospheric relief valve Proposed Question:
Common 61 Given the following:
The plant was at 100% power.
A fire developed in the control room, requiring the control room to be evacuated.
The crew is performing OP-901-502, Evacuation of Control Room and Subsequent Plant Shutdown.
Atmospheric Dump Valves have spuriously opened Which ONE of the following describes ONLY actions that will be performed prior to leaving the control room?
A. Initiate RCS boration and de-energize Atmospheric Dump Valve Controllers.
B. Trip RCPs and de-energize Atmospheric Dump Valve Controllers.
C. \\Initiate RCS boration and Place Atmospheric Dump Valves in MANUAL with 0 output.
D. Place Atmospheric Dump Valves in MANUAL with 0 output and trip RCPs.
Proposed Answer:
D Explanation (Optional):
A.
Incorrect. Do not de-energize controllers, place in manual. Boration initiated later B.
Incorrect. Do not de-energize controllers C.
Incorrect. Boration is initiated after evacuation D.
Correct. ADVs in manual with 0 output only if erratic operation is observed.
Technical Reference(s)
OP-901-502 (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPO51 obj 2 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis 10 CFR Part 55 Content:
55.41 10 Comments:
Editorial Change stem to read ADV spuriously opened to match procedural wording.
Changed to reflect procedural wording
Examination Outline Cross-reference:
1 Group #
2 K/A #
076 G2.1.32 Importance Rating 3.4 Conduct of Operations: Ability to explain and apply all system limits and precautions Proposed Question:
Common 62 Given the following:
- A load reduction from 100% to 70% power was performed.
- The CRS determines that a plant shutdown is required.
Which ONE (1) of the following describes additional actions taken to minimize the potential for radioactive release?
A. Isolate Letdown.
B. Place an additional ion exchanger in service if the DF is < 1.0.
C. Cool down the RCS to below 500 degrees F.
D. Place Condensate Polishers in service with resin per Chemistry instructions.
Proposed Answer:
C Explanation (Optional):
A.
Incorrect. Letdown would be raised to clean up RCS B.
Incorrect. If SF >1.0 would perform this action C.
Correct. RCS cooled down to below SG ARV setpoints in case of a subsequent SGTR D.
Incorrect. Clean up of secondary with this action. Primary has high activity Technical Reference(s)
TS 3.4.7 (Attach if not previously provided)
OP-901-410
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-TS04 obj 3 (As available)
Question Source:
Bank #
X Modified Bank #
(Note changes or attach parent)
New Question History:
Last NRC Exam Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
10 CFR Part 55 Content:
55.41 10 2
Comments:
SRO only question More than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> action Sop precautions and limits There are no credible system limits pertaining to High RCS activity. We would like to discuss this question.
If this question is still unacceptable we will have to replace the KA
Examination Outline Cross-reference:
1 Group #
2 K/A #
A11 G2.1.27 Importance Rating 2.8 Conduct of Operations: Knowledge of system purpose and or function.
Proposed Question:
Common 63 During an ESDE inside containment, which ONE of the following components functions to provide a boundary to allow controlled EFW flow to the unaffected SG?
A. Main Steam Isolation Valve.
B. Main Feedwater Isolation Valve.
C. Main Feedwater Regulating Valve.
D. Startup Feedwater Regulating Valves Proposed Answer:
B Explanation (Optional):
A.
Incorrect. MSIV ensures no more than 1 SG blows down B.
Correct.
C.
Incorrect. Ensures that RCS cooldown will be limited by closing D.
Incorrect. Same function as Main Feedwater Regulating Valve Technical Reference(s)
TS Basis 3.7.1.6 (Attach if not previously provided)
FW00 LP Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-FW00, obj 6 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
10 CFR Part 55 Content:
55.41 5
Comments:
SRO only Reference TS basis System procedure description Provide SD instead of tech specs System Description documentation provided
SD-FW also supplies condensate to the Feedwater System through a 12 inch bypass line around the steam generator feed pumps.
Emergency Feedwater System - supplies water in an emergency when the Feedwater System fails to operate.
One six-inch emergency feedwater pipe ties into each steam generator feedwater line downstream of feedwater isolation valves, FW-184A and B. Under normal conditions, the Emergency Feedwater System is not operating. Only in an emergency when the Feedwater System fails to operate does the Emergency Feedwater System start to deliver water to the steam generator at a sufficient rate for the safe shutdown of the reactor.
Steam Generator Blowdown - Two four-inch pipes from downstream of the feedwater control valves (one from each steam generator feedwater supply line) are connected to the steam generator blowdown line going to the blowdown filter and blowdown demineralizer. Used to clean the required volume of water by recirculating it from the condenser hotwell through condensate and feedwater piping, the blowdown demineralizer and then back to the condenser hotwell. The water is recirculated until it reaches the quality of condensate that is acceptable for feeding the steam generators. This method of feedwater cleanup is not used due to the installation of full flow Condensate Polisher System.
Main Steam Isolation Signal - controls in part the operation of the feedwater isolation valves.
o The Main Steam Isolation Signal (MSIS) is part of the Engineered Safety Features Actuation System (ESFAS). The Main Steam Isolation Signal isolates the steam generators and their main feedwater supply in the event of a steam line break accident. Main steam isolation is achieved by closing both Main Steam Isolation Valves MS-124A(B). Main Feedwater isolation is achieved by closing Main Feedwater Isolation Valves FW-184A(B). MSIS also closes FW-173A(B), Main Feedwater Regulating Valves and FW-166A(B), Startup Feedwater Regulating Valves as a backup to closing FW-184A(B). MSIS is initiated by two-out-of-four low steam generator pressure signals from either steam generator. Each steam generator pressure signal forms its own two-out-of-four logic. An MSIS is also generated by two-out-of-four high containment pressures.
o Manual initiation of an MSIS signal may be performed in the main Control Room.
A pretrip alarm is initiated at 100 PSIA above the setpoint to provide audible and visible indication of an approach to a trip condition.
Main Steam and Reheat Steam - Provide steam to drive Steam Generator Feed Pump Turbines.
Extraction Steam - Heats FW in the heaters.
Reactor Coolant - heats the feedwater in the steam generators.
Examination Outline Cross-reference:
1 Group #
2 K/A #
A13 AK1.1 Importance Rating 3.0 Knowledge of the operational implications of the following concepts as they apply to the (Natural Circulation Operations)
Components, capacity, and function of emergency systems.
Proposed Question:
Common 64 Given the following:
A loss of offsite power occurred 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ago due to a tornado touching down in the switchyard EFW pumps are supplying Steam Generators Thot is currently 500°F CSP level is 85 percent DWST is unavailable due to tornado damage Which of the following describes the AVAILABLE feedwater AND the MAXIMUM time remaining to place Shutdown Cooling in service?
A. 99,000 gal, 6.
B. 99,000 gal, 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.
C. 150,000 gal, 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
D. 150,000 gal, 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.
Proposed Answer:
A Explanation (Optional):
A.
Correct. 27000 gal required, DWST= 0 CSP=179010-53000 = 99010 available curve 2J 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after shutdown = 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> B.
Incorrect. 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> if using wrong time after shutdown curve C.
Incorrect. 150000 gal if 53000 not subtracted, 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> if curve 2H used D.
Incorrect. 150000 gal if 53000 not subtracted curve 2j for 150000 = 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> Technical Reference(s)
OP-902-003 step 24 OP-902-009 att 2-G, H, I, J (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
OP-902-009 att 2-G OP-902-009 att 2-H OP-902-009 att 2-I OP-902-009 att 2-J Learning Objective:
WLP-OPS-PPE01 obj 11 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
10 CFR Part 55 Content:
55.41 10 Comments:
W3-NRC-1704A A B not plausible Doesnt involve nat circ New question
Examination Outline Cross-reference:
3 Group #
1 K/A #
2.1.22 Importance Rating 2.8 Ability to determine Mode of Operation.
Proposed Question:
Common 66 Given the following plant conditions:
RCS average temperature: 425 °F All control rods: Fully inserted RCS cooldown rate: 30F/hour What is the current plant Mode as defined in Technical Specifications for these conditions?
A.) MODE 1 B.) MODE 2 C.) MODE 3 D.) MODE 4 Proposed Answer:
C Explanation (Optional):
A.
Incorrect. Mode 1 = >5% would require control rods to be withdrawn Keff >.99 B.
Incorrect. shutdown control rods would be withdrawn Keff >.99 C.
Correct. <.99, 0%. tavg >350 D.
Incorrect. Mode 4 350 > tavg >200 Technical Reference(s)
TS Definitions (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-TS00 0bj. 03 (As available)
Question Source:
Bank #
X Palisades NRC 2006
Modified Bank #
(Note changes or attach parent)
New Question History:
Last NRC Exam Palisades NRC 2006 Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis 10 CFR Part 55 Content:
55.41 10 Comments:
More than one variable to mode 6 Maybe multiple variables 250 RX.98 Pressure Based on this M-1,2,3,4 New question NRC Exam Palisades 2006
Examination Outline Cross-reference:
3 Group #
1 K/A #
G2.1.11 Importance Rating 3.0 Knowledge of less than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> technical specification action statements for systems Proposed Question:
Common 67 Given the following conditions:
- 1. Mode 5
- 2. RCS temperature 105°F
- 4. SG temperature 100°F
- 5. The operator notices that SG #1 has been overfilled and SG pressure is at 300 psig What is the SG status in regards to Technical Specifications?
A. Pressure/temperature limitation satisfied B. SG temperature high and SG pressure high, pressure/temperature LCO NOT met.
C. SG pressure and temperature low, pressure/temperature LCO NOT met.
D. SG temperature low and SG pressure high, pressure/temperature LCO NOT met Proposed Answer:
D Explanation (Optional):
A.
Incorrect. SG temp > 115 when SG press> 210 psig B.
Incorrect. SG temp > 115 when SG press> 210 psig C.
Incorrect. SG temp > 115 when SG press> 210 psig D.
Correct.
Technical Reference(s)
TS section 3.7.2 (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
None
Learning Objective:
WLP-OPS-CB00 obj 7 (As available)
Question Source:
Bank #
X Modified Bank #
(Note changes or attach parent)
New Question History:
Last NRC Exam Waterford 1995 Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
10 CFR Part 55 Content:
55.41 6
55.43 2
Comments:
WF3-NRC -3556-A Only one expected to know from memory Could recognize correct answer New question
Examination Outline Cross-reference:
3 Group #
2 K/A #
2.2.13 Importance Rating 3.6 Knowledge of tagging and clearance procedures.
Proposed Question:
Common 70 Which ONE of the following is TRUE if a Motor Operated Valve is being tagged for isolation and must be manually closed?
A. The Clearance's Tagged Position must be changed to Manually Closed.
B. The MOV must be manually stroked to prove operability.
C. The System Engineer must concur with closing the MOV manually.
D. The MOV should be manually cracked off its shut seat when clearing the Danger Tag.
Proposed Answer:
D Explanation (Optional):
Incorrect. Tagout position must be changed to Manually Torqued closed Incorrect. MOV must be electrically stroked to prove operability Incorrect. SM/CRS permission required Correct.
Technical Reference(s)
OP-102 (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPA00 obj 2 (As available)
Question Source:
Bank #
X Modified Bank #
(Note changes or attach parent)
New Question History:
Last NRC Exam 2002 Waterford Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis 10 CFR Part 55 Content:
55.41 10 Comments:
W3-OPS-7261-A Level of difficulty = 1 New question
Examination Outline Cross-reference:
3 Group #
4 K/A #
G2.4.2 Importance Rating 3.9 Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.
Proposed Question:
Common 74 Which of the following requires entry into OP-902-000, Standard Post Trip Actions?
A. S/G water level 26% Narrow range B. Pressurizer Pressure 2308 psia.
C. Departure from Nucleate Boiling Ratio 1.36 D. Lo Steam Generator flow 23 psid Proposed Answer:
A Explanation (Optional):
A.
Correct. SG level less than 27.4% requires a reactor trip B.
Incorrect. PZR press 2308 is pretrip, 2350 is RX trip setpoint C.
Incorrect. DNBR 1.36 is pretrip, Rx trip is 1.26 D.
Incorrect. Low SG flow RCS side = 19 PSID Technical Reference(s)
PPS SD (Attach if not previously provided)
OP-902-000, OP-901-201 Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPO20 obj 2 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis 10 CFR Part 55 Content:
55.41 10 Comments: