ML17354B287
| ML17354B287 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 12/20/2017 |
| From: | NRC/RGN-II |
| To: | |
| References | |
| 50-280/17-301, 50-281/17-301 | |
| Download: ML17354B287 (32) | |
See also: IR 05000280/2017301
Text
Surry Power Station
2017 NRC LICENSE EXAM
POST EXAM COMMENTS
&
EXAM ANALYSIS
Surry 2017 NRC Exam Post Exam Comments Question 1
A. Post Exam Comments:
Source: Applicant 55-23557
Question: 1
Given the following:
- A Reactor Trip occurs on Unit 1 from 100% power.
- 1-ES-0.1, Reactor Trip response, has been implemented.
- Control Bank D Rod H14 IRPI indicates 218 steps.
- All other control rods indicate 0 steps.
- TAVG is 547 oF and stable.
Which ONE of the following completes the statements below?
1) One minute after the trip, shutdown margin is rising due to the decay of
__(1)__.
2) In accordance with 1-ES-0.1, Reactor Trip Response, Emergency
Boration __(2)__ required.
A. 1) Iodine 2) is NOT
B. 1) Iodine 2) is
C. 1) Xenon 2) is
D. 1) Xenon 2) Is NOT
Answer: A
Reference: 1-ES-0.1
Comment: There is some ambiguity with the term shutdown margin vice
reactivity.
Facility The question is adequate as written, no change is required.
Position:
Change None required.
Reference:
Page 2 of 32
Surry 2017 NRC Exam Post Exam Comments Question 8
Source: Applicant 55-23557
Question: 8
The Crew is responding to a SGTR in accordance with 1-E-3, Steam
Generator Tube Rupture.
- The Rapid RCS cooldown has been completed.
Which ONE of the following describes:
1) The subcooling value for RCS depressurization termination.
2) The purpose for the RCS depressurization.
A. 1) 50 °F.
2) Minimize break flow and refill the pressurizer.
B. 1) 50 °F.
2) Minimize Reactor Vessel stress for PTS concerns.
C. 1) 30 °F.
2) Minimize break flow and refill the pressurizer.
D. 1) 30 °F.
2) Minimize Reactor Vessel stress for PTS concerns.
Answer: C
Reference: 1-E-3
Comment: Is 50 °F a potential subset of the answer, 30 °F
Facility We dont agree, there is no subset issue. The question is adequate as written.
Position:
Change None
Reference:
Page 3 of 32
Surry 2017 NRC Exam Post Exam Comments Question 13
Source: Applicant 55-23930
Question: 13
Initial Condition
- Unit 1 is operating at 100% power.
- Unit 2 is in RSD with core off-load to the SFP complete 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> ago.
Current Condition
- CC surge tank level is 55% and rising.
Which ONE of the following describes:
1) CC Surge Tank High Level alarm setpoint is ___(1)___.
2) The CC Surge Tank Vent Valve ___(2)___ automatically close on
high level.
A. 1) 93%
2) will not
B. 1) 93%
2) will
C. 1) 70%
2) will not
D. 1) 70%
2) will
Answer: A
Reference: ARP 0-VSP-D7, 1-AP-15.00
Comment: Is there a PCS alarm to support 70%?
Facility There is no PCS alarm for this function. Although this question had the highest
Position: Miss rate the question meets the K/A. The question is adequate as written.
Change None
Reference:
Page 4 of 32
Surry 2017 NRC Exam Post Exam Comments Question 15
Source: Applicants 55-23931, 55-23930, and 55-72754
Question: 15
Initial Conditions:
- Unit 1 and Unit 2 are operating at 100%.
- The plant has been notified by SOC that there are significant grid
instabilities due to numerous base load plants being out of service.
- The SOC has requested maximum power generation from both units.
Current Conditions:
- The SOC reports that the 500 KV system is most impacted and the
Emergency Low Limit for that network has been reached.
- The BOP reports the following Unit 1 changes (Note: Unit 2 parameters
are comparable):
GEN GEN Grid Gen Gen Gen H2
MWe MVARS Freq Amps Volts Press
Initial 907 + 10 60 Hz 23,500 22.3 75 psig
KV
Current 1020 - 210 58.0 27,500 21.6 75 psig
Hz KV
Which ONE of the following completes the statements below?
1) Based on the information given the Reactor __(1)__ required to be
tripped.
2) Which Emergency buses are most affected by the current conditions
stated above?
(REFERENCE PROVIDED)
A. 1) is
2) Buses 1J and 2H.
B. 1) is not
2) Buses 1J and 2H.
C. 1) is not
2) Buses 1H and 2J.
D. 1) is
Answer: A
Comment: Stem is confusing. Current conditions, 2nd bullet states, that (Unit 2
parameters are comparable).
Page 5 of 32
Surry 2017 NRC Exam Post Exam Comments Question 15
Facility Although this was another high miss question, the current conditions given
Position: indicate a grid frequency below the RCP breaker trip setpoint. The question is
adequate as written
Change None required.
Reference:
Page 6 of 32
Surry 2017 NRC Exam Post Exam Comments Question 18
Source: Applicant 55-72748
Question: 18
Initial Conditions:
- Unit 1 reactor operating at 100% power.
- The reactor is tripped and safety injection actuated.
- A steam leak is reported in Unit 1 Safeguards.
Current Conditions:
- The Crew has entered ECA-2.1, Uncontrolled Depressurization of All
- All SG NR levels are off-scale low.
- RCS Cooldown rate is 155°F/hour.
Which ONE of the following states:
1) What is the MINIMUM AFW flow (gpm) to each SG?
2) Will a transition to 1-FR-H.1 be required after AFW has been throttled?
A. 1) 60
2) No
B. 1) 100
2) No
C. 1) 60
2) Yes
D. 1) 100
2) Yes
Answer: C
Reference: ECA-2.1, FR-H.1
Page 7 of 32
Surry 2017 NRC Exam Post Exam Comments Question 18
Comment: ND-95.3-LP-41, FR-H.1 states the following; If feed flow is reduced due to
operator action to minimize feed flow as instructed in these guidelines
and the capability of providing the minimum feed flow is available, then a
transfer from these procedures is not required and FR-H.1 should not be
performed.
Reference: ND-95.3-LP-41:
Facility It is correct that FR-H.1 should not be performed, but the crew is still required to
Position: transition to FR-H.1 to read the caution, and then exit FR-H.1. License
candidates are trained to transition to appropriate FR and then exit if
appropriate. The question is adequate as written.
Change None required.
Reference:
Page 8 of 32
Surry 2017 NRC Exam Post Exam Comments Question 21
Source: Applicants 55-72754 and 55-23930
Question: 21
Given the following:
- Fuel movement is in progress in the Fuel Building.
- Fuel Handlers report an assembly has been dropped and appears to be
damaged.
- 1-RM-RI-153, FUEL PIT BRIDGE, HIGH Alarm is received.
- The Crew has initiated 0-AP-22.00, Fuel Handling Abnormal
Conditions.
Which ONE of the following identifies:
1) The MCR must be ISOLATED within ___(1)___ minutes.
2) The release is monitored using ___(2)____.
A. 1) 2
2) 1-VG-RI-104, Vent Vent 1 Gas
B. 1) 2
2) 1-VG-RI-131 A/B/C, Vent #2 Gas/Particulate
C. 1) 60
2) 1-VG-RI-104, Vent Vent 1 Gas
D. 1) 60
2) 1-VG-RI-131 A/B/C, Vent #2 Gas/Particulate
Answer: B
Reference: ARP 0-RM-D3, 0-AP-22.00
Comment: (55-72754) The labeling for A2 and C2 is confusing, we dont call it that.
(55-23930) Couldnt flow be aligned to Vent Stack #1?
Facility Regarding the label for A2 and C2; this is the label found in the plant.
Position: Regarding the alignment to Vent Stack #1; yes the flow can be aligned to Vent
stack #1 but there is nothing in the question to indicate a different alignment
than the normal alignment. No change required, the question is adequate as
written.
Change None required.
Reference:
Page 9 of 32
Surry 2017 NRC Exam Post Exam Comments Question 24
Source: Applicant 55-23932
Question: 24
Given the following:
- Unit 1 is operating at 100% power.
- The reactor is tripped and SI actuated.
- Containment pressure is 25 psia and rising slowly.
Which ONE of the following completes the statement:
1-RM-TV-100C, CTMT ATMOS RM INLET I/S TV, closes on a ___(1)___
containment isolation signal, and is checked in the required position using
___(2)___ of 1-E-0, Reactor Trip or Safety Injection.
A. 1) Phase I
2) Attachment 1, System Alignment Verification
B. 1) Phase I
2) Attachment 4, CLS Component Verification
C. 1) Phase II
2) Attachment 4, CLS Component Verification
D. 1) Phase II
2) Attachment 1, System Alignment Verification
Answer: C
Reference: 1-E-0
Comment: Attachment 1, also has direction to check the position of 1-RM-TV-100C.
Facility While the applicant is correct in that Attachment 1 step 8RNO has the position
Position: of 1-RM-TV-100A/B/C checked. This is only done if step 8a is answered as
NO. The stem of the question clearly states that CTMT pressure is 25 psia,
which is above step 8a setpoint of 23 psia. Therefore step 8 RNO should not
be performed and Attachment 4 should be entered at step 8e. The question is
adequate as written, no change is required. Step 8 reference is included on
next page.
Page 10 of 32
Surry 2017 NRC Exam Post Exam Comments Question 24
Change E-0 Attachment 1 step 8 RNO. No change to question is required.
Reference:
Page 11 of 32
Surry 2017 NRC Exam Post Exam Comments Question 28
Source: Applicant 55-72748
Question: 28
Given the following:
- Unit 1 is operating at 29% power.
- 1-RC-P-1A breaker spuriously trips open on overcurrent.
With no operator actions which of the following describes:
1) How Loop A Tavg will change as compared to previous Tave Loop A.
2) The reason for the Loop A Tavg change?
A. 1) Lower 2) due to no forced flow in the loop A.
B. 1) Lower 2) due to reverse flow in the loop A.
C. 1) Higher 2) due to reverse flow in the loop A.
D. 1) Higher 2) due to no forced flow in the loop A.
Answer: B
Reference: ND-95.3-LP-3, Loss of RCS Flow
Comment: For Part 1, why is Tave Lower? Couldnt it be higher? What is the
difference between Reverse Flow and Forward Flow?
Facility Tave is lower because at this power level B and C loops will provide load
Position: demand. Tave is lower because as flow is reversed, Tc rises, Th lowers and
TC is greater than Th. It is not correct to state that there is no forced flow such
as would exist if there was a locked rotor, because flow is reversed due to
forced flow from B and C loops. Re-ran this on the classroom simulator with
the same results. The question is adequate as written, no change is required.
Change None
Reference
Page 12 of 32
Surry 2017 NRC Exam Post Exam Comments Question 31
Source: Applicant 55-23930
Question: 31
Initial Conditions:
- Unit 1 is in CSD with the PRZR solid.
- 1-RC-P-1C, C RCP running for crud burst cleanup.
- RCS temperature is 158 °F and lowering.
- RCS pressure is 305 psig.
- Station Instrument Air is supplying containment, the CMT IA
compressors are in OFF.
Current Conditions:
- Unit 1 Instrument Air header ruptures.
Which ONE of the following completes the statements below:
1) RCS pressure will ___(1)___.
2) Procedure ___(2)___ is used to mitigate the effects of this transient.
A. 1) rise
2) 1-AP-27.00, Loss of Decay Heat Removal Capability
B. 1) lower
2) 1-AP-27.00, Loss of Decay Heat Removal Capability
C. 1) rise
2) 0-AP-40.00, Non-Recoverable Loss of Instrument Air
D. 1) lower
2) 0-AP-40.00, Non-Recoverable Loss of Instrument Air
Answer: C
Reference: 1-AP-27.00, 1-AP-40.00
Comment: Stem is confusing by use of the term Station Instrument Air in last
bullet of stem.
Facility The question is adequate as written, no change is required.
Position:
Reference None required.
Page 13 of 32
Surry 2017 NRC Exam Post Exam Comments Question 42
Source: Applicant 55-23930
Question: 42
Given the following:
- Unit 1 Turbine Control is in IMP IN.
- Control rods are in MANUAL.
- The following parameters are given:
Rx. Pwr Delta T Tave T ref. Gen MWe
89% 90% 569.7 569.7 784
- 1-MS-SOV-104, MSR Steam Supply fails CLOSED.
With no operator action which ONE of the following parameters would be
higher when steady-state conditions are reached?
A. Reactor Power.
B. Generator MWe.
C. T ref.
D. Tave.
Answer: D
Reference: ND-89.3-LP-3, Aux Steam
Comment: Are you sure that Tave will rise? IMP IN vs. IMP OUT appears to support
this question.
Facility Re-ran the question scenario on the classroom simulator with similar results,
Position: that support Tave rising, steady state to steady state. No change in the
question is required.
Reference None
Page 14 of 32
Surry 2017 NRC Exam Post Exam Comments Question 53
Source: Applicants 55-72746 and 55-72748
Question: 53
Initial Conditions:
- 1-SW-P-10A, CHG Pump SW Pump, is running in HAND
- 1-SW-P-10B, CHG Pump SW Pump is in AUTO and OFF.
alarmed.
Current Conditions (2 minutes later):
- 1-SW-P-10A, CHG Pump SW Pump, continues running in HAND.
- 1-SW-P-10B, CHG Pump SW Pump is in AUTO and OFF.
- The Service Building Inside Operator reports the following readings:
Parameter Previous Curren
1-SW-DPI-100A, 1-VS-S-1A, SW Strainer D/P 0.8 psid 0.8 psid
1-SW-DPI-27, 1-SW-S-2A, SW Suct. Strainer D/P 0.2 psid 1.8 psid
1-SW-PI-140A, 1-SW-P-10A, Suction press 3.8 psig 0.8 psig
1-SW-PI-26, 1-SW-P-10A, discharge pressure 27.5 psig 6 psig
Which of the following describes the actions the operator must take per 0-AP-
12.00, Service Water System Abnormal Conditions?
A. Start 1-SW-P-10B, place duplex strainer 1-SW-S-10 in service, and open
Cross-tie.
B. Place 1-SW-S-2A, suction strainer standby basket in service, and vent 1
C. Start 1-SW-P-10B, stop and vent 1-SW-P-10A, place 1-SW-S-2A, suctio
basket in service.
D. Place additional SW header in service, vent all three SW headers, vent 1
pump.
Answer: C
Reference: 0-AP-12.00
Comment: Choice B is also correct. 0-AP-12.00 Step 4 RNO supports choice B also
since the sub steps are bulleted and not numbered those steps can be
performed in any order.
Facility We agree with the applicants that choice B and C are both correct. Supporting
Position: documentation attached on the next page.
Page 15 of 32
Surry 2017 NRC Exam Post Exam Comments Question 53
Change 0-AP-12.00 (below)
Reference
Problem Statement: Although the correct answer Start 1-SW-P-10B, stop and vent 1-SW-P-
10A, place 1-SW-S-2A, suction strainer standby basket in service is
correct, conditions in the stem draw for a conclusion that the suction
strainer is fouled. The strainer DP is outside acceptable limits (Log
Spec) and therefore it is reasonable to conclude that placing the standby
suction strainer would restore pump function. Therefore, distracter B -
Place 1-SW-S-2A, suction strainer standby basket in service, and vent 1-
SW-P-10A is not only a reasonable response, but is an allowable
course of action within AP-12.00.
Page 16 of 32
Surry 2017 NRC Exam Post Exam Comments Question 53
Supporting Facts:
- Refer to the associated steps of AP-12.00 (full marked up and non-marked up copies are
attached to the email).
Step 4 flows as given below on page 3 using information provided in stem
Page 17 of 32
Surry 2017 NRC Exam Post Exam Comments Question 53
Step 4 continued (page 4)
Substep (marked A and B below) are of the same level of indent and although A is the
more appropriate action, B contains corrective actions for this scenario. It would be
reasonable for a team, performing a scenario with the given conditions, could choose either the
A or B path.
Page 18 of 32
Surry 2017 NRC Exam Post Exam Comments Question 53
Conclusion:
- Question 53 contains two correct answers as the reference given (AP-12.00) contains
response actions that support B and C answers.
Statement from Operations (Jim Shell - Assistant Operations Manager)
Question 53 - both answers B and C will restore the function of cooling to the
charging/HHSI pumps by restoring charging service water flow and in AP-12,
procedurally both are acceptable solutions the way the procedure is currently written
with the indications provided.
Page 19 of 32
Surry 2017 NRC Exam Post Exam Comments Question 57
Source: Applicant 55-23931
Question: 57
Given the following:
- A steam generator tube rupture has occurred.
- Due to multiple failures, the PRZR spray and PORVs are
unavailable to depressurize the RCS.
- PRZR level is offscale low.
- The Crew is attempting to re-establish Letdown flow in accordance
with ECA-3.3, SGTR with loss of Pressure Control.
In accordance with 1-ECA-3.3, which ONE of the following identifies:
1) The ______ fuses for LC-1-460C and LC-1-459C are removed.
2) 1-CH-LCV-1460A and B _______.
A. 1) input
2) open automatically
B. 1) input
2) are opened manually
C. 1) output
2) open automatically
D. 1) output
2) are opened manually
Answer: D
Reference: 1-ECA-3.3
Comment: Isnt B also correct? Wouldnt pulling the input fuses also allow 1-CH-
LCV-1460 A and B to be opened?
Facility No ECA-3.3 specifically states the output fuses. The question is adequate as
Position: written, no change required.
Change None
Reference
Page 20 of 32
Surry 2017 NRC Exam Post Exam Comments Question 62
Source: Applicant 55-72746
Question: 62
Given the following:
- Unit 1 is operating at 100%.
- Condenser Vacuum is 27.6 inches Hg and is lowering 0.4 inches
Hg/minute.
- Turbine 1 and 2 operators dispatched to look for leaks.
- Generator Megawatts are 890 Mwe and lowering rapidly.
- Annunciator 1A-G1, Traveling Screens Hi Diff Lvl is Lit.
Which of the following completes the following statements:
1) __(1)__ is required to be entered.
2) 1-E-0 is required to be entered if Main Condenser Vacuum lowers to
__(2)__.
A. 1) 0-AP-12.01, Loss of Intake Canal Level
2) 25.0 in-Hg
B. 1) 0-AP-12.01, Loss of Intake Canal Level
2) 22.5 in-Hg
C. 1) 1-AP-14.00, Loss of Main Condenser Vacuum
2) 25.0 in-Hg
D 1) 1-AP-14.00, Loss of Main Condenser Vacuum
2) 22.5 in-Hg
Answer: D
Reference: 1-AP-14.00
Comment: Wouldnt choice C also be correct? I based my answer on C because
at this vacuum, steam dumps will be lost?
Facility 1-AP-14.00 specifically states that if Condenser vacuum lowers to 22.5 in - Hg,
Position: the turbine must be tripped (if power is > 10%). The question is adequate, no
change is required.
Reference None
Page 21 of 32
Surry 2017 NRC Exam Post Exam Comments Question 63
Source: Applicant 55-72748
Question: 63
Unit 1 is operating at 100% when the Reactor Operator notices that Main Feed
Pump suction pressure has lowered on both Main Feed pumps and is now
reading 400 psig (20 psig lower than before).
Which one of the following identifies a possible cause for this lower reading.
A. 1-SD-LCV-106, HP Heater Drain Pump Level Control valve fails OPEN.
B. 1-CN-FCV-107, Condensate Recirculation valve inadvertently opened.
C. 1-CP-MOV-100, Condensate Polisher Bypass valve fails OPEN.
D. 1-CN-126, Condensate bypass for LP FW Heaters 2, 3 and 4
inadvertently opened.
Proposed Answer: B
Answer: B
Reference: ND-89.3-LP-2
Comment: Why wouldnt choice A also be correct? Isnt 1-SD-LCV-106 the divert
valve?
Facility 1-SD-LCV-106 is the normal Discharge LCV to the Feed Pump Suctions. 1-
Position: SD-LCV-107 is the divert valve. Opening 1-SD-LCV-106 further will cause a
rise in Feed pump suction pressure. No change is required, the question is
adequate.
Reference None
Page 22 of 32
Surry 2017 NRC Exam Post Exam Comments Question 67
Source: Applicant 55-72748
Question: 67
Which ONE of the following completes the statement from 1-GOP-1.4, Unit
Startup, HSD to 2% Reactor Power, concerning the Reactivity Plan provided
by Reactor Engineering?
The plan shall contain recommendations for control of Delta Flux, rod
height and/or Boron adjustments, and _____.
B. startup rate limitations
C. RCS temperature control
D. source range counts at doubling points
Answer: A
Reference: 1-GOP-1.4
Comment: Choice C is also correct per GOP-1.4, Attachment 6 and 7.
Facility We agree. Although the correct answer expected Xenon transient is correct,
Position: 1-GOP-1.4 also references the distractor RCS temperature control in
attachment 7 (refer to following pages).
Reference 1-GOP-1.4
Page 23 of 32
Surry 2017 NRC Exam Post Exam Comments Question 67
Supporting Facts:
- This question references step 5.1.3 to support the correct answer:
And in this reference, Tave is not listed, but upon review of attachment 7 (Reactivity
Control and Monitoring During Startup), the following is given:
The statement Use the Reactivity Plan as a guide infers that the plan contains
this information.
- Upon review of an engineering supplied reactivity plan, Tave is a parameter given as a
reference (see next page)
Page 24 of 32
Surry 2017 NRC Exam Post Exam Comments Question 67
Page 25 of 32
Surry 2017 NRC Exam Post Exam Comments Question 67
Conclusion:
- Question 67 contains two correct answers as the reference given (GOP-1.4) contains
supportive information for A and C.
Statement from Operations (Jim Shell - Assistant Operations Manager)
Question 67. Based on the reactivity plan provided by reactor engineering referenced in
GOP-1.4, although A is correct as we submitted, C is also a correct answer since RCS
temp control is specifically on the reactivity plan and referenced in GOP-1.4 attachment
7.
Page 26 of 32
Surry 2017 NRC Exam Post Exam Comments Question 69
Source: Applicant 55-23930
Question: 69
According to surveillance procedure 1-OPT-RC-10.00, Reactor Coolant
Leakage-Computer Calculated, which of the following parameters is an input
into the calculation for IDENTIFIED RCS leakage?
A. Pressurizer Level.
B. VCT Level.
C. Pressurizer Relief Tank Level.
D. Containment Sump Level.
Answer: C
Reference: 1-OPT-RC-10.00
Comment: Believe choice B is also correct as VCT level is used to determine how
you calculate identified leakage.
Facility VCT, and Pressurizer level are used to calculate Total Leakage. Total leakage
Position: minus Identified leakage (PRT and PDTT level) would equal Unidentified
leakage. The question is adequate, no change is required.
Reference None required.
Page 27 of 32
Surry 2017 NRC Exam Post Exam Comments Question 75
Source: Applicant 55-23930
Question: 75
Given the following:
0130 Unit 1 was at 100% power when a spurious Safety Injection
occurred.
0131 The crew enters 1-E-0, Reactor Trip or Safety Injection.
0145 The crew transitions to 1-ES-1.1, SI Termination.
0155 The RCS is solid and PRZR PORV,1-RC-PCV-1456 begins to
cycle.
0158 HHSI flow has been isolated and charging placed in service.
0212 While placing letdown in service 1-RC-PCV-1456 opens and will
not close.
0217 The block valve for 1-RC-PCV-1456 will not close.
- RCS pressure is 1000 psig and lowering rapidly.
- All steam generators are at 900 psig and slowly lowering.
Which ONE of the following describes the correct actions and procedure
implementation.
A. Initiate Safety Injection and go to 1-E-0, Reactor Trip or Safety
Injection.
B. Transition to 1-E-1, Loss of Reactor or Secondary Coolant, and
use 1-E-1 guidance to reinitiate Safety Injection.
C. Manually start charging pumps and align HHSI flow path, and go
to 1-ES-1.2 Post LOCA Cooldown and Depressurization.
D. Manually start charging pumps and align HHSI flow path, and go
to 1-E-1, Loss of Reactor or Secondary Coolant.
Answer: D
Reference: 1-ES-1.1
Comment: The CAP page of 1-ES-1.1 affirms the answer of D.
Facility We agree, the question is adequate, no change is required.
Position:
Reference None required.
Page 28 of 32
Surry 2017 NRC Exam Post Exam Comments EXAM ANALYSIS Q13
B. EXAM ANALYSIS
2017 NRC Exam Questions with High Miss Rate (>50%)
Question: !13!
Initial Condition
- Unit 1 is operating at 100% power.
- Unit 2 is in RSD with core off-load to the SFP complete 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> ago.
Current Condition
- CC surge tank level is 55% and rising.
Which ONE of the following describes:
1) CC Surge Tank High Level alarm setpoint is ___(1)___.
2) The CC Surge Tank Vent Valve ___(2)___ automatically close on high level.
A. 1) 93%
2) will not
B. 1) 93%
2) will
C. 1) 70%
2) will not
D. 1) 70%
2) will
Proposed Answer: A.
Analysis: Question Miss Rate 80%. Seven (7) Candidates chose C, One (1) chose B, 2 chose
correct answer. Question dealt with knowledge of CC surge tank high level alarm setpoint and
conditions the tank vent valve to close. Part 1) Annunciator Response Procedure high level
alarm setpoint is 93%; distractor setpoint (70%) based on reasonable assumption that tank low
level alarm is approximately 20% below normal level, the high alarm would be approximately
20% above normal. Part 2) tests knowledge of signals that close tank vent; vent closes on CC
system High Radiation. Distractor based on Candidate confusion of operation of tank vent valve
with feed heater high level which secures flow to the feed heater.
Question is acceptable, no change required.
Page 29 of 32
Surry 2017 NRC Exam Post Exam Comments EXAM ANALYSIS Q15
Question: !15!
Initial Conditions:
- Unit 1 and Unit 2 are operating at 100%.
- The plant has been notified by SOC that there are significant grid instabilities due to
numerous base load plants being out of service.
- The SOC has requested maximum power generation from both units.
Current Conditions:
- The SOC reports that the 500 KV system is most impacted and the Emergency Low
Limit for that network has been reached.
- The BOP reports the following Unit 1 changes (Note: Unit 2 parameters are
comparable):
GEN MWe GEN Grid Freq Gen Amps Gen Volts Gen H2
MVARS Press
Initial 907 + 10 60 Hz 23,500 22.3 KV 75 psig
Current 1020 - 210 58.0 Hz 27,500 21.6 KV 75 psig
Which ONE of the following completes the statements below?
3) Based on the information given the Reactor __(1)__ required to be tripped.
4) Which Emergency buses are most affected by the current conditions stated above?
(REFERENCE PROVIDED)
A. 1) is
2) Buses 1J and 2H.
B. 1) is not
2) Buses 1J and 2H.
C. 1) is not
2) Buses 1H and 2J.
D. 1) is
2) Buses 1H and 2J.
Proposed Answer: A
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Surry 2017 NRC Exam Post Exam Comments EXAM ANALYSIS Q15
Analysis: Question Miss Rate 60%. Four (4) Candidates chose correct response, Two (2)
chose distractor B, two (2) chose distractor C, and two (2) chose distractor D. Question based
on Candidate analysis of data provided to determine that a reactor trip is required based on 2/3
Station service bus underfrequency (<58.05 Hz), and knowledge of 500 kV distribution from
switchyard to emergency buses via the RSSTs. Part 1) distinguishes Candidate knowledge of
reactor trip setpoints. Part 2) assesses Candidate knowledge of Electrical Distribution.
Question is acceptable, no change required.
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Surry 2017 NRC Exam Post Exam Comments EXAM ANALYSIS Q69
Question: !69!
According to surveillance procedure 1-OPT-RC-10.00, Reactor Coolant Leakage-Computer
Calculated, which of the following parameters is an input into the calculation for IDENTIFIED
RCS leakage?
A. Pressurizer Level.
B. VCT Level.
C. Pressurizer Relief Tank Level.
D. Containment Sump Level.
Proposed Answer: C
Analysis: Question Miss Rate 60%. Four (4) Candidates chose correctly, four (4) chose
distractor B, one (1) chose distractor A, and one (1) chose distractor D. Question dealt with
determination of RCS leak rate. Leak rate is determined by calculating the Total change in RCS
Inventory and subtracting Identified Leakage to determine Unidentified leakage. A and B
responses are used in the calculation of the change in RCS Inventory. Change in PRT and
PDTT are considered Identified leakage (response C). Response D is Unidentified since any
condensation or leakage of any component/system inside of containment would be collected in
the containment sump.
Question is acceptable, no change required.
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