ML18038B436
| ML18038B436 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 02/06/2018 |
| From: | Exelon Nuclear |
| To: | Brian Fuller Operations Branch I |
| Shared Package | |
| ML17138A091 | List: |
| References | |
| U01956 | |
| Download: ML18038B436 (410) | |
Text
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 1 ID: 1740800 Points: 1.00 Unit 2 is operating at rated power when the "2C" SRV inadvertently opens.
What indications are observed on the 20C603 panel for Total Main Steam Flow indication and how do Turbine Control Valves (TCVs) respond?
Indicated Total Steam Flow Total Control Valve Position A. Lowers Closes B. Lowers Opens C. Rises Closes D. Rises Opens Answer: A Answer Explanation See P&ID M-0001 sheet 3 and M-0041 sheet 5, for the physical relationship between the SRVs and the MSL flow elements; the SRVs are upstream. Thus, an open SRV (discharging to the suppression pool) robs steam flow away from the MSL and its flow elements (M-0041 sheet 5). Therefore, indicated Total Main Steam Flow on flow recorder FR 2R607(at 20C603) lowers.
The steam pressure sensed at the pressure averaging manifold (PT-201A and 201B) also lowers, causing the DEHC system pressure regulator to respond by throttling the TCVs in the closed direction in an effort to control steam pressure.
Therefore the correct answer is "A" B, C and D are plausible to the student who does not recall the relative locations of the SRV connections in relation to the flow nozzles or EHC pressure transmitters.
LMK DEC 2017 ILT NRC Page: 1 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 1 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1740800 User-Defined ID: Q #01 BANK Lesson Plan Objective: LGSOPS0001B.2B Unit 2 is operating at rated power when the "2C" SRV inadvertently opens.
Topic:
What indications are o RO Importance: 3.6 SRO Importance: 3.7 K/A Number: (239002 K1.04 LMK DEC 2017 ILT NRC Page: 2 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments:
General Data Level RO Tier 2 Group 1 239002 SRV K1.04 3.6 /
KA # and Rating 3.7 Knowledge of the physical connections and/or causeeffect relationships KA Statement between RELIEF/SAFETY VALVES and the following:
Main steam Cognitive level Higher 3 - Reactor Pressure Safety Function Control 10 CFR 55 41.2 Technical Reference with Rev M-0001 Sheet3 Revision No: #:
Justification for Non SRO CFR Link:
Question History: (i.e. LGS GGNS 2012 NRC exam NRC-05, OYS CERT-04)
Question Source: (i.e. New, Bank Bank, Modified)
Low KA Justification (if required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments Grand Gulf Nuclear Station (GGNS) 2012 NRC ILT #4 LMK DEC 2017 ILT NRC Page: 3 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 2 ID: 1740823 Points: 1.00 Unit 2 is operating at 100% power.
WHICH ONE of the following describes the expected effect on the APRM reading(s) and the APRM Gain Adjustment Factors (AGAF) data of a 3-D Monicore Periodic Log (P-1), over the next 30 days due to LPRM aging?
Assume core thermal power will be constant for the next 30 days.
APRM Reading AGAF A. Increase Increase B. Increase Decrease C. Decrease Increase D. Decrease Decrease Answer: C Answer Explanation LMK DEC 2017 ILT NRC Page: 4 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Answer: APRM reading decreases AGAF increases The sensitivity of the LPRMs changes with exposure.
As LPRMs age the effect seen on the APRMs is a lower than normal reading. The APRMs are than adjusted per the Gain adjustments to reflect actual real power. APRM Gain Adjustment Factors are used to adjust APRM amplifiers so that APRM reflects real power as calculated by the heat balance.
APRM gain adjustment factors are given by:
CTP Actual AGAF ( I ) = REFCTP =
RAP ( I ) Indicated REFRAP ( I )
From DBD L-S-20 Distracters:
APRM reading AGAF Increase Increase - Plausible to the student that believes that the sensitivity of the LPRMs rise via exposure Increase Decrease - Plausible to the student that believes that the sensitivity of the LPRMs rise via exposure and plausible to the student that inverts the numerator and denominator to the AGAF equation.
Decrease Decrease - plausible to the student that inverts the numerator and denominator to the AGAF equation.
LMK DEC 2017 ILT NRC Page: 5 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 2 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1740823 User-Defined ID: Q #02 BANK Lesson Plan Objective: LLOT0038E.2 Predict Response of APRM Readings and AGAFs to LPRM Topic:
Aging RO Importance: 2.6 SRO Importance: 2.9 K/A Number: 215005 K1.07 LMK DEC 2017 ILT NRC Page: 6 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 2 Group 1 KA # and Rating 215005 K1.07 2.6/2.9 Knowledge of the physical connections and/or causeeffect relationships between AVERAGE POWER RANGE MONITOR/LOCAL KA Statement POWER RANGE MONITOR SYSTEM and the following: K1.07 Process computer, performance monitoring system Cognitive level higher Safety Function 7 10 CFR 55 41.6 & 7 Technical Reference with Rev DBD L-S-20 Revision No: #:
Justification for Non SRO n/a CFR Link:
Question History: (i.e. LGS bank NRC-05, OYS CERT-04)
Question Source: (i.e. New, bank 561184 Bank, Modified)
Low KA Justification (if n/a required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 7 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 3 ID: 1740930 Points: 1.00 Unit 1 is operating at 100% power, with the following:
- D134-R-E is de-energized A steam leak develops in the U1 RCIC room with room temperatures reaching 195° F.
WHICH ONE of the following identifies the RCIC Isolation Valve status for the above conditions?
HV-49-1F007, RCIC MAIN HV-49-1F008, RCIC STEAM STEAM SUPPLY INBRD PCIV LINE OUTBOARD PCIV (INBOARD) (OUTBOARD)
A. Open Open B. Open Closed C. Closed Open D. Closed Closed Answer: B Answer Explanation D134-R-E powers the motor-actuator for the RCIC Inboard Steam Line Isolation Valve, HV 1F007. Therefore, without D134-R-E, there is no way to electrically stroke the 1F007 valve.
The Outboard Steam Line Isolation, HV-49-1F008, motor-actuator is powered from D114-R-G1 and is, therefore, unaffected by the loss of D134-R-E.
The stem of the question provides room temperature of 195° F which is above the RCIC room temperature isolation set point (Tech Spec Table 3.3.2-2 5.d) of 180° F.
With an isolation signal, normally both isolations valves will close, due to D134-R-E being de-energized only HV-049-1F008 will close.
'B' is correct for the above reasons.
'A' is wrong but plausible to the student who incorrectly recalls the RCIC room isolation temperature setpoint and believes that the set point has not been reached. Therefore determining that both isolation valves remain open.
'C' is wrong but plausible to the student who incorrectly recalls the power supplies to the isolation valves and believes that HV-049-1F008 is powered from D134-R-E.
'D' is wrong but plausible to the student who incorrectly recalls the power supplies to the isolation valves and believes that neither isolation valve is powered from D134-R-E.
LMK DEC 2017 ILT NRC Page: 8 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 3 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1740930 User-Defined ID: Q #03 NEW Lesson Plan Objective: LGSOPS0049.4 Topic: Impact of Loss of 480V AC on RCIC isolation valve RO Importance: 3.4 SRO Importance:
K/A Number: 217000 K6.01 LMK DEC 2017 ILT NRC Page: 9 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 2 Group 1 217000 K6.01 RO KA # and Rating Importance 3.4 217000 Reactor Core Isolation Cooling System (RCIC) K2. Knowledge of KA Statement electrical power supplies to the following: Motor operated valves Cognitive level high 2 - Reactor Water Inventory Safety Function Control 10 CFR 55 41.7 0
Technical Reference with E-0058 Sheet Rev 4
Revision No: 003 #:
2 Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS NEW NRC-05, OYS CERT-04)
Question Source: (i.e. New, NEW Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 10 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 4 ID: 1740951 Points: 1.00 WHICH ONE of the following describes the effect of placing the HPCI Emergency Shutdown Switch (HS-56-162) to "OFF" at the Remote Shutdown Panel (RSP)?
A. Shuts down HPCI by removing power to the speed governor which closes the control valve B. Shuts down HPCI by closing the steam admission valve HV-55-1F001 C. Trips the HPCI turbine by energizing the trip solenoid SV1 D. Isolates HPCI by closing the outboard steam isolation valve HV-55-1F003 Answer: A Answer Explanation Per E41-1040 Sht 2 E41-1040 Sht 9 taking HS-56-162 to OFF removes power to the speed governor. This keylock functions regardless of the position of the Remote Shutdown Panel Transfer Switches.
Per lesson plan LGSOPS0055 page 21 F. Manual Shutdown from the Remote Shutdown Panel
- 1. Operating the HPCI EMERG S/D Switch,HSS-56-*62, isolates control power to the Governor resulting in the Turbine Control Valve failing close.
A correct for the above reasons B Incorrect, plausible to the candidate incorrectly recalls which valve HS-56-162 closes C Incorrect, plausible to the candidate who equates HS-56-162 in off to tripping the HPCI turbine D incorrect, plausible to the candidate who believe that HS-56-162 performs the same function at the RSP as as the HPCI Isolation PB in the MCR LMK DEC 2017 ILT NRC Page: 11 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 4 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1740951 User-Defined ID: Q #04 BANK Lesson Plan Objective: LOT-0340, OBJ. #3 describes the operation of placing the Emergency Shutdown Topic:
Switch (HS-56-162) to "OFF" at the Remot RO Importance: 2.5 SRO Importance: 2.7 K/A Number: 206000 K2.04 LMK DEC 2017 ILT NRC Page: 12 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 2 Group 1 KA # and Rating 206000 K2.04 2.5/2.7 High Pressure Coolant Injection System Knowledge of electrical KA Statement power supplies to the following: Turbine control circuits: BWR-2,3,4 Cognitive level lower Safety Function 2 10 CFR 55 41.7 E41-1040 Technical Reference with Sht 2 Rev 18 Revision No: E41-1040 #: 19 Sht 9 Justification for Non SRO n/a CFR Link:
Question History: (i.e. LGS bank 557618 NRC-05, OYS CERT-04)
Question Source: (i.e. New, bank Bank, Modified)
Low KA Justification (if n/a required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section:
(i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 13 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 5 ID: 1741393 Points: 1.00 Unit 2 is in a refueling outage with the RPV Head fully tensioned, with the following:
- 2B RHR is in Shutdown Cooling (SDC)
- SDC flow rate is 9000 gpm
- RWCU is in service
- RWCU bottom head drain temperature is reading 260°F
- 2B RHR heat exchanger inlet temperature is 145°F
- 2B heat exchanger outlet temperature is 125°F
- 2B recirc suction and discharge valves are open WHICH ONE of the following identifies (1) reactor temperature and (2) reactor pressure?
A. (1) 125°F (2) 0 psig B. (1) 145°F (2) 0 psig C. (1) 260°F (2) 20.7 psig D. (1) 260°F (2) 35.4 psig Answer: C Answer Explanation LMK DEC 2017 ILT NRC Page: 14 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Correct answer: 'C'. With 'B' loop SDC in service and both the 2B recirc suction and discharge valves open the shutdown cooling flow is bypassing the reactor. Rather than the cooled water returning to the reactor vessel through the Jet Pumps, the cooled water is returning to the suction of the RHR pump through the recirc pump. With bypass flow, RHR temperature indication is not valid. Therefore, the operator must determine that with RWCU in service RPV Bottom Head temperature is an accurate temperature reading. Based on information given in the stem Reactor temperature is 260°F. Using the steam tables and a temperature of 260°F the student is to determine that the pressure of the saturated system is 20.7 psig.
125° is not correct because RHR hx outlet temp is not reflective of core exit temp.
145° is not correct because cooling flow is bypassing the reactor.
260° 35.4 psig is incorrect plausible if candidate misreads the steam tables and uses the psiA value.
From S51.8.B:
LMK DEC 2017 ILT NRC Page: 15 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 5 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1741393 User-Defined ID: Q #05 NEW Lesson Plan Objective: LGSOPS0051.13D Topic: Determine RCS temperature given SDC configuration RO Importance: 3.3 SRO Importance: 3.6 K/A Number: 205000 K3.01 LMK DEC 2017 ILT NRC Page: 16 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments:
General Data Level RO Tier 2 Group 1 KA # and Rating 205000 K3.01 3.3/3.6 Shutdown Cooling System (RHR Shutdown Cooling Mode) Knowledge of the effect that a loss or malfunction of the KA Statement SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) will have on following: Reactor pressure Cognitive level higher Safety Function 4 10 CFR 55 41.7, 41.5 S51.8.B page Technical Reference with 2 Rev 81 Revision No: M-0043 sht #:
2&3 Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS new NRC-05, OYS CERT-04)
Question Source: (i.e. New, new Bank, Modified)
Low KA Justification (if n/a required):
Revision History: Revision History: (i.e. Modified distractor b to make new plausible based on OTPS review)
ILT Supplied Ref (If Steam Tables appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments S51.8.B, page 2 Steam Tables LMK DEC 2017 ILT NRC Page: 17 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 6 ID: 1741408 Points: 1.00 Unit 2 is operating at 100% power:
- D24 DG is paralleled with the 201 Safeguard Bus
- An inadvertent LOCA signal is received on the 2D Core Spray Subsystem WHICH ONE of the following identifies the impact on the D24 DG Output Breaker and MCR Speed Governor and Voltage Regulator controls, if any?
D24 Output Breaker MCR DG Speed/Voltage Controls A. Trips Still function B. Trips Will NOT function C. Remains closed Still function D. Remains closed Will NOT function Answer: B Answer Explanation A Incorrect, plausible to the candidate that mistakenly believes the EDG will remain in Droop mode (with speed and voltage controls available in the MCR).
B Correct, With the DG operating in parallel with an offsite source, a LOCA signal will trip the output breaker and convert the DG from Droop to Isochronous mode. The LOCA signal also results in disabling the speed governor and voltage regulator controls with the governor locked into a 60 Hz frequency and the voltage regulator operating at a fixed 4280 VAC.
C Incorrect, Plausible to the candidate that believes that since the EDG is running in parallel with the D24 BUS, the EDG output breaker will remain closed. This would be true for a LOOP situation but not a LOCA signal and plausible to the candidate that mistakenly believes the EDG will remain in Droop mode (with speed and voltage controls available in the MCR).
D Incorrect, Plausible to the candidate that believes that since the EDG is running in parallel with the D24 BUS, the EDG output breaker will remain closed. This would be true for a LOOP situation but not a LOCA signal.
LMK DEC 2017 ILT NRC Page: 18 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 6 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1741408 User-Defined ID: Q #06 BANK MOD Lesson Plan Objective: LGSOPS0092B.06 Effect On Breaker And Speed/Voltage Controls From LOCA Topic:
While Synchronized RO Importance: 2.9 SRO Importance: 3.0 K/A Number: 209001 K3.03 LMK DEC 2017 ILT NRC Page: 19 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments:
General Data Level RO Tier 2 Group 1 KA # and Rating 209001 K3.03 2.9/3.0 Low Pressure Core Spray System Knowledge of the effect that a loss or malfunction of the LOW KA Statement PRESSURE CORE SPRAY SYSTEM will have on following:Emergency generators Cognitive level Lower Safety Function 2 10 CFR 55 41.7, 41.8 Technical Reference with Rev Revision No: #:
Justification for Non SRO n/a CFR Link:
Question History: (i.e. LGS Bank 846362 slightly NRC-05, OYS CERT-04) modified Question Source: (i.e. New, Bank 846362 slightly Bank, Modified) modified Low KA Justification (if n/a required):
Revision History: Revision Modified stem to be a C.S History: (i.e. Modified logic failure to cause DG distractor b to make start rather than actual plausible based on OTPS LOCA. Change to match review) KA ILT Supplied Ref (If appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 20 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 7 ID: 1741563 Points: 1.00 Unit 1 plant conditions are as follows:
- Reactor power is 31%
- Reactor level is +35"
- FWLC is as follows:
- 1A RFP in Manual at 1.5X106 pounds per hour
- 1B RFP in Auto at 2.8X106 pounds per hour
- 1C RFP secured The 1B RFP trips WHICH ONE of the following identifies the Recirc Pump speed runback signal, and the reason for the signal?
Recirc Runback Received Reason for Recirc Runback A. 28% speed Ensure NPSH to Recirc Pumps & Jet Pumps.
B. 28% Speed Prevent RFP trip on low suction pressure C. 42% speed Ensure NPSH to Recirc Pumps & Jet Pumps D. 42% Speed Prevent RFP trip on low suction pressure Answer: A Answer Explanation LMK DEC 2017 ILT NRC Page: 21 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Automatic RRP Runbacks
- 1) High Limit Runback - 699 rpm (42%)
a) >12Mlbm/hr FW Flow AND any condensate pump breaker tripped.
b) < 27.5" Rx Level AND any FW loop flow less than 0.94 Mlbm/hr flow.
- 2) Low Limit Runback - 466 rpm (28%)
a) < +12.5" Rx Level b) Discharge valve not full open c) FW Flow less than 2.8 Mlbm/hr
- 3) Speed Hold has no effect on any Automatic Runback.
- 4) Runback Reset pushbutton resets all runback signals for both Recirc Pumps A Correct, 28% runback on <2.8x106 lbm/hr feedwater flow is to ensure NPSH to Recirc and jet pumps B Incorrect, 28% runback is correct but the basis, prevent RFP trip is basis for 42% runback, plausible to the candidate the mistakenly recalls that basis for a different Recirc Runback.
C Incorrect, <2.8x106 feedwater flow is a 28% runback. Plausible to the candidate who mistakenly recalls the recirc speed runback for a different event.
D Incorrect, <2.8x106 feedwater flow is a 28% runback prevent RFP trip is basis for 42%
runback. Plausible to the candidate who mistakenly recalls the recirc speed runback for a different event and plausible to the candidate the mistakenly recalls that basis for a different Recirc Runback.
LMK DEC 2017 ILT NRC Page: 22 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 7 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 4 Difficulty: 0.00 System ID: 1741563 User-Defined ID: Q #07 NEW LGSOPS0043A.IL7 &
Lesson Plan Objective:
LLOT0540.4A Topic: DFLCS - reason for total flow less than 2.8 Mlbm RR Runback RO Importance: 3.0 SRO Importance: 3.1 K/A Number: 295002 K4.01 LMK DEC 2017 ILT NRC Page: 23 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments:
General Data Level RO Tier 2 Group 1 KA # and Rating 295002 K4.01 3.0/3.1 Reactor Water Level Control System Knowledge of REACTOR WATER LEVEL CONTROL SYSTEM design feature(s)
KA Statement and/or interlocks which provide for the following:
Ensuring adequate NPSH for recirculation pumps: Plant-Specific Cognitive level High 2 Reactor Water Inventory Safety Function Control 10 CFR 55 41.7 Technical Reference with Rev Revision No: #:
Justification for Non SRO n/a CFR Link:
Question History: (i.e. LGS new NRC-05, OYS CERT-04)
Question Source: (i.e. New, Bank, Modified)
Low KA Justification (if na required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 24 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 8 ID: 1741662 Points: 1.00 Unit 1 plant startup is in progress.
All IRMs are on Range 3 with the following indications:
A - 80/125 B - 72/125 C - 78/125 D - 124/125 E - 75/125 F - 83/125 G - 122/125 H - 74/125 WHICH ONE of the following describes the plant response related to the rod withdraw block and scram functions?
A. Rod withdraw block, only B. Rod withdraw block and RPS 'A' half-scram, only C. Rod withdraw block and RPS 'B' half-scram, only D. Rod withdraw block and full scram Answer: D Answer Explanation Use alarm response card ARC-MCR-107, F3 to validate the following: IRM Upscale rod block setpoint is 85/125 of scale on any one of the 8 IRM channels. Use ARC-MCR-107, H3 to validate the following: IRM Upscale trip (RPS actuation) setpoint is 120/125 of scale. IRMs A, C, E, and G input to RPS Trip System 'A'; IRMs B, D, F, and H input to RPS Trip System 'B'.
IRM trips are enabled so long as the Reactor Mode Switch is NOT in RUN.
'D' is correct: Rod withdraw block and full scram. Channel 'D' is above 120/125; therefore RPS 'B' actuates. Channel 'G' is above 120/125; therefore RPS 'A' acutates. A full scram results. It's not possible to actuate RPS (at 120/125 scale) without also generating a rod block (at 85/125 scale).
'A' is wrong: Rod withdraw block, only. Plausible to the examinee who doesn't recall the IRM Upscale Trip (RPS) setpoint of 120/125 scale.
'B' is wrong: Rod withdraw block and RPS 'A' half-scram, only . Plausible to the examinee who fails to recognize that the two IRMs that are above 120/125 scale ('D' and 'G') are associated with opposite sides of RPS.
'C' is wrong: Rod withdraw block and RPS 'B' half-scram, only. Plausible for the same reason as for choice 'B'.
LMK DEC 2017 ILT NRC Page: 25 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 8 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1741662 User-Defined ID: Q #08 BANK Lesson Plan Objective: LLOT0071.7 Topic: Recall IRM Rod Blocks RO Importance: 3.7 SRO Importance: 3.7 K/A Number: 215003 K 4.01 LMK DEC 2017 ILT NRC Page: 26 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments:
General Data Level RO Tier 2 Group 1 KA # and Rating 215003 K4.01 3.7/3.7 Intermediate Range Monitor (IRM) System Knowledge of INTERMEDIATE RANGE KA Statement MONITOR (IRM) SYSTEM design feature(s) and/or interlocks which provide for the following: Rod withdrawal blocks Cognitive level lower Safety Function 7 Instrumentation 10 CFR 55 41.6,41.7 Re ARC-MCR-v.
Technical Reference with 107, F3, Rev 1R Revision No: ARC-MCR- #:
ev 107, H3,
.0 Justification for Non SRO CFR Link:
Question History: (i.e. LGS bank 1149956 which is NRC-05, OYS CERT-04) 560453 modified Question Source: (i.e. New, bank 1149956 Bank, Modified)
Low KA Justification (if required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 27 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 9 ID: 1741722 Points: 1.00 If not properly ventilated, an accumulation of ___(1)___ in the battery room would occur. This accumulation would occur faster during battery ___(2)___
(1) (2)
A. hydrogen charging B. hydrogen discharging C. sulfuric acid charging D. sulfuric acid discharging Answer: A Answer Explanation From Lesson plan LGSOPS0078
- Hydrogen production is greater during charging. Sulfuric acid, although produced during charging will remain in aqueous form A correct for the reasons stated above B Incorrect Hydrogen production is greater during charging. Plausible to the examinee who believe that the increased load on the battery during discharge will increase hydrogen production C incorrect Sulfuric acid, although produced during charging will remain in an aqueous form and not buildup in the battery room. Plausible to the examinee who does not fully understand battery charging.
D incorrect Sulfuric acid, although produced during charging will remain aqueous form and not buildup in the battery room plausible for the reasons stated above LMK DEC 2017 ILT NRC Page: 28 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 9 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1741722 User-Defined ID: Q #09 NEW Lesson Plan Objective: LGSOPS0078.1C Topic: Battery H2 buildup RO Importance: 2.6 SRO Importance: 2.9 K/A Number: 263000 K5.01 LMK DEC 2017 ILT NRC Page: 29 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 2 Group 1 KA # and Rating 263000 K5.01 2.6/2.9 D.C. Electrical Distribution Knowledge of the operational implications of the following concepts as KA Statement they apply to D.C.
ELECTRICAL DISTRIBUTION :
Hydrogen generation during battery charging Cognitive level lower Safety Function 6 10 CFR 55 41.5 Technical Reference with Rev 2 M-078 sht 4 Revision No: #: 2 Justification for Non SRO n/a CFR Link:
Question History: (i.e. LGS new NRC-05, OYS CERT-04)
Question Source: (i.e. New, new Bank, Modified)
Low KA Justification (if n/a required):
Revision History: Revision History: (i.e. Modified distractor b to make new plausible based on OTPS review)
ILT Supplied Ref (If none appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 30 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 10 ID: 2029729 Points: 1.00 Unit 2 plant conditions are as follows:
- GP-2, Normal Plant Startup, is in progress
- The Neutron Monitoring Overlap Surveillance Test is complete SRMs are being retracted with the following conditions:
IRM CHANNEL IRM RANGE A 4 B 3 C 2 D 4 E BYPASSED F 3 G 5 H 3 While being retracted, the reading from the "2A" SRM drops to 90 cps.
WHICH ONE of the following describes the status of the SRM RETRACTED WHEN NOT PERMITTED alarm and the rod block response?
SRM RETRACTED WHEN NOT PERMITTED ALARM ROD BLOCK A. off enforced B. off NOT enforced C. on enforced D. on NOT enforced Answer: C Answer Explanation LMK DEC 2017 ILT NRC Page: 31 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Answer: SRM retract permit is on: Rod Block is enforced CONTROL ROD WITHDRAWAL BLOCKS, through interface to Reactor Manual Control System (RMCS). The SRMs produce a control rod withdrawal block under the following conditions:
- UPSCALE - channel output greater than 1 x 105 cps
- INOP - Channel Inoperative is caused by any one of the following:
Low detector high voltage (< 90% of actual high voltage value)
Module Unplugged Drawer selector switch (located in Aux Equipment Room) not in operate
- DOWNSCALE - channel output less than 3 cps
- SRM not fully inserted and less than 100 cps. (This prevents premature withdrawal of the detectors).
CONTROL ROD WITHDRAWAL BLOCK Bypass Conditions
- Manual Joystick located on Panel *0C603 can manually bypass one SRM channel at a time.
- All SRM Rod Blocks are bypassed when the Reactor Mode Switch is in RUN
- All SRM Rod Blocks are bypassed when all 4 associated IRM channels are on Range 8 or above (or bypassed)
IRM Channels A, C, E, and G for SRM Channels A and C IRM Channels B, D, F and H for SRM Channels B and D The SRM Upscale Rod Block is bypassed under ANY of the following conditions:
- Reactor Mode Switch in RUN
- All 4 associated IRM channels on Range 8 or above (or bypassed)
SRM Downscale Rod Block is bypassed when all 4 associated IRM Channels are on Range 3 or above (or bypassed)
The SRM Rod Block on Detector Not Fully Inserted is bypassed on EITHER of the following conditions:
- SRM Channel count rate > 100 cps
- All 4 associated IRM Channels are on Range 3 or above (or bypassed)
- The SRM Upscale Hi-Hi Trip is bypassed when the RPS shorting links are installed A Wrong - plausible to the candidate that fails to recall the associated IRMs that provide interlocks to the 2A SRM (IRMs A,C,E,G Vice IRMs B,D,F,H).
B Wrong - plausible to the candidate that fails to recall the associated IRMs that provide interlocks to the 2A SRM (IRMs A,C,E,G Vice IRMs B,D,F,H) and plausible to the candidate that fails to recall the SRM count rate that causes the rod out block C Correct for the above reasons D Wrong - plausible to the candidate that fails to recall the SRM count rate that causes LMK DEC 2017 ILT NRC Page: 32 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 10 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 2029729 User-Defined ID: Q #10 Lesson Plan Objective: LGSOPS0074.2 Topic: SRM Operation RO Importance: 2.6 SRO Importance: 2.6 K/A Number: 215004 K5.01 LMK DEC 2017 ILT NRC Page: 33 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 2 Group 1 KA # and Rating 215004 K5.01 2.6/2.6 Source Range Monitor (SRM) System Knowledge of the operational implications of the following concepts as KA Statement they apply to SOURCE RANGE MONITOR (SRM)
SYSTEM : Detector operation Cognitive level high Safety Function 7 instrumentation 10 CFR 55 41.6,41.7 Technical Reference with ARC-MCR-207 Rev 0 Revision No: I4 #: 1 Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS 2015 CERT NRC-05, OYS CERT-04)
Question Source: (i.e. New, Bank 1149961 Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make N/A plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 34 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 11 ID: 1742911 Points: 1.00 Unit 2 is operating at 20% power during power ascension with the main generator synched to the grid.
House Loads have been transferred to the Aux Busses per S91.6.A, TRANSFERRING HOUSE LOADS TO UNIT AUXILIARY TRANSFORMER A Main Turbine trip / Generator lockout occurs.
WHICH ONE of the following describes the status of the Startup Source and the 13.2 KV ASD Supply Breakers following the Generator Lockout?
10-22 and 20-21 Breakers 13.2 KV ASD Breakers A. Closed Closed B. Closed Open C. Open Closed D. Open Open Answer: B Answer Explanation LMK DEC 2017 ILT NRC Page: 35 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written A Closed Closed is incorrect as the 13.2 KV ASD Breakers trip on a Aux Bus Fast transfer.
Plausible to the candidate who confuses the Fast Transfer trip with the RPT EOC trip which would not actuate at 20% power.
B Closed Open - Correct C Open Closed is incorrect as the Startup Breakers should be closed following a fast transfer and the 13.2 KV ASD breakers would be Open. Plausible to the candidate who does not remeber the fast transfer action of the Generator Trip or the Auto Tripping action of the 13 KV Breakers on a Generator Trip.
D Open Open is incorrect since the startup breakers would be closed. Plausible to the candidate who does not recall the fast transfer action on a Generator Trip.
Actuating any one of the unit protection lockout relays will initiate the following actions:
(1) Trip of the Main Generator output breakers - Isolates fault to or from the main generator (2) Trip of the Alterrex exciter field breaker - Limits internal damage to the Alterrex exciter (3) Trip of the Main Turbine - Prevents main turbine overspeed due to loss of load (4) Trip of the Stator Water Cooling pumps - Limits water input to the main generator stator if a stator bar has ruptured (5) Auxiliary Bus fast transfer - 11, 12 or 21, 22 Busses transfer from the Main Generator to the Start-Up busses - Maintains power to selected vital loads (6) Transfer of the main generator voltage regulator to MANUAL - Prevents voltage regulator damage (7) Trip of the Reactor Recirculation pumps, if powered from the main generator - Minimizes reactor power during the transient (8) Energization of the main generator output breaker failure circuit - To ensure main generator has been isolated from the 220 KV switchyard (9) Trip of the main unit transformer cooling units - No need for cooling of main unit transformer, and/or to protect against a fault in the main unit transformer (10)Trip of the unit auxiliary transformer cooling unit - No need for cooling of unit auxiliary transformer, and/or to protect against a fault in the unit auxiliary transformer LMK DEC 2017 ILT NRC Page: 36 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 11 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1742911 User-Defined ID: Q #11 Lesson Plan Objective: LGSOPS0035.6 Topic: Electrical Distribution Main Generator Trip RO Importance: 3.5 SRO Importance: 3.7 K/A Number: 262001 K6.03 LMK DEC 2017 ILT NRC Page: 37 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 2 Group 1 KA # and Rating 262001 K6.03 3.5 / 3.7 Knowledge of the effect that a loss or malfunction of the following will have on KA Statement the A.C. ELECTRICAL DISTRIBUTION: Generator trip Cognitive level High Safety Function 6 10 CFR 55 41.7 1
Technical Reference with S91.6.A Rev 5 Revision No: E-0001 #: 3 0
Justification for Non SRO CFR Link:
Question History: (i.e. LGS NRC-05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 38 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 12 ID: 1798989 Points: 1.00 Unit 1 is operating at 100% Power when the following process radiation monitors momentarily spike to the indicated values due to an electrical transient:
RISH-26-1K609C, REACTOR BLDG VENTILATION MON: 1.4 mR/hr and RISH-26-1K609D, REACTOR BLDG VENTILATION MON: 1.7 mR/hr WHICH ONE of the following identifies the status of the Standby Gas Treatment System (SGTS) for the above conditions:
A SGTS Fan B SGTS Fan A. NOT Running NOT Running B. NOT Running Running C. Running NOT Running D. Running Running Answer: B Answer Explanation LMK DEC 2017 ILT NRC Page: 39 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written From the stem the candidate determines that both process radiation monitors malfunctions took them above the isolation set point of 1.35 mR/hr. Based on this information the candidate concludes that the B SGTS fan is now in service.
From LGSOPS0076 Lesson Plan:
A Wrong - Plausible to the candidate that recalls the incorrect isolation set point (2.0 mR/hr for refuel ventilation exhaust).
B Correct for the above reasons C Wrong - Plausible to the candidate that recalls the incorrect Logic system association (i.e.
they incorrectly recall that the 0A Fan is associated with an Div 2 isolation)
D Wrong - plausible to the candidate the confuses the isolation logic with that of the CREFAS system where an upscale condition in the C detector would start the A Fan and an upscale on the D detector would start the B Fan.
LMK DEC 2017 ILT NRC Page: 40 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 12 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1798989 User-Defined ID: Q #12 Lesson Plan Objective: LGSOPS0076.05 Topic: SGTS - Response to Process Rad Monitor Spikes RO Importance: 2.9 SRO Importance:
K/A Number: 261000 K6.04 LMK DEC 2017 ILT NRC Page: 41 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 2 Group 1 261000 K6.04 RO KA # and Rating Importance 2.9 261000 SGTS K6.04 - Knowledge of the effect that a loss or malfunction of the following KA Statement will have on the STANDBY GAS TREATMENT SYSTEM : Process radiation monitoring Cognitive level High Safety Function 9- Radioactivity Release 10 CFR 55 41.7 0
Technical Reference with Rev LGSOPS0076 0 Revision No: #:
0 Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS New NRC-05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make N/A plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 42 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 13 ID: 1744279 Points: 1.00 The PRO is preparing to parallel D12 DG with the 201 Safeguard Bus, per ST-6-092-312-1 (D12 DG Slow Start Operability Test Run).
WHICH ONE of the following describes one of the PRO actions and the reason why the action is performed?
As soon the D12 DG output breaker closes, the PRO is directed to immediately load the DG to...
A. 200-300 KW. Prevent oil buildup in the exhaust manifold B. 200-300 KW. Prevent motoring the generator C. 100-150 KVAR. Prevent oil buildup in the exhaust manifold D. 100-150 KVAR. Prevent motoring the generator Answer: B Answer Explanation Refer to ST-6-092-312-1, steps 4.8.10 thru 4.8.12. Step 4.8.10 closes the DG output breaker.
Step 4.8.11 directs the operators to immediately load the DG to 200-300 KW using the Speed Governor. Step 4.8.12 directs the operator to immediately load the DG to 100-150 KVAR.
'B' is correct: 200-300 KW. Per step 4.8.11, a real load of 200-300 KW must be immediately picked up by the DG in order to prevent actuating the "reverse power" relay (a device that senses ONLY "real" power (KW); it does not sense/respond to "reactive" power (KVAR)).
'A' is wrong: 200-300 KW. Plausible to the examinee who recalls a low load will cause oil buildup in the exhaust manifold, but who confuses "200-300" band KW requirement for preventing a reverse power trip with the 855KW for oil buildup.
'C' is wrong: 100-150 KVAR. Plausible to the examinee who properly recalls both values from the ST (real load value and reactive load value), but who incorrectly associates the KVAR requirement with the 855KW for oil buildup.
'D' is wrong: 100-150 KVAR. Plausible to the examinee who correctly recalls a "100-150" value but who confuses KVAR loading requirement as being associated with preventing a reverse power trip.
LMK DEC 2017 ILT NRC Page: 43 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 13 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1744279 User-Defined ID: Q #13 BANK Lesson Plan Objective: LGSOPS0092B.IL6 Recall how the operator prevents a reverse power D/G trip Topic:
when paralleling RO Importance: 3.0 SRO Importance: 3.1 K/A Number: 264000 A1.09 LMK DEC 2017 ILT NRC Page: 44 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments:
General Data Level RO Tier 2 Group 1 KA # and Rating 264000 A1.09 (3.0/3.1) 264000 EDGs Ability to predict and/or monitor changes in parameters associated with operating the EMERGENCY KA Statement GENERATORS (DIESEL/JET) controls including: A1.09 Maintaining minimum load on emergency generator (to prevent reverse power)
Cognitive level Low Safety Function 6 - Electrical 10 CFR 55 41.5 Technical Reference with Rev 9 ST-6-092-312-1 Revision No: #: 6 Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS 2015 CERT Bank 1149941 NRC-05, OYS CERT-04)
Question Source: (i.e. New, Bank 1149941 Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make N/A plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 45 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 14 ID: 1744293 Points: 1.00 Unit 1 reactor pressure is 1045 psig when a T-112, Emergency Blowdown is directed.
The PRO has taken an SRV handswitch to "OPEN" and is monitoring tailpipe temperature to confirm the SRV is open.
Select the temperature which best approximates the expected tailpipe temperature for an open SRV with the above conditions. (Assume the suppression pool is at atmospheric pressure)
A. 548°F B. 428°F C. 300°F D. 212°F Answer: C Answer Explanation
- a. Incorrect: Plausible to the candidate who assumes that since a BWR is a saturated system, the temperature of the steam at the discharge of the SRV would be at saturation temperature for 1050 psig. See C for reason
- b. Incorrect: Plausible to the candidate who misreads the steam table or Mollier Diagram c Correct: When an SRV lifts, the enthalpy contained in the steam does not change when it passes through the SRV. However, due to the lower pressure in the downcomer and suppression pool (the questions assumes atmospheric), the temperature of the steam will drop from approximatley 550°F to 300°F.
d Incorrect: Plausible to the candidate who assumes that the suppression pool is a saturated system and therefore steam discharged into the pool would immediately cool that temperature of 212°F.
LMK DEC 2017 ILT NRC Page: 46 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 14 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1744293 User-Defined ID: Q #14 NEW Lesson Plan Objective: LGSOPS0050.7.A Topic: Indications of Open SRV RO Importance: 3.4 SRO Importance: 3.6 K/A Number: 218000 A1.01 LMK DEC 2017 ILT NRC Page: 47 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 2 Group 1 KA # and Rating 218000 A1.01 3.4 / 3.6 Ability to predict and/or monitor changes in parameters associated with operating the AUTOMATIC KA Statement DEPRESSURIZATION SYSTEM controls including: ADS valve tail pipe temperatures Cognitive level Higher 3 - Reactor Pressure Safety Function Control 10 CFR 55 41.5 Technical Reference with Rev Steam Tables Revision No: #:
Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS New NRC-05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If Steam Tables appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments Reference used to answer: Mollier Diagram Lesson Plan: GF Thermodynamics K/A
Reference:
218000, A1.01 LMK DEC 2017 ILT NRC Page: 48 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 15 ID: 2027153 Points: 1.00 Unit 1 is operating at 60%
- The 1A Service Water Pump is unavailable
- The 1B and 1C Service Water Pumps are in service when the 1C trips.
- Annunciator 106-K3, GENERATOR ROTOR HI TEMP alarms and EO investigation confirms rising temps Which of the following identifies (1) what action is required for the given conditions and (2) the reason for the action?
A. (1) Valve out the spare TECW Heat Exchanger (2) In order to raise cooling flow to Service Water Loads B. (1) Valve out the spare TECW Heat Exchanger (2) In order to lower SW Pump dP C. (1) Secure Feedwater Heater Access Area Unit Coolers (2) In order to raise cooling flow to Service Water Loads D. (1) Secure Feedwater Heater Access Area Unit Coolers (2) In order to lower SW Pump dP Answer: A Answer Explanation A Correct: the stem indicates a trip of one of the two running SW pumps. SE-25, Degraded Service Water Capability, is entered for trip of the running pump and high temperatures of components cooled by service water. The options presented by the procedure are to start another cooling pump, which is unavailable. The next option is to secure flow to out of service components to increase cooling to in service loads. TECW out of service Heat Exchanger is one of the components directed to be secured B Wrong: Plausible if the candidate identifies the reverse response on pump dP for lowering system flow C Wrong: Plausible if the candidate does not realize that the Feedwater Heater Access Area Unit Coolers are cooled by Drywell Chill Water not Service Water D Wrong: Plausible if the candidate does not realize that the Feedwater Heater Access Area Unit Coolers are cooled by Drywell Chill Water not Service Water and if the student identifies the reverse response on pump dP for lowering system flow LMK DEC 2017 ILT NRC Page: 49 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 15 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 2027153 User-Defined ID: Q #15 Lesson Plan Objective: LGSOPS0010.10 Topic: Partial Loss of Service Water RO Importance: 2.9 SRO Importance: 3.0 K/A Number: 400000 AA2.03 LMK DEC 2017 ILT NRC Page: 50 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 1 Group 1 KA # and Rating 400000 AA2.03 2.9 / 3.0 Ability to (a) predict the impacts of the following on the CCWS and (b) based on those predictions, use procedures to KA Statement correct, control, or mitigate the consequences of those abnormal operation: High/low CCW temperature Cognitive level Higher 10 CFR 55 41.5 Technical Reference LGSOPS0010 004 Rev #:
with Revision No: SE-25 6 Justification for Non N/A SRO CFR Link:
Question History:
(i.e. LGS NRC-05, OYS CERT-04)
Question Source:
(i.e. New, Bank, New Modified)
Low KA Justification (if N/A required):
Revision History:
Revision History:
(i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. none ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 51 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 16 ID: 1797416 Points: 1.00 Unit 1 was operating at 100% when a transient occurred resulting in the following:
Reactor Power is 25%
Reactor Level is -90" T-221, MSIV Isolation Bypass Procedure, is complete Five minutes later, a loss of 1B-Y160 occurs.
T-270 is directed by TRIPs and Rx level is stabilized at -175" Given:
T-251, Establish A HPIC Injection Flow Path Via Feedwater Only T-245, RPV Injection From RHR S/D Cooling WHICH ONE of the following identifies 1) the status of the MSIVs and 2) Secondary T-200 Procedure that will assist in RPV level control?
MSIV Status Secondary T-200 Procedure for RPV Level Control A. Open T-251 B. Open T-245 C. Closed T-251 D. Closed T-245 Answer: C Answer Explanation LMK DEC 2017 ILT NRC Page: 52 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written With a loss of 1B-Y160, T-221 will be ineffective in preventing the MSIVs from closing on low RPV Level. This is identified in E-1BY160 step 1.23:
When RPV Level lowers below -129" all MSIVs will close. From LG-19 of T-117; HPCI thru Feedwater only using T-251 and RHR S/D Cooling - Through HTX ASAP (T-245)
Again from the E-1BY160 step above T-245 will not work.
A Wrong - plausible to the candidate that fails to recall the fact that T-221 will not work with the loss of 1B-Y160.
B Wrong - plausible to the candidate that fails to recall the fact that T-221 and T-245 will not work with the loss of 1B-Y160.
C Correct for the above reasons D Wrong - plausible to the candidate that fails to recall the fact that T-245 will not work with the loss of 1B-Y160.
LMK DEC 2017 ILT NRC Page: 53 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written LMK DEC 2017 ILT NRC Page: 54 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 16 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1797416 User-Defined ID: Q #16 Lesson Plan Objective: LLOT0180.08 Topic: Impact of loss of AC power on NSSSS RO Importance: 3.2 SRO Importance:
K/A Number: 223002 A2.01 LMK DEC 2017 ILT NRC Page: 55 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 2 Group 1 KA # and Rating 223002 A2.01 RO 3.2 223002 PCIS/Nuclear Steam Supply Shutoff A2.01 - Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR KA Statement STEAM SUPPLY SHUT-OFF ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: A.C. electrical distribution failures Cognitive level High Safety Function 5 - Containment Integrity 10 CFR 55 41.5 2
Technical Reference with E-1BY160 Rev 7 Revision No: E-0032 Sheet 1 #: 6 5
Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS New NRC-05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make N/A plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 56 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written LMK DEC 2017 ILT NRC Page: 57 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 17 ID: 2029824 Points: 1.00 Unit 1 is in a startup with the following conditions:
- Reactor Pressure is 150 psig
- Reactor Power is 5%
- 1B RHR is blocked out of service with a Tag Out Consider the following sequence of events:
The 10 Bus experiences a loss of power One minute later - the following two events occur simultaneously:
- Drywell Pressure rapidly rises to 2 psig
- The 20 Bus experiences a loss of power WHICH ONE of the following identifies the order in which the LPCI Loops will begin injecting into the RPV?
A. 1A and 1C simultaneously followed by 1D B. 1A and 1C and 1D simultaneously C. 1C followed by 1A followed by 1D D. 1C and 1D simultaneously followed by 1A Answer: A Answer Explanation LMK DEC 2017 ILT NRC Page: 58 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written From the stem, reactor pressure is below 455 psig (1/2 of the LOCA signal).
A loss of the 10 Bus will result in a loss of the 101 Bus. D11 and D13 Buses are aligned to the 101 Bus. Upon a loss of the 101 Bus, after 0.5 seconds the associated EDG will receive a start signal and the 201 breaker will close re-powering the D11 and D13 Buses after 1 second.
At this point all four divisional safegard buses are aligned to the 201 Bus with D11 EDG and D13 EDG running.
The next simultaneous event is a loss of the 20 bus which will result in a loss of the 201 Bus.
As a result the D11 and D13 Buses will re-power from their associated EDG following a 0.5 second time delay. At the same time as the 20 Bus loss drywell pressure rapidly rises to 2 psig (above the 2nd half of the required LOCA signal of 1.68 psig). With this situation all LPCI pumps will start and inject as soon as power to the bus is available. For the D14 Bus the associated EDG was not already running resulting in a 10 second delay (the required time for the EDG to start and reach rated voltage and frequency) to power the D14 Bus.
The expected sequence of event is:
The 1A LPCI Loop starts at T=0.5 second The 1C LPCI Loop starts at T=0.5 second and the 1D LPCI Loop starting at T=~10 seconds.
A Correct for the above reasons B Wrong - plausible to the candidate the believes that all the requirements for a LOCA/LOOP signal are met and all three will start at time 1 seconds. This would requirethe D14 EDG to already be running C Wrong - plausible to the candidate that recognizes that the 1A and 1C RHR Pumps will have power sooner than the 1D pump but erroneously applies the LOCA loading sequence where the 1C pump starts before the 1A RHR Pump D Wrong - plausible to the candidate that fails take into consideration the loss of the offsite power sources and just applies the LOCA loading sequence.
LMK DEC 2017 ILT NRC Page: 59 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 17 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 2029824 User-Defined ID: Q #17 Lesson Plan Objective: LGSOPS0051.06 Topic: LPCI - Loop Selection RO Importance: 4.2 SRO Importance:
K/A Number: 203000 A3.07 LMK DEC 2017 ILT NRC Page: 60 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 2 Group 1 203000 A3.07 RO KA # and Rating Importance 4.2 203000 RHR/LPCI:
Injection Mode A3.07 - Ability to monitor automatic operations of the KA Statement RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) including: Loop selection:
Plant-Specific Cognitive level High 2- Reactor Water Inventory Safety Function control 10 CFR 55 41.7 Technical Reference with Rev LGSOPS0092A Revision No: #:
Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS New NRC-05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 61 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 18 ID: 2029736 Points: 1.00 Unit 2 plant conditions are as follows:
- An ATWS is in progress
- RRCS has been initiated
- At time 0630, SLC Tank level is 3700 gallons
- At time 0650, SLC Tank level is 2875 gallons WHICH ONE of the following identifies how many pumps are injecting at Tech Spec rated flow and at what SLC tank level will the SLC Pumps trip?
Number of SLC pumps injecting SLC tank level when SLC Pumps trip A. two 700 Gallons B. two 0 Gallons C. one 700 Gallons D. one 0 Gallons Answer: D Answer Explanation LMK DEC 2017 ILT NRC Page: 62 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written From the stem the candidate determines that SLC has been initiated automatically by the RRCS system. With the system in operation, tank level begins to decrease from the inital value of 3700 gallons to 2875 gallons 20 minutes later. The candidate should mathematically determine that the level dropped 825 gals in 20 minutes for an injection rate of ~41.2 gallons per minute.
That is equal to the injection rate of a single SLC pump injecting to the reactor. 41.2 Gal/min X 20 min.= 825 gal The injection rate is identifed in Tech Spec surveaillance 4.1.5.c as 41.2 GPM.
From the notes of T-101 The below step from T-101 could lead to confusion with the candidate as to when the SLC pumps trip A Wrong - plausible to the candidate that fails to recognise that only 1 pump is injecting based on flow rate and plausible to the candidate that incorrectly recalls that the SLC pumps automatically trip at 700 gallons (referenced in step RC/P-18)
B Wrong - plausible to the candidate that fails to recognise that only 1 pump is injecting based on flow rate.
C Wrong - plausible to the candidate that incorrectly recalls that the SLC pumps automatically trip at 700 gallons (referenced in step RC/P-18)
D Correct for the above reasons LMK DEC 2017 ILT NRC Page: 63 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 18 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 2029736 User-Defined ID: Q #18 Lesson Plan Objective: LGSOPS0048.12 Topic: SLC- monitor automatic operations - Tank Level RO Importance: 3.9 SRO Importance:
K/A Number: 211000 A3.02 LMK DEC 2017 ILT NRC Page: 64 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 2 Group 1 211000 A3.02 RO KA # and Rating Importance 3.9 211000 SLC A3.02 - Ability to monitor automatic operations of the KA Statement STANDBY LIQUID CONTROL SYSTEM including: Tank level:
Plant-Specific Cognitive level High Safety Function 1 - Reactivity Conrol 10 CFR 55 41.7 Technical Reference with Tech Spec 4.1.5 Rev 2
Revision No: T-101 #:
4 Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS New NRC-05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 65 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 19 ID: 1799006 Points: 1.00 Unit 1 plant conditions are as follows:
- GP-2, Normal Plant Shutdown, is in progress
- Reactor Mode Switch is in START UP
APRM READING "1" 18%
"2" 16%
"3" 14%
"4" 14%
WHICH ONE of the following identifies the RPS Scram channels that de-energize, if any?
A. None B. RPS channel A1 de-energizes only C. RPS channels A1 and B1 de-energize only D. RPS channels A1, A2, B1 and B2 de-energize Answer: D Answer Explanation LMK DEC 2017 ILT NRC Page: 66 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written From the stem the candidate determines that APRM 1 and APRM 2 are reading above the Setdown scram value of 15 %. As a result, each APRM provides a Vote to the 4 APRM t-out-of-4 Voters. Each Voter (with two or more votes) de-energizes it's associated RPS Channel.
From Tech Spec Bases Page B3/4 3-9:
A Wrong - Plausible to the candidate that incorrectly recalls the Scram setpoint for the Setdown portion of the APRM and believes that none of the APRMs have exceeded the Scram setpoint B Wrong - Plausible to the candidate that incorrectly recalls the Scram setpoint for the Setdown portion of the APRM and believes that only the 1A APRM has exceeded the Scram setpoint and incorrectly associates this with the De-energization of the RPS channel A1 C Wrong - Plausible to the candidate that correctly recalls the scram setpoint for the setdown portion of the APRM and believes but believes that only the A1 and B1 RPS channels de-energize D Correct for the above reasons LMK DEC 2017 ILT NRC Page: 67 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written LMK DEC 2017 ILT NRC Page: 68 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 19 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1799006 User-Defined ID: Q #19 Lesson Plan Objective: LGSOPS0071.04 Topic: RPS- Ability to Monitor Power (APRMs spike due to LPRMs)
RO Importance: 4.3 SRO Importance:
K/A Number: 212000 A4.05 LMK DEC 2017 ILT NRC Page: 69 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments:
General Data Level RO Tier 2 Group 1 212000 A4.05 RO KA # and Rating Importance 4.3 212000 RPS A4.05 - Ability to manually KA Statement operate and/or monitor in the control room: Reactor power Cognitive level Low Safety Function 7 - Instrumentation 10 CFR 55 41.7 T. S. Table Technical Reference with 2.2.1-1 Rev Revision No: T. S. Bases #:
Figure B3/4.3-2 Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS New NRC-05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make N/A plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 70 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 19 Table-Item Links NRC EXAM - 10 CFR 55 Operators' Licenses CFR: 41.2 General design features of the core, including core structure, fuel elements, control rods, core instrumentation, and coolant flow.
CFR: 41.3 Mechanical components and design features of the reactor primary system.
CFR: 41.5 Facility operating characteristics during steady state and transient conditions, including coolant chemistry, causes and effects of temperature, pressure and reactivity changes, effects of load changes, and operating limitations and reasons for these operating characteristics.
CFR: 41.6 Design, components, and functions of reactivity control mechanisms and instrumentation.
CFR: 41.7 Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
10 CFR 55.41 RO WRITTEN EXAMINATION 10 CFR 55.43 SRO WRITTEN EXAMINATION CFR: 45.4 Identify the instrumentation systems and the significance of facility instrument readings.
CFR: 45.5 Observe and safely control the operating behavior characteristics of the facility.
CFR: 45.6 Perform control manipulations required to obtain desired operating results during normal, abnormal, and emergency situations.
CFR: 45.7 Safely operate the facility's heat removal systems, including primary coolant, emergency coolant, and decay heat removal systems, and identify the relations of the proper operation of these systems to the operation of the facility.
CFR: 45.8 Safely operate the facility's auxiliary and emergency systems, including operation of those controls associated with plant equipment that could affect reactivity or the release of radioactive materials to the environment.
LMK DEC 2017 ILT NRC Page: 71 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 20 ID: 1799032 Points: 1.00 Unit 1 plant conditions are as follows:
- Backup Service Air Compressor is in AUTO and aligned to Unit 1
- Service Air/Instrument Air cross-tie is aligned to the '1A' Instrument Air header
- Service Air Compressor is in AUTO
'1A' and '1B' Instrument Air header pressures drop and are now as indicated below:
WHICH ONE of the following identifies the compressor(s) supplying the U1 Instrument Air System and the compressor(s) supplying the U1 Service Air System?
Compressor(s) supplying the Compressor(s) supplying the U1 Instrument Air System U1 Service Air System A. Instrument Air Compressors -ONLY Service Air Compressor - ONLY B. Instrument Air Compressors -ONLY Service Air Compressor and Backup Service air Compressor C. Instrument Air Compressors and Backup Service Air Compressor - ONLY Service Air Compressor D. Instrument Air Compressors and Service Air Compressor and Service Air Compressor and Backup Service Air Compressor Backup Service Air Compressor LMK DEC 2017 ILT NRC Page: 72 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Answer: D Answer Explanation As pressure in the instrument air headers lowers the following occurs:
- the instrument air compressors continue to supply the instrument air headers
- When the IA header pressure drops below the SA header pressure, the SA compressor services both the IA header (for which it is aligned to) and the service air header
- When SA header pressure lowers to 90 psi, the Backup Service Air Compressor starts and supports the SA header (and in this case, the 1A Instrument Air header also)
- 67 closes to isolate service air header from the service air compressor. This allows the Service Air compressor to be dedicated to supply the more vital Instrument Air header.
A Wrong - Plausible if the candidate incorrectly believes normal plant air system alignment remains as the IA header pressure drops B Wrong - plausible if the candidate incorrectly recalls the pressure set point where PV-015-
- 67 closes and believes that PV-015-*67 closes to isolate service air header from the IA header (the opposite of the actual outcome of the closure of PV-015-*67)
C Wrong - plausible if the candidate incorrectly recalls the pressure set point where PV-015-
- 67 closes and believes that it is closed D Correct for the above reasons LMK DEC 2017 ILT NRC Page: 73 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 20 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1799032 User-Defined ID: Q #20 Lesson Plan Objective: LGSOPS0015.02 Topic: Monitoring of Instrument Air Pressure Gauges from MCR RO Importance: 2.6 SRO Importance: 2.7 K/A Number: 300000 A4.01 LMK DEC 2017 ILT NRC Page: 74 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 2 Group 1 KA # and Rating 300000 A4.01 2.6/2.7 300000 Instrument Air System (IAS)
KA Statement Ability to manually operate and / or monitor in the control room:
Pressure gauges Cognitive level High Safety Function 8 - Plant Service Systems 10 CFR 55 41.7 Technical Reference with LGSOPS0015 Rev #: 4 Revision No: M-0015 sh1,4 Justification for Non N/A SRO CFR Link:
Question History: (i.e.
LGS NRC-05, OYS CERT- Modified 2016 ILT NRC Exam 04)
Question Source: (i.e.
Modified - from bank 1153967 New, Bank, Modified)
Low KA Justification (if N/A required):
Revision History:
Revision History: (i.e.
Changed 1A I/A pressure value Modified distractor b from 60 psi to 80 psi.
to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. ABN- None
- )
LORT PRA: (i.e. Yes or No or #)
LORT Question Section:
(i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 75 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 20 Table-Item Links NRC EXAM - 10 CFR 55 Operators' Licenses CFR: 41.7 Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
LIMERICK LO Question Category ILT NRC RO HI COG LMK DEC 2017 ILT NRC Page: 76 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 21 ID: 1799034 Points: 1.00 Unit 1 is operating at 100% power when a loss of 1B RPS UPS Power occurs. The CRS directs the prompt performance of the below procedure steps:
WHICH ONE of the following identifies an additional Confirming Indication of the Loss of the 1B RPS UPS Power, and the reason the above steps are to be performed promptly?
Reason for prompt performance Additional Confirming Indication of the above steps A. Loss of power to both the APRM 1/3 and Restore Cooling to Recirc Pump Seal and APRM 2/4 Operator Display Assemblies Motor Oil Coolers B. Loss of power to both the APRM 1/3 and Prevent MSIVs drifting closed APRM 2/4 Operator Display Assemblies C. Drywell Equipment and Floor Drain Restore Cooling to Recirc Pump Seal and Inboard Isolation Valves close Motor Oil Coolers D. Drywell Equipment and Floor Drain Prevent MSIVs drifting closed Inboard Isolation Valves close Answer: B LMK DEC 2017 ILT NRC Page: 77 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Answer Explanation From the stem the candidate concludes that procedure E-1BY160 is entered and executed.
Confirming indication 1.22 reads as follows:
This is unique to E-1BY160 (it is not a confirming indication to E-1AY160)
The steps listed in the stem are from E-1BY160 with the a Caution above the steps that reads:
A Wrong - plausible to the candidate that believes that the Instrument Gas system is required to support long term operation of the cooling to the Recirc seals and Motor Oil Coolers.
This flow path is supported by Motor Operated Valves.
B Correct for the above reasons C Wrong - plausible to the candidate that mistakenly recalls a Confirming Indication that actually only applies to a loss of the 1A RPS UPS Power and plausible to the candidate that believes that the Instrument Gas system is required to support long term operation of the cooling to the Recirc seals and Motor Oil Coolers. This flow path is supported by Motor Operated Valves D Wrong - plausible to the candidate that mistakenly recalls a Confirming Indication that actually only applies to a loss of the 1A RPS UPS Power LMK DEC 2017 ILT NRC Page: 78 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 21 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1799034 User-Defined ID: Q #21 Lesson Plan Objective: LGSOPS0071.9B Topic: RPS/UPS - Interpreting Procedure Steps RO Importance: 4.6 SRO Importance:
K/A Number: 262002 2.1.20 LMK DEC 2017 ILT NRC Page: 79 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 2 Group 1 262002 2.1.20 RO KA # and Rating Importance 4.6 262002 UPS (AC/DC) 2.1.20 - Conduct of KA Statement Operations: Ability to interpret and execute procedure steps.
Cognitive level Low Safety Function 6 - Electrical 10 CFR 55 41.10 2
Technical Reference with E-1AY160 Rev 8 Revision No: E-1BY160 #: 2 7
Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS New NRC-05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make New plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 80 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 22 ID: 1799035 Points: 1.00 WHICH ONE of the following events would, by itself, require an entry into T-103 (Secondary Containment Control)?
A. SGTS Start with 1 REAC ENCL / REFUEL FLR VENT EXHAUST RAD MON A/B HI-HI /
DOWNSCALE alarm due to confirmed valid R.E. exhaust rad hi-hi B. CONT. ENCL STEAM FLOODING DAMPER PNL 00C728 TROUBLE alarm; damper closure is confirmed C. REFUELING FLOOR LOW DELTA P alarm; d/p is confirmed to be -0.1" w.g., steady D. REACTOR ENCL AREA HI RADIATION alarm due to confirmed valid alarm on the SLC System Area Radiation Monitor (ARM)
Answer: A Answer Explanation Refer to alarm response card ARC-MCR-109, E1 (1 REAC ENCL REFUEL FLR VENT EXHAUST RAD MON A/B HI-HI / DOWNSCALE). Operator Action #2 directs entry into T-103.
'A' is correct: SGTS Start with 1 REAC ENCL REFUEL FLR VENT EXHAUST RAD MON A/B HI-HI / DOWNSCALE alarm due to confirmed valid R.E. exhaust rad hi-hi. Correct for the reason described above.
'B' is wrong: CONT. ENCL STEAM FLOODING DAMPER PNL 00C728 TROUBLE alarm; damper closure is confirmed. Alarm response card ARC-MCR-002, C5 provides direction for this alarm. Plausible to the candidate who too quickly relates this alarm to the similar T-103 entry condition..."R.E. steam flooding damper actuation". The Control Enclosure is NOT associated with/connected to the Reactor Enclosure.
'C' is wrong: REFUELING FLOOR LOW DELTA P alarm; d/p is confirmed to be -0.1" w.g.,
steady. Plausible to the candidate who recalls that a sustained (50 minute time delayed) low d/p (setpoint = -0.1" w.g.) is in fact an automatic R.E. HVAC isolation, and so believes that, by itself, warrants a T-103 entry. It does not; only an R.E. HVAC isolation due to hi-hi radiation is a T-103 entry.
'D' is wrong: REACTOR ENCL AREA HI RADIATION alarm due to confirmed valid alarm on the SLC System Area Radiation Monitor (ARM). Plausible to the candidate who recalls that any alarming ARM for one of the Areas listed on Table SCC-1 of T-103 is a T-103 entry condition, but who incorrectly concludes that the SLC System Area is one of those Table SCC-1 Areas...it is NOT.
LMK DEC 2017 ILT NRC Page: 81 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 22 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1799035 User-Defined ID: Q #22 Lesson Plan Objective: LLOT1560.2D Topic: SGTS - Recognize T-103 entry condition RO Importance: 4.6 SRO Importance:
K/A Number: 261000 2.4.1 LMK DEC 2017 ILT NRC Page: 82 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 2 Group 1 261000 2.4.1 RO KA # and Rating Importance 4.6 261000 SGTS 2.4.1 - Emergency Procedures / Plan:
KA Statement Knowledge of EOP entry conditions and immediate action steps.
Cognitive level Low Safety Function 9 Radioactivity Release 10 CFR 55 41.10 2
T-103 4
ARC-MCR-109, 0
E1 2
ARC-MCR-002, Technical Reference with Rev 0 C5 Revision No: #: 0 ARC-MCR-002, 0
F2 4
ARC-MCR-109, 0
B4 2
Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS 2015 CERT NRC-05, OYS CERT-04)
Question Source: (i.e. New, Bank 1149969 Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified added reference to SGTS distractor b to make starting to answer "A" plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 83 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 22 Table-Item Links NRC EXAM - 10 CFR 55 Operators' Licenses CFR: 41.10 Administrative, normal, abnormal, and emergency operating procedures for the facility.
10 CFR 55.41 RO WRITTEN EXAMINATION LIMERICK LO Question Category ILT NRC RO LOW COG LMK DEC 2017 ILT NRC Page: 84 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 23 ID: 1799057 Points: 1.00 Plant conditions are as follows:
- A loss of offsite power has occurred
- Both units have scrammed and all rods are in
- D14 Diesel Generator has failed to start
- All other Diesel Generators are running and supplying power to their respective buses A large break LOCA results in Unit 1 RPV level lowering to -150" and RPV pressure lowering to 250 psig.
Given the following two procedures:
S52.2.A, Core Spray System Shutdown After Automatic or Manual Initiation S52.7.B, Core Spray Injection with a Single Operable Pump WHICH ONE of the following identifies the automatic response of the '1B' Core Spray Pump and the follow up action to be performed?
Automatic Response of the
'1B' Core Spray Pump Follow up action to be performed A. Starts 7 seconds following LOCA signal Perform S52.2.A to minimize operation on min flow B. Starts 7 seconds following LOCA signal Perform S52.7.B to prevent pump runout C. Starts 15 seconds following LOCA signal Perform S52.2.A to minimize operation on min flow D. Starts 15 seconds following LOCA signal Perform S52.7.B to prevent pump runout Answer: B Answer Explanation LMK DEC 2017 ILT NRC Page: 85 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written From the stem the candidate determines that the station has experienced a LOOP. With a LOOP and LOCA signal present, all the Core Spray Pumps will start in 7 seconds. Since D14 D/G failed to start and offsite power is not available, all Div 4 AC loads will be de-energized.
This included the '1D' Core Spray Pump, therefore only one of the two core spray pumps in the 1B Core Spray loop will be in operation and S52.7.B is appropriate to implement.
A Wrong - plausible if the candidate confuses the power source for the injection valve, HV-52-1F037 (actually powered from Div 2).
B Correct for the above reasons C Wrong - plausible if the candidate recalls the loading sequence for a LOCA signal due to a misconception that the LOOP and the LOCA have to happen at exactly the same time for the LOCA/LOOP loading sequence to occur and plausible if the candidate confuses the power source for the injection valve, HV-52-1F037 (actually powered from Div 2).
D Wrong - plausible if the candidate recalls the loading sequence for a LOCA signal due to a misconception that the LOOP and the LOCA have to happen at exactly the same time for the LOCA/LOOP loading sequence to occur.
LMK DEC 2017 ILT NRC Page: 86 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 23 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1799057 User-Defined ID: Q #23 Lesson Plan Objective: LGSOPS0052 13.A Effect of loss of D14 Bus on 'B' Core Spray Pump during Topic:
LOCA/LOOP and how to mitigate event RO Importance: 3.4 SRO Importance:
K/A Number: 209001 A2.03 LMK DEC 2017 ILT NRC Page: 87 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 2 Group 1 209001 A2.03 RO KA # and Rating Importance 3.4 209001 LPCS A2.03 - Ability to (a) predict the impacts of the following on the LOW PRESSURE CORE SPRAY SYSTEM ;
and (b) based on those KA Statement predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
A.C. failures Cognitive level higher 2 - Reactor Water Inventory Safety Function Control 10 CFR 55 41.5 3
7 T-101 Technical Reference with Rev 2 T-101 Bases Revision No: #: 4 LGSOPS0092A 0
2 Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS Modified Bank NRC-05, OYS CERT-04)
Question Source: (i.e. New, Modified Bank 833400 Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If none appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 88 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written LMK DEC 2017 ILT NRC Page: 89 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 24 ID: 1799072 Points: 1.00 Unit 2 conditions are as follows:
- Recirc leak in Drywell is occurring
- Drywell pressure is 6.5 psig and rising up slow
- Reactor pressure is 880 psig down slow
- RCIC is injecting
- Reactor level is -98" and lowering ~ 2 inches/min
- ADS has not been inhibited Beginning when RPV level drops below -129", which statement below describes the subsequent RPV pressure response?
RPV pressure will...
A. immediately begin to lower rapidly due to ADS valve actuation.
B. lower slowly until 105 seconds have elapsed, then lower rapidly due to ADS valve actuation.
C. lower slowly until 525 seconds have elapsed, then lower rapidly due to ADS valve actuation.
D. lower slowly over the next 10 minutes due to the LOCA condition ONLY.
Answer: B Answer Explanation LMK DEC 2017 ILT NRC Page: 90 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written ADS automatic valve operation requires the following logic requirements. RPV level at either -129 or the High Drywell timer initiated with a confirmatory low RPV level of 12.5. Along with the RPV low level a sequence of ECCS pumps must be operating, either the A or C RHR pumps or the A & C Core Spray pumps for Div 1, or the B or D RHR pumps or B & D Core Spray pump operation. And finally a 105 second timer initiated which following the timer ADS will initiate.
From ARC-MCR-110 A4 A Wrong - plausible if candidate does not recall specific ADS initiation criteria B Correct for the above reasons C Wrong - plausible if candidate does not recall specific ADS initiation criteria D Wrong - plausible if candidate does not recall specific ADS initiation criteria LMK DEC 2017 ILT NRC Page: 91 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 24 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1799072 User-Defined ID: Q #24 Lesson Plan Objective: LGSOPS0050.07B Topic: ADS operation during a LOCA - Rx Pressure Response RO Importance: 4.2 SRO Importance:
K/A Number: 218000.A3.08 LMK DEC 2017 ILT NRC Page: 92 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 2 Group 1 218000 A3.08 importance KA # and Rating 4.2 218000 ADS A3.08 - Ability to monitor automatic operations of the KA Statement AUTOMATIC DEPRESSURIZATION SYSTEM including:
Reactor pressure Cognitive level High 3 - Reactor Pressure Safety Function Control 10 CFR 55 41.7 Technical Reference with ARC-MCR-110 Rev 0 Revision No: A4 #: 1 Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS Bank PBAPS April 2013 NRC-05, OYS CERT-04) Question #17 Question Source: (i.e. New, Used LGS bank # 561192 Bank, Modified) as source Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 93 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 24 Table-Item Links NRC EXAM - 10 CFR 55 Operators' Licenses CFR: 41.7 Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
10 CFR 55.41 RO WRITTEN EXAMINATION LIMERICK LO Question Category ILT NRC RO HI COG LMK DEC 2017 ILT NRC Page: 94 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 25 ID: 1799089 Points: 1.00 Unit 1 plant conditions are as follows:
- OPCON 4
- 1A-Y160 power supply is aligned normally
- 1B-Y160 is being powered from its Primary Alternate power supply due to inverter maintenance Then:
- Shortly thereafter, a loss of Div 1 DC occurs WHICH ONE of the following describes the effect on 1A-Y160 and 1B-Y160?
1A-Y160 1B-Y160 A. Energized De-energized B. Energized Energized C. De-energized Energized D. De-energized De-energized Answer: D Answer Explanation LMK DEC 2017 ILT NRC Page: 95 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Justification:
A. Wrong: Plausible if the applicant (1) does not recall that 1A RPS UPS Inverter is normally powered by DIV 1 250 VDC, or (2) believes that 1A RPS UPS Inverter static switch will successfully AUTO transfer to Primary Alternate Source power upon the loss of DIV 1 DC (i.e., inability to recall that Primary Alternate Source power (TSC MCC) is the same for both 1AY160 and 1BY160).
B. Wrong: For 1A-Y160: Plausible if the applicant (1) does not recall that 1A RPS UPS Inverter is normally powered by DIV 1 250 VDC, or (2) believes that 1A RPS UPS Inverter static switch will successfully AUTO transfer to Primary Alternate Source power upon the loss of DIV 1 DC (i.e., inability to recall that Primary Alternate Source power (TSC MCC) is the same for both 1AY160 and 1BY160).
For 1B-Y160: Plausible if the applicant does not recall that the TSC MCC is the Primary Alternate Source for 1BY160, or (2) believes that automatic transfer capabilities exist between Alternate Sources when the selected Alternate Source becomes unavailable (i.e., incorrectly believes that 1BY160 would be automatically powered by its Secondary Alternate Source following loss of the TSC MCC). Manual local operator action is necessary to select between Alternate Sources.
C. Wrong: Plausible if the applicant does not recall that the TSC MCC is the Primary Alternate Source for 1BY160, or (2) believes that automatic transfer capabilities exist between Alternate Sources when the selected Alternate Source becomes unavailable (i.e., incorrectly believes that 1BY160 would be automatically powered by its Secondary Alternate Source following loss of the TSC MCC). Manual local operator action is necessary to select between Alternate Sources.
D. Correct: The RPS UPS Inverters are normally powered from Safeguard 250 VDC. On a loss of 250 VDC, the inverter output is lost. Normally, the static switch will automatically transfer to Alternate Source power. This Alternate Source is selectable between the normally aligned Primary Alternate and the Secondary Alternate, which requires manual local operator action to select. Note that the Primary Alternate Source for both the 1A and 1B RPS Buses (1AY160 & 1BY160) is the TSC UPS via the TSC MCC. A loss of RPS Bus 1BY160 occurs due to loss of the Primary Alternate source (TSC MCC), which is powering the bus as indicated in the initial conditions. This results in a B side Half Scram signal. RPS Bus 1AY160 (Alternate Source aligned to Primary Alternate), is initially unaffected because it is being powered by the 1A RPS UPS Inverter. The Loss of DIV 1 DC (DIV 1 250 VDC is the normal power supply to the 1A RPS UPS Inverter) would normally initiate an automatic transfer of 1AY160 Bus power to the selected Alternate Source if available (the Primary Alternate in this case). However, the 1A RPS UPS Inverter static switch will not AUTO transfer to Primary Alternate because it is unavailable. The result is a loss of all power to RPS Bus 1AY160. With both 1AY160 and 1BY160 de-energized, a Full Scram occurs.
LMK DEC 2017 ILT NRC Page: 96 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 25 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1799089 User-Defined ID: Q #25 Lesson Plan Objective: LGSOPS0071 2.F UPS - Transfer from preferred power to alternate power Topic:
supplies RO Importance: 3.1 SRO Importance: 3.4 K/A Number: 262002 K4.01 LMK DEC 2017 ILT NRC Page: 97 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments:
General Data Level RO Tier 2 Group 1 262002 K4.01 RO KA # and Rating Importance 3.1 262002 UPS (AC/DC)
K4.01 - Knowledge of UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) design KA Statement feature(s) and/or interlocks which provide for the following: Transfer from preferred power to alternate power supplies Cognitive level High Safety Function 5 - Electrical 10 CFR 55 41.7 0
ARC-MCR-120 0 Technical Reference with A5 Rev 1 Revision No: ARC-MCR-122 #: 0 A5 0 1
Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS LGS NRC 2012 NRC-05, OYS CERT-04)
Question Source: (i.e. New, Bank 1097855 Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 98 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 26 ID: 1799092 Points: 1.00 Unit 2 is at 100% power when the following power failures are experienced:
At 1200: Trip of: 2AY160 CKT 3, "2A APRM UPS INVERTER 2AD185" At 1210: Trip of: 2PP01 CKT 21, "2A APRM UPS INVERTER 2AD185 29-A10821" At what time did Unit 2 experience a half scram and what annunciator/indication serves as an additional confirmation identified by procedure E-2AY185?
Time half scram was received Additional confirmation A. 1200 ARC-MCR-210, B2, "SAFETY RELIEF VALVE OPEN" B. 1200 Loss of Full Core Display RED (FULL OUT) and GREEN (FULL IN) indication lights C. 1210 ARC-MCR-210, B2, "SAFETY RELIEF VALVE OPEN" D. 1210 Loss of Full Core Display RED (FULL OUT) and GREEN (FULL IN) indication lights Answer: C Answer Explanation LMK DEC 2017 ILT NRC Page: 99 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written From the stem the candidate determines that the Alternate source (From the A side RPS/UPS) to the 2A APRM UPS Inverter (2AD185) has tripped.
From E-0032 Sheet 2 This will cause alarm ARC-MCR-221 F3, 2A APRM UPS INVERTER TROUBLE, however all loads from distribution panel 2A-Y185 will remain energized.
When the preferred source to the inverter trips (2PP01 CKT 21), normally the static switch would respond by automatically transferring to the Alternate, however in this situation the Alternate Source is de-energized causing a loss of all loads on distribution panel 2A-Y185.
When this occurs, APRM 2 out of 4 voters 2 and 4 will loose power causing an A side RPS half scram. A loss of distribution panel 2A-Y185 is addressed by procedure E-2AY185. An additional confirming indication in this procedure is receipt of ARC-MCR-221, F5, "2A APRM UPS INVERTER TROUBLE" From E-2AY185:
LMK DEC 2017 ILT NRC Page: 100 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written LMK DEC 2017 ILT NRC Page: 101 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 26 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1799092 User-Defined ID: Q #26 Lesson Plan Objective: LGSOPS0074A 18 Topic: APRM/LPRM knowledge of effect from a malfunction of RPS RO Importance: 3.7 SRO Importance:
K/A Number: 215005 K6.01 LMK DEC 2017 ILT NRC Page: 102 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 2 Group 1 215005 K6.01 RO KA # and Rating Importance 3.7 215005 APRM / LPRM K6.01 - Knowledge of the effect that a loss or malfunction of the following KA Statement will have on the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM : RPS Cognitive level High Safety Function 7 - Instrumentation 10 CFR 55 41.7 4
0 E-0032 Sheet 2 0
ARC-MCR-221 Technical Reference with Rev 0 F5 Revision No: #: 0 E-2AY185 1
E-2BY185 0
1 Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS New NRC-05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 103 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 27 ID: 1799112 Points: 1.00 Unit 2 is at 100% when the following occurs:
A leak develops from the Low Pressure sensing line of Jet pump 18 and the Excess Flow Check Valve for that line functions to isolate the leak and maintain RPV integrity.
WHICH ONE of the choices below identifies the impact on the indicated total core flow and the Recirc Loop that will experience the indicated flow change?
Impact on indicated Total Core Flow Recirc Loop experiencing indicated flow change A. Rises A B. Rises B C. Lower A D. Lower B Answer: A Answer Explanation LMK DEC 2017 ILT NRC Page: 104 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written From the stem the candidate identifies that with a break in the low pressure potion of the Jet pump instrumentation the dP instrumentation for Jet Pump 18 will see a very high dP. This high dP will be converted into a very high jet pump flow signal. As a result of this high signal, indicated total core flow rises. Jet pumps 11 - 20 are associated with Recirc Loop A.
From M-0042 Sheet 4.
A Correct for the above reasons B Wrong - plausible to the candidate the incorrectly recalls Jet Pump number assignments a belives Jet Pumps 1-10 are associated with the A Loop C Wrong - plausible to the candidate the incorrectly recalls the response of the flow instrumentation to the Excess Flow Check Valve closure and concludes that indiated flow would go down D Wrong - plausible to the candidate the incorrectly recalls the response of the flow instrumentation to the Excess Flow Check Valve closure and concludes that indiated flow would go down and plausible to the candidate the incorrectly recalls Jet Pump number assignments a belives Jet Pumps 1-10 are associated with the A Loop LMK DEC 2017 ILT NRC Page: 105 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 27 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1799112 User-Defined ID: Q #27 Lesson Plan Objective: LGSOPS0042 Topic: Nuclear Instrumentation Connection to RPV - cause-effect RO Importance: 3.6 SRO Importance:
K/A Number: 216000 K1.22 LMK DEC 2017 ILT NRC Page: 106 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 2 Group 2 216000 K1.22 RO KA # and Rating Importance 3.6 216000 Nuclear Boiler Inst.
K1.22 - Knowledge of the physical connections and/or cause- effect relationships KA Statement between NUCLEAR BOILER INSTRUMENTATION and the following: Reactor vessel Cognitive level High Safety Function 7 - Instrumentation 10 CFR 55 41.2 to 41.9 2
Technical Reference with M-0042 Sheet 3 Rev 1 Revision No: M-0042 Sheet 4 #: 1 2
Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS New NRC-05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 107 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 28 ID: 1799137 Points: 1.00 Unit 1 is at 60% power when the following occurs:
An electrical fault has occurred resulting in the following alarm associated with the 1A Rod Block Monitor (RBM).
- ARC-MCR-108, D4, RBM DOWNSCALE/TROUBLE Given the following procedures:
- E-1AY185, Loss of 1A APRM UPS Power WHICH ONE of the following identifies the Event Procedure containing this annunciator as an expected alarm and whether the 1A RBM requires bypass to allow control rod withdraw?
Event Procedure Bypassing the 1A RBM is required A. E-1AY160 No B. E-1AY160 Yes C. E-1AY185 No D. E-1AY185 Yes Answer: C Answer Explanation LMK DEC 2017 ILT NRC Page: 108 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written From the stem the candidate determines there is a loss of 1A-Y185. 1A-Y185 is one of the APRM power supplies. 1A-Y185 and its counterpart 1B-Y185 provided power to multiple Low Voltage Power Supplies (LVPS) with each LVPS receiving power from both 1A-Y185 and 1B-Y185. The LVPS provide power to the APRM/LPRM and RBM Chassis.. Upon a loss of 1A-Y185 All APRM/LPRM and RBM Chassis continue to function.
From ARC-MCR-108- D4, a loss of 1AY185, ckt 1 or 1BY185 ckt 1 will cause the RBM DOWNSCALE/TROUBLE alarm From E-1AY185:
Also from E-1AY185:
A Wrong - plausible to the candidate the fails to recall the power supply that would result in the isted alarm. (believes power for the RBM comes from the RPS UPS rather than the APRM UPS)
B Wrong - plausible to the candidate the fails to recall the power supply that would result in the isted alarm. (believes power for the RBM comes from the RPS UPS rather than the APRM UPS) and plausible to the candidate the believes the loss of the APRM Power supply will required the bypass of the RBM to continue rod withdraw. (Due to a false upscale condition)
C Correct for the above reasons D Wrong - plausible to the candidate the believes the loss of the APRM Power supply will required the bypass of the RBM to continue rod withdraw. (Due to a false upscale condition)
LMK DEC 2017 ILT NRC Page: 109 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 28 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1799137 User-Defined ID: Q #28 Lesson Plan Objective: LGSOPS0074B 3.D Topic: RBM - knowledge of APRM Power Supplies RO Importance: 2.8 SRO Importance:
K/A Number: 215002 K2.03 LMK DEC 2017 ILT NRC Page: 110 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 2 Group 2 215002 K2.03 RO KA # and Rating Importance 2.8 215002 RBM K2.03 - Knowledge of KA Statement electrical power supplies to the following: APRM channels: BWR-3,4,5 Cognitive level Low Safety Function 7 - Instrumentation 10 CFR 55 41.7 ARC-MCR-108 Technical Reference with Rev 5 D4 Revision No: #: 1 E-1BY185 Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS New NRC-05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 111 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 29 ID: 1799143 Points: 1.00 Unit 2 is at 100% power at the completion of ST-6-055-230-1, HPCI Pump, Valve and Flow Test with the following Suppression Pool Parameters:
- Suppression Pool Temperature is 94 °F down 2 °F/hr A logic malfunction with the 2A RHR Initiation Logic causes a 2A RHR LOCA signal to be generated:
For the above conditions, WHICH ONE of the following correctly completes the following statement about the impact on Suppression Pool Temperature?
If directed to restore the Suppression Pool Temperature cooldown, HV-051-2F024A, RHR Full Flow Test Return, can be opened (and will remain open) ___(1)___ and HV-051-2F048A, Heat Exchanger Bypass, can be closed (and will remain closed) ___(2)___.
(1) (2)
A. immediately immediately B. immediately in three minutes C. in three minutes immediately D. in three minutes in three minutes Answer: B Answer Explanation LMK DEC 2017 ILT NRC Page: 112 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written From the stem the candidate determines that the LOCA signal malfunction of the LPCI system has impacted the ability of the 2A RHR system to cool the suppression pool. The candidate then recalls that HV-051-2F024A receives a close signal (with no seal in) and HV-051-2F048A receives an open signal (with a three minutes seal in).
From S51.8.A And A Wrong - plausible if the candidate fails to recall the three minutes seal in for HV-051-2F048A open signal B Correct for the above reasons C Wrong - plausible if the candidate incorrectly recall that the three minutes seal in applies to HV-051-2F024A instead of HV-051-2F048A D Wrong - plausible if the candidate incorrectly recall that the three minutes seal in applies to HV-051-2F024A in addition to HV-051-2F048A LMK DEC 2017 ILT NRC Page: 113 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 29 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1799143 User-Defined ID: Q #29 Lesson Plan Objective: LGSOPS0051 9.C Topic: RHR Pool Cooling - suppression pool temp RO Importance: 3.9 SRO Importance:
K/A Number: 219000 K3.01 LMK DEC 2017 ILT NRC Page: 114 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 2 Group 2 219000 K3.01 RO KA # and Rating Importance 3.9 219000 RHR/LPCI:
Torus/Pool Cooling Mode K3.01 - Knowledge of the effect that a loss or malfunction of the KA Statement RHR/LPCI:
TORUS/SUPPRESSION POOL COOLING MODE will have on following:
Suppression pool temperature control Cognitive level Low Safety Function 5 - Containment Integrity 10 CFR 55 41.7 Technical Reference with Rev 4 S51.8.A Revision No: #: 9 Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS Clinton ILT 12-1 NRC NRC-05, OYS CERT-04) Exam Q #56 Question Source: (i.e. New, Clinton ILT 12-1 NRC Bank, Modified) Exam Q #56 Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 115 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 30 ID: 1799175 Points: 1.00 Unit 1 plant startup is in progress with the 1B condensate pump inservice.
Condensate System startup in progress At t = 0 seconds:
- PRO places the '1A' Condensate Pump control switch in START At t = 33 seconds:
- '1A' Condensate Pump Discharge Valve reaches 90% open and stops there (torque switch problem)
No operator action is taken.
WHICH ONE of the following describes the '1A' Condensate Pump response?
A. Immediately trips when the Discharge Valve stops.
B. Trips 2 seconds after the Discharge Valve stops.
C. Remains running with 6000 gpm through the Min Flow Valve.
D. Remains running with 7500 gpm through the Min Flow Valve.
Answer: B Answer Explanation Refer to S05.1.A, page 19, Step 4.22.2 NOTE, where we see that "if the Condensate Pump discharge valve is not open or (at least still) stroking open 35 seconds after the pump control switch is taken to START, the pump will trip.
'B' is correct for the above reasons. Trips 2 seconds after the Discharge Valve stops. At t =
33 seconds, there are still 2 seconds left before the T.D. relay times out (at t = 35 seconds).
When it does, it sees that the discharge valve is neither open, nor stroking open; therefore, the pump trips at that time (i.e., at t = 35 seconds).
'A' is wrong. Immediately trips when the Discharge Valve stops. Plausible to the examinee who can recall neither the correct time delay (35-seconds), nor the extent to which the discharge valve must be open (90% versus fully).
'C' is wrong. Remains running with 6000 gpm through the Min Flow Valve. Plausible to the examinee who does not recall the auto-trip feature of the pump and instead believes that, so long as there is a Min Flow Valve, there is no reason to design the pump with such a trip.
'D' is wrong. Remains running with 7500 gpm through the Min Flow Valve. Plausible for the same reason as for choice 'C'; this examinee is distracted by the 6000 gpm of choice 'C' and the 7500 gpm, here (i.e., vaguely recalls that adequate min flow requires either 2500 gpm per running pump, or 7500 gpm, regardless of the number of running pumps).
LMK DEC 2017 ILT NRC Page: 116 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written LMK DEC 2017 ILT NRC Page: 117 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 30 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1799175 User-Defined ID: Q #30 Lesson Plan Objective: LGSOPS0005.IL4A Topic: Recall Condensate Pump Auto-Trip Feature RO Importance: 2.8 SRO Importance: 2.8 K/A Number: 256000 K4.03 LMK DEC 2017 ILT NRC Page: 118 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments:
General Data Level RO Tier 2 Group 2 KA # and Rating 256000 K4.03 2.8 / 2.8 Knowledge of REACTOR CONDENSATE SYSTEM design KA Statement feature(s) and/or interlocks which provide for the following: Condensate and/or booster pump protection Cognitive level Lower Safety Function 2 10 CFR 55 CFR: 41.7 Technical Reference with S05.1.A, page Rev 3 Revision No: 19, Step 4.22.2 #: 8 Justification for Non SRO CFR Link:
Question History: (i.e. LGS NRC-05, OYS CERT-04)
Question Source: (i.e. New, Bank 558666 Bank, Modified)
Low KA Justification (if required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments From LGSOPS0005.IL4A and KA 256000 K4.03 LMK DEC 2017 ILT NRC Page: 119 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 31 ID: 2029590 Points: 1.00 WHICH ONE of the following correctly completes the statements below about the "*A(B) Rx Recirc Pump Speed Lower/Raise" pushbuttons at *0C602?
If the pushbutton is held for anytime greater than _____(1)_____ seconds, a "Stuck Button" alarm will be generated and the pushbutton backlight will remain illuminated.
Upon release of the pushbutton that received the "Stuck Button" alarm, if the pushbutton is subsequently depressed again the associated ASD speed _____(2)_____ change.
(1) (2)
A. 5 will NOT B. 5 will C. 10 will NOT D. 10 will Answer: C Answer Explanation LMK DEC 2017 ILT NRC Page: 120 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written From LGSOPS0043B From S43.1.F and typical for all 6 pushbutton errors In addition to the feedback provided from the ASD machine that the signal was recevied from the pushbutton (the normal purpose of the pushbutton backlight) the secondary purpose of the backlight feedback is that ASD machine has been receiveing a signal from the pushbutton for 10 seconds or greater and the ASD is going to ignore any subsequent signals from the pushbutton until the Fault Reset Pushbutton is depressed for 6 to 10 seconds.
A Wrong: plausible to the candidate that fails to recall that a stuck button error does not occur until 10 seconds B Wrong: plausible to the candidate that fails to recall that a stuck button error does not occur until 10 seconds and plausible to the candidate that fails to recall that you must hold the Fault Reset Pushbutton for 6 to 10 seconds before the function of the pushbutton is restored.
C Correct for the above reasons.
D Wrong: plausible to the candidate that fails to recall that you must hold the Fault Reset Pushbutton for 6 to 10 seconds before the function of the pushbutton is restored.
LMK DEC 2017 ILT NRC Page: 121 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 31 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 2029590 User-Defined ID: Q #31 Lesson Plan Objective: LGSOPS0043B.6.A Topic: ASD Pushbutton Feedback RO Importance: 2.6 SRO Importance: 2.6 K/A Number: 202002 K5.02 LMK DEC 2017 ILT NRC Page: 122 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 2 Group 2 KA # and Rating 202002 K5.02 2.6 / 2.6 Knowledge of the operational implications of the following concepts as KA Statement they apply to RECIRCULATION FLOW CONTROL SYSTEM :
Feedback signals Cognitive level Lower Safety Function 1 - Reactivity Control 10 CFR 55 41.5 Technical Reference with Rev LGSOPS0043B 6 Revision No: #:
Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS New NRC-05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 123 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 32 ID: 1799183 Points: 1.00 Unit 1 is operating at 18% power with the Main Turbine at rated speed in preparation for synchronization to the grid when the following occurs:
- Main Seal Oil Pump (MSOP) trips on overload
- Emergency Seal Oil Pump (ESOP) will not start (automatically or manually)
WHICH ONE of the following describes the operational implication of this event, and why?
A. Main Turbine can remain operating because the Main Generator is not yet on the grid.
B. Main Turbine can remain operating because the Main Generator casing has not yet been purged.
C. Main Turbine must be tripped because bearing oil pressure is rapidly dropping.
D. Main Turbine must be tripped because operators will have to rapidly vent off hydrogen from the Main Generator.
Answer: D Answer Explanation LMK DEC 2017 ILT NRC Page: 124 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written A loss of both the MSOP and ESOP leaves the bearing oil header directly supplying the generator seals at a pressure of only 8 to 10 psig. At 18% power (actually, before plant startup),
the main generator has already been filled with hydrogen to a casing pressure of 75 psig. With such a large delta-P between the casing pressure and seal pressure, hydrogen will rapidily leak out of the machine. As such, ON-126, step 2.3.2 directs us to trip the main turbine, and then step 2.10 directs us to vent off generator hydrogen (to a pressure of 5 to 8 psig).
A Wrong - Plausible to the candidate who does recognize that the generator is not yet on the grid, but who thinks this has to do with the problem of hydrogen escaping from the generator.
B Wrong - Plausible to the candidate who does comprehend the problem but who believes the generator has not yet been filled with hydrogen.
C Wrong - Plausible to the candidate who beleives that the problem is not with the seal oil system but rather with the fact that since the seal oil system is taking its supply directly from the turbine bearing oil header it robs oil away from going to the turbine bearings (it does not).
D Correct for the above reasons LMK DEC 2017 ILT NRC Page: 125 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 32 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 2 Difficulty: 0.00 System ID: 1799183 User-Defined ID: Q #32 Lesson Plan Objective: LGSOPS0028A.IL3A Topic: Main Generator - impact of Loss of Both MSOP and ESOP RO Importance: 2.8 SRO Importance:
K/A Number: 245000 K6.03 LMK DEC 2017 ILT NRC Page: 126 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 2 Group 2 245000 K6.03 RO KA # and Rating Importance 2.8 245000 Main Turbine Gen.
/ Aux.
K6.03 - Knowledge of the effect that a loss or malfunction of the following KA Statement will have on the MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS : Hydrogen seal oil Cognitive level High 4 -Heat Removal From Safety Function Core 10 CFR 55 41.7 Technical Reference with Rev 1 ON-126 Revision No: #: 4 Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS Bank 907635 NRC-05, OYS CERT-04)
Question Source: (i.e. New, Bank 907635 Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 127 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 33 ID: 1799184 Points: 1.00 Unit 1 plant conditions are as follows:
- Leak from 1B RHR suction piping
- Suppression Pool level is 16 feet
- A coolant leak from a recirc loop has developed
- Drywell pressure has risen to 15 psig
- Drywell and Suppression Pool sprays are attempted WHICH ONE of the following describes the approximate value of Suppression chamber pressure as compared to Drywell pressure, based on the above conditions?
A. Equal to Drywell pressure B. 2 psi below Drywell pressure C. 5 psi below Drywell pressure D. 8 psi below Drywell pressure Answer: B Answer Explanation LMK DEC 2017 ILT NRC Page: 128 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written
- a. Wrong: Plausible to the candidate who confuses the minimum level for HPCI operation of 18 feet with the bottom of the drywell downcommers at 12 feet. If the downcomer were uncovered, the water seal is lost and the drywell and suppression pool would directly communicate through the downcomer. D/P = 0 Psid
- b. Correct: With a lower level in the downcomer, the differential pressure required to overcome the weight of water in the Pool drops. Curve PC/P3 illustrates the effect of lowering level. At 37' in the pool, the drywell pressure would be approximately 11 pounds different. As level drops, the delta drops as well until at 12 ft, the difference is 0 psid as the pool level uncovers the downcomer.
The candidate can calculate the backpressure required by determining the water level above 12 feet in the pool (16'-12' = 4') multiplied by the pressure exerted by a column of water. ~27.7" = 1 lb.
So: 4 ft X 12" / 27.7"/lb = 1.73 # rounded to 2 psid.
- c. Wrong: Plausible to the candidate who does not consider the changing pool level and only recalls the normal differential pressure experienced during a drywell leak with pool level in the normal band of approximately 5 psig. 12' delta X 12" / 27.7"/lb = 5 psid
- d. Wrong: Plausible to the candidate who incorrectly calculates impact that the change in level will have and adds the change in level to the inital pool level and determines that the delta is 8ft. X 12" / 27.7"/lb = 3.4 lbs and then adds this value to the normal delta 5 +
3.4 = approx. 8 lbs.
LMK DEC 2017 ILT NRC Page: 129 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 33 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1799184 User-Defined ID: Q #33 Lesson Plan Objective: LLOT0130.06 Leak from RHR suction - Suppression Pool level dropped to 16 Topic:
feed before the leak was isolated - A RO Importance: 3.2 SRO Importance: 3.3 K/A Number: 223001 A1.07 LMK DEC 2017 ILT NRC Page: 130 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments:
General Data Level RO Tier 2 Group 2 KA # and Rating 223001 A1.07 3.2 / 3.4 Ability to predict and/or monitor changes in parameters associated with operating the PRIMARY CONTAINMENT SYSTEM KA Statement AND AUXILIARIES controls including:
Drywell/suppression chamber differential pressure (drywell to containment building): Plant-Specific Cognitive level Higher Safety Function 5 10 CFR 55 CFR: 41.5 Technical Reference with Rev Revision No: #:
Justification for Non SRO CFR Link:
Question History: (i.e. LGS NRC-05, OYS CERT-04)
Question Source: (i.e. New, Bank 561514 Bank, Modified)
Low KA Justification (if required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments Procedure Ref.: T-102 02NRC Cognitive Level: H LLOT0130.06 LMK DEC 2017 ILT NRC Page: 131 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 34 ID: 2029611 Points: 1.00 Unit 1 is at 100% power with MAPRAT from the P-1 edit reading 1.07.
The Thermal Limit is being addressed in accordance with GP-14, Resolution of Thermal Limit Violations.
WHICH ONE of the following identifies (1) the impact to the nuclear fuel and (2) the Tech Spec time requirement for initiating corrective action?
Impact to the Nuclear Fuel Time to initiate corrective action A. the post-LOCA Peak Cladding Temperature 15 minutes is not assured to remain below design limits B. the post-LOCA Peak Cladding Temperature 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is not assured to remain below design limits C. the requirement of less than 0.1% of fuel 15 minutes rods in the core being susceptible to transition boiling is not assured D. the requirement of less than 0.1% of fuel 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> rods in the core being susceptible to transition boiling is not assured Answer: A Answer Explanation LMK DEC 2017 ILT NRC Page: 132 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written From Tech Spec Bases 3/4.2.1:
From Tech Spec 3.2.1 A Correct for the above reasons B Wrong - plausible to the candidate that fails to recall the correct response time for exceeding the APLHGR LCO C Wrong - Plausible to the candidate the confuses the bases for MFLCPR (MCPR) with the bases for MAPRAT (APLHGR)
D Wrong - Plausible to the candidate the confuses the bases for MFLCPR (MCPR) with the bases for MAPRAT (APLHGR) plausible to the candidate that fails to recall the correct response time for exceeding the APLHGR LCO LMK DEC 2017 ILT NRC Page: 133 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written LMK DEC 2017 ILT NRC Page: 134 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 34 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 2029611 User-Defined ID: Q #34 Lesson Plan Objective: LGSOPS0041 6.A Topic: Vessel Internals - impact of Thermal Limit Violation RO Importance: 3.7 SRO Importance:
K/A Number: 290002 A2.05 LMK DEC 2017 ILT NRC Page: 135 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 2 Group 2 KA # and Rating 290002 A2.05 290002 Reactor Vessel Internals A2.05 - Ability to (a) predict the impacts of the following on the REACTOR VESSEL INTERNALS ; and (b)
KA Statement based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Exceeding thermal limits Cognitive level Low Safety Function 5 - Containment Integrity 10 CFR 55 41.5 Technical Reference with Tech Spec 3.2.1 Rev Revision No: and Bases #:
Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS New NRC-05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 136 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 35 ID: 2029750 Points: 1.00 Unit 2 plant conditions:
- Reactor has scrammed
- Drywell pressure is 4.4 psig and rising slowly
- Suppression Pool Spray is in service using 2A RHR
- RPV pressure is 955 psig and steady Five minutes later:
- RPV level dropped to -135" and has recovered to -110" and is rising slowly.
WHICH ONE of the following identifies the response of HV-51-2F027A for the above conditions and whether the MOV for HV-51-2F027A has a Thermal Overload Bypass or not?
- HV-51-2F027A, RHR Suppression Pool Spray Valve HV-51-2F027A Has Thermal Overload Bypass feature A. Automatically closes Yes B. Automatically closes No C. Remains open Yes D. Remains open No Answer: A Answer Explanation LMK DEC 2017 ILT NRC Page: 137 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written From the stem the candidate determines that Suppression Pool Spray is in service when a LOCA signal is received (RPV Level drops below -129"). When this occurs HV-51-2F027A receives an automatic close signal.
From OP-LG-108-101-1004, Valves. HV-51-2F027A is a valve containing the MOV Thermal Overload Bypass feature.
A Correct for the above reasons B Wrong - plausible to the candidate that fails to recall HV-51-2F027A is a valve that contains the Thermal Overload Bypass C Wrong - plausible to the candidate that fails to recall the RHR automatic response of the RHR system to a LOCA signal (or fails to recognize the conditions for a LOCA signal are present)
D Wrong - plausible to the candidate that fails to recall the RHR automatic response of the RHR system to a LOCA signal (or fails to recognize the conditions for a LOCA signal are present) and plausible to the candidate that fails to recall HV-51-2F027A is a valve that contains the Thermal Overload Bypass LMK DEC 2017 ILT NRC Page: 138 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 35 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 2029750 User-Defined ID: Q #35 Lesson Plan Objective: LGSOPS0051.IL8F Topic: Determine RHR Valve interlocks on a LOCA RO Importance: 3.4 SRO Importance:
K/A Number: 226001 A3.07 LMK DEC 2017 ILT NRC Page: 139 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments:
General Data Level RO Tier 2 Group 2 KA # and Rating 226001 A3.07 3.4 / 3.3 Ability to monitor automatic operations of the RHR/LPCI:
KA Statement TORUS/SUPPRESSION POOL SPRAY MODE including: Valve operation Cognitive level Lower Safety Function 5 - Containment Integrity 10 CFR 55 41.7 8031-M-1-E11-1040-005, sh1 Technical Reference with 8031-M-1-E11- Rev Revision No: 1040-015, sh1 #:
8031-M-1-E11-1040-016, sh1 Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS New NRC-05, OYS CERT-04)
Question Source: (i.e. New, New Bank,5 Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 140 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 36 ID: 1799214 Points: 1.00 Unit 1 is at 100% power when FQRSH-061-112, Channel 3, "D/W FLR DRAIN Sump Total Flow" indicates a rise in Drywell Leakage.
IS the leakage IDENTIFIED or UNIDENTIFIED and which choice identifies a possible source of the leakage?
IDENTIFIED or UNIDENTIFIED POSSIBLE SOURCE A. UNIDENTIFIED INPUT from the Drywell Unit Coolers B. UNIDENTIFIED Recirc Pump Seal Leakage C. IDENTIFIED INPUT from the Drywell Unit Coolers D. IDENTIFIED Recirc Pump Seal Leakage Answer: A Answer Explanation LMK DEC 2017 ILT NRC Page: 141 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written A Correct: Unidentified leakage in the drywell is considered leakage that is collected in the DW Floor Drain Sump. This includes drainage from the Drywell Floor Drains as well as Under Vessel Area and Drywell Unit Coolers Drains.
Identified Leakage is from the Recirc Pump Seals, RPV Bottom head drain, Head Seal Leakage, RPV Bellows Seal leakage and RPV Vent drains which all drain to the equipment drain tank.
Channel 3 and 4 of FQRSH-061-112 are the Flow Totalizer or Integrator channels.
Channel 3 is the Floor Drain Sump Totalizer and Channel 4 is the Equipment Drain Sump Totalizer.
B Wrong: Plausible to the candidate who remembers that Floor Drain Sump is considered Unidentified Leakage but believes that Recirc Pump Seal leakage is an input to the Floor Drain Sump when it actually drains to the Equipment Drain Sump C Wrong: Plausible to the candidate who remembers that Drywell Unit Coolers drain into the Floor Drain Sump (channel 3 of the sump integrator recorder) but believes that to be identified leakage D Wrong: Plausible to the candidate who recalls that Recirc pump seal leakage is considered identified leakage but does not recall that it drains to the equipment drain tank, not the flooor drain sump LMK DEC 2017 ILT NRC Page: 142 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 36 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1799214 User-Defined ID: Q #36 Lesson Plan Objective: LGSOPS0060B.01 Topic: DW floor drain sump integrator RO Importance: 3.4 SRO Importance: 3.6 K/A Number: 268000 A4.01 LMK DEC 2017 ILT NRC Page: 143 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 2 Group 2 KA # and Rating 268000 A4.01 3.4 / 3.6 Ability to manually operate and/or monitor in the KA Statement control room: Sump integrators Cognitive level Lower Safety Function 9 - radioactivity release 10 CFR 55 CFR: 41.7 Technical Reference with Rev 1 M-0061 Sht. 4 Revision No: #: 5 Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS New NRC-05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 144 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 37 ID: 1799196 Points: 1.00 WHICH ONE of the following requires a Unit 1 Tech Spec entry (i.e., actual implementation of a Required Action)?
A. All IRM's on range 7 during a normal reactor startup when IRM 'D' is declared inoperable B. All IRMs on Range 8 during a normal reactor startup when APRM '3' fails upscale C. Mode Switch in STARTUP; reactor is at the POAH when power is lost to the RWM D. 20% reactor power during a normal plant startup when RBM 'A' fails and is declared inoperable Answer: C Answer Explanation A Wrong: Plausible to the candidate who does not remember that Per TS Table 3.3.1-1, only 3 IRMs per RPS Trip System are required to be OPERABLE B Wrong: Plausible to the candidate who does not remember that Per TS Table 3.3.1-1, only 3 (total) APRMs are required to be OPERABLE. Therefore, the OPERABILITY requirements for Trip Functions #1 and #4 of the Control Rod Block Instrumentation TS 3.3.6, Table 3.3.6-1, are satisfied, C Correct: Per TS 3.1.4.1, the RWM is required to be OPERABLE in OPCON 1 or 2 at <=
10% RTP. Examinee is expected to recognize that power is well below 10% RTP when the "reactor is at the POAH." This is generally 1 to 2% Rx Power The applicable action is not required to be identified by the candidate but in this case is action 3.1.4.1.a which requires a second licensed operator or technically qualified individual to verify rod movement and compliance with the rod pattern.
D Wrong: Plausible to the candidate who does not remember that Per TS 3.1.4.3, RBM Operability is NOT required until power is at least 30%; therefore the Control Rod Block Instrumentation requirements of TS 3.3.6, Table 3.3.6-1, Trip Function #1 do not apply either LMK DEC 2017 ILT NRC Page: 145 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 37 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1799196 User-Defined ID: Q #37 Lesson Plan Objective: LLOT0073B.7 Topic: Recognize Tech Spec required entry condition RO Importance: 3.4 SRO Importance: 4.7 K/A Number: 201006 (2.2.40)
LMK DEC 2017 ILT NRC Page: 146 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 2 Group 2 KA # and Rating 201006 2.2.40 3.4 / 4.7 Rod Worth Minimizer/
KA Statement Ability to apply Technical Specifications for a system Cognitive level Higher Safety Function 7 10 CFR 55 41.10 Technical Reference with LGS TS Rev Revision No: 3.1.4.1 #:
Justification for Non SRO CFR Link:
Question History: (i.e. LGS NRC-05, OYS CERT-04)
Question Source: (i.e. New, Bank 1102524 Bank, Modified)
Low KA Justification (if required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments ILT #1102524 LMK DEC 2017 ILT NRC Page: 147 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 38 ID: 2029609 Points: 1.00 A coolant leak into the Unit 1 drywell has resulted in the following:
- Drywell pressure is 20 psig up slow
- RPV level is -90" down slow
- RPV pressure is 850 psig down slow
- RHR "A" Loop Injection "INITIATION" pushbutton was armed and depressed
- "A" RHR Loop is in Drywell Spray A fault on the 101 Bus occurs WHICH ONE of the following correctly completes the description of the automatic response of the "A" RHR loop?
Following re-energization of the D11 Bus, the 1A RHR Pump ___(1)___ and the drywell spray valves
___(2)___.
(1) (2)
A. remains shutdown remain open B. remains shutdown close C. restarts remain open D. restarts close Answer: C Answer Explanation LMK DEC 2017 ILT NRC Page: 148 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written From the stem the candidate determines that a LOCA signal has been provided to the RHR system ("initiation" pushbutton was armed and depressed). At this time the 1A RHR Pump is being powered from the D11 bus through the 101-D11 Bus. The next event is the trip of the 101 Bus. From this the candidate determines that the D11 Bus experiences a Dead Bus condition which causes the 1A RHR Pump Breaker to trip, the D11 EDG to get a start signal (0.5 seconds after dead bus condition) and the 201-D11 Bus Breaker to close (1.0 seconds after dead bus condition). Once the D11 Bus is re-energized from the 201 bus, the 1A RHR pump will start following a time delay (5 seconds).
From LGSOPS0051 A Wrong - plausible to the candidate the fails to recognize that the RHR LOCA signal will remain and will restart the RHR Pump once power is again available. (Candidate mistakenly believes that a Core Spray System LOCA signal is required, i.e. the D11 EDG will not get a LOCA start signal)
B Wrong - plausible to the candidate the fails to recognize that the RHR LOCA signal will remain and will restart the RHR Pump once power is again available. (Candidate mistakenly believes that a Core Spray System LOCA signal is required, i.e. the D11 EDG will not get a LOCA start signal) and plausible to the candidate that confuses the response of the Drywell Spray valve with other RHR valves that auto reposition under various Initiation signals.
C Correct for the above reasons D Wrong - plausible to the candidate that confuses the response of the Drywell Spray valve with other RHR valves that auto reposition under various Initiation signals.
LMK DEC 2017 ILT NRC Page: 149 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 38 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 2029609 User-Defined ID: Q #38 Lesson Plan Objective: LGSOPS0051 9.A Topic: RHR - Drywell Spray - Pump Starts RO Importance: 3.5 SRO Importance:
K/A Number: 226001 A3.07 LMK DEC 2017 ILT NRC Page: 150 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: Bank 846285 General Data Level RO Tier 2 Group 2 226001 A3.07 RO KA # and Rating Importance 3.5 226001 RHR/LPCI: CTMT Spray Mode A3.07 - Ability to monitor automatic operations of the KA Statement RHR/LPCI:
CONTAINMENT SPRAY SYSTEM MODE including:
Pump start Cognitive level High Safety Function 5 - Containment Integrity 10 CFR 55 41.7 Technical Reference with Rev 0 LGSOPS0051 Revision No: #: 4 Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS Modified 846285 NRC-05, OYS CERT-04)
Question Source: (i.e. New, Modified 846285 Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 151 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 39 ID: 1799231 Points: 1.00 Unit 1 is Operating at 100% power
- The 1B Reactor Recirc Pump Trips Which P-1 parameter listed below will rise as a result?
A. MFLCPR B. MFLPD C. MAPRAT D. PCMARG Answer: A Answer Explanation A Correct: Maximum Fraction Of Limiting Critical Power Ratio (MFLCPR), is the Critical power ratio limit divided by the critical power ratio multiplied by a flow biasing factor. When core flow drops, CPR drops and this causes MFLCPR to rise B Wrong: Maximum Fraction Of Limiting Power Density (MFLPD). Plausible to the candidate who confuses the changes in MFLPD with MFLCPR. Actual MFLPD value will drop as power in the core drops C Wrong: Plausible to the candidate who confuses the changes in MAPRATwith MFLCPR.
Maximum Average Planar Ratio (MAPRAT) will also drop as core power drops D Wrong: Plausible to the candidate who confuses the changes in PCMARG with MFLCPR.
PCMARG is the margin to preconditioning and is proportional to pin power. As power drops, so does PCMARG LMK DEC 2017 ILT NRC Page: 152 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 39 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1799231 User-Defined ID: Q #39 Lesson Plan Objective: LLOT1540.05 Topic: Loss of Forced Circulation RO Importance: 3.6 SRO Importance: 4.1 K/A Number: 295001 AK1.03 LMK DEC 2017 ILT NRC Page: 153 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 1 Group 1 KA # and Rating 295001 AK1.03 3.6 / 4.1 Knowledge of the operational implications of the following concepts as they KA Statement apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION : Thermal limits Cognitive level Higher Safety Function 1, 4 10 CFR 55 CFR: 41.8 to 41.10 Technical Reference with Rev 5 OT-112, P-1 Revision No: #: 7 Justification for Non SRO CFR Link:
Question History: (i.e. LGS NRC-05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 154 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 40 ID: 1799234 Points: 1.00 T-111, Steam Cooling, is in progress with the following:
- Reactor water level is -207"
- No injection systems are available to the RPV WHICH ONE of the following correctly completes the following two statements:
For the above conditions Adequate Core Cooling _____(1)_____ present.
With no injection into the RPV, adequate core cooling is defined to exist as long as peak clad temperature remains below _____(2)_____?
(1) (2)
A. is 1800oF B. is 2200oF C. is NOT 1800oF D. is NOT 2200oF Answer: C Answer Explanation LMK DEC 2017 ILT NRC Page: 155 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written LR-9 Any system, subsystem, OR alt subsystem lined up with at least one pump running The terms "systems", "subsystems", and "alternate subsystems" have been defined previously in this Bases document, and are repeated here for clarity.
A "NO" response indicates that no RPV injection sources are available, and that steam cooling is required. Operators are directed to continue at Step LR-10, where the steam cooling section of the T-111, Level Restoration/Steam Cooling, flowchart begins.
Step LR-10 directs an exit from the RPV pressure (RC/P) control flowpath of T-101, RPV Control. The steam cooling section of T-111, Level Restoration/Steam Cooling, contains RPV pressure control steps which are in conflict with those in the RC/P flowpath of T-101. To avoid the occurrence of concurrently effective, yet conflicting, RPV pressure control guidance between T-101 and T-111, operators are directed to exit the RC/P flowpath of T-101.
Steam cooling is performed to prolong the time that adequate core cooling is assured when no RPV injection sources are available. With no injection into the RPV, adequate core cooling is defined to exist as long as peak clad temperature remains below 1800 deg, the threshold for significant metal-water reaction. The RPV level at which this occurs is designated as the Minimum Zero-Injection RPV Water Level (MZIRWL) and is -198 inches.
A wrong - plausible to the candidate that confuses the RPV level for 2/3 core coverage (-
211") with the RPV level for MZIRWL.
B wrong - plausible to the candidate that confuses the RPV level for 2/3 core coverage (-
211") with the RPV level for MZIRWL and plausible if the candidate mistakenly believes that the ECCS design criteria of peak cladding temperature below 2200 degrees F constitutes adequate core cooling.
C Correct for the above reasons D Wrong - plausible if the candidate mistakenly believes that the ECCS design criteria of peak cladding temperature below 2200 degrees F constitutes adequate core cooling.
LMK DEC 2017 ILT NRC Page: 156 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 40 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 4 Difficulty: 0.00 System ID: 1799234 User-Defined ID: Q #40 Lesson Plan Objective: LGSOPS1560.03 Topic: T-111 - Recognize if Adequate Core Cooling Exists RO Importance: 4.6 SRO Importance: 4.7 K/A Number: 295031 EK1.01 LMK DEC 2017 ILT NRC Page: 157 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments:
General Data Level RO Tier 1 Group 1 KA # and Rating 295031 EK1.01 4.6/4.7 Reactor Low Water Level Knowledge of the operational implications of the following KA Statement concepts as they apply to REACTOR LOW WATER LEVEL :
EK1.01 Adequate core cooling Cognitive level lower Safety Function 2 - Reactor Water Inventory Control 10 CFR 55 41.8 Technical Rev Reference with T-111 15 Revision No:
Justification for Non SRO CFR n/a Link:
Question History: (i.e. LGS Modified 1151444 (Used on LGS ILT NRC NRC-05, OYS Exam January 2016)
CERT-04)
Question Source: (i.e.
Modified 1151444 New, Bank, Modified)
Low KA Justification (if n/a required):
Revision History:
Revision History: (i.e. Changed RPV Level in Stem from -178" to -
Modified 207", this changes correct answer from A to distractor b to C.
make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. none ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
LMK DEC 2017 ILT NRC Page: 158 of 410 21 December 2017 Comments 560666
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 40 Table-Item Links NRC EXAM - 10 CFR 55 Operators' Licenses CFR: 41.7 Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
10 CFR 55.41 RO WRITTEN EXAMINATION LIMERICK LO Question Category ILT NRC RO LOW COG LMK DEC 2017 ILT NRC Page: 159 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 41 ID: 1799237 Points: 1.00 Plant conditions are as follows:
- Unit 1 is at 100%.
- Unit 2 is in OPCON 5 with refueling activities in progress with secondary containment set on the refuel floor.
- All, "REFUEL FLOOR/RX ENCL CNTMT ISO INTERLOCK" switches are in "NORMAL"
- A fuel handling accident results in Refuel Floor ventilation radiation levels of 13 mR/hr Regarding the reactor enclosure and the refuel floor, which of the following describes the Zones SBGT will maintain at a negative pressure and the reason for the initiation of SBGT?
Zones SBGT will maintain negative Reason for SBGT Initiation A. Refuel Floor ONLY Limit iodine and particulate concentration in gases, prior to discharge B. Refuel Floor ONLY Limit particulate concentration in gases ONLY, prior to discharge C. Unit 1 reactor enclosure and Refuel floor Limit iodine and particulate concentration in gases, prior to discharge D. Unit 1 reactor enclosure and Refuel floor Limit particulate concentration in gases ONLY, prior to discharge Answer: A Answer Explanation A Correct Refuel HVAC isolates at 2.00 mr/h. Although refuel floor containment and Unit 1 Reactor Containment are set, only when Zones are crosstied will a refuel HVAC isolation also isolate the Reactor enclosure. The purpose of the SBGT filters per the Design basis document L-S-32 is The SGTS/RERS filters iodine and particulate concentrations in gases potentially present within the Secondary Containment prior to discharge to the environment via the North Stack.
B Incorrect Limit particulate only is incorrect but plausible to the examinee who does not recall the purpose of the charcoal filters C incorrect plausible to the examinee who recognizes that the radiation levels are above the Reactor Enclosure setpoint, but either does not recall the crosstie logic or believe that hi refuel radiation will isolate the reactor enclosure as long as the zone is established D incorrect plausible to the examinee who recognizes that the radiation levels are above the Reactor Enclosure setpoint, but either does not recall the crosstie logic or believe that hi refuel radiation will isolate the reactor enclosure as long as the zone is established and does not recall the purpose of the charcoal filters LMK DEC 2017 ILT NRC Page: 160 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 41 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1799237 User-Defined ID: Q #41 Lesson Plan Objective: LLOT0076B.6 Topic: High Off-site Release Rate - protection of the general public RO Importance: 4.2 SRO Importance:
K/A Number: 295038 EK1.02 LMK DEC 2017 ILT NRC Page: 161 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 1 Group 1 295038 EK1.02 RO KA # and Rating importance 4.2 295038 High Off-site Release Rate / 9 EK1.02 - Knowledge of the operational implications of KA Statement the following concepts as they apply to HIGH OFF-SITE RELEASE RATE :
Protection of the general public Cognitive level Low Safety Function 9 - Radioactivity Release 10 CFR 55 41.8 Technical Reference with Rev 1 S76.1.C Revision No: #: 5 Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS New NRC-05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 162 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 42 ID: 1799238 Points: 1.00 An electrical fault has caused a loss of AC power to the DIV I Battery Charger 1BCA2.
WHICH ONE of the following describes the effect on the DIV I, 125 VDC loads?
A. Some loads are lost immediately B. All loads are lost immediately C. All loads are lost when the battery is fully discharged D. Some loads are lost when the battery is fully discharged Answer: D Answer Explanation Answer: Some loads are lost when the battery is fully discharged When a battery charger becomes inoperable the batteries act as a backup to keep DC available for all DC loads. As the batteries discharge some of the DC loads will become unavailable, while others use an auctioneering circuit to an alternate source to ensure availability.
A Wrong - plausible to the candidate that fails to recall that the battery charger loss does not result in the immediate loss of DC loads B Wrong - plausible to the candidate that fails to recall that the battery charger loss does not result in the immediate loss of DC loads and plausible to the candidate that fails to recall that there are two 125VDC batteries and two battery chargers. The 1BCA1 will continue to carry loads for approximately half of the Division 1 DC loads.
C Wrong - plausible to the candidate that fails to recall that there are two 125VDC batteries and two battery chargers. The 1BCA1 will continue to carry loads for approximately half of the Division 1 DC loads.
D Correct for the above reasons LMK DEC 2017 ILT NRC Page: 163 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 42 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1799238 User-Defined ID: Q #42 Lesson Plan Objective: LGSOPS0095.02A Topic: Partial loss of DC Power - battery chargers RO Importance: 3.1 SRO Importance: 3.1 K/A Number: 295004 AK2.01 LMK DEC 2017 ILT NRC Page: 164 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 1 Group 1 KA # and Rating 295004 AK2.01 3.1 / 3.1 Knowledge of the interrelations between PARTIAL OR COMPLETE KA Statement LOSS OF D.C. POWER and the following: Battery charger Cognitive level Lower Safety Function 6 - Electrical 10 CFR 55 41.7 Technical Reference with Rev 4 E-0033 sh. 1 Revision No: #: 5 Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS Bank 833421 NRC-05, OYS CERT-04)
Question Source: (i.e. New, Bank 833421 Bank, Modified)
Low KA Justification (if required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 165 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 43 ID: 1799263 Points: 1.00 Unit 2 is at 65% power when a fire is reported. The 2B Condensate Pump Motor is burning.
Using portions of Pre-Fire Plan F-T-266, the CRS directs de-energizing the 2B Condensate Pump.
WHICH ONE of the following identifies the breaker to be opened, and the additional transient procedure requiring entry?
Breaker to be opened Additional Transient Procedure A. 21 Aux Bus-04 OT-100 B. 21 Aux Bus-04 OT-112 C. 22 Aux Bus-04 OT-100 D. 22 Aux Bus-04 OT-112 Answer: C Answer Explanation LMK DEC 2017 ILT NRC Page: 166 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written From the stem the candidate is informed that the 2B Condensate Pump is burning. The candidate recalls that the 2B Condensate Pump is powered from the 22 Aux Bus and determines the equipment isolation for 22 Aux Bus-04. Upon the isolation of the 2B Condensate Pump entry into OT-100 is required.
From F-T-266 From OT-100 A Wrong - plausible to the candidate that incorrectly recalls the Condensate Pump power supply and selects the breaker for the 2A Condensate Pump B Wrong - plausible to the candidate that incorrectly recalls the Condensate Pump power supply and selects the breaker for the 2A Condensate Pump and plausible to the candidate that mistakenly determines that a 42% recirc runback will occur for the given situation (this would occur if total feedwater flow was >12 Mlbm/hr) For information in the stem, the total feedwater flow is ~9.9 Mlbm/hr (full power FW flow is ~15.3 Mlbm/hr X 0.65 = 9.945)
C Correct for the above reasons D Wrong - plausible to the candidate that mistakenly determines that a 42% recirc runback will occur for the given situation (this would occur if total feedwater flow was >12 Mlbm/hr)
For information in the stem, the total feedwater flow is ~9.9 Mlbm/hr (full power FW flow is
~15.3 Mlbm/hr X 0.65 = 9.945)
LMK DEC 2017 ILT NRC Page: 167 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 43 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1799263 User-Defined ID: Q #43 Lesson Plan Objective: LGSOPS0022 8 Topic: Fire - impact on motors RO Importance: 2.5 SRO Importance:
K/A Number: 600000 AK2.03 LMK DEC 2017 ILT NRC Page: 168 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 1 Group 1 600000 AK2.03 RO KA # and Rating Importance 2.5 600000 Plant Fire On-site /
8 AK2.03 - Knowledge of the KA Statement interrelations between PLANT FIRE ON SITE and the following: Motors Cognitive level High Safety Function 8 - Plant Service Systems 10 CFR 55 41.7 0
F-T-266 5 Technical Reference with OT-100 Rev 3 Revision No: ARC-MCR-204 #: 6 F2 0 1
Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS New NRC-05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 169 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 44 ID: 1799241 Points: 1.00 Unit 1 plant conditions:
- 90% power
- Both Recirc Pumps running at 75% Speed Operators are swapping in-service Stator Water Cooling (SWC) Pumps:
- SWC trips have not been bypassed During the swap, system flow drops to 0 gpm for a period of 12 seconds before system parameters return to normal.
WHICH ONE of the following identifies the Recirc Pump speeds?
1A 1B A. 75% 75%
B. 42% 75%
C. 75% 42%
D. 42% 42%
Answer: B Answer Explanation LMK DEC 2017 ILT NRC Page: 170 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written A Wrong: Plausible to the candidate who believes that the power level listed above is below that which would cause a runback B Correct: From ON-114-IF Stator current >7,469 amps and Loss of Stator Cooling detected by any of the following:
- Inlet pressure (U1: <45 psig, U2: < 39.4 psig)
- High Stator Water bulk outlet temperature >80 °C
- Bushing coolant flow < 84 gpm.
Then IF Total FW flow >6.7 Mlbm/hr
-Reactor recirculation Pump "A" runs back to 42% speed after 9 second time delay AND
- *B after 18 second time delay As a result of a mod installed during 1R15, the Recirc Pumps will receive a high-limit (42%) runback (so long as Total FW flow is >6.7 Mlbm/hr). The 9 and 18-second time delays (from the point of the SWC trip signal being generated) remain the same as before the mod.
C Wrong: Plausible to the candidate who remembers the power level required to receive a runback but believes that the B RRP will runback 1st D Wrong: Plausible to the candidate who remembers the power level requirements but forgets the 9 and 18 second time delay or believes that both pumps will run back regardless whether the signal clears.
With the SWC trip signal existing only for 12 seconds, the 1A Recirc Pump will run back to 42%
speed (i.e., >9 seconds), but the 1B Recirc Pump will remain at 75% speed (i.e., <18 seconds).
LMK DEC 2017 ILT NRC Page: 171 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 44 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1799241 User-Defined ID: Q #44 Lesson Plan Objective: LGSOPS0033.03.A Topic: 12 second loss of Stator Coolant RO Importance: 3.4 SRO Importance: 3.6 K/A Number: 295018 AK2.02 LMK DEC 2017 ILT NRC Page: 172 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 1 Group 1 KA # and Rating 295018 AK2.02 3.4 / 3.6 Knowledge of the interrelations between PARTIAL OR COMPLETE KA Statement LOSS OF COMPONENT COOLING WATER and the following: Plant operations Cognitive level Higher Safety Function 8 - Plant Service Systems 10 CFR 55 CFR: 41.7 Technical Reference with Rev 4 ON-114 Revision No: #: 6 Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS Bank 988524 NRC-05, OYS CERT-04)
Question Source: (i.e. New, Bank 988524 Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 173 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 45 ID: 1799264 Points: 1.00 Unit 2 is shutdown for a forced outage following a 192 day run.
- Reactor coolant temperature is 177°F in OPCON 4
- 2A RHR Pump is running in Shutdown Cooling
- ON-121, Loss of Shutdown Cooling, is entered Which of the following methods of Decay Heat Removal is available?
A. Swap to the 2B RHR Pump and restore Shutdown Cooling B. Swap to the 2C RHR Pump and restore Shutdown Cooling C. Restore cooling by placing RHR in ADHR D. Use SRVs and Suppression Pool Cooling as Alternate SDC Answer: D Answer Explanation A Wrong: Plausible to the candidate who believes that Swapping to the 2B pump would use a different flowpath. The HV-51-2F009 valve is failed closed and cannot be reopened.
This path is not available B Wrong: Plausible to the candidate who believes that Swapping to the 2C pump would allow injection on a different flow path.
C Wrong:restore cooling by placing RHR in ADHR is plausible to the candidate who recalls that ADHR has a different flowpath then SDC through the F009 Valve. However, this flowpath is only available when the reactor is flooded up.
D Correct: From ON-121, step 2.1.9 "IF required to implement Alternate Shutdown Cooling due to the failure of HV-051-*F008 OR HV-051-*F009 THEN PERFORM Attachment 6". Attachment 6 then directs the operator to perform S41.7.B LMK DEC 2017 ILT NRC Page: 174 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 45 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1799264 User-Defined ID: Q #45 Lesson Plan Objective: LGSOPS1550.01 Topic: Feed and Bleed RO Importance: 3.3 SRO Importance: 3.4 K/A Number: 295021 AK3.02 LMK DEC 2017 ILT NRC Page: 175 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 1 Group 1 KA # and Rating 295021 AK3.02 3.3 / 3.4 Knowledge of the reasons for the following responses as they apply to LOSS OF KA Statement SHUTDOWN COOLING :
Feeding and bleeding reactor vessel Cognitive level Higher Safety Function 4 10 CFR 55 CFR: 41.5 Technical Reference with Rev S41.7.B 8 Revision No: #:
Justification for Non SRO CFR Link:
Question History: (i.e. LGS Perry 2015 NRC Exam RO NRC-05, OYS CERT-04) #5 Question Source: (i.e. New, Modified Bank, Modified)
Low KA Justification (if required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 176 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 46 ID: 1799276 Points: 1.00 Unit 1 plant conditions are as follows:
- Reactor Power is 100%
- Outside air temperature is 95° F
- "1B" Drywell Chiller is in service
- "1A" and "1B" Drywell Chilled Water Pumps are in service A Dead Bus Transfer of the D12 Bus results in a loss of Drywell Chilled Water with the following indications:
- Drywell temperature is 143 ° F and up slow
- Drywell pressure rises to 0.7 psig WHICH ONE of the following identifies the required action(s) to restore a DWCW flow path to the containment, if any?
A. No action required, flow path is maintained B. Reopen the DWCW Containment isolation valves C. Reset isolation R2 with Blue/Green reset per GP 8.3 and reopen the DWCW Containment isolation valves D. Bypass the isolation per GP 8.5 and reopen the DWCW Containment isolation valves Answer: B Answer Explanation LMK DEC 2017 ILT NRC Page: 177 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written From E-D12 Justification:
A. Incorrect but plausible: Plausible if the applicant fails to recognize that DW cooling isolation valves will close upon restoration of power to the MOVs due to the affects of the interposing relays.
B. Correct: The Dead Bus transfer of D12 will de-energize the interposing relays, resulting in isolation/closure of the DWCW Containment Isolation Valves upon re-energization of the bus. The valves can be re-opened when D12 power is restored because no isolation signal is present.
C. Incorrect but plausible: Plausible if the applicant believes an isolation signal exists.
Performing an R2 with Blue/Green reset would clear an existing isolation signal when the monitored parameter (i.e., High DW Pressure for DWCW Containment Isolation Valves) has returned to a normal value. With no isolation signal present, the DWCW Containment Isolation Valves can be re-opened once power is restored to the D12 bus.
D. Incorrect but plausible: Bypassing the isolation per GP-8.5 is plausible if the applicant believes that an isolation signal exists. With no isolation signal present, the DWCW Containment Isolation Valves can be re-opened once power is restored to the D12 bus.
In addition, GP-8.5 is not directed until DW temperature rises above 145°F in accordance with T-102, Step DW/T-4.
LMK DEC 2017 ILT NRC Page: 178 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 46 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1799276 User-Defined ID: Q #46 Lesson Plan Objective: LGSOPS0072 Topic: Loss of AC power effect on DWCW system RO Importance: 3.7 SRO Importance: 3.7 K/A Number: 295003 AK3.06 LMK DEC 2017 ILT NRC Page: 179 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 1 Group 1 KA # and Rating 295003 Knowledge of the reasons for the following responses as they apply to PARTIAL KA Statement OR COMPLETE LOSS OF A.C. POWER : Containment isolation Cognitive level Higher Safety Function 6 10 CFR 55 CFR: 41.5 / 45.6 Technical Reference with Rev 1 E-D12 Revision No: #: 1 Justification for Non SRO CFR Link:
Question History: (i.e. LGS NRC LGS2012 NRC-05, OYS CERT-04)
Question Source: (i.e. New, Bank 1097448 Bank, Modified)
Low KA Justification (if required):
re-worded question and Revision History: Revision changed disctractor A due History: (i.e. Modified to the chiller and distractor b to make circulating pumps tripping plausible based on OTPS when this is run in the review) simulator (low flow condition)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments Original Q#1097448 LMK DEC 2017 ILT NRC Page: 180 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 47 ID: 1799329 Points: 1.00 Unit 1 is in OPCON 3, with the following:
- MSIVs are closed
- Cooldown is in progress using SRVs
- HV-59-129A and HV-59-129B, 'PCIG PROCESS LINES', to the Drywell are closed due to loss of power The PRO opens HV-59-128A and HV-59-128B, 'INST AIR TO INST GAS.'
WHICH ONE of the following describes the availability of the '1E' and '1F' SRVs for continuing the cooldown?
'1E' SRV '1F' SRV A. available available B. available NOT available C. NOT available available D. NOT available NOT available Answer: B Answer Explanation From the stem the candidate determines that Normal PCIG supply to the Drywell has been isolated via HV-59-129A and HV-59-129B. These valves isolate the PCIG compressors and the PCIG Receivers. This is the normal Instrument Air/Gas supply to all SRV solenoid valves. With the opening of HV-59-128A and HV-59-128B Instrument Air is introduced to the PCIG header.
This connection is upstream of the closed HV-59-129A and HV-59-129B, therefore Instrument Air will not enter the drywell to support Drywell loads. With the normal PCIG supply gone, the remaining Instrument Air/Gas supply is limited to N2 bottles (1AS252 and 1BS252) and PCIG thrugh HV-59-151A and HV-59-151B supplying only the ADS SRVs (S,H,M,E,K).
A Wrong - plausible to the candidate that fails to recall where the Instrument Air system backup connects to the PCIG and believes that the connection is down stream of the HV-59-129A and HV-59-129B and that Instrument Air is supplying all SRVs.
B Correct for the above reasons C Wrong - plausible to the candidate the confuses the SRVs that receive backup N2 and PCIG supply D Wrong - plausible to the candidate that fails to recall that ADS SRVs (S,H,M,E,K) have backup bottles and PCIG supplying N2 for operation LMK DEC 2017 ILT NRC Page: 181 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 47 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1799329 User-Defined ID: Q #47 Lesson Plan Objective: LGSOPS0059.3A Topic: Loss of IA/PCIG - Backup RO Importance: 3.3 SRO Importance:
K/A Number: 295019 AK3.01 LMK DEC 2017 ILT NRC Page: 182 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments:
General Data Level RO Tier 1 Group 1 295019 AK3.01 RO KA # and Rating Importance 3.3 295019 Partial or Total Loss of Inst. Air / 8 AK3.01 - Knowledge of the reasons for the following KA Statement responses as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR : Backup air system supply: Plant-Specific Cognitive level High Safety Function 8 - Plant Service Systems 10 CFR 55 41.5 M-0059, Sheet 3 Technical Reference with 001 Rev 8 Revision No: M-0059, Sheet #: 3 002 7 Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS Bank 556930 NRC-05, OYS CERT-04)
Question Source: (i.e. New, Bank 556930 Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 183 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 48 ID: 1799332 Points: 1.00 Plant conditions are as follows:
- PJM has declared a 'Maximum Emergency Generation Action'
- 230K Grid Voltage has dropped 10KV As a result:
- Generator H 2 pressure is 75 psig
- Generator MW load is 1170 MWe
- Generator Field Current is 6,382 Amps
- Generator Terminal Voltage is 20.9 KV WHICH ONE of the following describes the required operator action?
A. Notify the TSO that generator terminal voltage cannot be corrected without first reducing generator MW load.
B. Notify the TSO that generator terminal voltage cannot be corrected without first reducing the MVAR load.
C. Lower the setting on 90P-G103 to reduce the MVAR load and thus restore generator terminal voltage to above its lower limit.
D. Raise the setting on 90P-G103 to restore generator terminal voltage to above its lower limit.
Answer: A LMK DEC 2017 ILT NRC Page: 184 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Answer Explanation S32.3.A sets limits for main generator parameters during heavy grid load. Step 4.6 and its NOTE requires maintaining generator field current less than 6382 amps. Stem conditions indicate generator field current is currently 6,382 amps; therefore, that limit is already being exceeded. That same step requires maintaining generator terminal voltage above 21.0 KV.
Stem conditions indicate the generator terminal voltage is currently 20.9 KV; therefore, it is too low. E-5 Grid Emergency, step 3.4 requires maintaining generator parameters within the limits of the Generator Capability Curve or Table in Attachment 2. The Table shows that for a real load of 1170 MWe at 75 psig H2 pressure, the maximum allowed reactive load is 481 MVARs.
[NOTE - Each MWe load versus MVAR load combination (at 75 psig) shown on the Table equates to operating the machine precisely at its 1265 MVA (apparent power) rating. Use the Power Triangle to demonstrate this claim: Square Root of [(1170 MW)2 + (481 MVAR)2] = 1265 MVA, where this 1265 MVA rating is shown on the Generator Capability Curve (page 2 of Attachment 2), as well as in the NOTE associated with step 3.1.21 of GP-5.].
'A' is correct. In order to raise the generator terminal voltage, operators would have to RAISE the setting on the automatic voltage regulator adjuster, 90P-G103. However, with the MVAR load already at its max limit for a real load of 1170 MWe, raising the 90P-G103 setting will also cause MVARs to increase above the E-5 Attachment 2 Table limit (i.e., the machine's MVA rating would be exceeded). Additionally, the higher setting on 90P-G-103 would also increase the generator field current above its <6,382 amp limit. Therefore, operators should notify the TSO that generator terminal volts cannot be corrected without first reducing the generator's real load (MWe); that will allow for a higher MVAR load (to accomodate having to raise the 90P-G103 setting) without exceeding the machine's MVA rating, as well as provide more margin for the increased generator field current without exceeding the <6,382 amp limit.
'B' is wrong. To reduce the MVAR load operators must LOWER the setting on 90P-G103. The problem is, this will also lower the generator terminal voltage, making that situation worse than it already is. This is plausible to the examinee who does not completely understand the relationship between a 90P-G103 adjustment and the resulting generator terminal volts.
'C' is wrong. As explained for choice 'B' above, lowering the 90P-G103 setting will result in a lower generator terminal voltage, not a higher one. This is plausible to the examinee who does not completely understand the relationship between a 90P-G103 adjustment and the resulting generator terminal volts.
'D' is wrong. As already explained for the correct answer 'A', while restoring generator terminal volts to above the lower limit, raising the 90P-G103 setting will also raise the generator field current to above the 6,382 Amp limit. This is plausible to the examinee who either does not completely understand the relationship between a 90P-G103 adjustment and the resulting generator field current, or who fails to recognize that the pre-existing generator field current is already at (actually, is exceeding) its <6,382 amp limit.
LMK DEC 2017 ILT NRC Page: 185 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 48 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1799332 User-Defined ID: Q #48 Lesson Plan Objective: LLOT1566.02 E Determine Actions based on Main Gen Parameters Topic:
During Grid Emergency RO Importance: 3.6 SRO Importance: 3.7 K/A Number: 700000.AA1.01 LMK DEC 2017 ILT NRC Page: 186 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 1 Group 1 KA # and Rating 700000 AA1.01 3.6 / 3.7 Ability to operate and/or monitor the following as they apply to KA Statement GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES: Grid frequency and voltage Cognitive level Higher Safety Function 6 - Electrical 10 CFR 55 CFR: 41.5 S32.3.A Technical Reference with Rev E-5 Revision No: #:
GP-5 Justification for Non SRO CFR Link:
Question History: (i.e. LGS NRC-05, OYS CERT-04)
Question Source: (i.e. New, Bank 988823 Bank, Modified)
Low KA Justification (if required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 49 ID: 1799353 Points: 1.00 Unit 1 is in OPCON 3, with the following:
- '1A' RHR Pump is in Shutdown Cooling (SDC)
- Drywell Pressure rises to 3 psig Consider the following Shutdown Cooling Valves:
- HV-51-1F008 RHR S/D Clg Suction (OUTBOARD)
- HV-51-1F009 RHR S/D Clg Suction (INBOARD)
- HV-51-1F015A RHR S/D/ Clg Rtn (OUTBOARD)
WHICH ONE of the following identifies the Shutdown Cooling Valves status one minute after the LPCI initiation signal is generated and whether the 1A RHR Pump is adding inventory to the RPV?
(Assume no operator actions.)
Shutdown Cooling Valves 1A RHR adding inventory to the RPV A. Open No B. Open Yes C. Closed No D. Closed Yes Answer: A Answer Explanation LMK DEC 2017 ILT NRC Page: 188 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written From the stem the candidate is told that Shutdown Cooling is in service. This required RPV level above 12.5" and Reactor Pressure to be below 75# psig. When Drywell pressure rises above 1.68# with Reactor Pressure less than 455#, the conditions for a LOCA signal are met.
As can be seen in the table below, Drywell pressure does not isolate Shutdown Cooling therefore the Shutdown Cooling Valves remain open.
From GP-8 With Shutdown Cooling not isolated, and a LOCA signal, 1A RHR will inject however it will not be adding any inventory due to its suction source and discharge location both being the RPV.
A Correct for the above reasons B Wrong - plausible to the candidate the fails to recall the suction source is the RPV and will not add inventory C Wrong - plausible to the candidate that incorrectly believes that Shutdown cooling will isolate on 1.68 psig in the drywell D Wrong - plausible to the candidate that incorrectly believes that Shutdown cooling will isolate on 1.68 psig in the drywell and believes the RHR suction is from the suppression pool such that 1A RHR would add inventory to the RPV LMK DEC 2017 ILT NRC Page: 189 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 49 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1799353 User-Defined ID: Q #49 Lesson Plan Objective: LGSOPS0051.8A Topic: High Drywell Pressure - Operate or monitor RHR/LPCI RO Importance: 4.1 SRO Importance:
K/A Number: 295024 EA1.04 LMK DEC 2017 ILT NRC Page: 190 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 1 Group 1 295024 EA1.04 RO KA # and Rating Importance 4.1 295024 High Drywell Pressure / 5 EA1.04 - Ability to operate KA Statement and/or monitor the following as they apply to HIGH DRYWELL PRESSURE:
RHR/LPCI Cognitive level High Safety Function 5 - Containment Integrity 10 CFR 55 41.7 Technical Reference with Rev 1 GP-8 Revision No: #: 8 Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS Modified Bank 555993 NRC-05, OYS CERT-04)
Question Source: (i.e. New, Modified Bank 555993 Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified Changed LOCA signal to distractor b to make pressure and changed part plausible based on OTPS 2 to adding inventory review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 191 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 50 ID: 1799575 Points: 1.00 Plant conditions are as follows:
- Main Turbine tripped from 100% power
- 120 Control Rods failed to fully scram due to a hydraulic lock
- Reactor Power is 10%
- Reactor Pressure is 900 psig
- Reactor Mode Switch is in "SHUTDOWN"
- CRD discharge pressure is 1155 psig WHICH ONE of the following identifies why the RO cannot manually insert the Control Rods?
A. RWM rod block B. APRM rod block C. CRD Drive Water Pressure control valve HV-46-1F003 failed closed D. Full Scram Discharge Volume Answer: A Answer Explanation A Correct: Reactor power is 10% which is below the LPSP. An out of sequence rod will have a Insert and Withdraw Blocks along with a ROD BLOCK annunciator. LPSP is approximately 13.9% Steam flow when power drops.
To move control rods T-101 reminds the operator to bypass the RWM B Wrong: APRM Rod Block is Plausible to the candidate who incorrectly recalls the APRM rod block power level (12% when Mode switch is in Shutdown (out of Run position)) and believes that power is above the RBM power level. This is an out block however not an insertion block.
C Wrong: Plausible to the candidate who confuses the operation of the Pressure Control Valve and believes that closing the valve would starve the flow control and drive water section of CRD when in actuality it would provide more pressure to the drive water header and assist in rod insertion.
D Wrong: Plausible to the candidate who believes that CRD exhaust header discharges to the Scram discharge volume and therefore has no flowpath instead of CRD Exhaust Header.
LMK DEC 2017 ILT NRC Page: 192 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 50 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1799575 User-Defined ID: Q #50 Lesson Plan Objective: LGSOPS1560.03 Manually insert control rods with failure to scram due to a 120 Topic:
rod hydraulic lock RO Importance: 2.7 SRO Importance: 2.8 K/A Number: 295005 AA1.03 LMK DEC 2017 ILT NRC Page: 193 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 1 Group 1 KA # and Rating 295005 AA1.03 2.7 / 2.8 Ability to operate and/or monitor the following as they apply to MAIN KA Statement TURBINE GENERATOR TRIP : Reactor manual control/Rod control and information system Cognitive level Higher 3 - Reactor Pressure Safety Function Control 10 CFR 55 41.7 Technical Reference with Rev Revision No: #:
Justification for Non SRO CFR Link:
Question History: (i.e. LGS NRC-05, OYS CERT-04)
Question Source: (i.e. New, Bank 557084 Bank, Modified)
Low KA Justification (if required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 194 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 51 ID: 1799355 Points: 1.00 A 30% ATWS is in progress on Unit 2.
Consider the following 2 sets of conditions:
Condition 1 Suppression Pool level is 20' and stable Suppression Pool temperature is 150 degrees and up slow Reactor pressure is 1000 psig Condition 2 Suppression Pool level is 23' and stable Suppression Pool temperature is 155 degrees and up slow Reactor pressure is 800 psig LMK DEC 2017 ILT NRC Page: 195 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written WHICH ONE of the following (1) identifies the set of conditions which will provide the GREATEST margin to Blowdown if Reactor pressure remains constant and (2) defines Heat Capacity Temperature Limit (HCTL)?
A. (1) Condition 1 (2)The highest suppression pool temperature at which initiation of RPV depressurization will not result in exceeding the max temperature capability of the suppression pool B. (1) Condition 1 (2) The suppression pool temperature limit that, when exceeded, requires RPV pressure reduction to the next lower pressure band to ensure the heat capacity of the suppression pool is not exceeded on a Blowdown C. (1) Condition 2 (2)The highest suppression pool temperature at which initiation of RPV depressurization will not result in exceeding the max temperature capability of the suppression pool D. (1) Condition 2 (2) The suppression pool temperature limit that, when exceeded, requires RPV pressure reduction to the next lower pressure band to ensure the heat capacity of the suppression pool is not exceeded on a Blowdown Answer: C Answer Explanation The candidate must apply each of the conditions to the Curve from T-102. At 800 psig reactor pressure and 23 feet, HCTL will be exceeded at approx. 168. At 155 degrees, there is a 13 degree margin to blowdown. For condition 1, HCTL will be exceeded at 160, which means a margin of only 10 degrees (160-150), therefore LESS margin. From T-102 Bases, The HCTL curve is based on "the highest suppression pool temperature at which initiation of RPV depressurization will not result in exceeding the max temperature capability of the suppression pool".
T-102 does not allow reducing reactor pressure once it is determined that the safe side of the HCTL curve can not be maintained. In this case, a Blowdown must be performed. This makes the last 2 choices incorrect.
A Wrong - Plausible to the candidate that incorrectly applies the provided parameters to the curve B Wrong - Plausible to the candidate that incorrectly applies the provided parameters to the curve and fails to correctly recall the definition of HCTL C Correct for the above reasons D Wrong - Plausible to the candidate that fails to correctly recall the definition of HCTL LMK DEC 2017 ILT NRC Page: 196 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 51 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1799355 User-Defined ID: Q #51 Lesson Plan Objective: LGSOPS1560.04 Topic: Suppression Pool high temp - impact Rx Pressure RO Importance: 3.9 SRO Importance:
K/A Number: 295026 EA2.03 LMK DEC 2017 ILT NRC Page: 197 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments:
General Data Level RO Tier 1 Group 1 295026 EA2.03 RO KA # and Rating Importance 3.9 295026 Suppression Pool High Water Temp. / 5 EA2.03 - Ability to determine and/or interpret KA Statement the following as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE: Reactor pressure Cognitive level High Safety Function 5 - Containment Integrity 10 CFR 55 41.10 Technical Reference with Rev 2 T-102 Bases Revision No: #: 6 Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS Bank 1149165 NRC-05, OYS CERT-04)
Question Source: (i.e. New, Bank 1149165 Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified Shaded in "Safe and distractor b to make "Unsafe" on graph plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 198 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 51 Table-Item Links NRC EXAM - 10 CFR 55 Operators' Licenses 10 CFR 55.41 RO WRITTEN EXAMINATION LIMERICK LO Question Category ILT NRC RO HI COG LMK DEC 2017 ILT NRC Page: 199 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 52 ID: 1799391 Points: 1.00 Plant conditions:
- A steam leak exists in the Drywell
- RPV pressure is 1040 psig, steady
- Drywell temperature is 200°F, up slow WHICH ONE of the following describes the effect on RPV level indication for the above conditions?
A. Indicated level currently reads slightly lower than actual level B. Indicated level currently reads slightly higher than actual level C. Reference leg flashing will occur when drywell temperature reaches 212° F, causing indicated RPV level to rise D. Indicated level is equal to actual level as long as drywell temperature remains less than 212oF Answer: B Answer Explanation LMK DEC 2017 ILT NRC Page: 200 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written From T-102 Bases:
A Wrong - plausible to the candidate that confuses the effect of temperature on the reference leg and reverses the relationship B Correct - With drywell temperature elevated, reference leg water density will be lower, causing the d/p across the d/p cell to be lower, which causes indicated level to be higher than actual level.
C Wrong - plausable to the candidate that fails to recognize that the reference leg is pressurize and will not flash D Wrong - plausable to the candidate that believes that the current elevated temperature has no effect on RPV level indication.
LMK DEC 2017 ILT NRC Page: 201 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 52 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1799391 User-Defined ID: Q #52 Lesson Plan Objective: LGSOPS1560.4 High Drywell Temperature - Determine and interpret Reactor Topic:
Water Level RO Importance: 3.7 SRO Importance: 3.9 K/A Number: 295028 EA2.03 LMK DEC 2017 ILT NRC Page: 202 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments:
General Data Level RO Tier 1 Group 1 295028 EA2.03 RO KA # and Rating Importance 3.7 295028 High Drywell Temperature / 5 EA2.03 - Ability to determine and/or interpret KA Statement the following as they apply to HIGH DRYWELL TEMPERATURE : Reactor water level Cognitive level High Safety Function 5 - Containment Integrity 10 CFR 55 41.10 Technical Reference with Rev 2 T-102 Bases Revision No: #: 6 Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS ILT Cert Exam 2005 NRC-05, OYS CERT-04)
Question Source: (i.e. New, ILT Cert Exam 2005 Bank Bank, Modified) 562330 Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 203 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 52 Table-Item Links NRC EXAM - 10 CFR 55 Operators' Licenses CFR: 41.7 Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
CFR: 41.10 Administrative, normal, abnormal, and emergency operating procedures for the facility.
10 CFR 55.41 RO WRITTEN EXAMINATION 10 CFR 55.43 SRO WRITTEN EXAMINATION CFR: 43.5 Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.
CFR: 45.6 Perform control manipulations required to obtain desired operating results during normal, abnormal, and emergency situations.
CFR: 45.8 Safely operate the facility's auxiliary and emergency systems, including operation of those controls associated with plant equipment that could affect reactivity or the release of radioactive materials to the environment.
CFR: 45.13 Demonstrate the applicant's ability to function within the control room team as appropriate to the assigned position, in such a way that the facility licensee's procedures are adhered to and that the limitations in its license and amendments are not violated.
LMK DEC 2017 ILT NRC Page: 204 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 53 ID: 1799469 Points: 1.00 Unit 2 plant conditions are as follows:
- Reactor Power is 20%, steady
- Drywell Pressure is 2.2 psig, steady
- RPV Level is -80", steady
- Suppression Pool temperature is 100 °F up 2.5 °F/min Assume the above trend continues, WHICH ONE of the following identifies the number of minutes until the conditions above require the performance of T-270, Terminate and Prevent, and identifies the basis for this action?
Minutes until conditions require performance of T-270 Basis for this Terminate and Prevent A. 2 To prevent/mitigate the consequences of power oscillations B. 2 Attempt to lower reactor power C. 4 To prevent/mitigate the consequences of power oscillations D. 4 Attempt to lower reactor power Answer: D Answer Explanation LMK DEC 2017 ILT NRC Page: 205 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written From the stem the candidate identifies that three of the four conditions of T-117 step LQ-13; Reactor Power above 4%, RPV Level above -161 inches, and drywell pressure above 1.68 psig.
The question asks when the conditions for Terminate and Prevent are met (in this case step LQ-13). The conditions will be met at a suppression pool temperature of 110 °F. At a rate of rise of 2.5 °F/min and a starting temperature of 100 °F this will take 4 minutes.
The basis for the Terminate and Prevent is found in T-117 bases for step LQ-13 The second column distractor is taken from the basis for the first lowering, T-117 bases for step LQ-7.
A Wrong - plausible to the candidate that fails to recall the Suppression Pool Temperature at which Terminate and Prevent is required (105 °F can be easily confused due to it being the Tech Spec 3.6.2.1a.2.a temperature limit during testing which adds heat to the suppression chamber) and plausible to the candidate that confuses the basis for the first lowering (T-117 step LQ-7) with that of LQ-13.
B Wrong - plausible to the candidate that fails to recall the Suppression Pool Temperature at which Terminate and Prevent is required (105 °F can be easily confused due to it being the Tech Spec 3.6.2.1a.2.a temperature limit during testing which adds heat to the suppression chamber)
C Wrong - plausible to the candidate that confuses the basis for the first lowering (T-117 step LQ-7) with that of LQ-13.
D Correct for the above reasons LMK DEC 2017 ILT NRC Page: 206 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 53 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1799469 User-Defined ID: Q #53 Lesson Plan Objective: LGSOPS1560.03 Topic: ATWS - determine/interpret Suppression Pool Temperature RO Importance: 4.0 SRO Importance:
K/A Number: 295037 EA2.04 LMK DEC 2017 ILT NRC Page: 207 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 1 Group 1 295037 EA2.04 RO KA # and Rating Importance 4.0 295037 SCRAM Conditions Present and Reactor Power Above APRM Downscale or Unknown / 1 EA2.04 - Ability to determine and/or interpret KA Statement the following as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN : Suppression pool temperature Cognitive level High Safety Function 1- Reactivity Control 10 CFR 55 41.10 T-117 Bases 1 Technical Reference with Rev Tech Specs 9 Revision No: #:
3.6.2.1 Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS New NRC-05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 208 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 54 ID: 1799491 Points: 1.00 Considering the Main Turbine Stop Valves input to RPS, WHICH ONE of the following identifies the Scram signal setpoint and describes the basis for this RPS trip during 100% power operation?
Scram Signal Setpoint Basis for RPS Trip A. Oil Pressure less than 500 psig Anticipates the RPV pressure, neutron flux, and heat flux increase B. Oil Pressure less than 500 psig Protect the turbine from excessive overspeed C. Valve Position less than 95% open Anticipates the RPV pressure, neutron flux, and heat flux increase D. Valve Position less than 95% open Protect the turbine from excessive overspeed Answer: C Answer Explanation LMK DEC 2017 ILT NRC Page: 209 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written From Tech Spec Limiting Safety System Settings Bases page B 2-9:
Distractor from TRM Bases B3/4 3-7 A Wrong - plausible to the candidate that mistakenly recalls the RPS set point for the Control Valves rather than the set point for the Stop Valves B Wrong - plausible to the candidate that mistakenly recalls the RPS set point for the Control Valves rather than the set point for the Stop Valves and confuses the basis for overspeed protection with that of the RPS scram basis C Correct for the above reasons D Wrong - plausible to the candidate that confuses the basis for overspeed protection with that of the RPS scram basis LMK DEC 2017 ILT NRC Page: 210 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 54 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1799491 User-Defined ID: Q #54 Lesson Plan Objective: LGSOPS0071.04 Topic: Stop Valve Scram setpoint and bases RO Importance: 3.6 SRO Importance:
K/A Number: 295006 G2.238 LMK DEC 2017 ILT NRC Page: 211 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments:
General Data Level RO Tier 1 Group 1 295006 G2.2.38 RO KA # and Rating Importance 3.6 295006 SCRAM / 1 2.2.38 - Equipment Control:
KA Statement Knowledge of conditions and limitations in the facility license.
Cognitive level Low Safety Function 1 - Reactivity Control 10 CFR 55 41.7 Technical Reference with Rev Tech Specs Revision No: #:
Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS New NRC-05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 212 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 55 ID: 1801599 Points: 1.00 Unit 1 plant conditions:
- OPCON 5
- Core Shuffle Part 2 is in progress
- Fuel bundle 43-20 has just been seated in the core
- The main hoist grapple is released and is being raised The Main Control Room receives:
- Alarm ARC-MCR-107 F4, SRM Period
- SRM '1C' count rate changing from 70 to 300 cps and continuing to rise.
WHICH ONE of the following describes the required actions?
A. Notify Health Physics to determine dose rates B. Re-grapple fuel bundle 43-20 and raise it until it clears the top guide C. Make PA announcement "Refuel Floor Secondary Containment breaches are to be restored per the Barrier Breach Contingency Plans."
D. Evacuate the fuel floor and ensure all insertable control rods are inserted Answer: D Answer Explanation LMK DEC 2017 ILT NRC Page: 213 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written From the stem the candidate determines the SRM count rates have more than doubled twice 70
- 140 - 280 CPS. This is symptom 1.1 of ON-120, Fuel Handling Problems". ON-120 section 1 addresses SRM count rates rising.
A Wrong - Plausible to the candidate who does not recognize that the SRM count rate has more than doubled and has not stabilized and is increasing, indicating criticality.
Determination of Dose rates is directed from a different section of ON-120 (section for any Fuel Floor ARM Alarm)
B Wrong - Plausible to the candidate who does not recognize that the SRM count rate has more than doubled and has not stabilized and is increasing, indicating criticality. If the count rate had stabilized then the correct action would be to raise the bundle until it clears the upper guide, however, after grapple has been released there is no direction to re-grapple.
C Wrong - Plausible to the candidate who recalls the actions for both - if an irradiated fuel bundle is dropped or damaged (ON-120 Attachment 3) and for if an Irradiated fuel rod is dropped or damaged (ON-120 Attachment 4) and believes this action is required for an SRM Rising event D Correct for the above reasons LMK DEC 2017 ILT NRC Page: 214 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 55 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1801599 User-Defined ID: Q #55 Lesson Plan Objective: LGSOPS1550 Topic: Recall ON-120 actions for signs of inadvertent criticality RO Importance: 4.2 SRO Importance:
K/A Number: 295023 G2.4.46 LMK DEC 2017 ILT NRC Page: 215 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments:
General Data Level RO Tier 1 Group 1 295023 G2.4.46 RO KA # and Rating Importance 4.2 295023 Refueling Accident 2.4.46 - Emergency Procedures / Plan: Ability to KA Statement verify that the alarms are consistent with the plant conditions.
Cognitive level Low Safety Function 8 - Plant Service Systems 10 CFR 55 41.10 Technical Reference with Rev 2 ON-120 Revision No: #: 8 Justification for Non SRO N/A CFR Link:
Bank 1149988 based on Question History: (i.e. LGS LGS NRC 2012 ILT NRC-05, OYS CERT-04)
(1097324)
Question Source: (i.e. New, Bank 1149988 Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make Replaced distractor "C" plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 216 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 55 Table-Item Links NRC EXAM - 10 CFR 55 Operators' Licenses CFR: 41.10 Administrative, normal, abnormal, and emergency operating procedures for the facility.
CFR: 41.11 Purpose and operation of radiation monitoring systems, including alarms and survey equipment.
10 CFR 55.41 RO WRITTEN EXAMINATION LIMERICK LO Question Category ILT NRC RO LOW COG LMK DEC 2017 ILT NRC Page: 217 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 56 ID: 1799569 Points: 1.00 Plant conditions:
- Unit 1 Reactor SCRAMMED 20 minutes ago due to a group I isolation.
- Reactor pressure is steady at 970 psig and being maintained by HPCI in pressure control mode.
- Reactor level is steady at -20" and RCIC is injecting at 600 gpm.
- Suppression Pool level is as indicated below:
WHICH ONE of the following describes the further operation of HPCI?
A. Can continue to operate at 5600 gpm B. Can continue to operate but only at a reduced flowrate C. HPCI must be secured only if suppression pool pressure begins to rise D. HPCI must be secured Answer: D Answer Explanation LMK DEC 2017 ILT NRC Page: 218 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written The candidate recognizes that because a Group 1 isolation occurred 20 minutes ago RCIC is/should be sufficient to maintain adequate core cooling by submergence.
Second, the candidate recalls the check/re-check from T-102 SP/L-4, which states that "If suppression Pool level cannot be maintained above 18 ft AND HPCI is not required from RPV injection, THEN secure HPCI."
This step is further defined from the basis as :
Operation of the HPCI turbine with its exhaust unsubmerged will tend to directly pressurize the suppression chamber. If suppression pool water level cannot be maintained above the elevation of the top of the HPCI exhaust, HPCI is therefore secured if not needed for core cooling.
Therefore, HPCI is secured because core cooling is assured.
A Wrong - plausible if the candidate fails to recall the fact that below a suppression Pool level of 18' HPCI exhaust will directly pressurize the Suppression Pool.
B Wrong - plausible to the candidate that confuses the provided conditions with those that would require reduced operation due to protecting from NPSH or suction vortexing.
C Wrong - plausible to the candidate that incorrectly applies the allowance of HPCI operation with the Suppression Pool Level below 18' for when HPCI is needed for adequate core cooling to this situation.
D Correct for the above reasons LMK DEC 2017 ILT NRC Page: 219 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 56 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1799569 User-Defined ID: Q #56 Lesson Plan Objective: LGSOPS1560.5 T-102 - Determine actions required for HPCI with low Supp Topic:
Pool level RO Importance: 4.2 SRO Importance:
K/A Number: 295030 G2.4.31 LMK DEC 2017 ILT NRC Page: 220 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 1 Group 1 295030 G2.4.31 RO KA # and Rating Importance 4.2 295030 Low Suppression Pool Water Level / 5 2.4.31 - Emergency KA Statement Procedures / Plan:
Knowledge of annunciator alarms, indications, or response procedures.
Cognitive level High Safety Function 5 - Containment Integrity 10 CFR 55 41.2 Technical Reference with Rev 2 T-102 Bases Revision No: #: 6 Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS Bank 1141088 NRC-05, OYS CERT-04)
Question Source: (i.e. New, Bank 1141088 Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified Added picture of the distractor b to make Suppression Pool Level plausible based on OTPS indicator.
review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 221 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 56 Table-Item Links NRC EXAM - 10 CFR 55 Operators' Licenses CFR: 41.5 Facility operating characteristics during steady state and transient conditions, including coolant chemistry, causes and effects of temperature, pressure and reactivity changes, effects of load changes, and operating limitations and reasons for these operating characteristics.
CFR: 41.10 Administrative, normal, abnormal, and emergency operating procedures for the facility.
10 CFR 55.41 RO WRITTEN EXAMINATION LMK DEC 2017 ILT NRC Page: 222 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 57 ID: 1799574 Points: 1.00 SRVs are automatically cycling open and closed due to high reactor pressure during an ATWS.
WHICH ONE of the following describes why SRV cycling is undesirable and warrants prompt manual action?
A. Prevent excessive damage to Bypass Valve/Main Condenser impingement plates during BPV operation at higher than normal RPV pressure B. Minimize reactor power transients due to RPV pressure and level oscillations C. Minimize SRV accumulator inventory loss D. Minimize potential for a Downcomer Vacuum Breaker sticking open Answer: B Answer Explanation LGS TRIP Step RC/P-7 is a decision diamond that has operators evaluate whether or not any of the SRVs are cycling.
"SRV cycling" is defined as multiple, closely sequenced SRV actuations where the SRV opens as RPV pressure exceeds the respective safety lift setpoint and closes as RPV pressure drops below the respective reset setpoint. SRV cycling is undesirable and warrants prompt manual action for the following reasons:
- It exerts significant dynamic loads upon the RPV, the SRV tail pipes and supporting structures, and the primary containment.
- Shrink and swell associated with SRV actuations cause RPV level fluctuations that complicate RPV level control actions.
- Under failure-to-scram conditions, the consequent RPV level and RPV pressure oscillations can result in significant reactor power transients.
- The potential for a stuck open SRV is increased.
A Wrong - plausible to the candidate the concludes that reactor pressure that causes SRV cycling (above 1170 psig) would cause significant damage on the impingment plates and this is the reasons for this step in T-101.
B Correct for the above reasons C Wrong - plausible to the candidate the believes that SRVs cycling (on their lift pressure settings) uses gas from the accumulators (it does not)
D Wrong - plausible to the candidate that confuses Downcomer Vacuum Breakers (those that relieve pressure from the Suppression Pool air space to the Drywell air space) with SRV tail pipe vacuum breakers.
LMK DEC 2017 ILT NRC Page: 223 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 57 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1799574 User-Defined ID: Q #57 Lesson Plan Objective: LGSOPS1560.5 Topic: T-101 - Recall Basis for Step RC/P-7 RO Importance: 3.9 SRO Importance:
K/A Number: 295025 EK2.09 LMK DEC 2017 ILT NRC Page: 224 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 1 Group 1 295025 EK2.09 RO KA # and Rating Importance 3.9 295025 High Reactor Pressure / 3 EK2.09 - Knowledge of the KA Statement interrelations between HIGH REACTOR PRESSURE and the following: Reactor power Cognitive level Low 3 - Reactor Pressure Safety Function Control 10 CFR 55 41.7 Technical Reference with Rev 2 T-101 Bases Revision No: #: 4 Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS Bank 560722 NRC-05, OYS CERT-04)
Question Source: (i.e. New, Bank 560722 Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 225 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 57 Table-Item Links NRC EXAM - 10 CFR 55 Operators' Licenses CFR: 41.5 Facility operating characteristics during steady state and transient conditions, including coolant chemistry, causes and effects of temperature, pressure and reactivity changes, effects of load changes, and operating limitations and reasons for these operating characteristics.
CFR: 41.7 Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
CFR: 41.10 Administrative, normal, abnormal, and emergency operating procedures for the facility.
10 CFR 55.41 RO WRITTEN EXAMINATION LIMERICK LO Question Category ILT NRC RO LOW COG LMK DEC 2017 ILT NRC Page: 226 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 58 ID: 1845773 Points: 1.00 Plant conditions:
- A fire in the Cable Spreading Room has caused a MCR evacuation
- All Immediate Operator Actions are complete
- All Remote Shutdown Transfer switches are in EMERGENCY WHICH ONE of the following interlocks remains enabled?
A. RCIC High Level Trip B. D11, D12, D13 DG Breaker auto-closure C. ESW Return to Spray Pond on '0A' ESW Pump start D. HV51-1F016A ,'1A' Containment Spray Outboard Isolation Valve open permissive interlock Answer: B Answer Explanation LMK DEC 2017 ILT NRC Page: 227 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Answer: D11, D12, D13 DG Breaker auto close SYSTEM INTERLOCK CHANGES DURING RSP OPERATIONS RCIC
- Will not auto start.
- Will not automatically isolate.
-Will not trip on Reactor high level, (i.e. HV-50-*F045 will not close).
-Min Flow Valve operation is not automatic.
-Turbine Steam Inlet Valve is not interlocked to prevent opening with Turbine Exhaust Valve closed.
- Condensate Pump will not cycle automatically on high level.
SAFEGUARD BUSES Interlocks inserted to prevent any breaker closure unless the other two breakers are open.
- D*1, D*2, AND D*3 D/G Breaker Control goes to "Auto Close" only.
-'A' LPCI auto start is defeated.
-'A' Min Flow Valve operation is not automatic.
- HV-51-*F017A, "'A' RHR Outboard Injection Valve," is not interlocked to prevent opening.
- HV-51-*F016A, "'A' Containment Spray Outboard Isolation Valve," is not interlocked to prevent opening.
- Group II Isolations for 'A' RHR Shutdown Cooling interlocks are defeated.
(Reactor Level 3-Low, 12.5" AND Reactor Pressure-High, RHR Valve permissive, 75#)
RHRSW/ESW
-Automatic actions returning ESW to the Spray Pond on ESW 'A' OR 'C' Pump starts do not occur.
- RHRSW Pump does not trip on RHRSW Loop 'A' Return High Radiation OR High Discharge Pressure.
Distracters:
RCIC High Level Trip - see explanation of RSP interlocks ESW Return to Spray Pond on "0A" ESW Pump start - see explanation of RSP interlocks HV-51-1F016A "1A" Containment Spray Outboard Isolation Valve" open permissive interlock -
see explanation of RSP interlocks LMK DEC 2017 ILT NRC Page: 228 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 58 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1845773 User-Defined ID: Q #58 Lesson Plan Objective: LLOT1563.03 Topic: SE Recall Enabled Interlocks with RSP Operations RO Importance: 3.1 SRO Importance: 3.2 K/A Number: 295016 AA1.04 LMK DEC 2017 ILT NRC Page: 229 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 1 Group 1 KA # and Rating 295016 AA1.04 3.1 / 3.2 Ability to operate and/or monitor the following as KA Statement they apply to CONTROL ROOM ABANDONMENT:
A.C. electrical distribution Cognitive level Lower Safety Function 7 - Instrumentation 10 CFR 55 41.7 Technical Reference with Rev SE-1 Revision No: #:
Justification for Non SRO CFR Link:
Question History: (i.e. LGS LGS NRC-05, OYS CERT-04)
Question Source: (i.e. New, Bank 560903 Bank, Modified)
Low KA Justification (if required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 230 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 59 ID: 1845763 Points: 1.00 The following sequence of events occurs on Unit 2:
- 10:00 REACTOR ENCL HVAC PANEL 2AC208 TROUBLE alarms
- 10:05 DIV 1 STEAM LEAK DET SYS HI TEMP/TROUBLE alarms
WHICH ONE of the following identifies when Initial and Re-Entry times into T-103, Secondary Containment Control, are required?
Initial Entry Time Re-Entry Time A. 10:00 10:25 B. 10:00 10:40 C. 10:05 10:25 D. 10:05 10:40 Answer: D Answer Explanation LMK DEC 2017 ILT NRC Page: 231 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Of the three alarms listed, Only the "DIV 1 STEAM LEAK DET SYS HI TEMP/TROUBLE" alarm required direct entry into T-103. From ARC-MCR-207 F5:
The other 2 alarms require investigation/confirmation prior to T-103 entry.
From ARC-MCR-219 A2:
From ARC-MCR-219 I3:
A Wrong - plausible to the candidate the confuses which alarms need confirmed prior to T-103 entry and which alarms require direct T-103 entry.
B Wrong - plausible to the candidate the confuses which alarms need confirmed prior to T-103 entry and which alarms require direct T-103 entry.
C Wrong - plausible to the candidate the confuses which alarms need confirmed prior to T-103 entry and which alarms require direct T-103 entry.
D Correct for the above reasons LMK DEC 2017 ILT NRC Page: 232 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 59 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1845763 User-Defined ID: Q #59 Lesson Plan Objective: LGSOPS1560.02A T-103, Identify the initial and reentry times for various T-103 Topic:
conditions RO Importance: 3.5 SRO Importance:
K/A Number: 295032 EK1.03 LMK DEC 2017 ILT NRC Page: 233 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 1 Group 2 295032 EK1.03 RO KA # and Rating Importance 3.5 295032 High Secondary Containment Area Temperature / 5 EK1.03 - Knowledge of the operational implications of the following concepts as KA Statement they apply to HIGH SECONDARY CONTAINMENT AREA TEMPERATURE:
Secondary containment leakage detection: Plant-Specific Cognitive level Low Safety Function 5 - Containment Integrity 10 CFR 55 41.8 2
T-103 Bases 5
ARC-MCR-219 0
A2 Technical Reference with Rev 1 ARC-MCR-207 Revision No: #: 0 F5 5
ARC-MCR-219 0
I3 1
Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS Bank 561057 NRC-05, OYS CERT-04)
Question Source: (i.e. New, Bank 561057 Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified Removed 10:30 MDDFP distractor b to make start from Stem and re-plausible based on OTPS structured second column review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 234 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 59 Table-Item Links NRC EXAM - 10 CFR 55 Operators' Licenses 10 CFR 55.41 RO WRITTEN EXAMINATION CFR: 43.5 Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.
LIMERICK LO Question Category ILT NRC RO LOW COG LMK DEC 2017 ILT NRC Page: 235 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 60 ID: 1845770 Points: 1.00 Unit 1 plant conditions:
- T-103, Secondary Containment Control, is in progress due to flooding in the RCIC Room
- The Reactor Enclosure Floor Drain Sump Pumps have tripped on Hi-Hi radiation
- The CRS has directed a procedure that places the HSS-61-104 REACTOR ENCL. FLOOR DRAIN SUMP SELECTION SW in the "HI-HI Rad" position.
WHICH ONE of the following correctly completes the following statements?
The purpose of the Hi-Hi Radiation trip of the Reactor Enclosure Sump Pump is to prevent transfer of highly radioactive water to the _____(1)_____. With HSS-61-104 selected to the HI-HI Rad position, the Reactor Enclosure Sump Pumps _____(2)_____ start/stop on sump level.
(1) (2)
A. Suppression Pool do not B. Suppression Pool auto C. Radwaste Enclosure do not D. Radwaste Enclosure auto Answer: D Answer Explanation LMK DEC 2017 ILT NRC Page: 236 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written From T-236:
From T-103 Bases LMK DEC 2017 ILT NRC Page: 237 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written LMK DEC 2017 ILT NRC Page: 238 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 60 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1845770 User-Defined ID: Q #60 Lesson Plan Objective: LGSOPS2003.2 T-236, Describe the purpose of performing T-236, Transferring Topic:
Reactor Enclosure Floor RO Importance: 3.1 SRO Importance:
K/A Number: 295036 EK2.01 LMK DEC 2017 ILT NRC Page: 239 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 1 Group 2 295036 EK2.01 RO KA # and Rating Importance 3.1 295036 Secondary Containment High Sump/Area Water Level / 5 EK2.01 - Knowledge of the interrelations between SECONDARY KA Statement CONTAINMENT HIGH SUMP/AREA WATER LEVEL and the following:
Secondary containment equipment and floor drain system Cognitive level Low Safety Function 5 - Containment Integrity 10 CFR 55 41.7 1
Technical Reference with T-236 Rev 5 Revision No: T-103 Bases #: 2 5
Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS New NRC-05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 240 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 60 Table-Item Links NRC EXAM - 10 CFR 55 Operators' Licenses CFR: 41.5 Facility operating characteristics during steady state and transient conditions, including coolant chemistry, causes and effects of temperature, pressure and reactivity changes, effects of load changes, and operating limitations and reasons for these operating characteristics.
CFR: 41.6 Design, components, and functions of reactivity control mechanisms and instrumentation.
CFR: 41.7 Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
CFR: 41.8 Components, capacity, and functions of emergency systems.
CFR: 41.10 Administrative, normal, abnormal, and emergency operating procedures for the facility.
10 CFR 55.41 RO WRITTEN EXAMINATION 10 CFR 55.43 SRO WRITTEN EXAMINATION CFR: 45.6 Perform control manipulations required to obtain desired operating results during normal, abnormal, and emergency situations.
CFR: 45.8 Safely operate the facility's auxiliary and emergency systems, including operation of those controls associated with plant equipment that could affect reactivity or the release of radioactive materials to the environment.
CFR: 45.13 Demonstrate the applicant's ability to function within the control room team as appropriate to the assigned position, in such a way that the facility licensee's procedures are adhered to and that the limitations in its license and amendments are not violated.
LMK DEC 2017 ILT NRC Page: 241 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 61 ID: 1845774 Points: 1.00 Unit 2 plant conditions:
- 50% power
- 2A RFP is blocked for maintenance
- Both Recirc Pumps running at 50% speed
- 2B RFP min flow valve fails open in AUTO
- Reactor level drops to + 25 inches before recovering WHICH ONE of the following describes the response of the Recirc Pumps and the reason for this response?
A. Runback to 28% speed; reduces power to restore level by reducing steam load B. Runback to 42% speed; reduces power to prevent RFP trip on low suction pressure C. Runback to 28% speed; reduces power to ensure adequate NPSH to Recirc Pumps D. Runback to 42% speed; reduces power to restore level by reducing steam load Answer: D Answer Explanation LMK DEC 2017 ILT NRC Page: 242 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written From the stem the candidate identifies that flow through the 2A Reactor Feed Pump is less than 0.94 Mlbm/hr and RPV water level is less than 27.5 inches.
This satisfies the conditions required for a High Limit Runback (42% Speed)
From S43.0.B A Wrong - plausible to the candidte that incorrectly recalls which runback is received for the stem conditions and chooses 28%
B Wrong - plausible to the candated that incorrectly recalls the basis for the 42% runback upon a trip of a condensate pump and applies it to the stem conditions.
C Wrong - plausible to the candidte that incorrectly recalls which runback is received for the stem conditions and chooses 28% and plausible to the candated that incorrectly recalls the basis for the 28% runback.
D Correct, per S43.0.B, NOTE Section 4.1; the basis for the 42% runback on FW loop low flow and level <27.5" is to reduce reactor power to restore level LMK DEC 2017 ILT NRC Page: 243 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 61 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1845774 User-Defined ID: Q #61 Lesson Plan Objective: LLOT0040.04 Topic: RPV low level - Recall Recirc Pump response and reason for RO Importance: 3,2 SRO Importance: 3.3 K/A Number: 295009 AK3.01 LMK DEC 2017 ILT NRC Page: 244 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 1 2 - Reactor Water Inventory Group Control KA # and Rating 295009 AK3.01 3.2 / 3.3 Knowledge of the reasons for the following responses as they apply to LOW KA Statement REACTOR WATER LEVEL : Recirculation pump run back: Plant-Specific Cognitive level Lower Safety Function 2 10 CFR 55 41.5 Technical Reference with Rev 2 S43.0.B Revision No: #: 7 Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS 2012 CERT NRC-05, OYS CERT-04)
Question Source: (i.e. New, Bank 1148918 Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 245 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 62 ID: 1845775 Points: 1.00 Unit 1 is at 95% power with the following conditions:
- Outside air temperature is 89 °F
- Circulating water temperature is 90 °F.
When the 1C Circ Water Pump trips.
WHICH ONE of the following identifies the predicted condensate temperature and procedure entry required as a result of the 1C Circ Water Pump trip?
Predicted Condensate Temperature Procedure Entry Required A. 139 °F OT-104 B. 139 °F OT-116 C. 141 °F OT-104 D. 141 °F OT-116 Answer: B Answer Explanation LMK DEC 2017 ILT NRC Page: 246 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written From the stem the candidate determines there is a reduction in circ water flow during a hot day with Unit 1 operating at 95% power. Using this information and S09.2.A Attachment 1 Page Table 1, the predicted Condensate Temperature with Circ water temp of 90 °F and 95% power operation is 139 °F.
Under the given conditions a reduction in Main condenser vacuum would result requiring entry into OT-116, Loss of Condenser Vacuum.
A Wrong - plausible to the candidate that believes that a trip of a Circ Water pump would have a direct impact on core reactivity and cause a reactor power change.
B Correct for the above reasons C Wrong - plausible to the candidate that applies the given plant conditions to Attachment 1 but reverses power and circ water temperature and plausible to the candidate that believes that a trip of a Circ Water pump would have a direct impact on core reactivity and cause a reactor power change.
D Wrong - plausible to the candidate that applies the given plant conditions to Attachment 1 but reverses power and circ water temperature.
LMK DEC 2017 ILT NRC Page: 247 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 62 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1845775 User-Defined ID: Q #62 Lesson Plan Objective: LGSOPS1450 2 Topic: Loss of Vacuum - Circ Water RO Importance: 3.1 SRO Importance:
K/A Number: 295002 AA1.07 LMK DEC 2017 ILT NRC Page: 248 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 1 Group 2 295002 AA1.07 RO KA # and Rating Importance 3.1 295002 Loss of Main Condenser Vac / 3 AA1.07 - Ability to operate and/or monitor the following KA Statement as they apply to LOSS OF MAIN CONDENSER VACUUM : Condenser circulating water system Cognitive level High 3 - Reactor Pressure Safety Function Control 10 CFR 55 41.7 Technical Reference with Rev 2 S09.2.A Revision No: #: 5 Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS New NRC-05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If S09.2.A Attachment 1 appropriate): (i.e. ABN-##) (Pages 6 & 7)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 249 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 63 ID: 1845777 Points: 1.00 Unit 1 is operating at 100% power, normal operating level
- A DFWLC malfunction causes water level to rise at a rate of 12 inches per minute.
- The feedpumps and main turbine fail to trip on high level
- The Reactor Operator trips the feedpumps 3 minutes later (3 minutes after malfunction) and scrams the reactor What level instrument will provide the most accurate indication of Reactor Water Level at the time the feedpumps are tripped?
A. Narrow Range B. Shutdown Range C. Wide Range D. Upset Range Answer: D Answer Explanation A Wrong: Plausible to the candidate who believes that water level stops rising prior to exceeding +60" on Narrow range because they do the math incorrectly B Wrong: Plausible to the candidate who recalls that the range of Shutdown overlaps with Upset range but fails to recall that Shutdown range calibrated cold.
The instruments are calibrated for a water temperature of 120°F at 0 psig in the RPV and 80°F in the Drywell C Wrong: Plausible to the candidate who believes that water level stops rising prior to exceeding +60" on Wide Range because they do the math incorrectly or believe that they can read level up to +70" and therefore must be correct D Correct: With the conditions given, Rx level at NOL of 35" and then level begins to rise at 12 inches per minute. when the pumps are tripped 3 minutes later, level would have risen to 71". This is above the range of the Narrow Range and PAMS indication which are limited to +60 inches. The Upset instruments are calibrated for saturated steam and water conditions at 1045 psig in the RPV and 117/135°F in the Drywell. The range of the upset instrument is 0 to +180 inches. Shutdown range indicates from 0 to +370 inches but as noted above, is calibrated for cold conditions. Therefore Upset is the most accurate indication of high level at Hot conditions.
LMK DEC 2017 ILT NRC Page: 250 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 63 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1845777 User-Defined ID: Q #63 Lesson Plan Objective: LLOT0041A.1K Topic: High RPV Level RO Importance: 3.9 SRO Importance: 3.9 K/A Number: 295008 AA2.01 LMK DEC 2017 ILT NRC Page: 251 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 1 Group 2 KA # and Rating 295008 AA2.01 3.9 / 3.9 Ability to determine and/or interpret the following as KA Statement they apply to HIGH REACTOR WATER LEVEL: Reactor water level Cognitive level Higher Safety Function 2 10 CFR 55 41.10 Technical Reference with LGSOPS0042 Rev 2 Revision No: DBD L-S-16 #: 7 Justification for Non SRO CFR Link:
Question History: (i.e. LGS NRC-05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 252 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 64 ID: 1845791 Points: 1.00 Unit 1 is performing a startup:
Reactor Power is 4%
Control Rod 34-27 is being withdrawn to position 48.
Alarm 108 REACTOR F-5, ROD OVERTRAVEL is received.
WHICH ONE of the following identifies what postulated UFSAR Chapter 15 transient is of concern in this situation and a component that mitigates the effect of this transient?
UFSAR Chapter 15 transient Component that minimizes the transient A. Control Rod Drop Accident Velocity Limiter B. Control Rod Drop Accident Collet Fingers C. Control Rod Withdrawal Error Velocity Limiter D. Control Rod Withdrawal Error Collet Fingers Answer: A Answer Explanation LMK DEC 2017 ILT NRC Page: 253 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written From the stem the candidate determines that Control Rod 34-27 is not coupled to the Control Rod Drive (CRD) and the control rod position is unknown (it could be anywhere between position 00 and 48). This is the situation of the Control Rod Drop Accident with the worst case being the control rod stuck at position 00 and dropping uncontrollably from 00 to 48. The analysis described in UFSAR 15.4.9.3.3 results in the assumed failure of 1200 fuel rods. This would result in radiation level requiring entry into The Emergency Action Plan, at a minimum for Threshold RU3 - 2 (Specific coolant activity > 4.0 micro curies per gram.) The equipment credited in minimizing the impact of this accident are the Rod Worth Minimizer (which enforces a control rod sequence that minimizes local power peaks) and the velocity limiter (physical component on the Control Rod Blade that creates hydraulic drag to limit the speed of the control rod and the subsequent rate of reactivity insertion).
A Correct for the above reasons B Wrong - plausible if the candidate confuses the components of the CRD with the Control Rod Blade. The Collet Fingers are a component designed to prevent the CRD from withdrawing without a command signal, not the Control Rod Blade C Wrong - Plausible to the candidate that believes the Control Rod Withdrawal error transient is the concern in this situation due to the assumption that the control rod has not actually been withdrawn (due to it being uncoupled).
D Wrong - Plausible to the candidate that believes the Control Rod Withdrawal error transient is the concern in this situation due to the assumption that the control rod has not actually been withdrawn (due to it being uncoupled) and plausible if the candidate confuses the components of the CRD with the Control Rod Blade. The Collet Fingers are a component designed to prevent the CRD from withdrawing without a command signal, not the Control Rod Blade LMK DEC 2017 ILT NRC Page: 254 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 64 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 2 Difficulty: 0.00 System ID: 1845791 User-Defined ID: Q #64 Lesson Plan Objective: LGSOPS1550.2 Topic: Reactivity Addition - Low Power Accident RO Importance: 3.8 SRO Importance:
K/A Number: 295014 G2.4.9 LMK DEC 2017 ILT NRC Page: 255 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 1 Group 2 295014 G2.4.9 RO KA # and Rating Importance 3.8 295014 Inadvertent Reactivity Addition / 1 2.4.9 - Emergency Procedures / Plan:
Knowledge of low power /
KA Statement shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.
Cognitive level High Safety Function 1 - Reactivity Control 10 CFR 55 41.10 UFSAR 15.4 0 Technical Reference with Rev Tech Spec 8 Revision No: #:
Bases 3/4.1.1 Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS New NRC-05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 256 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 65 ID: 1845792 Points: 1.00 Unit 2 is operating at 100% power
- 30 minutes ago the Div 1 DC Bus was lost
- The 2A MSL Flow Element Sensing Line Fails such that all the instruments on that line see upscale high flow.
2 minutes later
- Reactor Pressure is 1030 psig up slow
- Reactor Level is -48 inches up slow Which ONE of the following is available to control Reactor Pressure?
A. Main Turbine Bypass Valves B. Steam Spargers C. HPCI CST to CST D. ADS SRVs from AER Answer: D Answer Explanation LMK DEC 2017 ILT NRC Page: 257 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written A Wrong: Plausible to the candidate who doesn't recognize that the failure of the MSL transmitter would cause a full Group I isolation and make the BPV inoperable B Wrong: Plausible to the candidate who either doesn't recognize the Group I isolation or who believes that the Steam spargers would still be operable with the MSIVs closed C Wrong: Plausible to the the candidate who does not consider that level is below -38" and therefore the HPCI initiation signal would prevent placing HPCI in Full Flow test as the F011 valve would automatically close with hi drywell pressure (.1.68#) or low Rx level (-
38").
D Correct: Based on the explanation below for the MSL isolation logic, all MSIVs would receive an isolation signal. With all MSIVs closed, BPVs and Spargers are isolated from the condenser. HPCI is unavailable as noted above. The loss of Div 1 DC would appear to make ADS SRVs unavailable however, these valves can be locally operated from the AER panels or using ADS pushbuttons in the MCR, however this method is not desireable as all 5 ADS SRVs would open.
D/P transmitters (PDTs) (channels 'A', 'B', 'C', 'D') sense the d/p and convert it to a usable signal. Notice that the 4 PTDs are connected to the FE in pairs...e.g., PDTs 'C' & 'D' (a pair) share a common low-pressure sensing tap on the FE and a common high-pressure sensing tap on the FE. (Similar for the other pair, PDTs 'A' & 'B').
This question supposes that "a pressure sensing line on the flow restrictor has ruptured at the tap." Based on the information given in the step and the A Main Steam Flow element indicating off scale high, the failure is such that there is a false UPSCALE flow that is affecting the Flow Transmitter (FT-C32-1N003A in the section of the print provided). Once this is concluded, it can be observed that the A and B flow tranmitters are affected with an UPSCALE flow signal too.
This is sufficient to satisfy the (A or C) AND (B or D) logic to cause ALL 8 MSIVs to isolate on high steam flow.
LMK DEC 2017 ILT NRC Page: 258 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 65 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1845792 User-Defined ID: Q #65 Lesson Plan Objective: LLOT1566.02 Topic: Loss of Heat Sink RO Importance: 3.7 SRO Importance: 3.9 K/A Number: 295020 AK1.01 LMK DEC 2017 ILT NRC Page: 259 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 1 Group 2 KA # and Rating 295020 AK1.01 3.7 / 3.9 Knowledge of the operational implications of the following concepts as they KA Statement apply to INADVERTENT CONTAINMENT ISOLATION: Loss of normal heat sink Cognitive level Lower Safety Function 5, 7 10 CFR 55 41.8 Technical Reference with Rev E-2FA 9 Revision No: #:
Justification for Non SRO CFR Link:
Question History: (i.e. LGS NRC-05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 260 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 66 ID: 1845795 Points: 1.00 Plant conditions:
- Both Units are operating at 100% power
- The entire shift attended the morning Shift Turnover Meeting given by the CRS and Shift Manager At 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br />, the PRO relieves the Unit 2 RO for lunch.
The Unit 2 RO will be eating lunch in the MCR Lunchroom.
WHICH ONE of the following identifies the required MINIMUM turnover activity and the required MAXIMUM duration of the PROs mid-shift turnover, per OP-AA-112-101 (Shift Turnover and Relief)?
A. Read the MCR logs through the last previous day on shift.
The relief duration shall not exceed 30 minutes.
B. Read the MCR logs through the last previous day on shift.
The relief duration shall not exceed 60 minutes.
C. Review the Shift Turnover Checklist and review updated plant status.
The relief duration shall not exceed 30 minutes D. Review the Shift Turnover Checklist and review updated plant status.
The relief duration shall not exceed 60 minutes.
Answer: D Answer Explanation Correct: Review the Shift Turnover Checklist and review updated plant status. The relief duration shall not exceed 60 minutes: Mid-shift turnover of less than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> consists of a review of the Shift Turnover checklist and update of plant status, provided the original watch stander remains in the Main Control Room area Incorrect: Read the MCR logs through the last previous day on shift. The relief duration shall not exceed 30 minutes: Reading the MCR logs through the last previous day on shift applies to a full shift turnover, short turnover duration is 60 minutes, not 30.
Incorrect: Read the MCR logs through the last previous day on shift. The relief duration shall not exceed 60 minutes: Duration is correct, turnover criteria described applies to full turnover, not short duration Incorrect: Review the Shift Turnover Checklist and review updated plant status. The relief duration shall not exceed 30 minutes: Turnover criteria is correct, short turnover duration is 60 minutes, not 30.
LMK DEC 2017 ILT NRC Page: 261 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 66 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1845795 User-Defined ID: Q #66 Lesson Plan Objective: LGSOPS2010.24B Topic: OP-AA-112-101 - Recall Shift Turnover requirements RO Importance: 3.7 SRO Importance: 3.9 K/A Number: 2.1.3 LMK DEC 2017 ILT NRC Page: 262 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 3 Group KA # and Rating G 2.1.3 3.7 / 3.9 Knowledge of shift or KA Statement short-term relief turnover practices.
Cognitive level Lower Safety Function 10 CFR 55 41.10 Technical Reference with Rev 1 OP-AA-112-101 Revision No: #: 2 Justification for Non SRO CFR Link:
Question History: (i.e. LGS NRC-05, LGS ILT07-1 NRC-05, OYS CERT-04) CERT Question Source: (i.e. New, Bank 591149 Bank, Modified)
Low KA Justification (if required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments Previous Question #591149 LMK DEC 2017 ILT NRC Page: 263 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 67 ID: 1845800 Points: 1.00 Unit 2 is in OPCON 5 with Core Shuffle 2 in progress.
- The 2A SRM is bypassed
- The 2D SRM is INOP due to spiking WHICH ONE of the following identifies a core location where a fuel assembly may be inserted, if any, for the above conditions?
A. 35-06 B. 27-56 C. 07-18 D. No locations LMK DEC 2017 ILT NRC Page: 264 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Answer: A Answer Explanation From the stem the candidate determines that the 2A and 2D SRMs are INOP. Using this information, attachment 1 from NF-LG-310-2000 provided, and their knowledge of Tech Spec LCO 3.9.2 they determine that core alterations can continue in the B and C quadrants. Only 35-06 is in a quadrant where core alterations can continue.
A Correct for the above reasons B Wrong - plausible to the candidate that incorrectly uses attachment 1 (SRM Locations, Fuel Assembly coordinates, etc.)
C Wrong - plausible to the candidate that incorrectly uses attachment 1 (SRM Locations, Fuel Assembly coordinates, etc.)
D Wrong - plausible to the candidate the incorrectly applies Tech Spec 3.3.7.6.a where 3 SRMs are required to be operable for startup with IRMs on range 2 or below.
LMK DEC 2017 ILT NRC Page: 265 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 67 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1845800 User-Defined ID: Q #67 Lesson Plan Objective: LGSOPS1800. 5A Topic: Refueling Administrative requirements RO Importance: 2.8 SRO Importance:
K/A Number: G2.1.40 LMK DEC 2017 ILT NRC Page: 266 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 3 Group KA # and Rating G2.1.40 RO Importance 2.8 G2.1.40 Knowledge of KA Statement refueling administrative requirements Cognitive level High Safety Function N/A 10 CFR 55 41.10 Technical Reference with Tech Specs Rev Revision No: LCO 3.9.2 #:
Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS New NRC-05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 267 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 68 ID: 1845797 Points: 1.00 WHICH ONE of the following identifies the Unit 1 and Unit 2 RHR Loops used for alternate injection using RHRSW?
Unit 1 RHR Loop Unit 2 RHR Loop A. A A B. A B C. B A D. B B Answer: C Answer Explanation A Wrong: Plausible to the candidate who does not recall the connections for RHRSW to Unit 1 and 2 B Wrong: Plausible to the candidate who does not recall the connections for RHRSW to Unit 1 and 2 C Correct: Unit 1 = "0B" RHRSW via "1B" Loop RHR Unit 2 = "0A" RHRSW via "2A" Loop RHR T-243 ALTERNATE INJECTION BY WAY OF RHRSW TO RHR LOOP "B" for Unit 1 and LOOP "A" for Unit 2 D Wrong: Plausible to the candidate who does not recall the connections for RHRSW to Unit 1 and 2 LMK DEC 2017 ILT NRC Page: 268 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 68 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1845797 User-Defined ID: Q #68 Lesson Plan Objective: LLOT1870.1 Identify the Unit 1 and Unit 2 injection points for the alternate Topic:
injection subsystems RO Importance: RO 3.1 SRO Importance: SRO 3.3 K/A Number: K/A 2.2.3 LMK DEC 2017 ILT NRC Page: 269 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 3 Group KA # and Rating G 2.2.3 Knowledge of the design, procedural, and KA Statement operational differences between units.
Cognitive level Low Safety Function 10 CFR 55 41.5 1
Technical Reference with Rev 6/
T-243 U1/2 Revision No: #: 1 2
Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS Modified 561574 2002 NRC NRC-05, OYS CERT-04)
Question Source: (i.e. New, Modified 561574 Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision Changed question to History: (i.e. Modified address RHRSW only to distractor b to make avoid overlap with T-244 plausible based on OTPS inplant JPM.
review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 270 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 69 ID: 1845878 Points: 1.00 Unit 1 is operating at 100% power
- RCIC failed a surveillance test resulting in RCIC being declared INOPERABLE and UNAVAILABLE
- RCIC return to operable is expected to be 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> WHICH ONE of the following correctly identifies (1) the location of required protected equipment postings for the HPCI system and (2) if access near the HPCI system while it is protected is permitted for an Operator performing rounds, inspections, and alarm response?
Location of HPCI protection postings Access for Operator permitted A. In the field ONLY No B. In the field ONLY Yes C. Main Control Room and in the field No D. Main Control Room and in the field Yes Answer: D Answer Explanation LMK DEC 2017 ILT NRC Page: 271 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written From OP-AA-108-117 A Wrong - plausible to the candidate the fails to recall that OP-AA-108-117 required protection in the field in addition to remote locations (they may assume that the MCR Operators are already aware of the importance of maintain the equipment available) and plausible to the candidate that fails to recall that Operator performing rounds, inspections and alarm response are exempted B Wrong - plausible to the candidate the fails to recall that OP-AA-108-117 required protection in the field in addition to remote locations (they may assume that the MCR Operators are already aware of the importance of maintain the equipment available)
C Wrong - plausible to the candidate that fails to recall that Operator performing rounds, inspections and alarm response are exempted D Correct for the above reasons LMK DEC 2017 ILT NRC Page: 272 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 69 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1845878 User-Defined ID: Q #69 Lesson Plan Objective: LGSOPS2010.29.A Topic: Recall Protected Equipment process requirements RO Importance: 3.9 SRO Importance: 4.3 K/A Number: 2.2.14 LMK DEC 2017 ILT NRC Page: 273 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments:
General Data Level RO Tier 3 Group N/A KA # and Rating 2.2.14 3.9 / 4.3 Knowledge of the process for controlling KA Statement equipment configuration or status.
Cognitive level Low Safety Function 10 CFR 55 41.10 Technical Reference with Rev OP-AA-108-117 4 Revision No: #:
Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS New NRC-05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 274 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 70 ID: 1846054 Points: 1.00 An Operator is performing work in the RCA. Their Electronic Dosimeter (ED) alarm set points are set at the upper limit values per RP-AA-403 (Administration of RWPs).
WHICH ONE of the following identifies the ED Alarm set points for Dose Limit and Dose Rate Limit?
Dose Limit Alarm Setpoint Dose Rate Limit Alarm Setpoint A. 20 mR 80 mR/hr B. 20 mR 400 mR/hr C. 40 mR 80 mR/hr D. 40 mR 400 mR/hr Answer: D Answer Explanation LMK DEC 2017 ILT NRC Page: 275 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written The candidate is asked to recall the RWP set points when set to the upper limit of RP-AA-403.
From RP-AA-403, section 4.4.3:
Distractor values are taken from step 4.4.2 of the same procedure.
A Wrong - plausible if the candidate recalls the ED setpoint for both the Dose and Dose Rate from the wrong section of RP-AA-403 B Wrong - plausible if the candidate recalls the ED setpoint for the Dose from the wrong section of RP-AA-403 C Wrong - plausible if the candidate recalls the ED setpoint for the Dose Rate from the wrong section of RP-AA-403 D Correct for the above reasons.
LMK DEC 2017 ILT NRC Page: 276 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 70 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1846054 User-Defined ID: Q #70 Lesson Plan Objective: LLOT1760.8 Topic: RP-AA-403 - Recall RWP ED alarm setpoints for Operators RO Importance: 3.5 SRO Importance:
K/A Number: G2.3.7 LMK DEC 2017 ILT NRC Page: 277 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 3 Group KA # and Rating G2.3.7 RO Importance 3.5 G2.3.7 Ability to comply with radiation work permit KA Statement requirements during normal or abnormal conditions.
Cognitive level Low Safety Function 10 CFR 55 41.12 Technical Reference with Rev RP-AA-403 9 Revision No: #:
Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS Bank 986626 NRC-05, OYS CERT-04)
Question Source: (i.e. New, Bank 986626 Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified Re-wrote stem and distractor b to make changed structure to 2 X 2 plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 278 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 71 ID: 1846357 Points: 1.00 A Steam Leak occurs at the Main Turbine. The following condition is present:
- Turbine Building Ventilation is shutdown WHICH ONE of the following identifies the reason for restarting Turbine Enclosure Ventilation IAW T-104, "Radioactivity Release Control"?
A. Ensures radioactive release through elevated, monitored release point B. Maintain negative pressure in the Turbine Enclosure C. Provide a filtered release path to the environment D. Ensure max safe temperature limits are NOT reached Answer: A Answer Explanation Justification:
A. Correct: T-104 Bases states that the continued personnel access to the Turbine Enclosure and/or Radwaste Enclosure may be essential for responding to emergencies or transients which may degrade into emergencies. These areas are not always airtight structures, and a radioactivity release inside the structure would not only limit personnel access, but could eventually lead to an unmonitored ground level release. Operation of the respective HVAC system preserves accessibility and ensures radioactive discharges will be released through elevated, monitored release points.
B. Incorrect but plausible: Plausible, if the applicant determines that turbine building ventilation needs to be restarted to maintain negative pressure to prevent release to the environment C. Incorrect but plausible: Plausible, if the applicant determines that bases behind starting the turbine building ventilation is to provide a filtered path to the environment via north stack, since turbine building ventilation exhaust to the north stack, however the basis is to provide a monitored release path not filtered release path.
D. Incorrect but plausible: Plausible, if the applicant determines that due to the steam leak and blowout panel actuation, temperature in the turbine building is a concern and as a result turbine building is restarted to decrease temperature LMK DEC 2017 ILT NRC Page: 279 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 71 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1846357 User-Defined ID: Q #71 Lesson Plan Objective: LLOT1560 OBJ. 5 Topic: T-104 reason for re starting TE HVAC RO Importance: 3.8 SRO Importance: 3.8 K/A Number: G2.3.11 LMK DEC 2017 ILT NRC Page: 280 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 3 Group KA # and Rating 2.3.11 Ability to control KA Statement radiation releases Cognitive level Lower Safety Function 10 CFR 55 41.11 1
Technical Reference with T-104 Bases Rev 4 Revision No: T-104 #: 1 3
Justification for Non SRO CFR Link:
Question History: (i.e. LGS 2012 ILT NRC #71 NRC-05, OYS CERT-04)
Question Source: (i.e. New, Bank 1099858 Bank, Modified)
Low KA Justification (if required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments 2012 ILT NRC-71 Bank 1099858 LMK DEC 2017 ILT NRC Page: 281 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 72 ID: 1846393 Points: 1.00 The following conditions exist for Unit 1:
RPV Level is Unknown Reactor Power is 9%
T-116 Step RF-18 is being executed WHICH ONE of the following identifies conditions when the Operators are directed to continue and the bases for prioritizing this steps performance by the use of "IMMEDIATELY"?
Conditions requiring continuing Bases for step priority A. 3 SRVs Open and adequate core cooling has been lost RPV Pressure 450 psig B. 3 SRVs Open and RPV is now flooded to the Main Steam RPV Pressure 450 psig Lines C. 2 SRVs Open and adequate core cooling has been lost RPV Pressure 575 psig D. 2 SRVs Open and RPV is now flooded to the Main Steam RPV Pressure 575 psig Lines Answer: C Answer Explanation LMK DEC 2017 ILT NRC Page: 282 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written From the stem the candidate determines that T-116 Step RF-18 directs the performer to Immediately Continue when RPV Pressure drops below conditions of Table RF-1. (Note "MIN STM COOLING" has been covered up in the stem versions of this step)
From the bases of T-116 RF-18:
A Wrong - Plausible to the candiate that mis-interprets Table RF-1 B Wrong - Plausible to the candiate that mis-interprets Table RF-1 and plausible to the candidate that confuses the bases for RF-18 with the actions of non-ATWS section of T-116 step RF-35, where the operators are directed to maintain RPV injection as low as possible while maintaining the RPV flooded - this is palusible to the candiate that belives the main concern is damage to SRVs and tailpipes when injection is not reduced once the Main Steam Lines are flooded.
C Correct for the above reasons D Wrong - Plausible to the candidate that confuses the bases for RF-18 with the actions of non-ATWS section of T-116 step RF-35, where the operators are directed to maintain RPV injection as low as possible while maintaining the RPV flooded - this is palusible to the candiate that belives the main concern is damage to SRVs and tailpipes when injection is not reduced once the Main Steam Lines are flooded.
LMK DEC 2017 ILT NRC Page: 283 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 72 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1846393 User-Defined ID: Q #72 Lesson Plan Objective: LGSOPS1560.5 Topic: Emergency Procedure Prioritization bases RO Importance: 3.4 SRO Importance:
K/A Number: G2.4.23 LMK DEC 2017 ILT NRC Page: 284 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 3 Group KA # and Rating G2.4.23 RO Importance 3.4 G2.4.23 Knowledge of the bases for prioritizing KA Statement emergency procedure implementation during emergency operations.
Cognitive level High Safety Function 10 CFR 55 41.10 Technical Reference with Rev 1 T-116 Bases Revision No: #: 4 Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS New NRC-05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 285 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 73 ID: 1846438 Points: 1.00 Initial Unit 1 plant conditions:
- Reactor power is 75%
- RPV pressure is 1009 psig
'1B' Outboard MSIV fails closed.
Current conditions:
- Reactor power is 77%
- Reactor pressure is 1045 psig WHICH ONE of the following describes the required immediate operator action, if any?
A. No Immediate Operator Action required B. Reduce Reactor power to 75%
C. Open BPV Jack until Reactor Pressure is 1009 psig D. Reduce Reactor Power until Reactor Pressure is 1009 psig Answer: B Answer Explanation From the stem the candidate identifies that Reactor Power and Reactor Pressure have risen as a result of the closure of the 1B MSIV. This requires entry into OT-102, Reactor High Pressure (due to Unexpected/ Unexplained rise in Reactor Pressure) and entry into OT-104, Unexpected/
Unexplained Positive or Negative Reactivity Insertion. Of these two procedures, the only Immediate Operation Action (IOA) that applies is OT-104 step 2.1 to reduce reactor power to maintain reactor power at or below the initial pre-transient level.
A Wrong - plausible to the candidate that fails to recall the OT-104 IOA to reduce power to the pre-transient level (in this case 75%) or confuses this with the followup action from OT-102 for a close MSIV to reduce power to 75% (OT-102 Attachment 1 step 1)
B Correct for the above reasons C Wrong - plausible to the candidate the confuses the IOA of the OT-104 and OT-102 and believes that the OT-102 IOA is to reduce Reactor Pressure to or below the pre-transient pressure. (Using BPVs as described in OT-102 step 2.2)
D Wrong - plausible to the candidate the confuses the IOA of the OT-104 and OT-102 and believes that the OT-102 IOA is to reduce Reactor Pressure to or below the pre-transient pressure. (as described in OT-102 step 2.1)
LMK DEC 2017 ILT NRC Page: 286 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 73 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1846438 User-Defined ID: Q #73 Lesson Plan Objective: LLOT1540.02 Topic: OT-104 - Recall IOAs RO Importance: 4.6 SRO Importance: 4.4 K/A Number: 2.4.49 LMK DEC 2017 ILT NRC Page: 287 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 3 Group KA # and Rating G2.4.49 RO Importance 4.6 2.4.49 Ability to perform without reference to procedures those actions KA Statement that require immediate operation of system components and controls.
Cognitive level Low Safety Function 10 CFR 55 41.10 2
Technical Reference with OT-102 Rev 7 Revision No: OT-104 #: 5 3
Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS Modified 1006627 (LGS NRC-05, OYS CERT-04) 2012 CERT)
Question Source: (i.e. New, Modified 1006627 Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 288 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 73 Table-Item Links NRC EXAM - 10 CFR 55 Operators' Licenses CFR: 41.10 Administrative, normal, abnormal, and emergency operating procedures for the facility.
NRC EXAM - NUREG 1021 Question Cognitive Level Memory or Fundamental Knowledge - (F)undamental LMK DEC 2017 ILT NRC Page: 289 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 74 ID: 2029209 Points: 1.00 Unit 1 is operating at 100% power when a FWLCS trouble alarm occurs with the below indications:
Shortly thereafter, a lowering main condenser vacuum forces operators to successfully insert a manual scram using RPS.
WHICH ONE of the following identifies:
(1) the mode of level control (Single-element/Three-element), prior to the scram and (2) whether or not the Scram Profile will activate in response to the scram?
A. (1) Single-element (2) Scram Profile will activate B. (1) Single-element (2) Scram Profile will NOT activate C. (1) Three-element (2) Scram Profile will activate D. (1) Three-element (2) Scram Profile will NOT activate LMK DEC 2017 ILT NRC Page: 290 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Answer: A Answer Explanation A Correct: The candidate should discover from the included screen shot that 3 out of 4 Steam Flow Transmitters have failed downscale. Also, a Soft Majority Select Error occurs.
The candidate should recal from S06.1.H U/1, Attachment 1 Alarm List, specifically Signal Identity 1XX-FW301.ISFE. There, we find that the Steam flow Error SMS means that 3 of 4 Steam flow error signals means that FWLCS will operate in single element as steam flow in no longer available as the 3rd input. When a scram occurs and DFWLCS sees both RPS subsystems de-energize, it will force level control into post scram profile and 3 element mode. This mode will hold feedflow constant for 10 seconds and then ramp feedflow to 10% at 6% per second and then hold flow until scram profile de-activates per S06.1.D. This happens under all conditions except for a total Feedflow error (TFFE).
B Wrong: Plausible to the candidate who recognizes that DFWLC will swap to single but believes that scram profile is not available due to the failure mechanism.
C Wrong: Plausible to the candidate who does not recognize the conditions of total steam flow error and believes that the system remains in 3 element and scram profile will function.
D Wrong: Plausible to the candidate who believes that the system will remain in 3 element with the single steam flow transmitter but will not support scram profile.
LMK DEC 2017 ILT NRC Page: 291 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 74 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 2029209 User-Defined ID: Q #74 Lesson Plan Objective: LLOT0550,11 Topic: Steam Flow Transmitter Failure - Predict Plant response RO Importance: 3.9 SRO Importance: 3.8 K/A Number: G 2.1.19 LMK DEC 2017 ILT NRC Page: 292 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 3 Group KA # and Rating G2.1.19 RO Importance 3.9 G2.1.19 Ability to use plant KA Statement computers to evaluate system or component status.
Cognitive level High Safety Function 10 CFR 55 41.10 1
S06.1.H U/1 4 Technical Reference with S06.1.D U/1 Rev 2 Revision No: S06.1.D Appx 1 #: 3 U/1 1 6
Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS Modified Bank 976742 NRC-05, OYS CERT-04)
Question Source: (i.e. New, Bank Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision Removed direct statement History: (i.e. Modified of Steam Flow failure and distractor b to make provided FWLCS screen plausible based on OTPS shot requiring candidate to review) interpret picture ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 75 ID: 1846505 Points: 1.00 Fuel Shuffle Part 1 is underway on Unit 2 with the following conditions:
- Spent Fuel Pools are not cross-connected
- Unit 2 Refuel Bridge is moving fuel from the Unit 2 core to the Unit 2 SFP
- Reactor Level is 494" Reactor Well Seals #3 and #4 fail and current Reactor Cavity level is 475" and down slow (approximately 1"/30 minutes). All normal make-up sources have failed to inject and the CRS directs injecting with "C" LPCI.
Which ONE of the following identifies the approximate amount of time required to restore Reactor Level to 494" with rated LPCI flow?
A. 4 minutes B. 5 minutes 30 seconds C. 6 minutes 15 seconds D. 8 minutes 30 seconds Answer: B Answer Explanation LMK DEC 2017 ILT NRC Page: 294 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written From the stem the candidate determines there is a leak from the reactor cavity and ON-120 should be implemented. Also from the stem the candidate determines that Cavity Level needs to be raised 19". LPCI rated injection rate is 10,000 GPM.
Per the attached note from ON-120, with the fuel pools not cross-connected, the volume per inch is 2865 gal/inch. Since level has dropped 19", the volume to make up is 19 x 2865 = 54,435 gallons. LPCI is rated for 10,000 gpm, so operation for approx. 5 minutes and 30 seconds would restore reactor level.
A Wrong - plausible to the candidate that incorrectly uses the volume of the reactor cavity and dryer/separator storage pool only B Correct for the above reasons C Wrong - plausible to the candidate that incorrectly uses the volume of the reactor cavity and dryer/separator storage pool only and uses the rated flow rate for a loop of Core Spray (6,350 GPM)
D Wrong - plausible to the candidate that incorrectly uses the rated flow rate for a loop of Core Spray (6,350 GPM)
LMK DEC 2017 ILT NRC Page: 295 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 75 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1846505 User-Defined ID: Q #75 Lesson Plan Objective: LGSOPS1550.3 Topic: Refueling - lowering cavity level RO Importance: 3.8 SRO Importance:
K/A Number: G2.4.9 LMK DEC 2017 ILT NRC Page: 296 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level RO Tier 3 Group KA # and Rating G2.4.9 RO Importance G2.4.9 Knowledge of low power / shutdown implications in accident KA Statement (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.
Cognitive level High Safety Function 10 CFR 55 41.10 Technical Reference with Rev 2 ON-120 Revision No: #: 8 Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS Bank 833372 NRC-05, OYS CERT-04)
Question Source: (i.e. New, Bank 833372 Bank, Modified)
Low KA Justification (if required):
Added rate of level lowering Revision History: Revision (1"/30min) to inform the History: (i.e. Modified candidate that rate of level distractor b to make lowering is negligible for plausible based on OTPS this question. Added table review) from ON-120.
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #) .
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 297 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 76 ID: 1743064 Points: 1.00
- SRO ONLY**********
Unit 2 is in OPCON 4 with the following conditions:
- The reactor has been shutdown for 20 days
- "2A" RHR pump is operating in Shutdown Cooling Mode
- "2B" RHR pump is inoperable and unavailable
- RPV water temperature is currently 120° F At time 14:00, a loss of 2A-Y160 occurs At time 14:20 RPV coolant temperature is 130° F and rising slowly WHICH ONE of the following describes the required operator action, and the estimated time when Rx Enclosure Secondary Containment is required?
Time when RE Sec. Containment Required Action Required per TS LCO 3.6.5.1.1 A. Perform attachment 1 of ON-121 for 16:40 loss of 2A-Y160 B. Perform attachment 1 of ON-121 for 17:00 loss of 2A-Y160 C. Place "2C" RHR in Shutdown Cooling per 16:40 S51.8.H, Use of Dedicated LPCI Pumps for Shutdown Cooling/Reactor Coolant Circulation Operation D. Place "2C" RHR in Shutdown Cooling per 17:00 S51.8.H, Use of Dedicated LPCI Pumps for Shutdown Cooling/Reactor Coolant Circulation Operation Answer: A Answer Explanation LMK DEC 2017 ILT NRC Page: 298 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Source for 212 °F distractor:
a Correct: ON-121 directs the performance of Attachment 1 for The Loss of 2AY160.
This will jumper power to the valve open contactors of the Inboard isolation valve (009) and allow reset of the isolation to the outboard valve. This will allow restoration of SDC.
With the loss of cooling and the provided temperature changes, the candidate should calculate the heatup rate as 30°F per hour. With a starting point of 120°F, this means 200°F will be reached in 2.66667 hours or 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 40 minutes (time 16:40). At 200°F, a mode change occurs from mode 4 to mode 3 and secondary containment is required to be operable per Tech spec. 3.6.5.1.1. ON-121 step 2.1.3 also reminds the operator that secondary containment is required prior to changing modes.
b Wrong: Plausible to the candidate who calculates the heat up rate to 212° (Tech Spec 3.10.8 instead of 200°F.
c Wrong: Plausible to the candidate who fails to consider that the loss of 2AY160 would not allow the use of the same suction flowpath.
d Wrong: Plausible to the candidate who fails to consider that the loss of 2AY160 would not allow the use of the same suction flowpath and who calculates the time to 212°F.
LMK DEC 2017 ILT NRC Page: 299 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 76 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1743064 User-Defined ID: Q #76 Lesson Plan Objective: LGSOPS1550.02 (ON-121)
Topic: (SRO Only) Loss of SDC and Time to Boil RO Importance: 3.6 SRO Importance: 3.6 K/A Number: 295021 AA2.01 LMK DEC 2017 ILT NRC Page: 300 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level SRO Tier 1 Group 1 KA # and Rating 295021 AA2.01 3.5 / 3.6 Ability to determine and/or interpret the following as they apply to LOSS OF KA Statement SHUTDOWN COOLING:
Reactor water heatup/cooldown rate Cognitive level Hi Safety Function 4 10 CFR 55 CFR: 43.5 (b)(5)
Technical Reference with Rev 3 ON-121 Revision No: #: 2 Justification for Non SRO CFR Link:
Question History: (i.e. LGS NRC-05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 301 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 77 ID: 1744158 Points: 1.00
- SRO ONLY**********
Plant conditions are as follows:
- Suppression Pool temperature is 255° F
- Suppression Pool pressure is 14.8 psig up slow
- Suppression Pool level is 31.5 feet Given the above conditions: What actions are required per T-225, "Startup and Shutdown of Drywell and Suppression Pool Spray", regarding Drywell Spray?
LMK DEC 2017 ILT NRC Page: 302 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written A. Spray the Drywell with RHR with No Limitations B. Spray the Drywell with RHR Flow <9000 GPM to prevent exceeding NPSH Limits C. Spray the Drywell with RHRSW because RHR NPSH Limits are exceeded D. Don't Spray the Drywell, Suppression Pool Level is too high Answer: C Answer Explanation LMK DEC 2017 ILT NRC Page: 303 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written A Incorrect, plausible to the candidate who reads the RHR pump NPSH curve and interprets the area above the line as safe for pump operation and sprays.
B Incorrect plausible to the candidate who uses the top curve for S.P. pressure and determines that flow below 9000 GPM is acceptable.
C Correct, Spray the drywell with RHRSW as RHR is unavailable because SP Temperature is unsafe for NPSH. RHRSW should be used since level in Supp. Pool is below the high SP level requiring securing of drywell sprays. (37.4')
D Incorrect, Plausible to the candidate who reads the NPSH curve correctly but fails to recall the level at which Drywell Spray should be secured. Per T-102, SP/L-17, when SP water level > 37.4 ft, then SP spray should be secured. Above that level, the vacuum breakers would be obstructed and prevent pressure equalization between drywell and suppression pool.
LMK DEC 2017 ILT NRC Page: 304 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 77 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1744158 User-Defined ID: Q #77 NEW Lesson Plan Objective: LGSOPS0051.20 Topic: SRO Only - Suppression Pool Temperature RO Importance: 4.1 SRO Importance: 4.1 K/A Number: 295024 EA2.06 LMK DEC 2017 ILT NRC Page: 305 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level SRO Tier 1 Group 1 KA # and Rating 295024 EA2.06 4.1 / 4.1 Ability to determine and/or interpret the following as KA Statement they apply to HIGH DRYWELL PRESSURE:
Suppression pool temperature Cognitive level higher Safety Function 5 10 CFR 55 43.5(b)(5)
Re Technical Reference with T-102 v 25 Revision No:
Justification for Non SRO N/A CFR Link:
Question History: (i.e.
Question Source: (i.e.
New New, Bank, Modified)
Low KA Justification (if N/A required):
Revision History:
Revision History: (i.e.
Modified distractor b to N/A make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section:
(i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 306 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 78 ID: 1744190 Points: 1.00
- SRO ONLY************
Plant conditions:
- Both Units are operating at 100% power
- 10 Station Aux Bus Feeder Breaker, 105, tripped 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago and the associated offsite source was declared INOPERABLE
- All 8 Safeguard Buses are aligned to the 201 Bus The TSO notifies LGS that the 500 KV Substation voltage is 497 KV.
WHICH ONE of the following identifies the Tech Spec required action?
A. Restore one offsite circuit to OPERABLE within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and the second offsite circuit to OPERABLE within 68 hours7.87037e-4 days <br />0.0189 hours <br />1.124339e-4 weeks <br />2.5874e-5 months <br />.
B. Restore the 10 Bus Source to OPERABLE within 68 hours7.87037e-4 days <br />0.0189 hours <br />1.124339e-4 weeks <br />2.5874e-5 months <br /> and the 20 Bus Source to OPERABLE within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
C. Restore one AC source to OPERABLE within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and the second offsite circuit to OPERABLE within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
D. Within one hour take action to place both units in STARTUP within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Answer: A Answer Explanation LMK DEC 2017 ILT NRC Page: 307 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written The voltage provided in the stem would be the result of Grid Disturbance.
A Correct: With one (1) offsite circuit INOPERABLE with either unit in OPCONS 1, 2 OR 3, the INOPERABLE offsite circuit must be restored to OPERABLE within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> per Tech Spec 3.8.1, action "f'. With the MAX GRID EMERGENCY GENERATION action entered and 500 KV Substation less than 498 KV, the 20 Bus Source must be declared INOPERABLE per E-5, Grid Emergency. With two (2) offsite circuits INOPERABLE, Tech Spec 3.8.1, action "g" applies. Action "g" requires restoration of at least one (1) offsite circuit within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and two (2) offsite circuits restored to OPERABLE within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from the initial loss. Since the first loss occurred 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> previous, per the tech spec action, the second source must be restored within 68 hours7.87037e-4 days <br />0.0189 hours <br />1.124339e-4 weeks <br />2.5874e-5 months <br /> (72-4=68).
B Wrong: Plausible to the candidate who misreads 3.8.1.f and believes that each offsite source can be INOP for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> C Wrong: Plausible to the candidate who believes 1 offsite source and 2 EDGs are INOP and this would make action 3.8.1.h. plausible. The candidate could determine that the 20 bus was not INOP but the loss of the 10 bus, which resulted in auto start of the and start of the EDGs INOPed 1 offsite source and 2 EDGs.
D Wrong: Plausible to the candidate who believes that both offsite sources and 2 EDGs are INOP. No action exists in section 3.8.1 for this condition and therefore the actions of 3.0.3 would apply.
LMK DEC 2017 ILT NRC Page: 308 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 78 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1744190 User-Defined ID: Q #78 Lesson Plan Objective: LGSOPS0036A.2 Topic: (SRO Only) - Both Offsite Sources INOP RO Importance: 3.2 SRO Importance: 3.8 K/A Number: 700000 AA2.05 LMK DEC 2017 ILT NRC Page: 309 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments:
General Data Level SRO Tier 1 Group 1 KA # and Rating 700000 AA2.05 Ability to determine and/or interpret the following as they apply to GENERATOR VOLTAGE KA Statement AND ELECTRIC GRID DISTURBANCES:
Operational status of offsite circuit Cognitive level Higher Safety Function 6 10 CFR 55 CFR: 43.5 (b)(2)
Technical Reference with Rev 2 E-5 Revision No: #: 3 Justification for Non SRO CFR Link:
Question History: (i.e. LGS Bank 633775 NRC-05, OYS CERT-04)
Question Source: (i.e. New, Bank Bank, Modified)
Low KA Justification (if required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 310 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 79 ID: 1744191 Points: 1.00
- SRO ONLY**********
Both Unit 1 and Unit 2 are at 100% power with the following equipment out of service:
- 0D ESW Pump - was declared INOP 2 days ago D12 EDG was started for ST-6-092-312-1, D12 Diesel Generator Slow Start Operability Test Run.
- The PRO identifed that the associated ESW Pump was not running 1 minute and 20 seconds after the D12 EDG start. The PRO successfully started the associated ESW Pump manually using the MCR handswitch.
For the above conditions, what is the most limiting Tech Spec Action?
A. Restore the inoperable pump to OPERABLE status within 43 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
B. Restore at least one inoperable pump to OPERABLE status within 30 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
C. Restore the inoperable loop to OPERABLE status with at least one OPERABLE pump within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
D. Within one hour initiate action to place the unit in an OPERATIONAL CONDITION in which the Specification does not apply by placing it in at least STARTUP within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and at least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Answer: C Answer Explanation LMK DEC 2017 ILT NRC Page: 311 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written A Wrong, plausible to the candidate that fails to declare the 0B ESW Pump INOP (believes that since is was successfully started it remains Operable) and applies a continuation of Tech Spec 3.7.1.2 action a.1.
B Wrong, plausible to the candidate that confuses the associated ESW loop being impacted by the loss of the 0B ESW pump and believes that the 0D is in the other loop ESW cooling loop.
C Correct: From the stem, 0D ESW Pump is INOP. TS 3.7.1.2 action a applies. Also from the stem, during the D12 EDG start the associated ESW Pump failed to auto start (should have started at ~55 seconds, during the time between the auto start failure and the manual start of the 0B ESW Pump, the B ESW Loop experienced a complete loss of Component Cooling Water (CCW)). For D12 the candidate determines that the associated ESW Pump is the 0B ESW Pump.
Tech Spec surveillance requirement 4.7.1.2.b.2 requires ESW pumps to start automatically when its associated diesel generator starts.
D Wrong, plausible to the candidate that fails to determine that Tech Spec action 3.7.1.2.a.3 applies to 2 ESW pumps INOP in the same loop and incorrectly applies Tech Spec 3.0.3.
Since the 0B ESW Pump failed to automatically start, Tech spec 4.0.1 requires the 0B ESW Pump to be declared INOP.
0B and 0D ESW Pumps both support the B ESW Loop. With both ESW Pumps in the 0B ESW Loop INOP, Tech Spec Action 3.7.1.2.a.3 applies.
LMK DEC 2017 ILT NRC Page: 312 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 79 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1744191 User-Defined ID: Q #79 Lesson Plan Objective: LLOT1870.01I Topic: SRO Only degraded ESW and affect on Operability RO Importance: 3.6 SRO Importance: 4.6 K/A Number: G.2.2.37 LMK DEC 2017 ILT NRC Page: 313 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level SRO Tier 2 Group 1 KA # and Rating 295018 G.2.2.37 SRO 4.6 295018 Partial or Complete Loss of Component Cooling Water KA Statement G.2.2.37 Ability to determine operability and/or availability of safety related equipment.
Cognitive level High Safety Function 8- Plant Service Systems 10 CFR 55 43 (b)(2)
Technical Reference with Rev T.S.3.7.1.2 Revision No: #:
Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS New NRC-05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If Tech Spec 3.7.1.2 (Pages appropriate): (i.e. ABN-##) 3/4 7-3 and 7-4)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 314 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 80 ID: 1744192 Points: 1.00
- SRO ONLY*********
Both Units are at 100% power when the following occurs:
- A Loss of All Offsite Power
- All Unit 1 Diesel Generators have failed to start
- Unit 1 Reactor level is -40" and rising
- S55.1.D, HPCI System Full Flow Functional Test
- S55.2.A, HPCI Shutdown From Automatic or Manual Initiation WHICH ONE of the following describes 1) the instrument that can be used to determine Unit 1 Reactor pressure per E-1, Station Blackout and 2) what time critical action the crew must take?
Instrument Used Time Critical Action A. "A" PAMS, XR-42-1R623A Swap HPCI suction to the Suppression Pool per S55.1.D B. "A" PAMS, XR-42-1R623A Shutdown HPCI per S55.2.A C. RCIC Steam Pressure, PI-49-1R602 Swap HPCI suction to the Suppression Pool per S55.1.D D. RCIC Steam Pressure, PI-49-1R602 Shutdown HPCI per S55.2.A Answer: D Answer Explanation LMK DEC 2017 ILT NRC Page: 315 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written The Station Blackout is described in section 15.12 of the LGS USFAR Chapter 15 - Accident Analysis.
Station blackout is addressed by Limerick procedure E-1, Loss of all AC Power (Station Blackout)
During a station blackout very few instruments remain available for monitoring the reactor during the accident. They are identified by E-1.
From E-1 BASES The following RPV pressure instruments are available during a station blackout:
PI-42-*R605 WR PI-55-*R602 HPCI (available)
LMK DEC 2017 ILT NRC Page: 316 of 410 21 December 2017 PI-49 *R602 RCIC (available)
A. Incorrect but plausible to the candidate who remembers that "A" PAMS is a EQ Post
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written LMK DEC 2017 ILT NRC Page: 317 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 80 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1744192 User-Defined ID: Q #80 Lesson Plan Objective: LGSOPS2000.02 (SRO Only) Determine RPV pressure instr. available during a Topic:
Station Blackout and Required Actions RO Importance:
SRO Importance: 3.9 K/A Number: 295025 G.2.4.3 LMK DEC 2017 ILT NRC Page: 318 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level SRO Tier 1 Group 1 KA # and Rating 295025 G.2.4.3 High Reactor Pressure:
KA Statement Ability to identify post-accident instrumentation Cognitive level Lower Safety Function 3 10 CFR 55 43(b)(5)
Technical Reference with Rev 5 SE-1 Revision No: #: 0 Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS New NRC-05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 319 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 81 ID: 1744196 Points: 1.00
- SRO ONLY*********
Unit 2 was at 100% power when a FWLCS failure occurred.
- During the failure RPV level was as low as -60".
- The Reactor Mode Switch was placed in Shutdown when RPV Level was -20"
- Reactor Power is steady at 45%
In this event, 1) What is the basis for the RPS Setpoint that was exceeded first and 2) when is HPCI required to be secured?
Setpoint Basis When HPCI required to be secured A. Assure that there is adequate protection HPCI is required to be secured immediately for the fuel B. Assure that there is adequate protection HPCI is permitted to continue injecting for the fuel until T-270 is directed C. Reduce the amount of energy being HPCI is required to be secured immediately added to the coolant D. Reduce the amount of energy being HPCI is permitted to continue injecting added to the coolant until T-270 is directed Answer: B Answer Explanation LMK DEC 2017 ILT NRC Page: 320 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written From the stem the candidate determines that the RPV Low Level RPS setpoint (12.5") was exceeded and the reactor should have shutdown. Also from the stem the candidate determines that the scram was unsuccessful.
T-101 initial entry was RPV Level below 12.5". The basis for the 12.5" RPS Setpoint is found in Tech Spec 2.2.1 Bases Page B 2-8.
From the stem the candidate is given that RCIC and HPCI have started and are injecting (initiation based on RPV Level below -38"). The candidate now needs to recall the basis of T-117 step LQ-7 to conclude that HPCI is permitted to inject until T-270 is directed.
A Wrong - Plausible to the candidate that fails to recall that HPCI injection during an ATWS has been analyzed to continue due to split flow path B Correct for the above reason C Wrong - plausible to the candidate that recalls the basis for the RPS Setpoint for Drywell Pressure - High rather than the correct basis for RPV Low Level and plausible to the candidate that fails to recall that HPCI injection during an ATWS has been analyzed and is permitted until trips direct secure.
D Wrong - plausible to the candidate that recalls the basis for the RPS Setpoint for Drywell LMK DEC 2017 ILTPressure NRC - High rather than the correct basis Page: 321 of 410for RPV Low Level 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written LMK DEC 2017 ILT NRC Page: 322 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 81 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1744196 User-Defined ID: Q #81 Lesson Plan Objective: LLOT1560 #6 SRO Only - ATWS Basis for Entry Conditions and Automatic Topic:
Actions RO Importance:
SRO Importance: 4.6 K/A Number: 295037 2.4.2 LMK DEC 2017 ILT NRC Page: 323 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level SRO Tier 1 Group 1 295037 2.4.2 SRO KA # and Rating Importance 4.6 295037 SCRAM Conditions Present and Reactor Power Above APRM Downscale or Unknown / 1 2.4.2 - Emergency KA Statement Procedures / Plan:
Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.
Cognitive level High Safety Function 1 - Reactivity Control 10 CFR 55 43(b)(2)
Technical Reference with Tech Spec 2.2.1 Rev 0 Revision No: T-117 Bases #: 1 9
Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS New NRC-05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 324 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 82 ID: 2027351 Points: 1.00
- SRO ONLY***********
Unit 1 is at 100% power when the following occurs:
- The Reactor Mode Switch is placed in Shutdown when RPV Pressure is 1085 psig
- A group 1 MSIV Isolation occurs
- RPS fails to de-energize
- No injection sources are available 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> later the CRS is implementing the Steam Cooling section of T-111.
WHICH ONE of the following identifies (1) the safety limit violated, and (2) correctly completes the below statement from Tech Spec 6.7.1.a?
6.7.1.a The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within ___(2)___.
Safety Limit Violated (2)
A. Reactor Coolant System Pressure 15 minutes B. Reactor Coolant System Pressure 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> C. Reactor Vessel Water Level 15 minutes D. Reactor Vessel Water Level 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Answer: D Answer Explanation LMK DEC 2017 ILT NRC Page: 325 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written From the stem the candidate determines that during the transient Unit 1 entered OPCON 3 when the mode switch was placed in Shutdown and that RPV pressure peak at 1317 psig. This is below the Safety Limit value of 1325 psig. Also from the stem the candidate concludes that RPV level is below -161 inches (Top of Active Fuel) and above is -198 inches (the RPV level where the steam cooling section of T-111 is exited (Step LR-17). Based on this information the Reactor Vessel Water Level Safety Limit has been exceeded.
Excerpts from Tech Spec sections 2 and 6 A Wrong - plausible to the candidate that fails to recall the safety limit set points and/or the correct applicability for the associated Safety Limit and plausible to the candidate the confuses the time limit for notifying the state and local agencies (15 minutes) when LMK DEC 2017 ILTdeclaring NRC an emergency from thePage:Emergency 326 of 410 Plan with the time requirement for notifying2017 21 December the NRC.
B Wrong - plausible to the candidate fails to recall the safety limit set points and/or the correct applicability
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written LMK DEC 2017 ILT NRC Page: 327 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 82 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 2027351 User-Defined ID: Q #82 Lesson Plan Objective: LGSOPS1800.07C SRO ONLY - Determine Safety Limit Violated and Reporting Topic:
action Time RO Importance:
SRO Importance: 4.7 K/A Number: 295031 2.2.22 LMK DEC 2017 ILT NRC Page: 328 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments:
General Data Level SRO Tier 1 Group 1 295031 2.2.22 SRO KA # and Rating Importance 4.7 295031 Reactor Low Water Level 2.2.22 - Knowledge of KA Statement limiting conditions for operations and safety limits.
Cognitive level High 2 - Reactor Water Inventory Safety Function Control 10 CFR 55 43(b)(1)
Tech Specs Technical Reference with sections 2.0 and Rev Revision No: 6.0 #: 1 T-111 7 Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS New NRC-05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 329 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 83 ID: 2027489 Points: 1.00
- SRO ONLY********************
Unit 2 plant conditions are as follows:
- GP-2, Normal Plant Startup, in progress
- RPV pressure is 850 psig
- "2A" Control Rod Drive (CRD) pump is out for maintenance "2B" CRD pump trips, and HCU 30-11, CRD accumulator trouble alarms simultaneously 3 minutes later, HCU 18-27, CRD accumulator trouble alarms Both control rods 30-11 and 18-27 are verified at position 08, and accumulator pressures are:
HCU 30 925 psig HCU 18 960 psig WHICH ONE of the following describes the minimum REQUIRED action(s) for the above condition?
A. Restore the HCU accumulator 30-11 to Operable within 8 hrs B. Place the mode switch in SHUTDOWN C. Manually scram the reactor and place the mode switch in SHUTDOWN if a CRD pump cannot be started within 20 minutes D. Manually scram the reactor and place the mode switch in SHUTDOWN if a third accumulator trouble alarm comes in prior to starting a CRD pump Answer: A Answer Explanation A Correct: Accumulator 30-11 is INOP because pressure is below 955 psig Accumulator 18-27 is OPERABLE (alarm set point is 970 psig)
Per ON-107 attachment 5 step 1: IF one CRD scram accumulator is inoperable, THEN PERFORM the following within 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />s:
1.1 RESTORE the inoperable accumulator to operable OR DECLARE associated control rod inoperable.
B Wrong: Plausible if the student identifies the action for reactor pressure less than 900 psig for 2 accumulators INOP C Wrong: Plausible if the student identifies the action for reactor pressure greater than 900 psig for 2 accumulators INOP D Wrong: Pausible if the student misses that the accumulator trouble alarm set point is 970 and does not necessarily mean the pressure is below the tech spec value.
LMK DEC 2017 ILT NRC Page: 330 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 83 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 0.00 System ID: 2027489 User-Defined ID: Q #83 Lesson Plan Objective: LLOT1550.3 (SRO) GP-2, Normal Plant Startup, in progress - Reactor Topic:
pressure is 850 psig - "2A" CRD PP RO Importance:
SRO Importance: 3.6 K/A Number: 295022 AA2.01 LMK DEC 2017 ILT NRC Page: 331 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level SRO Tier 1 Group 2 295022 AA2.01 SRO KA # and Rating Importance 3.6 295022 Loss of CRD Pumps AA2.01 - Ability to KA Statement determine and/or interpret the following as they apply to LOSS OF CRD PUMPS :
Accumulator pressure Cognitive level High Safety Function 1 - Reactivity Control 10 CFR 55 43(b)(5)
Technical Reference with Rev 1 ON-107 Revision No: #: 9 Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS Modified 558686 NRC-05, OYS CERT-04)
Question Source: (i.e. New, Modified 558686 Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 332 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 84 ID: 1744249 Points: 1.00
- SRO ONLY*********
Unit 1 conditions are as follows:
- Unit 1 was scrammed due to an unisolable leak into the RWCU Room
- Division 1 DC power has been lost
Area TEMP(°F)
Room 309 127 RWCU Regen htx room 123 A nonregen htx room 118 B nonregen htx room 124 A RWCU pump room 168 B RWCU pump room 150 C RWCU pump room 149 Room 510 149 LMK DEC 2017 ILT NRC Page: 333 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Given:
- T-101, RPV Control
- T-112, Emergency Blowdown Given the above conditions, WHICH ONE of the following identifies the correct pressure control strategy required by TRIPs, and the location where the RO can achieve this strategy?
Pressure Control Strategy Required by Remote SRV Operation Location TRIPs A. Depressurize RPV within 100°F/hr per T- Auxiliary Equipment Room 101 B. Depressurize RPV within 100°F/hr per T- Remote Shutdown Panel 101 C. Perform Emergency Blowdown per T-112 Auxiliary Equipment Room D. Perform Emergency Blowdown per T-112 Remote Shutdown Panel Answer: A Answer Explanation LMK DEC 2017 ILT NRC Page: 334 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written From the stem the candidate determines that T-103, Secondary Containment Control, has been entered and the RWCU area ONLY is above MSO. Also from the stem DIV 1 DC has no power.
From E-1FA, DIV 1 ADS AND all non-ADS SRVs cannot be activated.
With EHC pumps off, bypass valves are not available. Pressure control is available using ADS SRVs only and only from the DIV 3 controls in the Auxilary Equipment Room. The SRV controls for the C,A,and N SRVs at the Remote Shutdown Panel are Division 1.
From E-0033 Sheet 1:
From T-101, step RC/P-22, Maintain cooldown rate less than 100°F/hr.
A Correct for the above reasons B Wrong - plausible to the candidate that incorrectly recalls the power supplying SRV control to the Remote Shutdown Panel as Division 3.
C Wrong - plausible to the candidate that incorrectly recalls T-103 step SCC/T-10 and believes that an Emergency Blowdown is required when 2 or more temperatures exceed MSO as opposed to the correct requirement of 2 or more Areas D Wrong - plausible to the candidate that incorrectly recalls T-103 step SCC/T-10 and believes that an Emergency Blowdown is required when 2 or more temperatures exceed MSO as opposed to the correct requirement of 2 or more Areas, and Wrong - plausible to the candidate that incorrectly recalls the power supplying SRV control to the Remote Shutdown Panel as Division 3.
LMK DEC 2017 ILT NRC Page: 335 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 84 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1744249 User-Defined ID: Q #84 Lesson Plan Objective: LGSOPS1560.02D SRO Only - Secondary Containment high temp - RO actions Topic:
outside the MCR RO Importance:
SRO Importance: 4.1 K/A Number: 295032 - 2.4.34 LMK DEC 2017 ILT NRC Page: 336 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level SRO Tier 1 Group 2 KA # and Rating 295032 - 2.4.34 - SRO 4.1 295032 High Secondary Containment Area Temperature 2.4.34 - Emergency Procedures / Plan:
KA Statement Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects.
Cognitive level High Safety Function 5 - Containment Integrity 10 CFR 55 43 (b) 5 T-103 Technical Reference with Rev 1 E-1FA Revision No: #: 5 E-0033 Sheet 1 Justification for Non SRO CFR Link:
Question History: (i.e. LGS New NRC-05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 337 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 85 ID: 1740796 Points: 1.00
- SRO ONLY*********
Unit 1 is operating at 100% power with the following conditions:
- Eight Drywell cooling fans are running.
- 1A Drywell Chiller is operating
- Drywell temperature is 125°F and steady
- Drywell pressure is 0.5 psig and steady.
An inadvertent Group 8A isolation occurs that cannot be reset.
- Drywell pressure is 0.7 psig up slow,
- Drywell temperature is 130°F up slow
- G532, DWCW Head Tank Level indicates Hi/Lo Level
- Pressure on PI-087-109A, "CHW CIRCULATION PUMP 1AP161", is 5 psig WHICH ONE of the following describes the Required Actions, if any?
A. Bypass the isolation per GP 8.5 to lower Drywell Pressure B. Vent the Drywell per OT-101 to lower Drywell Pressure C. Start 1B Drywell Chiller per S87.1.A to lower Drywell Temperature D. Spray the Drywell per T-225 to lower Drywell Temperature Answer: B Answer Explanation LMK DEC 2017 ILT NRC Page: 338 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written A Incorrect: Plausible to the candidate who considers bypassing the isolation the correct action but does not recognize that with G532 indicating "Hi/Low" level or Low suction pressure GP-8.5 bypass cannot continue. GP-8.5 requires G532 to be "normal" or Suction pressure to be greater than 35 psig to bypass the isolation.
B Correct: With an Inadvertent Group 8A isolation, Drywell Chillwater is isolated to the Drywell Unit coolers and the drywell will experience a loss of cooling and entry into OT-101. With an unbypassable isolation, the only option to reduce pressure in the drywell is to Vent the drywell per OT-101 Attachment 3, Loss of Drywell Cooling. Initial steps of the attachment direct restarting chillers but with the isolation signal, venting per step 5 of the attachment is correct.
C Incorrect: Plausible to the candidate who believes that the 1B Drywell chiller has a different flowpath from the 1A chiller and would therfore be available with an 8A isolation. In actual fact, the chillers share the same flowpath.
D Incorrect: Plausible to the candidate who believes that spraying the drywell is the only available action. Spraying the drywell is directed out of T-102 but the entry condition of 1.68# drywell presure or 145°F drywell temperature have not been met.
LMK DEC 2017 ILT NRC Page: 339 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 85 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1740796 User-Defined ID: Q #85 NEW Lesson Plan Objective: LGSOPS1540.3 Topic: (SRO Only) Hi Drywell Temperature RO Importance: 3.9 SRO Importance: 4.1 K/A Number: 295012 AA2.02 LMK DEC 2017 ILT NRC Page: 340 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level SRO Tier 1 Group 2 KA # and Rating 295012 AA2.02 Ability to determine and/or interpret the following as they apply to HIGH KA Statement DRYWELL TEMPERATURE: Drywell pressure Cognitive level High Safety Function 5 10 CFR 55 CFR: 43.5 (b)(5)
Technical Reference with Rev 3 OT-101 Revision No: #: 7 Justification for Non SRO CFR Link:
Question History: (i.e. LGS NRC-05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 341 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 86 ID: 1749051 Points: 1.00
- SRO ONLY**********
Unit 1 is operating at 100% power with the following 1A SRV plant data:
Baseline Values Current Values TE-41-113A 503°F 499°F TE-41-1N004A 120°F 253°F RHR run time total for the past 12 months is 907 hours0.0105 days <br />0.252 hours <br />0.0015 weeks <br />3.451135e-4 months <br />.
Given the above information, WHICH ONE of the following identifies the required actions, if any, to be directed from RT-6-041-490-1 and the system at risk of water hammer if restarted following a LOCA/LOOP?
(See Next Page)
LMK DEC 2017 ILT NRC Page: 342 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written LMK DEC 2017 ILT NRC Page: 343 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written LMK DEC 2017 ILT NRC Page: 344 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written If in Suppression Pool Cooling Mode, a restart of ______ pumps following RT-6-041-490-1 required action a LOCA/LOOP will cause water hammer.
A. Full power operation may continue per GP- RHR 5
B. Full power operation may continue per GP- RHRSW 5
C. Commence shutdown per GP-3 RHR D. Commence shutdown per GP-3 RHRSW Answer: C Answer Explanation LMK DEC 2017 ILT NRC Page: 345 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written From the stem the candidate determines that the pilot temperature for the 1A SRV has dropped by 4 °F which is less than the > 5 °F used in RT-6-041-490-1 Attachment 2 for Probable pilot leak. Also from the stem having tailpipe temperature of 253 °F is indicative of probable main seat leak. From Pg 3 of attachment 2, RHR run times of greater than 10% require a Shutdown per GP-3. From the stem RHR run times are 907 hours0.0105 days <br />0.252 hours <br />0.0015 weeks <br />3.451135e-4 months <br />. 365 days X 24 hrs = 8760 hours0.101 days <br />2.433 hours <br />0.0145 weeks <br />0.00333 months <br /> in a year. Run time for this question = 907/8760 = 10.35%. With run time greater than 10% the appropriate action is to "Commence Shutdown per GP-3".
The concern with operating Suppression Pool Cooling if a LOCA/LOOP occurs is found in NRC issued Information Notice No. 87-10, "Potential for Water Hammer during Restart of Residual Heat Removal Pumps". The purpose of this notice was to alert the industry of the potential for water hammer in the RHR system during design basis loss of coolant accident (LOCA) coincident with loss of offsite power (LOOP) if the RHR system is aligned to SPC. The power loss while aligned to suppression pool cooling will prevent full closure of HV-051-*F024A(B), allowing portions of the RHR system to drain down to the suppression pool as a result of elevation differences and causing voids in the piping. Upon the subsequent restart and alignment of RHR in the LPCI alignment, the voids may cause a water hammer that could challenge the integrity of the RHR piping.
The concern identified in the above Information Notice is also contained in S51.8.A step 3.10:
SRO Only: This question is SRO only because the candidate must assess plant conditions then select the section of the procedure to implement.
A Wrong - Plausible to the candidate that incorrectly determines Run time is less than 10%
B Wrong - Plausible to the candidate that incorrectly determines Run time is less than 10%
Also plausible to the candidate that incorrectly recalls the water hammer concern is with RHRSW C Correct for the reasons described above D Wrong - plausible to the candidate that incorrectly recalls the water hammer concern is with RHRSW LMK DEC 2017 ILT NRC Page: 346 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 86 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 0.00 System ID: 1749051 User-Defined ID: Q #86 Lesson Plan Objective: LGSOPS0001.12.C Topic: SRO ONLY - Leaky SRV RO Importance:
SRO Importance: 3.2 K/A Number: 239002 A2.02 LMK DEC 2017 ILT NRC Page: 347 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level SRO Tier 2 Group 1 239002 A2.02 SRO KA # and Rating importance 3.2 239002 SRVs A2.02 - Ability to (a) predict the impacts of the following on the RELIEF/SAFETY VALVES ; and (b) based on KA Statement those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Leaky SRV Cognitive level High 3 - Reactor Pressure Safety Function Control 10 CFR 55 43(b)(5) 0 ARC-MCR-110 1 Technical Reference with B1 Rev 2 Revision No: RT-6-041-490-1 #: 0 S51.8.A 4 9
Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS New NRC-05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT RT-6-041-490-1 Supplied Ref (If Attachment 2 PG 3 appropriate): (i.e. ABN-##)
Imbedded LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 348 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written LMK DEC 2017 ILT NRC Page: 349 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 87 ID: 1749131 Points: 1.00
- SRO ONLY**********
Plant conditions:
- A loss of the 220 kV and 500 kV Grid occurred 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ago
- D12 DG is running loaded
- D23 DG is running loaded
- All other Unit 1 and Unit 2 DGs have failed to start D22 Bus needs to be re-energized by cross-tying D23 Bus with D22 using the 201 Safeguard Bus.
WHICH ONE of the following identifies the event procedure requiring entry for the above conditions and the SOURCE BUS 4 kV breaker compartment where the TD-6U Test Device cover is to be removed to allow synchronization of the D23 Bus with the D22 Bus?
Given:
- E-1, Loss of all AC Power (Station Blackout)
- E-10/20, Loss of Offsite Power TD-6U Test Device Event Procedure Cover Removed A. E-1 201-D23 B. E-1 201-D22 C. E-10/20 201-D23 D. E-10/20 201-D22 Answer: C Answer Explanation LMK DEC 2017 ILT NRC Page: 350 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written From E-10/20 From E-1 From E-1 Bases:
From the stem the candidate determines the entry into E-10/20 is appropriate for the above conditions.
Cross-Tie operation in this case would be performed using E-10/20, Att. 3. Step 2.2.3 directs pulling the cover of the TD-6U device on the SOURCE bus, which will be 201-D23 in this case LMK DEC 2017 ILT NRC since D23 is energized. Page: 351 of 410 21 December 2017 Clarification of Source Bus vs Target Bus is found in step 2.1.5 of E-10/20:
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written LMK DEC 2017 ILT NRC Page: 352 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 87 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 4 Difficulty: 0.00 System ID: 1749131 User-Defined ID: Q #87 Lesson Plan Objective: LGSOPS0092A.05C Topic: SRO - E-10/20 EDG Sync RO Importance: 0 SRO Importance: 3.6 K/A Number: 264000 A2.05 LMK DEC 2017 ILT NRC Page: 353 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments:
General Data Level SRO Tier 2 Group 1 264000 A2.05 SRO KA # and Rating importance 3.6 264000 EDGs A2.05 - Ability to (a) predict the impacts of the following on the EMERGENCY GENERATORS (DIESEL/JET) ; and (b) based on those predictions, KA Statement use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Synchronization of the emergency generator with other electrical supplies Cognitive level High Safety Function 6 - Electrical 10 CFR 55 43(b)(5) 5 Technical Reference with E-10/20 Rev 6 Revision No: S32.1.A #: 3 8
Justification for Non SRO None CFR Link:
Question History: (i.e. LGS None NRC-05, OYS CERT-04)
Question Source: (i.e. New, Modified 1248900 Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make N/A plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 354 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written LMK DEC 2017 ILT NRC Page: 355 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 88 ID: 1749153 Points: 1.00
- SRO ONLY*************
Unit 2 plant conditions:
- OPCON 5
- Reactor level is 217"
- '2A' RHR is in Shutdown Cooling
- HV-51-2F008, SHUTDOWN COOLING SUCTION OUTBOARD, fails closed and cannot be reopened WHICH ONE of the following identifies the:
(1) Tech Spec required action, and (2) the basis for performing that action?
A. (1) Place ADHR in service (2) To maintain and reduce reactor coolant temperature B. (1) Place ADHR in service (2) To assure accurate reactor coolant temperature indication C. (1) Place 'A' Recirc pump in service (2) To maintain and reduce reactor coolant temperature D. (1) Place 'A' Recirc pump in service (2) To assure accurate reactor coolant temperature indication Answer: D Answer Explanation LMK DEC 2017 ILT NRC Page: 356 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written From the stem the candidate determines that SDC has no suction path (HV-51-2F008 closed).
Tech Spec 3.9.11.2 action c.1 requires the verification of reactor coolant circulation by an alternate method.
The current plant configuration does not support placing ADHR in service due to the need to have the Reactor cavity flooded up.
Placing a Recirc loop in service satisfies Tech Spec 3.9.11.2, ACTION c.1. This only provides for the coolant circulation need to ensure proper reactor coolant temperature monitoring; it does NOT constitute an "alternate Decay Heat Removal method."
Tech Spec 3.9.11 Bases:
S51.5.H, RHR Alternate Decay Heat Removal, Prerequisite # 2.7:
A Wrong - Plausible to the candidate that fails to recall that ADHR can not be placed in service without the Reactor cavity being flooded. Operation of ADHR would support maintaining and reducing reactor coolant temperature.
B Wrong - Plausible to the candidate that fails to recall that ADHR can not be placed in service without the Reactor cavity being flooded. Operation of ADHR would support ensuring adequate monitoring of reactor coolant temperature.
C Wrong - Plausbile to the candidate who belives core ciruclation with recirc is credidted as an alternate method of decay heat removal.
D Correct for the abover reasons.
LMK DEC 2017 ILT NRC Page: 357 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 88 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1749153 User-Defined ID: Q #88 Lesson Plan Objective: LGSOPS0051.24B Topic: SRO ONLY - OPCON 5 - Loss of SDC and Tech Spec bases RO Importance:
SRO Importance: 4.6 K/A Number: 295021 2.2.39 LMK DEC 2017 ILT NRC Page: 358 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: Bank 715236 General Data Level SRO Tier 2 Group 1 205000 2.2.42 SRO KA # and Rating Importance 4.6 205000 Shutdown Cooling 2.2.42 - Equipment Control:: Ability to KA Statement recognize system parameters that are entry-level conditions for Technical Specifications.
Cognitive level High 4 - Heat Removal from Safety Function Reactor Core 10 CFR 55 43(b)(2)
Tech Spec Technical Reference with 3.9.11.2 Rev Revision No: T.S. Bases #:
3.9.11 Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS Bank NRC-05, OYS CERT-04)
Question Source: (i.e. New, Bank 715236 Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 359 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 88 Table-Item Links NRC EXAM - 10 CFR 55 Operators' Licenses 10 CFR 55.43 SRO WRITTEN EXAMINATION LIMERICK LO Question Category ILT NRC SRO HI COG LMK DEC 2017 ILT NRC Page: 360 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 89 ID: 1752990 Points: 1.00
- SRO ONLY**********
Unit 2 plant conditions are as follows:
- 100% reactor power
- RCIC blocked for turbine governor maintenance The following sequence of events occur:
10:00 A reactor SCRAM occurs 10:05 Reactor power is 3%
10:05 Reactor water level is +35 inches 10:15 A HPCI Isolation occurs on High Room Temperature due to HVAC isolation Given: T-249, HPCI/RCIC HIGH AREA TEMPERATURE ISOLATION BYPASS WHICH ONE of the following identifies the type of HPCI isolation that occurred and the procedure, in addition to T-249, that must be used prior to injecting with HPCI?
Procedure that must be Type of HPCI Isolation used prior to injecting with HPCI A. Inboard and Outboard T-270 TERMINATE AND PREVENT INJECTION INTO THE RPV B. Inboard and Outboard T-251 ESTABLISH A HPCI INJECTION FLOW PATH VIA FEEDWATER ONLY C. Outboard Only T-270 TERMINATE AND PREVENT INJECTION INTO THE RPV D. Outboard Only T-251 ESTABLISH A HPCI INJECTION FLOW PATH VIA FEEDWATER ONLY Answer: B Answer Explanation LMK DEC 2017 ILT NRC Page: 361 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written
- a. Incorrect: Plausible to the SRO candidate who recognizes that with a HPCI high temperature isolation they must determine that HPCI injection requires the performance of T-249 to bypass the High Temp. Isolation and T-251 to inject through feedwater only. T-270 is not peformed because power level is not above 4% per step LQ-7.
- b. Correct: A high temperature isolation in the HPCI pump room would cause a Group 4 isolation on both the inboard and outboard isolation channels of NSSSS. To bypass the high temperature isolation, T-249 is performed. HPCI injection is directed in T-117 step LQ-18 through "Feedwater Only" by performing T-251. T-270 is not required per step LQ-7 with power <4%
- c. Incorrect: Plausible to the candidate who believes that High Temp in HPCI would only cause an Outboard isolation similar to the operation of the manual isolation pushbutton or outboard isolation of RWCU on High demineralizer inlet temperature. As noted above, a high temperature in the HPCI pump room would cause both an inboard and outboard isolation. T-270 is not peformed because power level is not above 4% per step LQ-7.
- d. Incorrect: Plausible to the candidate who believes that High Temp in HPCI would only cause an Outboard isolation similar to the operation of the manual isolation pushbutton or outboard isolation of RWCU on High RGHX inlet temperature.
HPCI room > 180 ISOL both in and outboard T-249 needed to bypass isolation SRO Only because candidate must recognize that T-270 not required per T-117 LQ-7. This is an assessment of plant conditions which will direct the SRO to chose a strategy for HPCI use.
LMK DEC 2017 ILT NRC Page: 362 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 89 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1752990 User-Defined ID: Q #89 Lesson Plan Objective: LGSOPS2003.04 Topic: HPCI Hi Temp Strategies RO Importance: 3.7 SRO Importance: 4.7 K/A Number: 206000 G.2.4.6 LMK DEC 2017 ILT NRC Page: 363 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments:
General Data Level SRO Tier 2 Group 1 KA # and Rating 206000 G.2.4.6 3.7 / 4.7 High Pressure Coolant Injection System KA Statement Knowledge of EOP mitigation strategies.
Safety function N/A Cognitive level high 10 CFR 55 43.5(b)(5)
Technical Reference with Rev Revision No: #:
Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS From ILT NRC Exam 2005 NRC-05, OYS CERT-04) 2015 CERT Question Source: (i.e. New, Bank 1242567 Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If none appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #) Y LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 364 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 90 ID: 1759804 Points: 1.00
- SRO ONLY**********
Unit 1 is at 95% power. The Unit 1 RO depresses the "Alarm Level Record" pushbutton (shown below for the #2 APRM) for all 4 Unit 1 APRMs and records the following:
APRM Reading (%)
1 108.7 2 108.0 3 108.7 4 108.0 Recirc Loop Flows are as follows:
Loop Flow (kG/min) 1A 36.5 1B 37.2 Given the above information, WHICH ONE of the following correctly identifies the required Tech Spec Actions, if any?
A. No Tech Spec Action required B. Declare the affected RBM channel inoperable and take the ACTION required by Specification 3.1.4.3 C. Restore the inoperable channel to OPERABLE status within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or place the inoperable channel in the tripped condition.
D. Place at least one inoperable channel in the tripped condition within one hour.
LMK DEC 2017 ILT NRC Page: 365 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Answer: C Answer Explanation From the stem the candidate determines that the pushbuttons that were pressed by the RO have the APRM recorders swap from displaying APRM power readings to displaying current APRM rod block values.
The equation for calculating the Rod Block Setpoint is found in Tech Spec 3.3.6-2 Combine this with Lesson Plan LGSOPS0074A definition of W:
The calculated Rod Block value is:
0.65(100*(36,500+37,200)/88,000))+54.3% = 108.7%. If the APRMs were working correctly they would output a value of 108.0% due to the second line of Tech Spec Table 3.3.6-2 "clamping" them to 108.0%.
Since 108.7% is above the Table 3.3.6-2 allowable value of 108.4% APRM channels 1 and 3 are INOP and Tech Spec 3.3.6 Action a and b apply. Table 3.3.6-1 identifies the minimum operable channels per trip function for function 2.a at 3. With APRM 1 and 3 INOP there are only 2 remaining channels that are operable and Tech Spec action 61. a applies.
A Wrong - plausible to the candidate that correctly calculates the Rod Block value using the equation but fails to recognize that this value is clamped at 108.0%
B Wrong - plausible to the candidate that correctly determines that an action is required but selects action 60. This is easily confused due to the fact that APRMs do provided a power input to the Rod Block Monitors.
C Correct for the above reasons D Wrong - plausible to the candidate that correctly determines that 2 APRMs are INOP for their Rod Block function but incorrectly determines this constitutes "two or more less than required" due to the fact that only 3 of the 4 APRMs are required.
LMK DEC 2017 ILT NRC Page: 366 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 90 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1759804 User-Defined ID: Q #90 Lesson Plan Objective: LLOT0074A.16 Topic: SRO Only - APRM/LPRM Controls RO Importance:
SRO Importance: 4.3 K/A Number: 215005 2.1.31 LMK DEC 2017 ILT NRC Page: 367 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level SRO Tier 2 Group 1 215005 2.1.31 SRO KA # and Rating importance 4.3 215005 APRM / LPRM 2.1.31 - Conduct of Operations: Ability to locate control room switches, KA Statement controls, and indications, and to determine that they correctly reflect the desired plant lineup.
Cognitive level High Safety Function 7 - Instrumentation 10 CFR 55 43(b)(2)
Technical Reference with Tech Spec 3.3.6 Rev Revision No: LGSOPS0074A #:
Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS New NRC-05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If Tech Spec 3.3.6 Pages 3/4 appropriate): (i.e. ABN-##) 3-57 to 3/4 3-60a LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 368 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 91 ID: 1759803 Points: 1.00 Unit 1 is operating at 100% power.
Hydrogen Water Chemistry (HWC) system parameters are as follows:
Given:
- T-103, Secondary Containment Control
- ON-102, Air Ejector Discharge or Main Steam Line High Radiation WHICH ONE of the following describes:
(1) the plant response, and (2) the required operator action?
A. (1) A rise in Offgas System temperatures (2) SCRAM the reactor and close the MSIV's per T-103 B. (1) A rise in Offgas System temperatures (2) Trip Hydrogen Water Chemistry per ON-102 C. (1) A rise in Main Steam Line radiation (2) SCRAM the reactor and close the MSIV's per T-103 D. (1) A rise in Main Steam Line radiation (2) Trip Hydrogen Water Chemistry per ON-102 LMK DEC 2017 ILT NRC Page: 369 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Answer: D Answer Explanation The primary mechanism by which H2 injection causes a temporary rise in MSL and consequently SJAE radiation monitor levels is the transition from oxidizing to reducing conditions in the reactor which cause a temporary reverse in the transport of N13, affecting the radiation monitors. This transition occurs between 5 and 20 SCFM of H2. If a Hydrogen Water Chemistry System malfunction exists, ON-102 (Air Ejector Discharge or Main Steam High Radiation),
THEN REDUCE reactor power in accordance with GP-5 Appendix 2, Section 3.1, Reducing Rx Power AND Reactor Maneuvering Shutdown Instructions to maintain air ejector discharge radiation level below Hi Hi Alarm setpoint (ARC-MCR-*09 G1)
AND Main Steam Line radiation below 3x normal full power background. (Hi Hi Alarm Setpoint)
'D is correct: (1) A rise in Main Steam Line radiation; (2) Trip Hydrogen Water Chemistr.
Correct for the reasons described above.
'A' is wrong: (1) A rise in Offgas System temperatures; (2) SCRAM the reactor and close the MSIV's Combustion in the Offgas System is indicated by a sudden drop in Offgas System hydrogen concentration. Plausible to the examinee who confuses the change in HWC H2 injection that is symptomatic of Offgas combustion. Part (2) is taken from T-103 actions for MSL rad hi rad if not caused by a HWC problem
'B' is wrong: (1) A rise in Offgas System temperatures; (2) Trip Hydrogen Water Chemistry.
Combustion in the Offgas System is indicated by a sudden drop in Offgas System hydrogen concentration. Plausible to the examinee who confuses the change in HWC H2 injection that is symptomatic of Offgas combustion.
'C' is wrong: (1) A rise in MSL rad; (2) SCRAM and close the MSIV's. Plausible to the candidate who confuses the ON-102 actions with the T-103 actions. MSL rad will rise, however the correct response is to take the action per step 2.3 of ON-102 to lower power as described above.
LMK DEC 2017 ILT NRC Page: 370 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 91 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1759803 User-Defined ID: Q #91 Lesson Plan Objective: LGSOPS1550.IL1 Topic: Predict plant response to increase in HWC H2 injection rate RO Importance: 2.6 SRO Importance: 2.8 K/A Number: 272000 A2.07 LMK DEC 2017 ILT NRC Page: 371 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level SRO Tier 2 Group 2 KA # and Rating 272000 A2.07 A2.07 - Ability to predict the impacts of the following on the RADIATION MONITORING SYSTEM ;
and (b) based on those predictions, use procedures KA Statement to correct, control, or mitigate the consequences of those abnormal conditions or operations:
Hydrogen injection operation: Plant-Specific Cognitive level Lower Safety Function 9 10 CFR 55 43.(b) (5)
Technical Reference with Rev 3 ON-102 Revision No: #: 0 Justification for Non SRO CFR Link:
Question History: (i.e. LGS NRC-05, OYS CERT-04)
Question Source: (i.e. New, Modified from #995211 Bank, Modified)
Low KA Justification (if required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 372 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 92 ID: 1763353 Points: 1.00
- SRO ONLY**********
Unit 2 plant conditions are as follows:
- The 2B Recirc Pump has tripped
- Reactor power is 30%
Subsequently, Power is lost to NXG-II A and NXG-II B for the 2A ASD Given:
- S43.1.A, Start Up of Recirculation System
- OT-112, Unexpected/Unexplained Change in Core Flow
- OT-200 Appendix 1, Reactor Scram Hard Card WHICH ONE of the following describes the required action and the basis for this action?
A. Restart a Recirc Pump per S43.1.A to prevent RPV thermal stratification.
B. SCRAM per OT-112 to prevent undue stress on the vessel nozzles and bottom head regions upon startup of an idle loop C. SCRAM per OT-112 to avoid the reactivity effects of starting a Recirc Pump in natural circulation.
D. SCRAM using OT-200 Appendix 1 to meet the requirements of LCO 3.0.3 Answer: C Answer Explanation LMK DEC 2017 ILT NRC Page: 373 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written From the stem the candidate determines that the loss of both NXG controllers to the 2A ASD results in a trip of the 2A Recirc Pump.
From S43.1.F In this condition (no recirc pumps in operation) OT-112 step 3.1 requires a manual reactor scram.
The basis for the scram is discussed in OT-112 step 6.3 A Wrong - Plausible to the candidate that recalls the concerns and cautions associated with starting the second Recirc Pump. Restarting of the first recirc pump is implicitly prohibited based on step 6.3.
B Wrong - Plausible to the candidate that confuses the Tech Spec bases for temperature limits prior to start of an idle recirc pump (3/4.4.1 Bases)
C Correct for the reasons discussed above D Wrong - plausible to the candidate that does not recall that there is a Tech Spec LCO for operation with no recirc pumps in service (3.4.1.1)
LMK DEC 2017 ILT NRC Page: 374 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 92 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1763353 User-Defined ID: Q #92 Lesson Plan Objective: LLOT1540.05 Topic: SRO Only - Recirc Flow Control Emergency - actions required RO Importance:
SRO Importance: 4.4 K/A Number: 202002 2.4.49 LMK DEC 2017 ILT NRC Page: 375 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level SRO Tier 2 Group 2 202002 2.4.49 SRO KA # and Rating importance 4.4 202002 Recirculation Flow Control 2.4.49 - Emergency Procedures / Plan: Ability to KA Statement perform without reference to procedures those actions that require immediate operation of system components and controls.
Cognitive level High Safety Function 1 - Reactivity Control 10 CFR 55 43.(b)(5) 5 Technical Reference with OT-112 Rev 7 Revision No: S43.1.F #: 0 4
Justification for Non SRO CFR Link:
Question History: (i.e. LGS New NRC-05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make N/A plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 376 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 93 ID: 2029740 Points: 1.00 Unit 1 is at 72% with power ascension in progress.
A steam leak results in the following Turbine Enclosure Steam Line Tunnel temperature indications:
- TE25-115C, TURB ENCL MSLT AMB, indicates 193°F up slow @ 1°F/min.
- TE25-115D, TURB ENCL MSLT AMB, indicates 153°F up slow @ 2°F/min.
The following annunciator is in alarm:
- ARC-MCR-107, REACTOR, Window H-5, DIV 3 STEAM LEAK DET SYS HI TEMP/TROUBLE WHICH ONE of the following identifies how long until a Reactor Scram occurs and how long after the RPS actuation NRC notification required?
Scram Time Reporting Time A. 6 minutes 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> B. 6 minutes 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> C. 20 minutes 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> D. 20 minutes 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Answer: A Answer Explanation LMK DEC 2017 ILT NRC Page: 377 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Justification:
A. Correct: Group 1 isolation occurs if A or C AND B or D channels are tripped, and the trip set points are reached when Div 3 Steam Leak Detection System High temp/Trouble annunciator is alarmed. The trip set point for the Turbine Enclosure MSL Leak Detection Channel is 165°F. At the current rate of rise, this would occur in 6 minutes. SAF 1.6 of the Reportability Reference Manual requires NRC notification within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of an RPs acuation on a critical reactor.
B. Wrong: Plausible to the candidate who incorrectly recalls the reporting requirements of SAF 1.6 for a "Not Critical" reactor which is 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
C. Wrong: Plausible if the applicant does not understand that Group 1 isolation occurs at 165° but instead confuses this with the Outboard MSIV room setpoint of 192°F. At the current rate of rise, it would take approx. 20 minutes to reach 192°F.
D. Wrong: Plausible if the applicant does not understand that Group 1 isolation occurs at 165° but instead confuses this with the Outboard MSIV room setpoint of 192°F. Also if the candidate incorrectly recalls SAF 1.6 LMK DEC 2017 ILT NRC Page: 378 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 93 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 2029740 User-Defined ID: Q #93 Lesson Plan Objective: LGSOPS0072.5G Topic: Steam leak in Turbine Enclosure RO Importance: 3.6 SRO Importance: 4.5 K/A Number: 239001 G2.2.38 LMK DEC 2017 ILT NRC Page: 379 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level SRO Tier 2 Group 2 KA # and Rating 239001 2.2.38 3.6 / 4.5 Main and Reheat Steam:
Equipment Control:
KA Statement Knowledge of conditions and limitations in the facility license.
Cognitive level High Safety Function 3 10 CFR 55 43 (b)(1)
ARC-MCR107 Technical Reference with Rev H-5, I-5 Revision No: #:
T-101 Justification for Non SRO CFR Link:
Question History: (i.e. LGS NRC-05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 94 ID: 1769592 Points: 1.00
- SRO ONLY**********
WHICH ONE of the following correctly completes the below statements regarding Tech Spec system limits associated with surveillance test frequencies?
Each Surveillance Requirement shall be performed within the specified surveillance time interval with a maximum allowable extension not to exceed ___(1)___ of the surveillance interval.
If it is discovered that a Surveillance was not performed within its specified Surveillance time interval and allowed extension, then compliance with the requirement to declare the LCO not met may be delayed, up to ___(2)___ or up to the limit of the specified Surveillance time interval, whichever is greater.
A. (1) 10%
(2) 12 Hours B. (1) 10%
(2) 24 Hours C. (1) 25%
(2) 12 Hours D. (1) 25%
(2) 24 Hours Answer: D Answer Explanation The answer to both statements is found in Tech Spec sections 4.0.2 and 4.0.3 A Wrong - plausible to the candidate that incorrectly recalls both the value of the allowable grace and the missed surveillance extension time. The values of 10% and 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> appear multiple times in Tech Specs for various items.
B Wrong - plausible to the candidate that incorrectly recalls both the value of the allowable grace. The value of 10% appears multiple times in Tech Specs for various items.
C Wrong - plausible to the candidate that incorrectly recalls the missed surveillance extension time. The value of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> appears multiple times in Tech Specs for various items.
D Correct for the above reasons LMK DEC 2017 ILT NRC Page: 381 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written LMK DEC 2017 ILT NRC Page: 382 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 94 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1769592 User-Defined ID: Q #94 Lesson Plan Objective: LGSOPS1800.6 Topic: SRO Only - Explain and apply system limits and precautions RO Importance:
SRO Importance: 4.0 K/A Number: LGSOPS1800.6 LMK DEC 2017 ILT NRC Page: 383 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level SRO Tier 3 Group KA # and Rating 2.1.32 2.1.32 - Ability to explain KA Statement and apply all system limits and precautions.
Cognitive level Low Safety Function N/A 10 CFR 55 43(b)(2)
Technical Reference with Tech Spec 4.0.2 Rev Revision No: and 4.0.3 #:
Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS New NRC-05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 384 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 95 ID: 1770570 Points: 1.00
- SRO ONLY**********
Given the following:
Unit 1 is operating at 100% power
- A MCR annunciator has alarmed 12 times within the first two hours of the shift
- It has been determined that the alarm is a nuisance and that placing the annunciator mode switch in MANUAL will prevent further nuisance alarms.
- I&C has concluded that lifting a lead to the annunciator will allow the annunciator mode switch to be restored to AUTO.
Per the guidance of OP-AA-103-102 Watch-Standing Practices AND OP-LG-103-102-1001 "Alarms And Indications":
The ___(1)___ must authorize placing the annunciator mode switch in MANUAL.
Prior to lifting the lead to the annunciator engineering must complete ___(2)___.
A. (1) CRS (2) Technical Evaluation/TCCP (CC-AA-112)
B. (1) CRS (2) MAINTENANCE ALTERATIONS LOG (MA-AA-716-100-F-01)
C. (1) Shift Manager (2) Technical Evaluation/TCCP (CC-AA-112)
D. (1) Shift Manager (2) MAINTENANCE ALTERATIONS LOG (MA-AA-716-100-F-01)
Answer: A Answer Explanation LMK DEC 2017 ILT NRC Page: 385 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written The question is asking requirement of OP-AA-103-102, Watch-Standing Practices and OP-LG-103-102-1001, Alarms and Indications.
From OP-AA-103-102 step 4.5.5:
From OP-LG-103-102-1001:
AND The MA-AA-716-100 Distractor is wrong but plausible due to this process used at Limerick for some plant alterations.
From MA-AA-716-100:
The shift manager distractor is wrong but plausible due the following step in CC-AA-112:
A Correct for the above reasons B Wrong - plausible to the candidate that recalls a different temporary control process C Wrong - plausible to the candidate that believes that the shift manager is required to authorize the annunciator mode switch repositioning D Wrong - plausible to the candidate that believes that the shift manager is required to authorize the annunciator mode switch repositioning and plausible to the candidate that recalls a different temporary control process LMK DEC 2017 ILT NRC Page: 386 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 95 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 4 Difficulty: 0.00 System ID: 1770570 User-Defined ID: Q #95 NEW Lesson Plan Objective: LOT1572 COND. OF OPS Topic: SRO Only - INOP annunciator RO Importance:
SRO Importance: 3.3 K/A Number: 2.2.43 LMK DEC 2017 ILT NRC Page: 387 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level SRO Tier 3 Group n/a 2.2.43 SRO importance KA # and Rating 3.3 Knowledge of the process KA Statement used to track inoperable alarms.
Cognitive level lower Safety Function n/a 10 CFR 55 43(b)(5) 9 OP-LG-103-1 Technical Reference with 102-1001 Rev 3
Revision No: MA-AA-716-100 #:
1 OP-AA-103-102 6
Justification for Non SRO n/a CFR Link:
Question History: (i.e. LGS New NRC-05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if n/a required):
Revision History: Revision History: (i.e. Modified distractor b to make n/a plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 388 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 96 ID: 2036649 Points: 1.00
- SRO ONLY*************
Unit 1 is operating at 100% power, with the following:
- The Containment Leak Detection Radiation Monitor has failed downscale
- The Drywell Sump Monitoring System has failed its monthly Channel Functional Test WHICH ONE of the following identifies the most limiting Tech Spec required action?
A. Perform primary containment atmospheric grab sampling/analysis every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and restore the Containment Leak Detector Radiation Monitor to OPERABLE status within 30 days.
B. Perform primary containment atmospheric grab sampling/analysis every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and monitor Reactor Coolant System leakage by administrative means once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and restore either the Containment Leak Detector Radiation Monitor or the Drywell Sump Monitoring System to OPERABLE status within 7 days.
C. Be in HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
D. Restore the Drywell Sump Monitoring System to OPERABLE within 30 days and increase monitoring of Drywell Unit Cooler flow rate to once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
Answer: C Answer Explanation LMK DEC 2017 ILT NRC Page: 389 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Provided reference(s): U/2 Tech Spec 3.4.3.1 The Containment Leak Detection Radiation Monitor is used to aid the MCR staff in identifying a potential leak in the drywell. As such when it is not working (INOP) Tech Specs requires entry into an LCO. Given the conditions in the stem the candidate determines that the Containment Leak Detection Radiation Monitor is INOP as a result of failing downscale. Additionally the candidate determines that the drywell sump monitoring system is also INOP due to failing its channel functional test.
Refer to Tech Spec 3.4.3.1, where 3.4.3.1.a identifies the inop Containment Leak Detection Rad Monitor, and 3.4.3.1.b identifies the inop Drywell Floor Drain Tank Monitor. ACTIONs A, B, C, D, E, and F considers various combinations of inoperable portions of this LCO, except for the combined rad monitor and drywell sump monitor. Therefore, ACTION 'G' applies, which requires the plant to be in HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, etc.
A Wrong - Although an accurate LCO for the conditions in the stem, it is not the most limiting LCO. Plausible to the candidate that fails to recognize that action G applies and is the most limiting.
B Wrong - plausible to the candidate the mis-interprets action F and applies it to the stem conditions, and plausible to the candidate that fails to recognize that action G applies and is the most limiting.
C Correct for the above reasons.
D Wrong - Although an accurate LCO for the conditions in the stem, it is not the most limiting LCO. Plausible to the candidate that fails to recognize that action G applies and is the most limiting.
LMK DEC 2017 ILT NRC Page: 390 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 96 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 2036649 User-Defined ID: Q #96 Lesson Plan Objective: LLOT0135.7B (SRO Only) - Tech Spec - Determine Action for INOP Topic:
Containment Leak Detection Systems RO Importance: 2.9 SRO Importance: 2.9 K/A Number: G2.3.5 LMK DEC 2017 ILT NRC Page: 391 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments:
General Data Level SRO Tier 3 Group KA # and Rating G2.3.5 2.9 / 2.9 Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, KA Statement portable survey instruments, personnel monitoring equipment, etc.
Cognitive level High Safety Function 9 10 CFR 55 43(b)(2)
Technical Reference with Rev T.S. 3.4.3.1 Revision No: #:
Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS 556506 NRC-05, OYS CERT-04)
Question Source: (i.e. New, Bank 556506 Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision Removed reference to 3 History: (i.e. Modified days into the 30-day LCO distractor b to make from the stem. Re-wrote plausible based on OTPS choice B to make it more review) plausible.
ILT Supplied Ref (If U/1 T.S. 3.4.3.1 Pages 4-8 appropriate): (i.e. ABN-##) to 4-8a LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 392 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 97 ID: 1770590 Points: 1.00
- SRO ONLY**********
Unit 1 was operating at 100% power
- Drywell pressure began to rise due to an unisolable leak from a Reactor Recirc Pump Seal
- Annunciator 107-F2, DRYWELL HI/LO PRESS alarms
- OT-112, "Unexpected/Unexplained Change in Core Flow" is entered
- At 1.3 psig Drywell pressure the crew performed a GP-4 "Rapid Plant Shutdown" Then:
- Drywell pressure is 1.72 psig up slow
- Drywell temperature is 148°F up slow Given:
- OT-101, Hi Drywell Pressure
- T-101, RPV Control
- T-102, Primary Containment Control Which one of the following is correct regarding additional procedures to be used to mitigate the event?
A. T-101 and T-102 must be entered. All AOPs must be exited. Response to the event is as directed by the TRIPs B. T-101 and T-102 must be entered. OT-101 may also be entered as determined by the CRS. If a conflict arises, the actions of applicable OTs take precedence.
C. OT-101 must be entered. T-101 and T-102 must be entered and executed concurrently.
If a conflict arises, the actions of the TRIPs take precedence D. OT-101 must be entered. T-101 and T-102 are entered but execution/actions are delayed until intial actions of AOPs are completed.
Answer: C Answer Explanation LMK DEC 2017 ILT NRC Page: 393 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written A Wrong: Plausible to the candidate who confuses the guidance for EOP completion. With the given condition, T-101 and T-102 entry are appropriate. However, during execution of EOPs, AOPs and Off Normal Procedures (ONs, OTs, SEs etc.) are not exited. They would be performed concurrently B Wrong: Plausible to the candidate who incorrectly assumes that if an ON or OT is entered, the actions of the ON or OT takes precedence since it is written for the specific transient whereas the EOP is more generic in design.
C Correct: During a transient condition, the EOPs are the most important procedure. ONs and OTs are subordinate to the EOPs. While both EOPs and AOPs can proceed in parallel, in the event of conflicting direction, the EOP takes precedence.
D Wrong: Plausible to the candidate who believes that all actions in an AOP must be completed first prior to EOP execution.
LMK DEC 2017 ILT NRC Page: 394 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 97 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1770590 User-Defined ID: Q #97 Lesson Plan Objective: LGSOPS1560.02A Topic: Use of AOPs and EOPs RO Importance: 3.8 SRO Importance: 4.5 K/A Number: 2.4.8 LMK DEC 2017 ILT NRC Page: 395 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level SRO Tier 3 Group KA # and Rating 2.4.8 3.8 / 4.5 Knowledge of how abnormal operating KA Statement procedures are used in conjunction with EOPs Cognitive level L Safety Function 10 CFR 55 43(b)(5)
Technical Reference with OP-LG-103- Rev 2 Revision No: 102-1002 #: 6 Justification for Non SRO CFR Link:
Question History: (i.e. LGS NRC-05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 396 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 98 ID: 1795570 Points: 1.00
- SRO ONLY***********
Unit 2 LOCA is in progress, with the following:
- A Hurricane is in progress with sustained winds of 100 mph coming from 120 degrees.
- No emergency classification has been made
- No turnover of command and control has taken place
- North Stack effluent reading is 2.1 E +7 µCi/sec
- Offsite dose assessment is 5125 mRem CDE Thyroid
- State has notified LGS of impediments to evacuation As a result of the radiation hazard posed by the above conditions, WHICH ONE of the following identifies the required PAR, if any?
A. No PAR Required B. Shelter 2 mile radius and shelter 2-5 miles WSW / W / WNW / NW / NNW C. Evacuate 2 mile radius and evacuate 2-5 miles WSW / W / WNW / NW / NNW D. Evacuate 2 mile radius, evacuate 2-5 miles WSW / W / WNW / NW / NNW, and shelter 5-10 miles WSW / W / WNW / NW / NNW Answer: B Answer Explanation LMK DEC 2017 ILT NRC Page: 397 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Provide EP-AA-111-F-11 and EP-AA-1008 Addendum 3 From the stem conditions the student should make a General Emergency declaration based on the 5125 mRem CDE Thyroid (the proceeding note refers the student to use the dose assessment instead of the north stack readings) meeting the threshold for RG1 - 2.b.
With no emergency classification and no change of command and control the student is expected to reach the box to Evacuate 2 mile radius and evacuate 2-5 miles downwind on Page 1 of EP-AA-111-F-11.
LMK DEC 2017 ILT NRC Page: 398 of 410 21 December 2017 However, with a hurricane in progress the student should realize that it is prudent to shelter (see note 2) vice evacuate.
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written LMK DEC 2017 ILT NRC Page: 399 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 98 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1795570 User-Defined ID: Q #98 Lesson Plan Objective: LIMERICK LOT 7340 Topic: SRO ONLY - Determine PAR due to radiation hazards RO Importance:
SRO Importance: 3.8 K/A Number: 2.3.14 LMK DEC 2017 ILT NRC Page: 400 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level SRO Tier 3 Group N/A 2.3.14 SRO Importance KA # and Rating 3.8 2.3.14 Knowledge of radiation or containment hazards that may arise KA Statement during normal, abnormal, or emergency conditions or activities.
Cognitive level High Safety Function N/A 10 CFR 55 43.(b)(4)
EP-AA-111-F-Technical Reference with 11 Rev A Revision No: EP-AA-1008 #: 2 Add 3 Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS LGS 2010 CERT NRC-05, OYS CERT-04)
Question Source: (i.e. New, Bank 562492 Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified Replaced wrong wind distractor b to make direction disctractor to plausible based on OTPS make more plausible.
review)
ILT EP-AA-111-F-11 Supplied Ref (If EP-AA-1008 Addendum 3 appropriate): (i.e. ABN-##)
Page 13 LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 401 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 98 Table-Item Links NRC EXAM - 10 CFR 55 Operators' Licenses 10 CFR 55.43 SRO WRITTEN EXAMINATION LIMERICK LO Question Category ILT NRC SRO HI COG LMK DEC 2017 ILT NRC Page: 402 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 99 ID: 1795598 Points: 1.00
- SRO ONLY**********
In reference to HU3, FIRE potentially degrading the level of safety of the plant, WHICH ONE of the SE-8, FIRE, response results listed below would require declaration of an Unusual Event?
A. A fire on the 3rd floor of the SSB extinguished by the LGS Fire Brigade 51 minutes following initial fire alarm B. A fire on the 2nd floor of the Kemper building extinguished by the LGS Fire Brigade and Linfield Fire Department 27 minutes following initial fire alarm.
C. A fire alarm only, in the Spray Pond Pump House that took 16 minutes for the FBL to confirm no smoke/no fire.
D. A fire in the Unit 2 EDG corridor extinguished by the FBL using a handheld fire extinguisher 12 minutes following initial alarm. The fire was contained to a dirty rag barrel.
LMK DEC 2017 ILT NRC Page: 403 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Answer: B Answer Explanation All answer options require entry into SE-8, Fire. SE-8 contains actions to be implemented upon the discovery of a fire, among those actions is to document start times for potential Emergency declaration clocks and notifications to the Shift Manager and WCS. This question is asking which response and results would required declaration of an Unusual Event. With only HU3 section of EP-AA-1008 Addendum 3 being provided, the candidate must recall what areas are part of the Table H2 Vital Areas and the definition of the plant PROTECTED AREA.
A Wrong - Threshold 3 is being approached but is not met until the fire burns for 60 minutes or more B Correct - Threshold 4 has been met due to offsite fire response agency assistance C Wrong - Threshold 2 is being approached but is not met due to FBL confirmation of no fire prior to D Wrong - Threshold 1 is being approached but is not met until the fire burns for 15 minutes or more LMK DEC 2017 ILT NRC Page: 404 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 99 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1795598 User-Defined ID: Q #99 Lesson Plan Objective: EAL OBJECTIVES Topic: SRO Only - Fire in the plant procedures - EAL RO Importance:
SRO Importance: 3.9 K/A Number: 2.4.27 Comments: General Data Level SRO Tier 3 Group N/A KA # and Rating 2.4.27 SRO Importance 3.9 2.4.27 - Knowledge of "fire KA Statement in the plant" procedures.
Cognitive level Low Safety Function N/A 10 CFR 55 43(b)(5)
Technical Reference with EP-AA-1008 Rev 2
Revision No: Add. 3 #:
Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS New NRC-05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 405 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written LMK DEC 2017 ILT NRC Page: 406 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written 100 ID: 1795594 Points: 1.00
- SRO ONLY*********
A Unit 1 activity has been determined to be a 'Special Test or Evolution' (STE), per OP-AA-108-110.
The STE is to be performed by the on-watch, Main Control Room personnel.
WHICH ONE of the following personnel can be assigned to be the 'STE Coordinator'?
A. Shift Manager B. Unit 1 CRS C. PRO D. Responsible System Manager Answer: D Answer Explanation Refer to OP-AA-108-110, section 4.3 CAUTION, which states that the STE Coordinator is NOT to be an active performer of the test. Stem conditions indicate that U1 MCR personnel are the "performers"; therefore, given the answer choices, only the Responsible System Manager is eligible to act as Coordinator.
ANSWER: Responsible System Manager A Wrong - plausible if the candidate confuses the requirements of step 3.4 (Operations Shift Management responsibilities) with those of The STE Coordinator B Wrong - plausible if the candidate confuses the requirements of step 3.4 (Operations Shift Management responsibilities) with those of The STE Coordinator C Wrong - Plausible if the candidate fails to recall the content of the CAUTION described above D Correct for the above reasons LMK DEC 2017 ILT NRC Page: 407 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 100 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 2 Difficulty: 0.00 System ID: 1795594 User-Defined ID: Q #100 Lesson Plan Objective: LGSOPS2005A.4 SRO ONLY - Recall who can act as Coordinator for a Special Topic:
Test or Evolution RO Importance:
SRO Importance: 3.6 K/A Number: 2.2.7 LMK DEC 2017 ILT NRC Page: 408 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Comments: General Data Level SRO Tier 3 Group N/A KA # and Rating 2.2.7 SRO Importance 3.6 2.2.7 Knowledge of the KA Statement process for conducting special or infrequent tests.
Cognitive level Low Safety Function N/A 10 CFR 55 43(b)(5)
Technical Reference with Rev OP-AA-108-110 3 Revision No: #:
Justification for Non SRO N/A CFR Link:
Question History: (i.e. LGS Bank NRC-05, OYS CERT-04)
Question Source: (i.e. New, Bank 985682 Bank, Modified)
Low KA Justification (if N/A required):
Revision History: Revision History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If None appropriate): (i.e. ABN-##)
LORT PRA: (i.e. Yes or No or #)
LORT Question Section: (i.e, A-Systems or B-Procedures)
Comments LMK DEC 2017 ILT NRC Page: 409 of 410 21 December 2017
EXAMINATION ANSWER KEY December 2017 ILT NRC - SRO Written Question 100 Table-Item Links LIMERICK LO Question Category ILT NRC SRO HI COG NRC EXAM - 10 CFR 55 Operators' Licenses 10 CFR 55.43 SRO WRITTEN EXAMINATION CFR: 43.3 Facility licensee procedures required to obtain authority for design and operating changes in the facility.