ML14241A709

2014-02 - Draft Written Exam Comments-Attachment

ML14241A709
Person / Time
Site:	Arkansas Nuclear
Issue date:	02/27/2014
From:	Vincent Gaddy Operations Branch IV
To:	Entergy Operations
References
Download: ML14241A709 (226)

Text

Q1 - NRC recommended changes to Rev 1 Notes: Rev 1 Notes a re acceptable, however format/style below should be considered for future question submittals. Also, spell out RTR the first time used, and correct spelling of the word Reactor "or Trip the Rector-"

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A. Incorrect. OP

-2202.002 directs using AFW pump 2P

-75 to feed the SGs. Plausible because EFAS is manually actuated during SPTAs, at Step 8.A (Contingency Actions), because FW will not be maintaining SG levels. However, during implementation of OP

-2202.002, operators will secure 2P-7A/B and start 2P

-75 to feed the SGs.

B. Incorrect. OP

-2202.002 directs using AFW pump 2P

-75 to feed the SGs. Plausible because EFAS is manually actuated during SPTAs, at Step 8.A (Contingency Actions), because FW will not be maintaining SG levels. However, during implementation of OP

-2202.002, operators will secure 2P-7A/B and start 2P

-75 to feed the SGs.

C. Correct. Based on OP

-2202.002, Step 12.A (Contingency Actions), the operators are directed to start and commence SG feed with AFW pump 2P

-75 using 2202.010, Standard Attachments, Attachment 46, EFW Flow.

D. Incorrect.

OP-2202.002 directs using AFW pump 2P

-75 to feed the SGs.

Plausible because OP-2203.027, Loss of Main Feedwater Pump AOP, does direct attempting to restart tripped MFP (Step 3.B

- Contingency Actions) and then if Reactor power greater than 4% and feedwater cannot be restored, then trip the Reactor and go to SPTAs. Since the stem indicates that the CRS has directed a Reactor trip, if can be assumed that MFP "B" was not able to be started and feedwater restored using a Main Feedwater Pump.

---

References:

Add OP-2202.001, Standard Post Trip Actions EOP to those already listed Change format for RTR to match others (OP

-2202.002, RTR EOP, -.)

Data for 2014 NRC RO/SRO Exam 29-Jan-14Bank:1925Safety Function 1System Number E02System Title:Reactor Trip Recovery K/AEK1.3Description:Knowledge of the operational implications of the following concepts as they apply to the (Reactor TripRecovery): - Annunciators and conditions indicating signals, and remedial actions associated with the(Reactor Trip Recovery)RO Imp: 3.0SRO Imp: 3.4Lic Level:

RDifficulty:

3Taxonomy: HQuestion:Consider the following: - Unit 2 is operating at 60% power - "A" MFP has been tagged out for bearing replacement - Annunciator 2K03 A-11 "FEED PUMP TRIP" is in alarm for "B" MFP - CRS directs tripping the Reactor - SPTAs have been completed - Control Room has been informed that "B" MFP was tripped inadvertently by maintenance personnel - OP-2202.002, Reactor Trip Recovery EOP, has been enteredUpon completion of OP-2202.002, S/G levels will be maintained at 60% by ______________________ . A. 2P-7A Emergency Feedwater Pump B. 2P-7B Emergency Feedwater Pump C. 2P-75 Auxiliary Feedwater Pump D. 2P-1B Main Feedwater PumpAnswer:C. Correct Notes:S/G levels will lower rapidly with a loss of both feed pumps ("A" OOS and "B" Tripped) the ACA will direct entry into Lossof Feed Pump AOP. Step 3 contingency actions does direct placing the tripped MFP (do not know reason why it tripped) inservice or Trip the Rector (which is the action given in stem as directed by the CRS). SPTAs are entered and direct actuatingEFW due to the lowering S/G levels (this will start both "A" and "B" EFW pumps). At the completion of SPTAs, all safetyfunctions will be satisfied and RTR will be entered. RTR will restore S/G levels by placing AFW pump (2P-75) in service andsecuring both EFW pumps.C. Correct: based on OP-2202.002 step 12.AA. B. and D. Incorrect due to procedural guidance to place the AFW pump in service to restore S/G levels OP-2202.002 step12.A

References:

OP-2203.012C, Annunciator Corrective Actions 2K03 window A-10, Rev 030, pages 134 and 135 of 176OP-2203.027, Loss of Main Feedwater Pump AOP, Rev 013, step 3, contingency 3.E.1) and 2) page 2 of 11Reactor Trip Recovery EOP, OP-2202.002, Rev 010, step 12.A, contingency A.1) page 6 of 17Source: NEWRev: 1Rev Date:1/28/2014 2:06:53Search00CE02K10310CFR55:41.8 / 41.10 / 45.3 Tier: 1Group: 1Author:fosterL. Plan:A2LP-RO-ERTR OBJ 1QID #: 1 1Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 29-Jan-14Reactor Trip Recovery Tech Guide, EOP-2202.002, Rev 010, step 12., page 19 of 33Historical Comments:Rev. 1: added entry into RTR to bullet list. Reworded question (based on validate comments) added explanation to notessection.2Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 30-Jan-14Bank:1925Safety Function 1System Number E02System Title:Reactor Trip Recovery K/AEK1.3Description:Knowledge of the operational implications of the following concepts as they apply to the (Reactor TripRecovery): - Annunciators and conditions indicating signals, and remedial actions associated with the(Reactor Trip Recovery)RO Imp: 3.0SRO Imp: 3.4Lic Level:

RDifficulty:

3Taxonomy: HQuestion:Consider the following: - Unit 2 is operating at 60% power - "A" MFP has been tagged out for bearing replacement - Annunciator 2K03 A-11 "FEED PUMP TRIP" is in alarm for "B" MFP - CRS directs tripping the Reactor - SPTAs have been completed - Control Room has been informed that "B" MFP was tripped inadvertently by maintenance personnel - OP-2202.002, Reactor Trip Recovery EOP, has been enteredUpon completion of OP-2202.002, S/G levels will be maintained at 60% by ______________________ . A. 2P-7A Emergency Feedwater Pump B. 2P-7B Emergency Feedwater Pump C. 2P-75 Auxiliary Feedwater Pump D. 2P-1B Main Feedwater PumpAnswer:C. Correct Notes:A. Incorrect. OP-2202.002 directs using AFW pump 2P-75 to feed the SGs. Plausible because EFAS is manually actuatedduring SPTAs, at Step 8.A (Contingency Actions), because FW will not be maintaining SG levels. However, duringimplementation of OP-2202.002, operators will secure 2P-7A/B and start 2P-75 to feed SGs.B. Incorrect. OP-2202.002 directs using AFW pump 2P-75 to feed the SGs. Plausible because EFAS is manually actuatedduring SPTAs, at step 8.A (Contingency Actions), because FW will not be maintaining SG levels. However, duringimplementation of OP-2202.002, operators will secure 2P-7A/B and start 2P-75 to feed the SGs.C. Correct. Based on OP-2202.002, Step 12.A (Contingency Actions), the operators are directed to start and commence SGfeed with AFW pump 2P-75 using OP-2202.010, Standard Attachments, Attachment 46, EFW Flow.D. Incorrect. OP-2202.002 directs using AFW pump 2P-75 to feed the SGs. Plausible because OP-2203.027, Loss of MainFeedwater Pump AOP, does direct attempting to restart tripped MFP (Step 3.B - Contingency Actions) and then if Reactorpower greater than 4% and feedwater cannot be restored, then trip the Reactor and go to SPTAs. Since the stem indicates thatSource: NEWRev: 2Rev Date:1/30/2014 7:36:30Search00CE02K10310CFR55:41.8 / 41.10 / 45.3 Tier: 1Group: 1Author:fosterL. Plan:A2LP-RO-ERTR OBJ 1QID #: 1 1Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 30-Jan-14the CRS has directed a Reactor trip, it can be assumed that MFP "B" was not able to be started and feedwater restored using aMain Feedwater Pump.

References:

OP-2203.012C, Annunciator Corrective Actions 2K03 window A-10, Rev 030, pages 134 and 135 of 176OP-2203.027, Loss of Main Feedwater Pump AOP, Rev 013, step 3, contingency 3.E.1) and 2) page 2 of 11OP-2202.002, Reactor Trip Recovery EOP, Rev 010, step 12.A, contingency A.1) page 6 of 17EOP-2202.002, Reactor Trip Recovery Tech Guide, Rev 010, step 12., page 19 of 33OP-2202.001, Standard Post Trip Actions EOP, Rev 014, step 8.A.1 page 10 of 19Historical Comments:Rev. 1: added entry into RTR to bullet list. Reworded question (based on validate comments) added explanation to notessection.Rev. 2, updated per NRC comments. (mwf 1/30/14) 2Form ES-401-5 Written Exam Question Worksheet

Data for 2014 NRC RO/SRO Exam 29-Jan-14Bank:1926Safety Function 3System Number 008System Title:Pressurizer (PZR) Vapor Space Accident (Relief K/A AA2.30Description:Ability to determine and interpret the following as they apply to the Pressurizer Vapor Space Accident: -Inadequate core coolingRO Imp: 4.3SRO Imp: 4.7Lic Level:

RDifficulty:

2Taxonomy: FQuestion:Consider the following: - Unit 2 has been taken off line due to indications of a LOCA inside Containment - SPTAs are complete and OP-2202.003, Loss of Coolant Accident EOP, has been entered - Pressurizer level 90% and trending up - Pressurizer pressure 1055 psia and trending up - Tc 468°F and lowering - Th 552°F and rising - Average CET temperature 558°F and rising - Containment pressure 25 psiaThe RCS leak is in the Pressurizer ___________ space and natural circulation ________ established. A. water; is B. water; is not C. steam; is D. steam; is notAnswer:D. Correct Notes:A steam space leak will cause PZR level to rise (venting off of the steam space) the insurge will cause PZR heaters to energize(colder water entering into the PZR from the RCS) Containment Spray will actuate and the RCPs will be secured (directed byprocedure, section 1, step 16, page 11) cooling flow is lost to the reactor vessel head region, combined with low RCS pressure,a void will form. Natural Circulation is not established [<30°F MTS and >50°F delta between Th and Tc]

References:

OP-2202.003, Loss of Coolant Accident EOP, Rev 014, section 3, step 7.A. contingency A.2) d), page 31 of 67EOP-2202.003, Loss of Coolant Accident Tech Guide, Rev 014, section 3, step 7, page 90 of 140Source: NEWRev: 1Rev Date:1/28/2014 3:42:52Search000008A23010CFR55:41.7 / 41.10 / 43.5 / 45Historical Comments:New QuestionRev 1: changed to incorporate NRC comments (mwf 1/28/14)

Tier: 1Group: 1Author:fosterL. Plan:A2LP-RO-ELOCA OBJ 17QID #: 2 3Form ES-401-5 Written Exam Question Worksheet

Data for 2014 NRC RO/SRO Exam 29-Jan-14Bank:1927Safety Function 3System Number 011System Title:Large Break LOCA K/A2.1.20Description:Conduct of Operations - Ability to interpret and execute procedure steps.RO Imp: 4.6SRO Imp: 4.6Lic Level:

RDifficulty:

2Taxonomy: HQuestion:Consider the following: - Unit 2 has experienced a LOCA - OP-2202.003, Loss of Coolant Accident EOP, is being implemented - Pressurizer pressure is 1450 psia - Pressurizer level is 32% and trending up - Margin to Saturation (MTS) is 32°F and stable - Reactor Vessel Level Monitoring System (RVLMS) indicates level 01 - Containment temperature 210°F and trending down - Containment pressure is 22.3 psia and trending down - Emergency Feed Actuation Signal (EFAS) has actuated and "A" and "B" S/G levels are 25% - "A" and "B" Emergency Feedwater (EFW) pumps are running on recirculationTerminate/Throttle criteria has NOT been met for High Pressure Safety Injection [HPSI] due to _________________ . A. Pressurizer level is too low B. Containment pressure is too high C. Feedwater flow to the S/Gs is too low D. Margin To Saturation (MTS) is too lowAnswer:A. Correct Notes:Containment is in a "Harsh Environment" condition (>200°F) which changes the values used to determine HPSITerminate/Throttle criteria. (numbers to be used are bracketed) pressurizer level is required to be 50% or greater with thegiven conditions. Containment pressure is not included in the criteria to terminate HPSI. Steam Generator levels are adequatefor HPSI termination. Margin to Saturation is greater than 30 degrees F which meets HPSI termination criteria.

References:

OP-2202.003, Loss of Coolant Accident EOP, Rev 014, section 3, step 15, page 35 of 67EOP-2202.003, Loss of Coolant Accident Tech Guide, Rev 014, section 3, step 15, page101 of 140STM 2-75, Reactor Vessel Monitoring System, Rev 6, section 2.1 page 3Source: NEWRev: 1Rev Date:1/28/2014 3:45:38Search000011212010CFR55:41.10 / 43.5 / 45.12Historical Comments:Rev 1: changed to incorporate NRC comments, added STM reference (mwf 1/28/14)

Tier: 1Group: 1Author:fosterL. Plan:A2LP-RO-ELOCA OBJQID #: 3 4Form ES-401-5 Written Exam Question Worksheet

Data for 2014 NRC RO/SRO Exam 29-Jan-14Bank:1928Safety Function 4System Number 015System Title:017 Reactor Coolant Pump (RCP) Malfunction K/A AK1.01Description:Knowledge of the operational implications of the following concepts as they apply to Reactor Coolant PumpMalfunctions: - Natural circulation in a nuclear reactor power plantRO Imp: 4.4SRO Imp: 4.6Lic Level:

RDifficulty:

2Taxonomy: FQuestion:Consider the following: - Unit 2 has been tripped from 100% power - Reactor Coolant Pumps (RCPs) have been secured due to a power issue - SPTAs are complete - OP-2203.013, Natural Circulation AOP, is being implementedOP-2203.013 directs maintaing Margin to Saturation (MTS) ______ or greater to minimize reactor vessel head voiding. TheReactor Coolant System (RCS) is determined to be void free if Pressurizer level ____________ with Pressurizer spray inservice. A. 30°F; goes up B. 30°F; is stable C. 50°F; goes up D. 50°F; is stableAnswer:D. Correct Notes:The Natural Circulation AOP requires a higher MTS [>50°F] step 5 and has the operator verify stable pressurizer level whenPzr spray is in service to check the RCS is void free. The Reactor Coolant Pumps malfunctioned due to a power issue and weresecured. The operational implication is that the operators must recognize that while in the Natural Circulation AOP, the MTSminimum value is 50 degrees F. The operators must also know that head voiding is a concern while on natural circulation. Sothe question asks the operator how to recognize if the RCS is void free during natural circulation conditions by monitoring thePressurizer level effects while Pressurizer spray is in service.

References:

OP-2203.013, Natural Circulation AOP, Rev 014, step 5, page 3 of 32 and step 32 page18 of 32AOP-2203.013, Natural Circulation Tech Guide, Rev 014, step 5, page 2 of 32 and 18 of 32Source: NEWRev: 1Rev Date:1/29/2014 8:03:27Search000015K10110CFR55:41.8 / 41.10 / 45.3Historical Comments:Rev 1: changed to incorporate NRC comments (mwf 1/21/14)

Tier: 1Group: 1Author:fosterL. Plan:A2LP-RO-CIRC OBJ 4QID #: 4 5Form ES-401-5 Written Exam Question Worksheet

Data for 2014 NRC RO/SRO Exam 29-Jan-14Bank:1929Safety Function 2System Number 022System Title:Loss of Reactor Coolant Makeup K/A AK1.03Description:Knowledge of the operational implications of the following concepts as they apply to Loss of Reactor CoolantMakeup: - Relationship between charging flow and PZR levelRO Imp: 3.0SRO Imp: 3.4Lic Level:

RDifficulty:

3Taxonomy: HQuestion:(REFERENCE PROVIDED)Consider the following: - Unit 2 is operating at 100% power - Annunciator 2K12 B-3 "HEADER FLOW LO" comes into alarm - Charging Header Flow (2FIS-4863) is reading 15 gpm - Letdown Flow (2FIS-4802) is reading 26 gpm - Pressurizer level is 60.0%Assuming no further changes in charging or letdown flow and NO operator action, the first backup Charging Pump (CCP)would reach its auto start setpoint in approximately ______ minutes. A. 7 B. 9.5 C. 11 D. 15Answer:C. Correct Notes:Student should know that Pzr level setpoint is 60% at 100% power. Pzr level would decrease by 15 gpm with the statedconditions. 15 gpm in [from charging] minus (26 gpm out [from letdown] plus 4 gpm out [from controlled Bleedoff] ) equals -15 gpm from the primary. Pzr level is 53.5 gallons per percent. 53.5 gal/% x 3.1% = 165.85 gallons required to be lost fromthe system to reach the 1st CCP auto start setpoint. [165.85 gals / 15 gpm = 11.06 minutes]A. Incorrect: Number is based on using the VCT gallons per percent and accounting for RCP controlled Bleedoff flow: 15 gpm in [form charging] minus [(26 gpm out [from letdown] plus 4 gpm out [from controlled Bleedoff] )] = -15 gpm from the primary. VCT level is 33.8 gallons per percent. 33.8 gal/% x 3.1% = 104.78 gallons required to be lost from the system to reach the 1st CCP auto start setpoint. [104.78 gals / 15 gpm = 6.98 minutesB. Incorrect: Number is based on using the VCT gallons per percent and not accounting for RCP controlled Bleedoff flow: 15 gpm in [form charging] minus [(26 gpm out [from letdown] ] = -11 gpm from the primary. VCT level is 33.8 gallons per percent. 33.8 gal/% x 3.1% = 104.78 gallons required to be lost from the system to reach the 1st CCP auto start setpoint. [104.78 gals / 11 gpm = 9.5 minutesD. Incorrect: Number is based on using the Pzr gallons per percent and not accounting for RCP controlled Bleedoff flow: 15 gpm in [form charging] minus (26 gpm out [from letdown] = -11 gpm from the primary.Source: NEWRev: 1Rev Date:1/29/2014 7:13:54Search000022K10310CFR55:41.8 / 41.10 / 45.3 Tier: 1Group: 1Author:fosterL. Plan:A2LP-RP-ACCP OBJ 2QID #: 5 6Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 29-Jan-14 Pzr level is 53.5 gallons per percent. 53.5 gal/% x 3.1% = 165.85 gallons required to be lost from the system to reach the 1st CCP auto start setpoint. [165.85 gals / 11 gpm = 15.07 minutes

References:

OP-2305.002, Reactor Coolant Leak Detection, Rev 024, exhibit 1, page 39 of 54 [PROVIDED to STUDENT]OP-2203.012L, Annunciator Corrective Actions 2K12 window B-3, Rev 044, page 36 of 116STM 2-04, Chemical and Volume Control System, Rev 29, PZR level control program diagram, page 78STM 2-03-1, Pressurizer Pressure and Level Control, Rev 16, section 3.1 page 15Historical Comments:Rev 1: changed to incorporate NRC comments, added STM references (mwf 1/29/14) 7Form ES-401-5 Written Exam Question Worksheet

Data for 2014 NRC RO/SRO Exam 29-Jan-14Bank:1930Safety Function 4System Number 025System Title:Loss of Residual Heat Removal System (RHRS)

K/A AA1.03Description:Ability to operate and/or monitor the following as they apply to the Loss of Residual Heat Removal System: -LPI pumpsRO Imp: 3.4SRO Imp: 3.3Lic Level:

RDifficulty:

3Taxonomy: HQuestion:Consider the following: - Unit 2 is in Mode 5 - RCS level is currently 24" from the bottom of the hot leg - "A" LPSI pump [2P-60A] is in service - "B" LPSI pump [2P-60B] is in standby - Annunciator 2K12 A-8 "Instr Air Press HI/LO" comes into alarm - Annunciator 2K07 C-7 "LPSI PUMP MOTOR AMPS HI/LO" is in alarm - ATC reports "A" LPSI pump amperage and flow rate is oscillating - CRS has entered OP-2203.029, Loss of Shutdown Cooling AOPUsing OP-2203.029, the CRS would direct _______________________ . A. placing "B" LPSI pump [2P-60B] in service B. placing HIC for LPSI Discharge Header valve 2CV-5091 in MANUAL C. throttling LPSI Discharge Header valve 2CV-5091 Bypass valve 2SI-5091-3 closed D. securing "A" LPSI pump [2P-60A] and transition to OP-2202.011, Lower Mode Functional EOPAnswer:D. Correct Notes:D. Correct: With a Loss of IA, the flow control valve will fail open causing high system flowrate. The Loss of SDC AOP, step 12 contingency C.1) and 2) will direct securing the in service SDC pump and entering the Lower mode Functional EOPA. Incorrect: The AOP would not direct placing the standby pump in service with signs of pump cavitationB. Incorrect: placing the HIC in MANUAL would try and send a signal to the valve, but the valve will not response due to the Loss of Instrument Air PressureC. Incorrect: Normal configuration for 2SI-5091-3 is closed (the temperature control valve bypass valve is normally throttled open when on SDC]

References:

OP-2203.012G, Annunciator Corrective Actions 2K07 window C-7, Rev 031, page 52 of 71OP-2203.012L, Annunciator Corrective Actions 2K12 window A-8, Rev 044, page 85 of 116OP-2203.029 Loss of Shutdown Cooling Rev 016, step 12, page 8 of 18Technical Guideline OP-2203.029, Loss of Shutdown Cooling, Rev 016, step 12, page 13 of 19Source: NEWRev: 1Rev Date:1/29/2014 7:16:35Search000025A10310CFR55:41.7 / 45.5 / 45.6 Tier: 1Group: 1Author: fosterL. Plan: A2LP-RO-SDC OBJ 3QID #: 6 8Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 29-Jan-14Historical Comments:Rev 1: changed to incorporate NRC comments (mwf 1/29/14) 9Form ES-401-5 Written Exam Question Worksheet

Data for 2014 NRC RO/SRO Exam 29-Jan-14Bank:1931Safety Function 8System Number 026System Title:Loss of Component Cooling Water (CCW)

K/A AK3.02Description:Knowledge of the reasons for the following responses as they apply to the Loss of Component CoolingWater: - The automatic actions (alignments) within the CCWS resulting from the actuation of the ESFASRO Imp: 3.6SRO Imp: 3.9Lic Level:

RDifficulty:

2Taxonomy: FQuestion:The PURPOSE for the CCW/ACW Return Isolation Valves (2CV-1543-1/2CV-1542-2) to automatically_________________. A. open on a Main Steam Isolation Signal (MSIS) to ensure cooling to the RCP seals is maintained B. open on a Main Steam Isolation Signal (MSIS) to cross-tie Loop 1 and Loop 2 Service Water returns C. close on a Main Steam Isolation Signal (MSIS) to separate Loop 1 and Loop 2 Service Water returns D. close on a Main Steam Isolation Signal (MSIS) to isolate seismic Category 1 piping from seismic Category 2 pipingAnswer:D. Correct Notes:D. Correct: MSIS and SIAS will CLOSE the inlets and outlets to CCW system to separate it from the Service Water system. SW provides cooling to components that are not safety related and therefore not seismic category 1. MSIS separates the seismic category 1 piping from the seismic category 2 piping.A. Incorrect: MSIS will close 2CV-1543-1 and 2CV-1542-2. These valves are normally open to provide SW return flow from the CCW Heat Exchangers and the Main Chiller condensers to the SW return header. SW provides cooling to the CCW Heat Exchangers which provides cooling to the RCP seals.B. Incorrect: MSIS will close 2CV-1543-1 and 2CV-1542-2. Loop 1 and Loop 2 Service Water returns are crosstied during an MSIS actuation via the Emergency Cooling Pond return valves.C. Incorrect: MSIS will close 2CV-1543-1 and 2CV-1542-2, so the first half of the answer is correct. But Loop 1 and 2 Service Water return headers will still be crossed tied with these return valves closed via the Emergency Cooling Pond return valves.

References:

System Training Manual (STM) 2-42, Rev 36, section 3.5.12, pages 36 and 37, and section 3.6.15.1, page 46, SimplifiedService Water drawing, page 61Source: NEWRev: 0Rev Date:9/26/2013 3:05:02Search000026K30210CFR55:41.5 / 41.10 / 45.6 / 45Historical Comments:Rev 1: changed to incorporate NRC comments (mwf 1/29/14)

Tier: 1Group: 1Author:fosterL. Plan: A2LP-RO-SWACW OBJ 11QID #: 7 10Form ES-401-5 Written Exam Question Worksheet

Data for 2014 NRC RO/SRO Exam 29-Jan-14Bank:1933Safety Function 1System Number 029System Title:Anticipated Transient Without Scram (ATWS)

K/AEA1.12Description:Ability to operate and/or monitor the following as they apply to a ATWS: - M/G set power supply and reactortrip breakersRO Imp: 4.1SRO Imp: 4.0Lic Level:

RDifficulty:

2Taxonomy: HQuestion:Consider the following: - Unit 2 is operating at 100% power - Pressurizer Transmitters 2PT-4600-2 AND 2PT-4600-4 that supply signals to the Diverse Scram System (DSS) have failed HIGHThe direct effects of these conditions would cause ________________________. A. These conditions would cause two Reactor trip circuit breakers to open AND NO Reactor trip B. These conditions would cause four Reactor trip circuit breakers to open AND a Reactor trip C. These conditions would cause only the #1' CEA MG Set output contactor to open AND NO Reactor trip D. These conditions would cause the #1 and #2 CEA MG Set output contactors to open AND a Reactor tripAnswer:D. Correct Notes:D. Correct: These conditions would cause the 'A' and 'B' CEA MG Set output contactors to open AND a Reactor Trip.A. Incorrect: These pressure transmitters are independent of the pressure transmitters that feed RPS and Reactor trip breakers would not open initially but all 8 circuit breakers eventually would trip open due to LPD and DNBR trips.B. Incorrect: Same reason as aboveC. Incorrect 2 out of 4 ATWS pressure transmitters failing high will give a full output opening both disconnect contactors causing a Reactor trip

References:

STM 2-63-1, Diverse Scram System, section 2.1, pages 3 and 4Source:NRC Bank QID #1495Rev: 1Rev Date:1/29/2014 8:01:49Search000029A11210CFR55:41.7 / 45.5 / 45.6Historical Comments:NRC Bank QID #1495 used on 2008 NRC ExamRev 1: changed to incorporate NRC comments (mwf 1/29/14)

Tier: 1Group: 1Author:fosterL. Plan:A2LP-RO-DSS OBJ 4QID #: 9 12Form ES-401-5 Written Exam Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Number:

11_(NRC proposed changes to Rev1)

(REFERENCE PROVIDED)

Consider the following:

- A Steam Line Break has occurred on the "B" Steam Generator (S/G) outside Containment

- Main Steam Isolation (MSIS) has automatically actuated

- OP-2205.005, Excess Steam Demand EOP

, has been entered

- "B" Steam Generator (S/G) level indicate s 0" (zero) wide range

- RCS Tcold has been stabilized at 398 o F using the "A" S/G

- RCS Thot has been stabilized at 400 oF using the "A" S/G

- Average CET temperature indicates 400 o F In accordance with OP-2202.010, Standard Attachments, t o prevent pressurized thermal shock (PTS) from causing brittle fracture of the Reactor Vessel, RCS pressure should be reduced below ________ psia using ______ spray.

A. 1540 ; Aux B. 1540 ; Main C. 1800 ; Aux D. 1800 ; Main

Proposed Answer:

__B:__1540; Main

__

Explanation:

A. Correct pressure but incorrect spray. With the rupture outside containment but upstream of the MSIV, RCPs would still be running and Main spray is available and it would be used by procedure.

B. Correct pressure and correct spray. Using OP-2202.10, Standard Attachments, Attachment 1, P-T Limits, the second bullet states "Use 200 oF MTS line for PTS limit for uncontrolled RCS cooldown below 500 oF Tcold." With conditions given in the stem, this line is the one to be used. The bullet also directs use of RCS Thot in forced circulation to determine RCS MTS. Given in the stem, Thot is stabilized at 400 oF. Using line "B" on the graph, 400 oF RCS temperature correlates to 1540 psia. Since RCPs would still be running, use of Main spray is correct.

C. Incorrect pressure and incorrect spray. 1800 psia is plausible because it is the value that correlates to 400 o F RCS temperature if the applicant incorrectly uses dashed curve "D ," PRI/SEC S/G DP LIMIT. Since RCPs would still be running, Aux spray is incorrect.

D. Incorrect pressure and correct spray. 1800 psia is plausible because it is the value that correlates to 400 oF RCS temperature if the applicant incorrectly uses dashed curve "D," PRI/SEC S/G DP LIMIT. Since RCPs would still be running, Main spray is correct.

Technical Reference(s):

1) OP-2202.005, Excess Steam Demand EOP, Rev 014, step 30, page 12 of 41 2) EOP-2202.005, Excess Steam Demand Tech Guide

, Rev 014, step 30, page 41 of 76

3) OP-2202.010, Standard Attachments, Rev 022, Attachment 1, page 5 of 204 Proposed references to be provided to applicants during examination:

OP-2202.010, Standard Attachments, Rev 022, Attachment 1, page 5 of 204

_

Learning Objective:

A2LP-RO-EESD objective 8

_

Question Source:

Bank # ______ Modified Bank #

___X___ (Note changes or attach parent)

New _______ Question History:

Last NRC Exam parent from NRC 2005 e xa m_(attached)___ Question Cognitive Level:

Memory or Fundamental Knowledge

_____ Comprehension or Analysis __X__ Question Level of Difficulty:

__3__ 10 CFR Part 55 Content:

55.41 __7__ 55.43 _____ Comments: NRC QID #0458 used on 2005 NRC Exam, changed stem conditions, changed answer and changed order of answers.

Data for 2014 NRC RO/SRO Exam 31-Jan-14Bank:1935Safety Function 4System Number E05System Title:Excess Steam Demand K/AEA2.2Description:Ability to determine and interpret the following as they apply to the (Excess Steam Demand): - Adherence toappropriate procedures and operation within the limitations in the facility's license and amendmentsRO Imp: 3.4SRO Imp: 4.2Lic Level:

RSDifficulty:

4Taxonomy: HQuestion:Consider the following:During an ESD event, you were assigned by the CRS to complete step 12 of Emergency Operating Procedure OP-2202.005,Excess Steam Deman EOP, which states "When RCS Tcold less than 510°F, then reduce the number of RCPs as follows."The procedural action taken is to "Verify a maximum of one RCP is running in each loop" but the actual concern is to addresscore lift problems with greater than _________________. A. three RCPs running below 505°F B. three RCPs running below 500°F C. two RCPs running below 505°F D. two RCPs running below 500°FAnswer:B. Correct Notes:Per the ESD EOP basis document, the concern with running greater then three RCP's below 500 degrees F is core lift.

References:

EOP-2202.005, Excess Steam Demand Basis Document, Rev. 013, page 25 of 762102.010, Plant CooldownANO-2 EOP Setpoint Document, setpoint B.5ANO-2 Final Safety Analysis ReportSource: NEWRev: 2Rev Date:1/31/2014 1:14:52Search00CE05A20210CFR55:41.7 / 41.10 / 43.5 / 45Historical Comments:Rev 1: changed to incorporate NRC comments. Corrected notes to include explanation that the Steam break is outside of theContainment Building. Added Thot to stem and changed Tcold to 398 degrees. Added Reference Provided to allow use of OP-2202.010 Attachment 1. (mwf 1/29/14)Rev. 2: changed question to one recommended by NRC. (mwf 1/31/14)

Tier: 1Group: 1Author:fosterL. Plan:A2LP-RO-EESD OBJ 8QID #: 11 14Form ES-401-5 Written Exam Question Worksheet New Question for Q11_Rev2 proposed Same KA E05.EA2.2, All new question for this KA.

Consider the following:

During an ESD event, your were assigned by the CRS to complete step 12 of Emergency Operating Procedure EOP

-2202.005, "Excessive Steam Demand,"

which states

12. WHEN RCS TC less than 510 o F, THEN reduce number of running RCPs as follows:

The procedural action taken is to "Verify a maximum of one RCP is running in each loop

" but the actual concern is to_______________.

A. address core lift problems with greater than three RCPs running below 505 o F B. address core lift problems with greater than three RCPs running below 500 o F C. address core lift problems with greater than two RCPs running below 505 o F D. address core lift problems with greater than two RCPs running below 500 o F Proposed Answer: B core lift is a concern with greater than 3 RCPs below 500F ANO -Please add the distracter pedigree here References provided:________None___ References for question

1. EOP 2205.005, EOP "ESD" Basis document, revision 013, page 25 of 76

2. 2102.010, Plant Cooldown.

3. ANO-2 EOP Setpoint Document, setpoint B.5.

4. FSAR

Question Number:

12_R 1 (NRC recommendations

) Proposed Question:

Consider the following:

- Unit 2 has tripped due to high Containment Building pressure

- Containment Building pressure is 24 psia and trending up

- Annunciator 2K01 B

-7 "LO RELAY TRIP" for 2A1 is in alarm

- Neither--.

- "A" Steam Generator--.

- "B" Steam ----

- SPTAs have been completed RCS cooling would be accomplished from the Control Room by starting ________Condensate Pump because _______________

. A. "A" (2P-2A); there is no control power for the "B" pump B. "B" (2P-2B); the MFIW signal cannot be overridden for the "A" pump C. "C" (2P-2C); the MFIW signal cannot be overridden for the "D" pump D. "D" (2P-2D); there is no control power for the "B" pump Proposed Answer:

__D_

Explanation:

Distracters "

A" and "C" are not correct because condensate pumps "A" and "C" are both powered by 2A1, which has a lockout on the bus and the second part of the distracter is not needed. For distracter "B" although it is correct that the MFIW signal cannot be overridden for the "A" pump (second part is true) the "B" pump has no DC control power because of (ANO put in reason here)---and therefore cannot be started from the control room.

This makes "D" the only correct answer for both parts and involves knowledge of the interlocks and features from the control room ANO please verify this is correct!

Data for 2014 NRC RO/SRO Exam 29-Jan-14Bank:1936Safety Function 4System Number E06System Title:Loss of Feedwater K/AEK2.1Description:Knowledge of the interrelations between the (Loss of Feedwater) and the following: - Components, andfunctions of control and safety systems, including instrumentation, signals, interlocks, failure modes, andautomatic and manual featuresRO Imp: 3.3SRO Imp: 3.7Lic Level:

RDifficulty:

4Taxonomy: HQuestion:Consider the following: - Unit 2 has tripped due to high Containment Building pressure - Containment Building pressure is 24 psia and trending up - Annunciator 2K01 B-7 "LO RELAY TRIP" for 2A1 is in alarm - Neither Emergency Feedwater (EFW) pump is available - "A" Steam Generator (S/G) Level is 200" (WR) and trending down - "B" Steam Generator (S/G) Level is 21% (NR) and trending down slowly - SPTAs have been completedRCS cooling would be accomplished by starting ______ Condensate Pump from the Control Room. A. "A" (2P-2A) B. "B" (2P-2B) C. "C" (2P-2C) D. "D" (2P-2D)Answer:D. Correct Notes:D. Correct: For the given conditions, a SIAS, CCAS, EFAS, CSAS, and a MSIS are all present. The CSAS and MSIS signals, along with the MFWIS, will isolate feed and steam to/from the containment to minimize the energy release into containment. OP-2202.009, Functional Recovery EOP, would be entered due to 2 events in progress (ESD and Loss of Feedwater) Normally the EFW pumps would supply feedwater for RCS heat removal but they are unavailable. AFW pump is powered from 2A1 is unavailable. The Functional would direct over riding the MFWIS signal on either the "B" or "C" condensate pumps by opening the control power breakers. This action makes the "B" and "C" Condensate Pumps unavailable to be started from the Control Room. "A" Condensate Pump is not available due to 2A1 being locked out. So the only remaining option is to start "D" Condensate pump from the Control Room.A. Incorrect: "A" Condensate pump is unavailable because 2A1 is locked out.B. Incorrect: "B" Condensate pump is unavailable because it has not control power. The action in the EOP to open "B" and "C" Condensate Pump control power breakers made "B" unavailable for start from the Control Room.C. Incorrect: "C" Condensate Pump is unavailable because 2A1 is locked out.Source: NEWRev: 1Rev Date:1/29/2014 9:06:59Search00CE06K20110CFR55:41.7 / 45.7 Tier: 1Group: 1Author:fosterL. Plan: A2LP-RO-ELOSF OBJ 3QID #: 12 16Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 29-Jan-14

References:

OP-2203.012A, Annunciator Corrective Actions 2K01 window B-7, Rev 045, page 98 of 179OP-2202.009, Functional Recovery EOP, Rev 016, HR-2 step 38.E page 60 of 95OP-2202.010, Standard Attachments, Rev 022, Attachment 57 step 2 page 176 of 204OP-2202.010, Standard Attachments, Rev 022, Attachment 50 step 3 page 146 of 204EOP-2202.009, Functional Recovery Tech Guide, Rev 017, HR-2 step 38 page 260 of 341STM 2-20, Condensate System, Rev 14 section 2.3.4 page 15STM 2-70, Engineered Safety Features Actuation System, Rev 18, section 2.2.4.1 pages 5 and 6, MFWIS table page 55Historical Comments:Rev 1: changed to incorporate NRC comments. Corrected notes to include explanation. Updated references. (mwf 1/29/14) 17Form ES-401-5 Written Exam Question Worksheet

NRC proposed changes to Q15_R1 Consider the following:

- Unit 2 is operating at 100% power - Annunciators "XXXXX" and "YYYYY" are in alarm

As the RO you are asked by the CRS to verify status of ESFAS channels at Panel 2C03. Based on the above plant status, you expect __________.

A. only Trip Path

-1 status lights are out B. only Trip Path

-2 status lights are out C. Trip Path-1 and Trip Path

-3 status lights are out D. Trip Path-2 and Trip Path

-4 status lights are out Proposed Answer:

"C" Trip Path-1 and Trip Pa th-3 status lights are out Explanation:

ANO- please provide the applicable alarm(s) for loss of 2RS

-1 bus in the stem of this question (don't provide the lost bus to them).

Please provide complete pedigree here.

Data for 2014 NRC RO/SRO Exam 31-Jan-14Bank:1939Safety Function 6System Number 057System Title:Loss of Vital AC Electrical Instrument Bus K/A AA2.04Description:Ability to determine and interpret the following as they apply to the Loss of Vital AC Instrument Bus: - ESFsystem panel alarm annunciators and channel status indicatorsRO Imp: 3.7SRO Imp: 4.0Lic Level:

RDifficulty:

2Taxonomy: HQuestion:Consider the following: - Unit 2 is at 100% power - Annunciator 2K01-F10, "2RS1 INVERTER TROUBLE" comes into alarm - Annunciator 2K01-J10, "DIST PNLS 2RS1/2RS3 GROUND" comes into alarm - 2RS-1, 120 Vital AC Bus, voltage is reading 0 volts on SPDSAs the RO you are asked by the CRS to verify status of ESFAS channels at Panel 2C03. Based on the above plant status, youexpect _______________. A. only Trip Path-1 status lights to be out B. only Trip Path-2 status lights to be out C. Trip Path-1 and Trip Path-3 status light to be out D. Trip Path-2 and Trip Path-4 status lights to be outAnswer:C. Correct Notes:2RS-1 powers the RED train (channel 1) components. Each Logic Matrix has 2 individual 12v power supply, powered by adifferent vital bus. A failure of 2RS-1 would cause one side of the AB Logic Matrix ladder, which would cause the AB1 andAB3 Logic Matrix relays to de-energized. This causes the AB1 contact in the Trip Path-1 circuit to open which de-energizesthe Trip Path-1 circuit and makes the indication light on 2C03 go out. The AB3 contact will also open in the Trip Path-3circuit, which causes the Trip Path-3 circuit to de-energized and the status light on 2C03 will go out.

References:

STM 2-70, Engineered Safety Features Actuation system, Rev 18, section 2.0 pages 2-4, section 3.2.8 pages 20-21STM 2-70, Engineered Safety Features Actuation system, Rev 18, Drawing on page 68 and 78OP-2107.008, 120 VAC and 125 VDC Bus Outage, Attachment A, 2RS1 Loads, Page 1 of 3Source: NEWRev: 2Rev Date:1/31/2014 10:40:1Search000057A20410CFR55:41.7 / 41.10 / 43.5 / 45Historical Comments:Rev 1: changed to incorporate NRC comments. Kept K/A and wrote another question. (mwf 1/29/14)Rev. 2: changed to incorporate Kelly's suggested question. (mwf 1/31/14)

Tier: 1Group: 1Author:fosterL. Plan: A2LP-RO-ESFAS OBJ 6QID #: 15 20Form ES-401-5 Written Exam Question Worksheet

Data for 2014 NRC RO/SRO Exam 30-Jan-14Bank:1940Safety Function 6System Number 058System Title:Loss of DC Power K/A AK3.02Description:Knowledge of the reasons for the following responses as they apply to the Loss of DC Power: - Actionscontained in EOP for loss of dc powerRO Imp: 4.0SRO Imp: 4.2Lic Level:

RDifficulty:

4Taxonomy: HQuestion:Consider the following: - Unit 2 is operating at 100% power - The RED battery (2D11) disconnect, 2D-51, has been tagged OPEN in preparations for a battery cell change out - Battery Charger, 2D31A, is supplying 2D01 - 2 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br /> later - Annunciator 2K01 A-10 "CONT CENTER 2D01 UNDER VOLT" comes into alarm - The IAO reports Battery Charger 2D31A has 0 VDC output - All other systems and components operate as designed - The CRS has entered OP-2203.037, Loss of 125 VDC AOPIn accordance with OP-2203.037, the CRS would direct placing ALL points on EITHER _________________________ inbypass to prevent ________________________. A. channel 1 (2C23-1) OR channel 2 (2C23-2); inadvertent Reactor trip B. channel 1 (2C23-1) OR channel 3 (2C23-3); inadvertent Reactor trip C. channel 1 (2C23-1) OR channel 2 (2C23-2); inadvertent actuations if the Reactor were to trip D. channel 1 (2C23-1) OR channel 3 (2C23-3); inadvertent actuations if the Reactor were to tripAnswer:D. Correct Notes:D. Correct: The loss of 125VDC AOP will direct bypassing all points in either Channel 1 or Channel 3 to prevent inadvertent actuations of Green train components. If this action were not performed and the Reactor were to trip, both red train Vital AC buses would be de-energized causing actuations on the ESFAS actuations that come in when the parameter is low.A. Incorrect: The Reactor will not inadvertently trip because the Inverters swap to Alternate Source when the Charger trips.B. Incorrect: The Reactor will not inadvertently trip because the Inverters swap to Alternate Source when the Charger trips.C. Incorrect: The Loss of 125V DC AOP instructs the operators to bypass all point on Channel 1 or Channel 3. Channel 2 is powered from the DC train that still has power.Source:Modified NRC Bank QID #0462Rev: 1Rev Date:1/30/2014 3:27:23Search000058K30210CFR55:41.5 / 41.10 / 45.6 / 45 Tier: 1Group: 1Author:fosterL. Plan:A2LP-RO-A125V OBJ 3QID #: 16 21Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 30-Jan-14

References:

OP-2203.012A, Annunciator Corrective Actions 2K01 window A-10, Rev 045, page 125 of 179OP-2203.037, Loss of 125 V DC AOP, Rev 009, section 2, step 5 page 6 of 57AOP-2203.037, Loss of 125 V DC Tech Guide, Rev 009, section 2, step 5 page 6 of 57STM 2-32-5, 125 Vdc Electrical Distribution, Rev 19, section 2.7.2 page 15, and simplified drawing page 24Historical Comments:NRC Bank QID #0462 used on the 2005 NRC ExamRev. 1, corrected based on NRC comments. (mwf 1/30/14) 22Form ES-401-5 Written Exam Question Worksheet Q 16_R1 (NRC proposed changes)

Proposed Question:

A. Proposed Answer:

Explanation:

The proposed changes submitted in R ev 1 of this question now meet the KA for "knowledge of the reasons for the actions-" but now it needs to have all the pencil marks typed up and submitted and the complete pedigree needs to be updated (the notes section as ANO calls it) to explain why an inadvertent rx trip is not a correct reason for two of the distracters as well as the trip discussion they had before in the original question for the other part of the distracters and the correct answer

.

Data for 2014 NRC RO/SRO Exam 30-Jan-14Bank:1941Safety Function 8System Number 065System Title:Loss of Instrument Air K/A AK3.03Description:Knowledge of the reasons for the following responses as they apply to the Loss of Instrument Air: - Knowingeffects on plant operation of isolating certain equipment from instrument airRO Imp: 2.9SRO Imp: 3.4Lic Level:

RDifficulty:

4Taxonomy: HQuestion:During a Loss of Instrument Air, CEDM coil temperatures will be monitored. This is due to a loss of air to___________________. A. CEDM Cooling Fan Dampers B. Containment Chilled Water Isolation Valves C. CEDM Cooling Water Temperature Control Valves D. Containment Cooling Fan DampersAnswer:B. Correct Notes:A. Incorrect: The CEDM Cooling Fan Dampers are Motor Operated not Air Operated.B. Correct: The Containment Chilled Water Isolation Valves fail closed on Instrument Air, which isolates chilled water to the CEDM Cooling Fans.C. Incorrect: The CEDM Coolers do not have temperature control valvesD. Incorrect: The Containment Cooler Dampers are motor operated.

References:

STM 2-45, Main Chill Water System, Rev. 18, pages 1 and 23. (mwf 1/30/14)Source:ANO BANK QID ANO-OpsUnit2-09557Rev: 1Rev Date:1/30/2014 3:40:31Search000065K30310CFR55:41.5 / 41.10 / 45.6 / 45Historical Comments:Rev. 1: Used ANO Bank question ANO-OpsUnit2-09557 per NRC suggestion. (mwf 1/30/14)

Tier: 1Group: 1Author:fosterL. Plan:A2LP-RO-ALIA OBJ 3QID #: 17 23Form ES-401-5 Written Exam Question Worksheet

Data for 2014 NRC RO/SRO Exam 29-Jan-14Bank:1945Safety Function 7System Number 033System Title:Loss of Intermediate Range Nuclear Instrument K/A AK3.01Description:Knowledge of the reasons for the following responses as they apply to the Loss of Intermediate Range NuclearInstrumentation: - Termination of startup following loss of intermediate-range instrumentationRO Imp: 3.2SRO Imp: 3.6Lic Level:

RDifficulty:

3Taxonomy: HQuestion:Consider the following: - Unit 2 is in Mode 2 with a Reactor Startup in progress - OP-2102.016, Reactor Startup, is in progress - Annunciator 2K10 K-4 "STARTUP CHANNEL 1 TROUBLE" comes in alarm - Annunciator 2K10 K-5 "STARTUP CHANNEL 2 TROUBLE" comes in alarm - The CRS declares Startup Channel #1 and #2 INOPERABLEOP-2102.016 _________________. A. allows the startup to continue because Startup Channels are not required in this mode B. allows the startup to continue as long as boron samples are taken every 15 minutes C. does NOT allow the startup to continue because BOTH Startup Channels are required to be OPERABLE during the startup D. does NOT allow the startup to continue because a minimum of ONE Startup Channel must be OPERABLE during the startupAnswer:C. Correct Notes:The Startup Channels provide source and intermediate range indication during the reactor startup. The Startup Channels arethe primary means of monitoring neutron count rate during a startup.C. Correct: OP-2102.016 limit and precaution 5.9 that states if unexpected conditions arise the reactor should be place in a safe condition, this is also covered during the pre-job brief, also step 7.38A. Incorrect:B. Incorrect: There are no contingency actions that can be taken if Startup Channels are lost so that the reactor startup can continue.D. Incorrect, BOTH Startup Channels are required to be OPERABLE to perform reactor startup.

References:

STM 2-67-1, Excore Nuclear Instrumentation, Rev 11 section 2.1 page 2 and section 2.3.3 page 8OP-2102.016, Reactor Startup, Rev 021 section 5.0, step 5.9 page 5 of 31 and Attachment C section 1.0 page 28 of 31OP-2203.012J, Annunciator Corrective Actions 2K10 window K-4, rev 039 page 54 of 84T.S. 3.3.3.5, Remote Shutdown instrumentationOP-2203.012J, Annunciator Corrective Actions window 2K10 K-5, rev 039 page 61 of 84Source:NRC Bank QID #1728Rev: 1Rev Date:1/29/2014 11:30:1Search000033K30110CFR55:41.5 / 41.10 / 45.6 / 45 Tier: 1Group: 2Author:fosterL. Plan: OBJQID #: 21 28Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 29-Jan-14Tech Spec 3.9.2, refueling instrumentationHistorical Comments:NRC Bank QID #1728, used on 2011 NRC Exam. Original QID 121 was used on the 1998 NRC ExamRev 1: changed to incorporate NRC comments. Updated notes to explain that Startup Channels serve the purpose ofIntermediate range instrumentation during a reactor startup. (mwf 1/29/14) 29Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 29-Jan-14Bank:1947Safety Function 3System Number 037System Title:Steam Generator (S/G) Tube Leak K/A AA2.11Description:Ability to determine and interpret the following as they apply to the Steam Generator Tube Leak: - When toisolate one or more S/GsRO Imp: 3.8SRO Imp: 3.8Lic Level:

RDifficulty:

3Taxonomy: HQuestion:Consider the following: - Unit 2 has shutdown due to a 1 gpm tube leak in the "A" Steam Generator (S/G) - SPTAs are complete - A natural circulation cooldown is in progress due to a common problem with the RCPs - OP-2203.038, Primary to Secondary Leakage AOP, is being implemented - "A" S/G hot leg temperature is 537°F - "A" S/G cold leg temperature is 508°F"A" S/G ______________ isolation criteria of OP-2203.038, based on _______ leg temperature. A. meets; hot B. does not meet; hot C. meets; cold D. does not meet; coldAnswer:B. Correct Notes:OP-2203.038 AOP directs isolating the leaking S/G when Thot is <535°F. The given conditions place the plant in naturalcirculation which will have a large loop temperature differential. Student has to know both isolation critieria is based on Thot,not Tcold and <535°F.

References:

OP-2203.038, Primary to Secondary Leakage AOP, Rev 014, step 25, page 17 of 32AOP-2203.038, Primary to Secondary Leakage Tech Guide, Rev 014, step 25, page 25 of 81Source: NEWRev: 1Rev Date:1/29/2014 11:30:0Search000037A21110CFR55:41.7 / 41.10 / 43.5 / 45Historical Comments:Rev 1: changed to incorporate NRC comments. (mwf 1/29/14)

Tier: 1Group: 2Author:fosterL. Plan: A2LP-RO-APSEC OBJ 3QID #: 23 31Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 29-Jan-14Bank:1948Safety Function 9System Number 067System Title:Plant Fire on Site K/A2.4.31Description:Emergency Procedures/Plan - Knowledge of annunciator alarms, indications, or response procedures.RO Imp: 4.2SRO Imp: 4.1Lic Level:

RDifficulty:

2Taxonomy: FQuestion:Consider the following: - Unit 2 is operating at 100% power - The Control room gets a report of a fire at the cooling tower - OP-2203.034, Fire and Explosion AOP, has been enteredFor this event, the ____________________ would respond to the fire and, at a MINIMUM, a ________________________must be dispatched to the scene as a communicator to coordinate with the Control Room. A. ANO Fire Brigade; knowledgeable member of plant staff B. ANO Fire Brigade; operator qualified Waste Control Operator (WCO) C. London Fire Department; knowledgeable member of plant staff D. London Fire Department; operator qualified Waste Control Operator (WCO)Answer:C. Correct Notes:IAW OP-2203.034, Fire and Explosion AOP section 4

References:

OP-2203.034, Fire and Explosion AOP, Rev 015, section 4, steps 2 and 5, page 24 of 36AOP-2203.034, Fire and Explosion Tech Guide, Rev 015, section 4, steps 2, page 37 of 44, and step 5, page 39 of 42Source: NEWRev: 1Rev Date:1/29/2014 12:18:0Search000067243110CFR55:41.10 / 45.3Historical Comments:Rev 1: changed to incorporate NRC comments. Changed distractor to say "operator qualified as WCO". (mwf 1/29/14)

Tier: 1Group: 2Author:fosterL. Plan:A2LP-RO AFIRE OBJ 2QID #: 24 32Form ES-401-5 Written Exam Question Worksheet

Data for 2014 NRC RO/SRO Exam 29-Jan-14Bank:1949Safety Function 8System Number 068System Title:Control Room Evacuation K/A AK3.18Description:Knowledge of the reasons for the following responses as they apply to the Control Room Evacuation: - Actionscontained in EOP for control room evacuation emergency taskRO Imp: 4.2SRO Imp: 4.5Lic Level:

RDifficulty:

3Taxonomy: HQuestion:Consider the following: - Unit 2 is operating at 100% power - Unit 1 Halon system is inadvertently discharging into the Control Room envelope - The Unit 2 Shift Manager directs the Unit 2 Control Room to be evacuated - OP-2203.030, Remote Shutdown AOP, has been enteredPrior to exiting the Control Room, OP-2203.030 verifies both ______________________ to prevent__________________________________ . A. Main Steam Isolation Valves (MSIVs) closed; overpressurizing the Main Condenser B. Main Feedwater pumps tripped; overpressurizing the Main Condenser C. Main Steam Isolation Valves (MSIVs) closed; overcooling the RCS D. Main Feedwater pumps tripped; overcooling the RCSAnswer:D. Correct Notes:D. Correct: The Remote Shutdown AOP verifies both MFPs are tripped prior to exiting the Control Room [step 7] to minimize the possibility of overcooling the RCS due to over feeding.A. Incorrect: Closing the Main Steam isolation Valves (MSIVs) prior to exiting the control room would prevent feeding the S/Gs with the MFPs [no steam to drive them] but is not directed in Remote Shutdown AOP [it is an action specified by the Alternate Shutdown AOP].B. Incorrect: , Both MFWPs are tripped prior to exiting the Control Room, but not to prevent overpressurizing the Main Condenser. The MFWP Turbines do exhaust to the Main Condenser, but in a Remote Shutdown scenario the Main Condenser is available.C. Incorrect: Closing the Main Steam isolation Valves (MSIVs) prior to exiting the control room would prevent prevent overcooling of the RCS, but is not directed in Remote Shutdown AOP [it is an action specified by the Alternate Shutdown AOP].

References:

OP-2203.030, Remote Shutdown AOP, Rev 014, step 7 page 2 of 49AOP-2203.030, Remote Shutdown Tech Guide, Rev 014, step 7 page 9 of 26Source: NEWRev: 1Rev Date:1/29/2014 8:40:10Search000068K31810CFR55:41.5 / 41.10 / 45.6 / 45Historical Comments:

Tier: 1Group: 2Author:fosterL. Plan:A2LP-RO-ARS OBJ 1&2QID #: 25 33Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 29-Jan-14Rev 1 changed question to ask a reason for actions based on NRC comments. Notes and References changed. (mwf 1/29/14) 34Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 19-Feb-14Bank:1949Safety Function 8System Number 068System Title:Control Room Evacuation K/A AK3.18Description:Knowledge of the reasons for the following responses as they apply to the Control Room Evacuation: - Actionscontained in EOP for control room evacuation emergency taskRO Imp: 4.2SRO Imp: 4.5Lic Level:

RDifficulty:

3Taxonomy: HQuestion:Consider the following: - Unit 2 is operating at 100% power - Unit 1 Halon system is inadvertently discharging into the Control Room envelope - The Unit 2 Shift Manager directs the Unit 2 Control Room to be evacuated - OP-2203.030, Remote Shutdown AOP, has been enteredPrior to exiting the Control Room, OP-2203.030 verifies both ______________________ to prevent__________________________________ . A. Main Steam Isolation Valves (MSIVs) closed; overpressurizing the Main Condenser B. Main Feedwater pumps tripped; overpressurizing the Main Condenser C. Main Steam Isolation Valves (MSIVs) closed; overcooling the RCS D. Main Feedwater pumps tripped; overcooling the RCSAnswer:D. Correct Notes:D. Correct: The Remote Shutdown AOP verifies both MFPs are tripped prior to exiting the Control Room [step 7] to minimize the possibility of overcooling the RCS due to over feeding.A. Incorrect: Closing the Main Steam isolation Valves (MSIVs) prior to exiting the control room would prevent feeding the S/Gs with the MFPs [no steam to drive them] but is not directed in Remote Shutdown AOP [it is an action specified by the Alternate Shutdown AOP].B. Incorrect: Both MFWPs are tripped prior to exiting the Control Room, but not to prevent overpressurizing the Main Condenser. The MFWP Turbines do exhaust to the Main Condenser, but in a Remote Shutdown scenario the Main Condenser is available.C. Incorrect: Closing the Main Steam isolation Valves (MSIVs) prior to exiting the control room would prevent prevent overcooling of the RCS, but is not directed in Remote Shutdown AOP [it is an action specified by the Alternate Shutdown AOP].

References:

OP-2203.030, Remote Shutdown AOP, Rev 014, step 7 page 2 of 49AOP-2203.030, Remote Shutdown Tech Guide, Rev 014, step 7 page 9 of 26Source: NEWRev: 2Rev Date:1/29/2014 8:40:10Search000068K31810CFR55:41.5 / 41.10 / 45.6 / 45Historical Comments:Rev 1 changed question to ask a reason for actions based on NRC comments. Notes and References changed. (mwf 1/22/14)

Tier: 1Group: 2Author:fosterL. Plan:A2LP-RO-ARS OBJ 1&2QID #: 25 30Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 19-Feb-14Rev 2: Changed distractors and notes [ 1/29/2014]

31Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 29-Jan-14Bank:1951Safety Function 0System Number E09System Title:Functional Recovery K/AEK1.2Description:Knowledge of the operational implications of the following concepts as they apply to the (FunctionalRecover): - Normal, abnormal and emergency operating procedures associated with (Functional Recovery)RO Imp: 3.2SRO Imp: 4.0Lic Level:

RDifficulty:

3Taxonomy: HQuestion:Consider the following: - Unit 2 has tripped from 100% power - "A" Steam Generator has a 0.12 gpm tube leak - Containment Pressure, Temperature and Humidity are trending up - Containment Low Range Rad monitors are trending up - SPTAs are complete __________________ EOP would be entered, and to control secondary contamination,_________________________________ would be implemented. A. Steam Generator Tube Rupture; Standard Attachment 10, SG Isolation B. Steam Generator Tube Rupture; Standard Attachment 17, LOCA Isolation C. Functional Recovery; Standard Attachment 10, SG Isolation D. Functional Recovery; Standard Attachment 17, LOCA IsolationAnswer:C. Correct Notes:Conditions given indicate 2 events in progress (SGTR and LOCA) which is an entry condition for the FRP. StandardAttachment 10 is directed by the FRP (HR-2 step 16) to isolate the "A" S/G and control secondary contamination.

References:

OP-2202.009, Functional Recovery EOP, Rev 017, section HR-1, step 13 page 10 of 95EOP-2202.009, Functional Recovery Tech Guide, Rev 016, section HR-1, step 16 page 239 of 341OP-2202.010, Standard Attachments, Rev 021, Att. 10 pages 26 and 27 of 204 and Att. 19, pages 62-66 of 186Source: NEWRev: 1Rev Date:1/29/2014 12:23:5Search00CE09K10210CFR55:41.8 / 41.10 / 45.3Historical Comments:Rev 1 changed question based on NRC comments. (mwf 1/29/14)

Tier: 1Group: 2Author:fosterL. Plan:A2LP-RO-EFRP OBJ 1&4QID #: 27 36Form ES-401-5 Written Exam Question Worksheet Q 29 Suggested Revisions

- TJ Farina Suggested revisions are in RED font. Consider the following:

- Unit 2 is tripped due to a Loss of Coolant Accident (LOCA)

- OP-2202.003, Loss of Coolant Accident EOP, is being implemented

- Reactor Coolant System (RCS) is water solid During water solid operations, placing letdown in service would cause __(1)____ to RAPIDLY lower. Void formation in SG U

-tubes is minimized by maintaining BOTH SGs pressure __(2)___ than RCS pressure.

(1) (2) A. Pressurizer leve l; less B. Pressurizer pressure; less C. Pressurizer level

greater D. Pressurizer pressure

greater Answer

B [Source: 2202.010 STANDARD ATTACHMENT 34: RCS WATER SOLID OPERATIONS, Step 2

]

Data for 2014 NRC RO/SRO Exam 30-Jan-14Bank:1953Safety Function 1System Number 004System Title:Chemical and Volume Control System (CVCS)

K/A K5.30Description:Knowledge of the operational implications of the following concepts as they apply to the CVCS: -Relationship between temperature and pressure in CVCS components during solid plant operationRO Imp: 3.8SRO Imp: 4.2Lic Level:

RDifficulty:

2Taxonomy: FQuestion:Consider the following: - Unit 2 is tripped due to a Loss of Coolant Accident (LOCA) - OP-2202.003, Loss of Coolant Accident EOP, is being implemented - The Reactor Coolant System (RCS) is water solidDuring water solid operations, placing letdown in service would cause _______________ to RAPIDLY lower. Void formationin SG U-tubes is minimized by maintaining BOTH SGs pressure _______ than RCS pressure. A. Pressurizer level; less B. Pressurizer level; greater C. Pressurizer pressure; less D. Pressurizer pressure; greaterAnswer:C. Correct Notes:Per OP-2202.010 Standard Attachment 34, in a solid plant condition small changes in either temperature or level will cause alarge change in pressure and to minimize void formation in SG U-tubes by maintaining BOTH SGs less than RCS pressure.

References:

OP-2202.003, Loss of Coolant Accident EOP, Rev 014, section 2 page 14 of 67OP-2202.010, Standard Attachment, Rev. 022, Attachment 34, RCS Water Solid Operations, Step 2, page 109 of 205Source: NEWRev: 1Rev Date:1/30/2014 4:34:00Search004000K53010CFR55:41.5 / 45.7Historical Comments:Rev. 1: changed based on NRC feedback. (mwf 1/30/14)

Tier: 2Group: 1Author:fosterL. Plan:A2LP-RO-CVCS OBJ 2QID #: 29 37Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 30-Jan-14Bank:1953Safety Function 1System Number 004System Title:Chemical and Volume Control System (CVCS)

K/A K5.30Description:Knowledge of the operational implications of the following concepts as they apply to the CVCS: -Relationship between temperature and pressure in CVCS components during solid plant operationRO Imp: 3.8SRO Imp: 4.2Lic Level:

RDifficulty:

2Taxonomy: FQuestion:Consider the following: - Unit 2 is tripped due to a Loss of Coolant Accident (LOCA) - OP-2202.003, Loss of Coolant Accident EOP, is being implemented - The Reactor Coolant System (RCS) is water solidDuring water solid operations, placing letdown in service would cause _______________ to RAPIDLY lower. Void formationin SG U-tubes is minimized by maintaining BOTH SGs pressure _______ than RCS pressure. A. Pressurizer level; less B. Pressurizer level; greater C. Pressurizer pressure; less D. Pressurizer pressure; greaterAnswer:C. Correct Notes:Per OP-2202.010 Standard Attachment 34, in a solid plant condition small changes in either temperature or level will cause alarge change in pressure and to minimize void formation in SG U-tubes by maintaining BOTH SGs less than RCS pressure.

References:

OP-2202.003, Loss of Coolant Accident EOP, Rev 014, section 2 page 14 of 67OP-2202.010, Standard Attachment, Rev. 022, Attachment 34, RCS Water Solid Operations, Step 2, page 109 of 205Source: NEWRev: 1Rev Date:1/30/2014 4:34:00Search004000K53010CFR55:41.5 / 45.7Historical Comments:Rev. 1: changed based on NRC feedback. (mwf 1/30/14)

Tier: 2Group: 1Author:fosterL. Plan:A2LP-RO-CVCS OBJ 2QID #: 29 37Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 29-Jan-14Bank:1954Safety Function 4System Number 005System Title:Residual Heat Removal System (RHRS)

K/A K2.01Description:Knowledge of bus power supplies to the following: - RHR pumpsRO Imp: 3.0SRO Imp: 3.2Lic Level:

RDifficulty:

3Taxonomy: FQuestion:Consider the following: - Unit 2 is in Mode 6 - Startup #3 Transformer is supplying plant 'in-house' loads - Startup #2 Transformer handswitches are OUT of Pull-to-Lock (PTL) for 2A1 and 2A2 - The Alternate AC Diesel Generator (AACDG) is Available - #2 EDG is OOS for maintenance - "A" Spray pump (2P-35A) is aligned for Shutdown Cooling and is in service - Annunciator 2K01 A-3 "L.O. RELAY TRIP" for Startup #3 comes into alarm - NO operator actions have been takenOP-2203.029, Loss of Shutdown Cooling AOP, entry conditions ____________ and the "A" Spray pump (2P-35A) ________running. A. have been met; is B. have not been met; is C. have been met; is not D. have not been met; is notAnswer:B. Correct Notes:The "A" Spray Pump is powered off of the RED vital AC train (2A3) which is supplied by 2A1 non vital switchgear. Offsitepower to the site during an outage is supplied by the Startup #3 transformer with the Startup #2 transformer in standby(available for fast transfer) to both RED and GREEN buses. A Startup #3 Lockout will initiate a fast transfer of 2A1 toStartup #2. The safety bus will not see a loss of power and the Spray pump will continue to run. The Loss of SDC Entryconditions are not met and the control room staff would respond to the Startup #3 Lock out per the ACA.

References:

OP-2107.001, electrical System Operations, Rev. 104, Note before section 7.0 step 7.2 page 26 of 311STM 2-14, Shutdown Cooling System, Rev 11, section 2.2.2 page 12Source: NEWRev: 1Rev Date:1/29/2014 12:29:2Search005000K20110CFR55: 41.7Historical Comments:Rev 1 changed question based on NRC comment to capitalize annunciator name. (mwf 1/29/14)

Tier: 2Group: 1Author:fosterL. Plan:A2LP-RO-ECCS OBJ 12QID #: 30 39Form ES-401-5 Written Exam Question Worksheet

Q 31 Suggested Revisions

- TJ Farina REVIEWER COMMENT:

Is there ever a time LPSI discharge would recirc back to suction piping?

If not, then that distractor is implausible.

REVISED OPTION: Consider the following:

- Unit 2 has tripped from 100% power due to a LOCA 15 minutes ago

- RCS pressure is 1400 psia and slowly trending down

- All systems operate as designed Low Pressure Safety Injection system (LPSI) ____ be injecting into the RCS and the Low Pressure Safety Injection pump recirculation flow path would be _________ .

A. would; aligned to Refueling Water Tank (RWT)

B. would not; aligned to Refueling Water Tank (RWT)

C. would; isolated D. would not; isolated Answer: B. Correct

Data for 2014 NRC RO/SRO Exam 29-Jan-14Bank:1955Safety Function 2System Number 006System Title:Emergency Core Cooling System (ECCS)

K/A K4.09Description:Knowledge of ECCS design feature(s) and/or interlock(s) which provide for the following: - Valve positioningon safety injection signalRO Imp: 3.9SRO Imp: 4.2Lic Level:

RDifficulty:

2Taxonomy: HQuestion:Consider the following: - Unit 2 has tripped from 100% power due to a LOCA 15 minutes ago - RCS pressure is 1400 psia and slowly trending downLow Pressure Safety Injection system (LPSI) injection MOVs are ________ and the LPSI pumprecirculation valves to the Refueling Water Tank (RWT) would be ____________ . A. open; open B. open; closed C. closed; open D. closed; closedAnswer:A. Correct Notes:A Safety Injection Actuation (SIAS) occurs when RCS pressure drops below 1650#. The SIAS will start the LPSI pumps andopen the injection MOVs to the RCS. The LPSI pump recirc flowpath is aligned to the RWT, if a Recirc Actuation Signal(RAS) occurred the LPSI pump is tripped and the recirc flowpath valves would go closed, isolating the LPSI recirc flowpathfrom the RWT. A RAS is not actuated based on the time given [15 minutes] the RWT holds enough inventory to supply theECCS pumps for 30 minutes during a DBA. The given conditions does not indicate a DBA in progress [RCS pressure 1400#and slowly trending down] therefore the LPSI recirc flowpath valves to the RWT are open.

References:

STM 2-05, Emergency Core Cooling System, Rev 27, section 4.4.2, pages 36 and 37STM 2-08, Containment Spray System, Rev 22, section 3.1.1 pages 7 and 8Source: NEWRev: 1Rev Date:1/29/2014 12:30:2Search006000K40910CFR55: 41.7Historical Comments:Rev 1 based on NRC comments. (mwf 1/29/14)

Tier: 2Group: 1Author:fosterL. Plan:A2LP-RO-ECCS OBJ 13QID #: 31 40Form ES-401-5 Written Exam Question Worksheet NRC proposed changes to Q 32_R0 (TJF) ORIGINAL QUESTION:

Consider the following

-Unit 2 is operating at 100% power

-Annunciator 2K07 A

-1 "SIAS ACT" is in alarm

- The Reactor did not trip

- RCS pressure 2200 psia and steady

- Containment parameters are normal and steady The CRS has entered the appropriate AOP and would direct the CBOT to override and _______ _

A. open Service Water (SW) to Aux Cooling Water (ACW) supply isolation valves B. open the Component Cooling Water (CCW) isolation valves to the containment building C. close the ECCS Containment Sump isolation valves inside the containment building D. close the ECCS Containment Sump isolation valves outside the containment building Answer: A. Correct Notes: Action is in accordance with the Inadvertent SIAS AOP REVIEWER COMMENT:

Distractors C and D are essentially the same. Is there a time when it would be procedurally directed to close one but not the other Ctmt Sump isolation valve? If not, replace one with a new distractor.

REVISED OPTION: Consider the following

-Unit 2 is operating at 100% power

-Annunciator 2K07 A

-1 "SIAS ACT" is in alarm

- The Reactor did not trip

- RCS pressure 2200 psia and steady

- Containment parameters are normal and steady The CRS has entered the appropriate AOP and would direct the CBOT to override and _______ _

A. open Service Water (SW) to Aux Cooling Water (ACW) supply isolation valves B. open the Component Cooling Water (CCW) isolation valves to the containment building C. close the HPSI Orifice Bypass Valves (2CV-5103-1 and 2CV-5104-2) D. close the ECCS Containment Sump isolation valves outside the containment building Answer: A. Correct Data for 2014 NRC RO/SRO Exam 29-Jan-14Bank:1956Safety Function 2System Number 006System Title:Emergency Core Cooling System (ECCS)

K/A A2.13Description:Ability to (a) predict the impacts of the following malfunctions or operations on the ECCS and (b) based onthose predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions oroperations: - Inadvertent SIS actuationRO Imp: 3.9SRO Imp: 4.2Lic Level:

RDifficulty:

3Taxonomy: HQuestion:Consider the following: - Unit 2 is operating at 100% power - Annunciator 2K07 A-1 "SIAS ACT" is in alarm - The Reactor did not trip - RCS pressure 2200 psia and steady - Containment parameters are normal and steadyThe CRS has entered the appropriate AOP and would direct the CBOT to override and ___________________ . A. open Service Water (SW) to Aux Cooling Water (ACW) supply isolation valves B. open the Component Cooling Water (CCW) isolation valves to the containment building C. close the ECCS Containment Sump isolation valves inside the containment building D. place Containment Spray Pumps in Pull-to-Lock (PTL)Answer:A. Correct Notes:A: Correct. An Inadvertent SIAS will cause the SW to ACW Supply Isolation Valves to close. These valves have to be overridden and opened to prevent a Turbine Runback and is directed early on in the AOP.B: Incorrect. SIAS does not automatically close the CCW isolation valves to the containment building. These will not have to be opened during an Inadvertent SIAS condition.C. Incorrect. The inside Containment Sump Suction Isolation Valves are normally open and do not receive an SIAS. They do receive a RAS and the Inadvertent RAS AOP directs overridding and closing these valves during an Inadvertent RAS. This action is done in the Inadvertent RAS AOP to prevent draining the RWT to the Containment Sump.D. Incorrect. The Containment Spray Pumps do not receive a SIAS and will not have to be secured during an Inadvertent SIAS.

References:

OP-2203.012G, Annunciator Corrective Actions 2K07 window A-1, Rev 030, page 4 of 70OP-2203.018, Inadvertent SIAS AOP, Rev 010, entry section, page 3 of 52AOP-2203.018, Inadvertent SIAS Tech Guide, Rev 009, page 6 of 60Source: NEWRev: 1Rev Date:1/29/2014 12:32:3Search006000A21310CFR55:41.5 / 43.5 / 45.3 / 45.Historical Comments:

Tier: 2Group: 1Author:fosterL. Plan:A2LP-RO-INAD OBJ 1&2QID #: 32 41Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 29-Jan-14Rev 1 added notes to explain incorrect answers and their credibility. Changed D distractor to secure Spray Pump.(mwf1/29/14)42Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 29-Jan-14Bank:1957Safety Function 5System Number 007System Title:Pressurizer Relief Tank/Quench Tank System (K/A A1.02Description:Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated withoperating the PRTS controls including: - Maintaining quench tank pressureRO Imp: 2.7SRO Imp: 2.9Lic Level:

RDifficulty:

3Taxonomy: FQuestion:Consider the following: - Unit 2 is operating at 100% power - Annunciator 2K10 D-4 "QUENCH TANK PRESSURE HI" is in alarm - 2PIS-4694, Quench Tank Pressure, is 42 psig and slowly trending up - 2LIS-4694, Quench Tank Level, is 78% and slowly trending upA possible source of inleakage to the Quench Tank is from ________________________ and the Quench Tank would bedrained to the __________________ to clear the alarm. A. RCS High Point Vents; Containment Sump B. RCS High Point Vents; Reactor Drain Tank C. Pressurizer Spray Valve Stem leakoff; Reactor Drain Tank D. Pressurizer Spray Valve Stem leakoff; Containment SumpAnswer:B. Correct Notes:B. Correct: RCS high point vents discharge into the quench tank and the quench tank is vented to the Reactor Drain TankA. Incorrect: RCS high points vents do go to the Quench Tank but venting to the containment sump is not an option in the OP-2103.007. The quench tank vent path could be aligned to the containment atmosphere thru the high point vent header but is not procedurally driven in the given mode.C. Incorrect: Pressurizer Spray Valve Stem leakoff is not directed to the Quench tank but the Reactor Drain Tank.D. Incorrect: Pressurizer Spray Valve Stem leakoff is not directed to the Quench tank but the Reactor Drain Tank.

References:

OP- 2203.012J, Annunciator Corrective Actions 2K10 window D-4, Rev 039, page 48 of 84STM 2-52, Liquid Radwaste/Boron Management system, Rev 17, section 3.1, page 13STM 2-03, Reactor Coolant System, Rev 22, section 2.3, pages 23 and 24OP-2103.007, Quench Tank and Reactor Drain Tank OPS, Rev 023, section 7.6, page10 of 30Source:NRC Bank QID #1742Rev: 1Rev Date:1/22/2014 1:10:25Search007000A10210CFR55:41.5 / 45.5Historical Comments:used on 2012 NRC Exam Tier: 2Group: 1Author:fosterL. Plan:A2LP-RO-RCS OBJ 25QID #: 33 43Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 29-Jan-14 44Form ES-401-5 Written Exam Question Worksheet

Data for 2014 NRC RO/SRO Exam 29-Jan-14Bank:1960Safety Function 3System Number 010System Title:Pressurizer Pressure Control System (PZR PCS)

K/A K6.01Description:Knowledge of the effect of a loss or malfunction of the following will have on the PZR PCS: - Pressuredetection systemsRO Imp: 2.7SRO Imp: 3.1Lic Level:

RDifficulty:

2Taxonomy: HQuestion:Consider the following: - Unit 2 is operating at 100% power - The "A" Pressurizer Pressure Control Channel is in service - Annunciator 2K12 E-6 "CNTRL CH 1 PRESSURE HI/LO" comes into alarm - "A" Pressurizer pressure instrument (2PS-4626A) reads 1400 psia - "B" Pressurizer pressure instrument (2PS-4626B) reads 2200 psia - No Operator action has been takenThe Pressurizer backup heater breakers would _______________ and the Proportional Heaters would go to a______________ firing rate. A. open; maximum B. close; maximum C. open; minimum D. close; minimumAnswer:B. Correct Notes:The pressure control system would see the false low pressure and with the control channel indicating <25 psia below setpoint(2200 psia @ 100% power) the backup heaters breakers will close and energize all Backup Heaters and send a maximum firecommand to the proportional heaters.

References:

OP- 2203.012J, Annunciator Corrective Actions 2K10 window E-6, Rev 039, page 68 of 84STM 2-03-01, Pressurizer Pressure and Level Control, Rev 16, section 2.0 pages 8, 11 and 12Source:Modified NRC Bank QID #1523Rev: 1Rev Date:1/29/2014 10:07:2Search010000K60110CFR55:41.7 / 45.7Historical Comments:NRC Bank QID #1523 used on 2008 NRC ExamRev 1: changed to incorporate NRC comments (mwf 1/29/14)

Tier: 2Group: 1Author:fosterL. Plan:A2LP-RO-PZR OBJ 4&5QID #: 36 47Form ES-401-5 Written Exam Question Worksheet

Data for 2014 NRC RO/SRO Exam 29-Jan-14Bank:1961Safety Function 7System Number 012System Title:Reactor Protection System K/A A4.03Description:Ability to manually operate and/or monitor in the control room: - Channel blocks and bypassesRO Imp: 3.6SRO Imp: 3.6Lic Level:

RDifficulty:

3Taxonomy: FQuestion:Consider the following: - Unit 2 is performing a plant cooldownAs the RCS is cooled down, the Low RWT Level/Low PZR Pressure Bypasses are ____________ bypassed and the HI/LowS/G Level Bypasses are ____________ bypassed. A. manually; automatically B. automatically; manually C. manually; manually D. automatically; automaticallyAnswer:C. Correct Notes:There is no automatic function to go into bypass for both but either will automatically come out of bypass. The Low RWTLevel/Low PZR Pressure Operating Bypass will come out of bypass when RCS pressure is >436 psia and the HI/Low S/GLevel Operating Bypass will automatically come out of bypass when RCS Th is >195F

References:

OP-2102.010, Plant Cooldown, Rev 049, section 9.6 page 23 of 54 and section 9.18 page 30 of 54STM 2-63, Reactor Protection system, Rev 11, section 6.2.2.2 and section 6.2.2.3 page 44Source: NEWRev: 1Rev Date:1/29/2014 10:07:3Search012000A40310CFR55:41.7 / 45.5 to 45.8Historical Comments:Rev 1: changed to incorporate NRC comments (mwf 1/29/14)

Tier: 2Group: 1Author:fosterL. Plan: A2LP-RO-RPS OBJ 10QID #: 37 48Form ES-401-5 Written Exam Question Worksheet

Data for 2014 NRC RO/SRO Exam 29-Jan-14Bank:1962Safety Function 2System Number 013System Title:Engineered Safety Features Actuation System (K/A K3.01Description:Knowledge of the effect that a loss or malfunction of the ESFAS will have on the following: - FuelRO Imp: 4.4SRO Imp: 4.7Lic Level:

RDifficulty:

3Taxonomy: FQuestion:To limit the peak cladding temperature of the fuel, the Emergency Safety Features Actuation Signal (ESFAS) is used toactuate components in the Emergency Core Cooling System (ECCS) and together they are designed for a loss or malfunction of: A. a failure of a single active component during the injection mode OR a failure of a single active or a single passive component during the recirculation mode B. a failure of a single active component during the injection mode AND a failure of a single active component and a single failure of a passive component during the recirculation mode C. a failure of a single passive component during the injection mode OR a failure of a single active or a single passive component during the recirculation mode D. a failure of a single passive component during the injection mode AND a failure of a single active component and a single passive component during the recirculation modeAnswer:A. Correct Notes:Design bases for ECCS

References:

STM 2-05, Emergency Core Cooling System, Rev 27, section 1.1 pages 1 and 2Tech Spec 3.5.2 and 3.5.3 basesSTM 2-70, Engineerd Safety Features Actuation system, Rev 18, section 2,2,1 page 5, Table on page 8Source: NEWRev: 1Rev Date:1/29/2014 10:08:5Search013000K30110CFR55:41.7 / 45.6Historical Comments:Rev 1: changed to incorporate NRC comments to make B and D distractors sound more plausible. (mwf 1/29/14)

Tier: 2Group: 1Author:fosterL. Plan:A2LP-RO-ECCS OBJ 4QID #: 38 49Form ES-401-5 Written Exam Question Worksheet Q38_R1: NRC comments Upon further review of the question and KA, the proposed question is not a good match to the KA. The KA is asking for knowledge of the effect of a loss or malfunction of ESFAS on the fuel. The question, as proposed, is asking for knowledge of the design requirements of a system that is actuated by an ESFAS signal in response to a design basis LOCA (where the system design is to provide for core cooling that is indirectly related to the KA

).

A better KA match would be a question that asks what would be the effect of failure of the ESFAS to generate an actuation signal(s) whose purpose is to protect the fuel.

For example

- feel free to develop another question

Which ESFAS signal(s), if not generated, would have the effect of more extensive core damage? A. Only SIAS B. SIAS and CIAS C. CIAS and CSAS

D. EFAS, SIAS and RAS

The Lesson Plan should be the one used to teach ESFAS and the Reference should be STM 2

-70, ESFAS.

Data for 2014 NRC RO/SRO Exam 29-Jan-14Bank:1963Safety Function 5System Number 026System Title:Containment Spray System (CSS)

K/A K4.08Description:Knowledge of CSS design feature(s) and/or interlock(s) which provide for the following: - Automaticswapover to containment sump suction for recirculation phase after LOCA (RWST low-low level alarm)RO Imp: 4.1SRO Imp: 4.3Lic Level:

RDifficulty:

3Taxonomy: HQuestion:Consider the following: - Unit 2 has tripped due to a Design Based Accident (DBA) LOCA - One (1) hour has elapsedThe suction source for the running Emergency Core Cooling Systems (ECCS) pumps is aligned to ____________________and adequate core heat removal would be verified using _______________ . A. Refueling Water Tank (RWT); Exhibit 2, HPSI Flow Curve B. Refueling Water Tank (RWT); Exhibit 3, LPSI Flow Curve C. Containment sump; Exhibit 2, HPSI Flow Curve D. Containment sump; Exhibit 3, LPSI Flow CurveAnswer:C. Correct Notes:The RWT inventory will be transferred into the containment building in approximately 30 minutes following the DesignBased Accident (DBA) LOCA. When RWT level reaches 6% (RAS actuation setpoint) the ECCS suction header automaticallyswaps to the containment sump. The LPSI pumps will trip on the RAS to prevent pump damage and cavitation of the HPSIand Spray pumps due to the LPSI high flowrate. LPSI pumps cannot be restarted unless RAS is reset or leads are lifted.Exhibit 2 shows the expected flow for given RCS pressure that is required for Inventory and Heat Removal.

References:

EOP 2202.010, Standard Attachments, Rev 022, exhibit 2, page 181 of 204STM 2-05, Emergency Core Cooling System, Rev 27 , section 1.3, pages 2 and 3STM 2-08, Containment Spray System, Rev 22, section 3.1.1, pages 7 and 8Source:NRC Bank QID #1749Rev: 1Rev Date:1/29/2014 12:48:5Search026000K40810CFR55: 41.7Historical Comments:NRC Bank QID #749 used on the 2006 NRC ExamRev 1 verified that nothing else would start the pump during this time frame. Clarified question statement. (mwf 1/29/14)

Tier: 2Group: 1Author:fosterL. Plan:A2LP-RO-SPRAY OBJ 4QID #: 39 50Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 29-Jan-14Bank:1966Safety Function 4System Number 039System Title:Main and Reheat Steam System (MRSS)

K/A A4.04Description:Ability to manually operate and/or monitor in the control room: - Emergency feedwater pump turbinesRO Imp: 3.8SRO Imp: 3.9Lic Level:

RDifficulty:

3Taxonomy: HQuestion:Consider the following: - Unit 2 is recovering from a complete loss of feedwater event - 2P-7B is out of service for maintenance - "A" S/G level 12% trending down - "B" S/G level 19% trending down - The WCO just reported she has reset 2P-7A and it is ready for startOP-2202.006, Loss of Feedwater EOP directs controlling the initial feed rate to the Steam Generators to prevent____________________ and this would be accomplished by ________________________ . A. damaging the feed ring; throttling the injection valves B. damaging the feed ring; controlling pump speed C. overcooling the RCS; throttling the injection valves D. overcooling the RCS; controlling pump speedAnswer:B. Correct Notes:With S/G level <49%, the feed ring is uncovered and the water will flash to steam. There is a possibility of collapsing thefeed ring when cold feed water is restored. The EOP direct controlling feedwater flow to <150 gpm to minimize the chance offeed ring damage. 2P-7A is the steam driven EFW pump and its S/G feed injection valves are not throttlable. The EOP directscontrolling pump speed to control feed rate. This scenario also assumes 2P-7B is out of service and not available to start. 2P-7B is normally the first choice when restoring feedwater in a loss of feedwater event.

References:

OP-2202.006, Loss of Feedwater EOP, Rev 011, step 12 page 5 of 25OP-2202.010, Standard Attachment, Rev 022, Att. 54 step 3 page 1 of 3, step 9 page 3 of 3EOP-2202.006, Loss of Feedwater Tech Guide, Rev 009, step 12 pages 19 and 20 of 62Source: NEWRev: 1Rev Date:1/29/2014 1:29:01Search039000A40410CFR55:41.7 / 45.5 to 45.8Historical Comments:Rev 1 added 2P-7B OOS in stem. (mwf 1/29/14)

Tier: 2Group: 1Author:fosterL. Plan: A2LP-RO-ELOSF OBJ 3&4QID #: 42 53Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 29-Jan-14Bank:1967Safety Function 4System Number 059System Title:Main Feedwater (MFW) System K/A K3.03Description:Knowledge of the effect that a loss or malfunction of the MFW System will have on the following: - S/GsRO Imp: 3.5SRO Imp: 3.7Lic Level:

RDifficulty:

2Taxonomy: HQuestion:Consider the following: - Unit 2 is operating at 80% power - The "A" Feed Water Control System (FWCS) Master Controller, 2FIC-1029, has been placed in MANUAL due to a malfunction - The Unit now trips - No Operator actions are takenThe "A" Steam Generator level would ________________ rise and operator action _________ required to prevent a HighLevel Override (HLO) from occurring. A. continuously; is B. continuously; is not C. initially shrink then slowly; is D. initially shrink then slowly; is notAnswer:C. Correct Notes:With the Master controller in manual the response to a reactor trip are unaffected allowing Steam Generator levels to bemaintained by the RTO signal. When the RTO condition has cleared [level >55% after 60 seconds] operator action would berequired to prevent S/G levels from continually rising as set by the manual demand on the master controller pre trip.

References:

STM 2-69, Feedwater Control System, Rev 13, section 2.1 page 3, section 2.7 page 31, and section 3.3 page 39Source:NRC BANK QID #0669Rev: 1Rev Date:1/29/2014 1:32:12Search059000K30310CFR55:41.7 / 45.6Historical Comments:NRC Bank QID #0669 used on the 2003 NRC Exam Tier: 2Group: 1Author:fosterL. Plan: A2LP-RO-FWCD OBJ 14QID #: 43 54Form ES-401-5 Written Exam Question Worksheet Comments on Question 4 3, Revision 1 There was no additional information provided on function of the HLO feature. This is needed to support why the proposed correct answer is correct.

Data for 2014 NRC RO/SRO Exam 29-Jan-14Bank:1968Safety Function 4System Number 059System Title:Main Feedwater (MFW) System K/A A2.07Description:Ability to (a) predict the impacts of the following malfunctions or operations on the MFW System and (b)based on those predictions, use procedures to correct, control, or mitigate the consequences of thosemalfunctions or operations: - Tripping of MFW pump turbineRO Imp: 3.0SRO Imp: 3.3Lic Level:

RDifficulty:

2Taxonomy: HQuestion:Consider the following: - Unit 2 has completed a plant startup and is raising power - Current power is 5% and trending up - "A" and "C" Condensate Pumps (2P-2A and 2P-2C) are running - "A" Main Feed Pump (2P-1A) is in operation - "B" Main Feed Pump (2P-1B) is idling for oxygen control - Auxiliary Feedwater Pump (2P-75) is running - 2P-75 Discharge to MFW Flow Control valve (2CV-0762) is open - Both Emergency Feedwater Pumps (2P-7A and 2P-7B) are in standby - Annunciator 2K03-A8 "FEED PUMP TRIP" is in alarm for "A" MFP - OP-2203.027, Loss of Main Feedwater Pump AOP has been enteredThe Main Feedwater Control System will _________________. A. automatically raise 2P-1B speed and Steam Generator levels will be maintained at setpoint B. automatically throttle Main Feedwater Regulating Valve and Steam Generator levels will be maintained at setpoint C. require manual operator action to raise 2P-1B speed to restore Steam Generator levels to setpoint D. require manual operator action to throttle Main Feedwater Regulating Valve to restore Steam Generator levels to setpointAnswer:C. Correct Notes:C. Correct. With 2P-1B idling for oxygen control, its speed controller is in manual and speed is too low to feed the Steam Generators without the operator manually raising speed. This action is directed by the AOP to restore SG levels.A. Incorrect. 2P-1B speed will not automatically raise because the speed controller is in manual while idling.B. Incorrect. The FWCS will open the MFRV's to try and restore level, but 2P-75 will not provide enough flow to restore SG level at 5% power. Per the procedure, it will only provide enough flow for 4% reactor power.D. Incorrect. Manually opening the MFRV's will not restore level to setpoint. 2P-75 will not provide enough flow at 5% to maintain Steam Generator levels at setpoint.Source: NEWRev: 1Rev Date:1/29/2014 5:39:58Search059000A20710CFR55:41.5 / 43.5 / 45.3 / 45.

Tier: 2Group: 1Author:fosterL. Plan: A2LP_RO-AMFP OBJ 3QID #: 44 55Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 29-Jan-14

References:

OP-2203.027, Loss of Main Feedwater Pump, Rev. 014, page 2 of 11, Step 3.A and Step 3.CSTM 2-19-2, EFW & AFW Systems STM, page 27, Section 3.2OP-2106.007, Main Feedwater Pump and FWCS Operation, Rev. 052, page 36 of 113, Step 9.6Historical Comments:Rev. 1, reworded stem and distractors to address NRC comments on K/A match. (mwf 1/29/14) 56Form ES-401-5 Written Exam Question Worksheet The submitted Revision 1 was re

-written to address the a) portion of the K/A statement, but deleted any testing of the b) portion of K/A A2.07.

A proposed modification to Revision 1 addressing the entire K/A statement is as follows:

Q 44_R1 (NRC proposed changes to Rev1)

Proposed Question:

Consider the following:

- Unit 2 has completed a plant startup and is raising power

- Current power is 5% and trending up

- "A" and "C" Condensate Pumps (2P

-2A and 2P-2C) are running

- "A" Main Feed Pump (2P

-1A) is in operation

- "B" Main Feed Pump (2P

-1B) is idling for oxygen control

- Auxiliary Feedwater Pump (2P

-75) is running

- 2P-75 Discharge to MFW Flow Control valve (2CV

-0762) is open

- Both Emergency Feedwater Pumps (2P

-7A and 2P-7B) are in standby

- Annunciator 2K03

-A8 "FEED PUMP TRIP" is in alarm for "A" MFP

- OP-2203.027, Loss of Main Feedwater Pump AOP

, has been entered The Main Feedwater Control System will . In accordance with OP

-2203.027, the first action taken to address the Main Feedwater Pump trip is to

. A. automatically maintain Steam Generator levels at setpoint; place "B" Main Feedwater pump (2P-1B) in service B. automatically maintain Steam Generator levels at setpoint; attempt to restart "A" Main Feedwater pump (2P

-1A) C. require manual operator action to restore Steam Generator levels to setpoint; place "B" Main Feedwater pump (2P

-1B) in service D. require manual operator action to restore Steam Generator levels to setpoint; attempt to restart "A" Main Feedwater pump (2P

-1A) Proposed Answer:

__C.__ Explanation:

C. Correct. The FWCS will open the MFRV's to try and restore level, but 2P

-75 will not provide enough flow to restore SG level at 5% power. Per the Contingency Actions in OP

-2203.027, it will only provide enough flow for 4% power

. Therefore, manual operator action is required to restore levels to setpoint. In OP-2203.027, the Contingency Actions for "Check at least ONE MFW pump operating," the steps are lettered, not bulleted. Therefore, the actions have to be performed in order. The first action is to attempt to place the standby MFW pump in service. Therefore, "B" Main Feedwater pump (2P

-1B) would be placed in service.

A. Incorrect. Although OP

-2203.027 requires placing 2P

-1B in service first, the FWCS, with the feedwater supply from 2P

-75, would not be able to automatically control level.

B. Incorrect. The FWCS, with 2P

-75, would not be able to automatically control level. In addition, attempting to start the tripped MFP is the second prioritized action in OP

-2203.027, Contingency Action 3.

D. Incorrect. Although manual operator action is required, the action cited from OP

-2203.027 is the secondary action.

Technical Reference(s):

OP-2203.027, Loss of Main Feedwater Pump, Rev. 014, page 2 of 11, Step 3.A and Step 3.C STM 2-19-2, EFW & AFW Systems STM, page 27, Section 3.2 OP-2106.007, Main Feedwater Pump and FWCS Operation, Rev. 052, page 36 of 113, Step 9.6 OP-2203.012C, Annunciator Corrective Actions 2K03 Window A

-8, Rev. 029, Page 87 of 176 AOP-2203.027, Loss of Main Feed Water Pump Tech Guide, Rev. 013, Step 3, Page 5 of 18 Proposed references to be provided to applicants during examination:

No Learning Objective:

A2LP-RO-AMFP objective 3_ Question Source:

Bank # ______ Modified Bank #

______ (Note changes or attach parent)

New ___X___ Question History:

Last NRC Exam

___

Question Cognitive Level:

Memory or Fundamental Knowledge

_____ Comprehension or Analysis __X__

Question Level of Difficulty:

__3__

10 CFR Part 55 Content:

55.41 __5__ 55.43 _____ Comments:

Took portions of Revisions 0 and 1 of the question and formed one question. This is proposed to address both the a) and b) portions of the A2.07 K/A statement.

Data for 2014 NRC RO/SRO Exam 29-Jan-14Bank:1969Safety Function 4System Number 061System Title:Auxiliary / Emergency Feedwater (AFW) Syste K/A K5.02Description:Knowledge of the operational implications of the following concepts as they apply to the AFW System: -Decay heat sources and magnitudeRO Imp: 3.2SRO Imp: 3.6Lic Level:

RDifficulty:

2Taxonomy: HQuestion:Consider the following: - Unit 2 has tripped from 100% power - EFAS has actuated to both Steam Generators - 'A' Steam Generator level is 5% - 'B' Steam Generator level is 7%15 minutes post trip, the required flow of greater than or equal to __________________________ from theEmergency Feed Water (EFW) system is required to adequately remove decay heat from theReactor Coolant System (RCS). A. 150 gpm to each Steam Generator B. 485 gpm to each Steam Generator C. 150 gpm total flow to the Steam Generators D. 485 gpm total flow to the Steam GeneratorsAnswer:D. Correct Notes:Total required EFW flow post trip is greater than or equal to 485 gpm total flow to the Steam Generators is required toremove decay heat.

References:

OP-2202.001, Standard Post Trip Actions, Rev. 14, step 8 contingency A.2, page 10 of 17EOP-2202.001, Standard Post Trip Actions Tech Guide, Rev. 014, step 8, page 19 of 42EOP Setpoint Document Setpoint F.3, Rev 13, section F.3, page 111Source: NEWRev: 1Rev Date:1/29/2014 4:43:48Search061000K50210CFR55:41.5 / 45.7Historical Comments:Rev. 1, added the word "heat" after decay, rewrote question to raise the difficulty level per NRC comments. (mwf 1/29/14)

Tier: 2Group: 1Author:fosterL. Plan:A2LP-RO-ESPTA OBJ 11QID #: 45 57Form ES-401-5 Written Exam Question Worksheet Comments on Question 4 5, Revision 1 Questions/comments on Revision 1:

1. Is there significance to the timing of 15 minutes post trip? Does that affect whether the proposed correct answer is the correct one?

2. The minimum feedwater flow criteria for SGs both lower than 10% level is "greater than" 485 gpm. The question says "greater than or equal to."

3. The basis for 150 gpm being a plausible distracter needs to be provided to defend why it yields incorrect answers.

Data for 2014 NRC RO/SRO Exam 29-Jan-14Bank:1970Safety Function 4System Number 005System Title:Residual Heat Removal System (RHRS)

K/A A1.01Description:Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated withoperating the RHRS controls including: - Heatup/cooldown ratesRO Imp: 3.5SRO Imp: 3.6Lic Level:

RDifficulty:

2Taxonomy: HQuestion:Consider the following: - Unit 2 is in Mode 5 - A loss of Shutdown Cooling (SDC) has occurred with an initial Reactor Coolant System (RCS) temperature at 1402 is 174°F - At 1404, RCS temperature has risen to 177°FIf NO operator actions are taken, at what time will the RCS reach the temperaturerequirement to enter Mode 4? A. 1412 B. 1413 C. 1420 D. 1422Answer:C. Correct Notes:C. Correct: With a Loss of SDC a Heatup will occur. the heatup rate for above conditions is 1.5°F/minute (177°F - 174°F = 3°F divided by 2 minutes = 1.5°F) The lower temperature for entry into mode 4 is 200°F. time difference, 201°F - 177°F = 24°F divided by 1.5°F/min = 16 minutes. 1404 + 16 minutes = 1420A. Incorrect: number based on the difference between 177°F but dividing by 3°F/minute (if they did not take into account for the 2 minutes between temperature readings)B. Incorrect: number based on 174°F vs. 177°F and dividing by 3°F/minD. Incorrect: number based on 174°F vs. 177°F

References:

T.S. Table 1.1Source: NEWRev: 1Rev Date:1/29/2014 6:10:59Search005000A10110CFR55:41.5 / 45.5Historical Comments:Rev. 1: changed anwsers to match stem. Old answers were calculated off of 174°F instead of 177°F changed caluations from200F to 201F per NRC comments. (mwf 1/29/14)

Tier: 2Group: 1Author:fosterL. Plan:A2LP-RO-TS OBJ 1QID #: 46 58Form ES-401-5 Written Exam Question Worksheet Recommendation to Question 4 6, Revision 1 Revise the question to say "..at what time will the RCS first reach the temperature requirement to enter Mode 4?"

Note: the italics are not required in the question, it is just to denote what word is being proposed for addition.

Comments on Question 4 7, Revision 0 There are no apparent changes to the question, references, or justifications. The question still does not match the K/A statement for Question 47 in the ES 401

-2, Revision 2. It needs to be replaced or revised to address the K/A statement.

Data for 2014 NRC RO/SRO Exam 29-Jan-14Bank:1972Safety Function 6System Number 062System Title:A.C. Electrical Distribution System K/A A2.12Description:Ability to (a) predict the impacts of the following malfunctions or operations on the A.C. Distribution Systemand (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of thosemalfunctions or operations: - Restoration of power to a system with a fault on itRO Imp: 3.2SRO Imp: 3.6Lic Level:

RDifficulty:

3Taxonomy: FQuestion:Consider the following: - Unit 2 has tripped from 100% power due to a large break LOCA - Annunciator 2K09 B-3 "2A4 L.O. RELAY TRIP" is in alarm - Containment Pressure is 25 psia and trending up - Annunciator 2K06 A-1 "2P-35A FAILURE ON ESFAS" is in alarmOP-2203.012F, Annunciator Corrective Actions for 2K06 A-1 directs "A" Containment Spray pump (2P-35A) and breaker __________________________________________ . A. are not required to be investigated prior to start due to no other alarms associated with the pump are in B. are required to be investigated prior to start due to possible electrical fault on the 4160V Bus C. are not required to be investigated prior to start due to a safety function not being met D. are required to be investigated prior to start due to #1 EDG runningAnswer:C. Correct Notes:C. Correct: The applicant should access the impact of the malfunction on the A.C. Distribution System [Loss of Green train vital power, loss of Red Train Spray Pump] and use the guidance in the ACAs to mitigate the consequences of the A.C. Bus and Pump by verifying no damage to the pump power supply [breaker] and restore of power to the "A" Spray Pump. Annunciator 2K06 A-1 "2P-35A failure on ESFAS" will come into alarm 45 seconds after the pump received its auto start command (CSAS) and the pump did not start. With a bus lock out on 2A4 [Green Train] the "B" Spray pump [green Train] is unavailable along with the Containment Coolers [Green Train]. With Containment Building pressure trending up, starting the "A" spray pump [Red Train] is needed to meet the containment safety function. 1 start attempt is allowed by the ACA if an emergency condition exists and the bus is powered from offsite. The Red bus (2A1/2A3) is aligned to offsite with the given conditions.A. Incorrect: The ACA does not allow a start attempt solely based on no other associated pump alarms are in, i.e. an investigation of the pump prior to start would be required even without any other associated pump alarms if 2P35B was running.B. Incorrect: is not required to be investigated prior to a start attempt per the ACA.D. Incorrect: The ACA would require the pump to investigated prior to a start attempt if the bus was powered from a EDG. The #1 EDG is running (started by the SIAS @ 18.3#) but is not tied to the bus.Source: NEWRev: 1Rev Date:1/22/2014 9:47:11Search062000A21210CFR55:41.5 / 43.5 / 45.3 / 45.

Tier: 2Group: 1Author:fosterL. Plan:A2LP-RO-SPRAY OBJ 8&13QID #: 48 60Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 29-Jan-14

References:

OP-2203.012F, Annunciator Corrective Actions 2K06 window A-1, Rev 037, page 4 of 79COPD-032, Transient Conduct of Operations, Rev 003, section 9.3 page 18 of 41Historical Comments:Rev. 1, swapped distracters A and D for symmetry (mwf 1/22/14) 61Form ES-401-5 Written Exam Question Worksheet Q 4 8_R1 (NRC proposed changes to Rev1)

Original comments stated that question was classified as unsatisfactory because of its faulted 2x2 logic (an applicant could get the correct answer without having knowledge to answer both parts of the question). Revision 1 provided by the licensee did not address this issue.

A question in the correct format is proposed as follows:

Proposed Question:

Consider the following:

- Unit 2 has tripped from 100% power due to a large break LOCA

- Annunciator 2K09 B

-3 "2A4 L.O. RELAY TRIP" is in alarm

- Containment pressure is 25 psia and trending up

- Annunciator 2K06 A

-1 "2P-35A FAILURE ON ESFAS" is in alarm OP-2203.012F, Annunciator Corrective Actions for 2K06 A

-1 __(1)_____ "A" Containment Spray pump (2P

-35A) to be started without assessment because (2)

. ________(1)

_________ (2)_____________

A. directs EDG #1 is supplying power to its safety bus

B. directs the Core Heat Removal safety function is not met

C. prohibits EDG #1 is supplying power to its safety bus D. prohibits the Core Heat Removal safety function is not met Proposed Answer:

__B__ Explanation:

B. Correct

To determine the correct answer, the applicant has to determine the effects of the 2A4 bus lockout during the LOCA. With the LOCA, ESFAS would start both EDGs. The 2A4 bus lockout prevents EDG #2 and offsite power from supplying this bus. EDG #1 has started, but with offsite power available, offsite power will continue to supply power to bus 2A3.

Procedure OP

-2203.012F, ACA for 2K06 A

-1, Step 2.3.1, directs the start of 2P

-35A without assessment. The basis for this is provided in procedure COPD

-032, Section 9.3. With offsite powered to a bus supplying a component that failed to automatically actuate, it directs that one attempt to start the component be attempted. This is because the safety function that the component addresses is not being fulfilled.

With no Containment Spray pumps running, the Containment Heat Removal safety function is not being met. See the Note prior to Step 2.2 in procedure OP

-2203.012F, ACA for 2K06 A

-1.

A. Incorrect: It is true that starting 2P

-35A is directed, but it is not because EDG #1is supplying power to its safety bus. Offsite power is being supplied to the safety bus.

C. Incorrect: Due to the situation, an attempted start of 2P

-35A is directed. In addition, the electrical supply to the Red Train safety bus is offsite power.

D. Incorrect: Due to the situation, an attempted start of 2P

-35A is directed.

It is plausible that an assessment could be required prior to meeting the safety function. For example, if EDG #1 was supplying its safety bus, even with the Containment Heat Removal safety function not met, an assessment would be required per procedure COPD

-032, Section 9.3, second bullet.

Technical Reference(s):

OP-2203.012F, Annunciator Corrective Actions 2K06 window A

-1, Rev 037, page 4 of 79 COPD-032, Transient Conduct of Operations, Rev 003, section 9.3 page 18 of 41 Proposed references to be provided to applicants during examination:

No Learning Objective:

A2LP-RO-SPRAY objective s 8 and 1 3_ Question Source:

Bank # ______ Modified Bank #

______ (Note changes or attach parent)

New ___X___ Question History:

Last NRC Exam

___

Question Cognitive Level:

Memory or Fundamental Knowledge

_____ Comprehension or Analysis __X__ Question Level of Difficulty:

__4__

10 CFR Part 55 Content:

55.41 __5__ 55.43 _____ Comments: Took Revision 1 initial conditions and developed a 2x2 format question

.

Data for 2014 NRC RO/SRO Exam 29-Jan-14Bank:1973Safety Function 6System Number 063System Title:D.C. Electrical Distribution System K/A K4.02Description:Knowledge of D.C. Electrical System design feature(s) and/or interlock(s) which provide for the following: -Breaker interlocks, permissives, bypasses and cross-tiesRO Imp: 2.9SRO Imp: 3.2Lic Level:

RDifficulty:

2Taxonomy: FQuestion:Consider the following: - Unit 2 is operating at 100% power - DC control power has been lost to the 2A2 non-vital 4160 V busWhich of the following would describe the operation of the breakers on 2A2? A. Breakers would trip open and operation would only be possible by local manual means B. Breakers would be able to be operated remotely but automatic trip functions would not be functional C. Breakers will remain in their "as is" condition and operation would only be possible by local manual means D. Automatic breaker trips would remain functional but remote operation of breakers would not be possibleAnswer:C. Correct Notes:C. Correct: 125 VDC power provides the motive power for remote breaker operations and permissives, and breaker bypass interlocks. This would prevent any remote manual operations and automatic breaker cycles.A. Incorrect: Tripping breakers open requires 125 VDC powerB. Incorrect: There are no remote operations without DC control powerD. Incorrect: For both reasons above

References:

STM 2.32-2, High Voltage Electrical Distribution, Revision 26, Section 6.2.2, page 63Source:NRC BANK QID #1758Rev: 1Rev Date:1/29/2014 5:50:58Search063000K40210CFR55: 41.7Historical Comments:NRC BANK QID #1758 used on 2009 NRC ExamRev. 1, reworded distractor B to make more clear based on NRC comments. (mwf 1/29/14)

Tier: 2Group: 1Author:fosterL. Plan:A2LP-RO-ED125 OBJ 1QID #: 49 62Form ES-401-5 Written Exam Question Worksheet Comments on Question 4 9, Revision 1 The change did not address the concern.

The basis for the proposed correct answer says that the loss of 125 VDC control power prevents any "remote manual operations." Based on Answer C's wording, "local manual means" must be available as the only option for operating the affected breakers.

When the wording of distracter B is reviewed, it says "Breakers would be able to be operated remotely.." Is operating a breaker by "local manual means," considered "remotely?" An

applicant could argue if this is vague that operating the breaker by local manual means can be completed outside the Control Room, so it is "remote." If there is a specific site definition for "remotely" that will ensure that distracter B is not correct, it needs to be documented in the question notes. If there isn't a basis, the next best thing would be to modify distracter B to say "Breakers would be able to be manually operated remotely,.."

The goal is to have all the terms clear so that there is no room to argue that there are two correct answers.

Data for 2014 NRC RO/SRO Exam 29-Jan-14Bank:1974Safety Function 6System Number 064System Title:Emergency Diesel Generator (ED/G) System K/A K6.08Description:Knowledge of the effect of a loss or malfunction of the following will have on the ED/G System: - Fuel oilstorage tanksRO Imp: 3.2SRO Imp: 3.3Lic Level:

RDifficulty:

3Taxonomy: HQuestion:Consider the following: - Unit 2 is operating at 100% power - #2 EDG monthly surveillance, OP-2104.036, Emergency Diesel Generator Operations, Supp. 2B, is in progress - #2 EDG is currently tied to the grid and is consuming 2.4 gallons of fuel oil each minute - #2 EDG fuel oil transfer pump (2P-16B) is running and filling #2 EDG fuel oil day tank (2T-30B) - Annunciator 2K08 K-1, "FUEL SYSTEM TROUBLE" comes into alarm - The EDG watch reports 2K128 "FUEL X-FER PUMP INOPERABLE" is in alarm - Both indicating lights are out on the local panel for 2P-16B - #2 EDG fuel oil day tank (2T-30B) level is 480 gallons - NO operator action is takenBased on these conditions, approximately how long can #2 EDG continue to operate at the current load until Tech SpecMinimum Day Tank Volume is reached? A. 37 minutes B. 75 minutes C. 125 minutes D. 200 minutesAnswer:B. Correct Notes:B. Correct: T.S. Minimum Day Tank Volume is 300 gallons. 480 - 300 gallons divided by 2.4 gpm is equal to 75 minutesA. Incorrect: number based on current level to the low level alarm value 391.3 gallons (480-391.3 = 88.7 gallons divided by 2.4gpm = 36.95 min, rounded up to 37 minutes)C. Incorrect: based on T.S. min 300 gallons divided by 2.4 gpm = 125 minD. Incorrect: based on 480 gallons divided by 2.4 gpm = 200 minutes

References:

OP-2203.012H, Annunciator Corrective Actions 2K08 window K-1, Rev 037, page 12 of 50OP-2203.012U, Annunciator Corrective Actions 2K128, Rev 020, page 25 of 33T.S 3.8.1.1 part bSource:Modified NRC BANK QID #1659Rev: 1Rev Date:1/21/2014 9:08:19Search064000K60810CFR55:41.7 / 45.7 Tier: 2Group: 1Author:fosterL. Plan:A2LP-RO-EDG OBJ 11&12QID #: 50 63Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 29-Jan-14Historical Comments:NRC BANK QID #1659 used on 2009 NRC Exam.REV. 1: Question has been modified by changing which EDG (B vs. A), changed volume of day tank (from 500 gallons to480 gallons), and changed fuel oil consumption rate (2.4 gpm vs. 2.2 gpm) 64Form ES-401-5 Written Exam Question Worksheet

Data for 2014 NRC RO/SRO Exam 29-Jan-14Bank:1975Safety Function 4System Number 039System Title:Main and Reheat Steam System (MRSS)

K/A A2.05Description:Ability to (a) predict the impacts of the following malfunctions or operations on the MRSS and (b) based onthose predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions oroperations: - Increasing steam demand,RO Imp: 3.3SRO Imp: 3.6Lic Level:

RDifficulty:

3Taxonomy: HQuestion:Consider the following: - Unit 2 is at 20% power and rising after an outage - 2CV-0402, "A" MSR Reheat Steam Low Load Valve (RSLLV), controller is in automatic IAW OP-2106.009, Turbine Generator Operations - 2PIT-0407, 'A' MSR Shell pressure input into RSLLV controller 2PDI-0402, fails and causes the RSLLV for the 'A' MSR to fail openBased on the above conditions, 'A' MSR outlet temperature would ____________ and OP-2106.009 Attachment F, 2nd StageLow Load Control, would be used to ____________ RSLLV to prevent large temperature mismatches on the Low PressureTurbine inlet. A. rise; manually throttle B. rise, manually close C. lower, manually throttle D. lower, manually closeAnswer:A. Correct Notes:The ability to predict the impact of the operations on the MRSS is addressed in the NOP (att. F) because Reactivity impact ofdirectly adjusting Main Steam flow/pressure [MSR 2nd stage heating is supplied from main steam system and opening theRSLLV will raise steam flow therefore raise reactor power (change reactivity)] and based on the prediction of the ReactivityPotential, a reactivity brief per COPD-30 is required and the notes and cautions in the Attachment F is use to control andmitigate the consequences of the increasing steam demand,

References:

OP-2106.009, Turbine Generator Operations, Rev 071, Att. F step 4.0 page 86 of 143STM 2-16, Reheat Steam, Rev 8 section 3.3.1.3 pages 5 and 6, simplified drawing page 17Source: NEWRev: 1Rev Date:1/21/2014 3:54:45Search039000A20510CFR55:41.5 / 43.5 / 45.3 / 45.Historical Comments:

Tier: 2Group: 1Author:SimpsonL. Plan: OBJQID #: 51 65Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 30-Jan-14Bank:1975Safety Function 4System Number 039System Title:Main and Reheat Steam System (MRSS)

K/A A2.05Description:Ability to (a) predict the impacts of the following malfunctions or operations on the MRSS and (b) based onthose predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions oroperations: - Increasing steam demand,RO Imp: 3.3SRO Imp: 3.6Lic Level:

RDifficulty:

3Taxonomy: HQuestion:Consider the following: - Unit 2 is at 20% power and rising after an outage - 2CV-0402, "A" MSR Reheat Steam Low Load Valve (RSLLV), controller is in automatic IAW OP-2106.009, Turbine Generator Operations - 2PIT-0407, 'A' MSR Shell pressure input into RSLLV controller 2PDI-0402, fails and causes the RSLLV for the 'A' MSR to fail openBased on the above conditions, 'A' MSR outlet temperature would ____________ and OP-2106.009 Attachment F, 2nd StageLow Load Control, would be used to ____________ RSLLV to prevent large temperature mismatches on the Low PressureTurbine inlet. A. rise; manually throttle B. rise, manually close C. lower, manually throttle D. lower, manually closeAnswer:A. Correct Notes:A. Correct. Second stage heating comes from Main Steam. When the RSLLV fails full open, it causes more Main Steam flowto go to the second stage heating coil, which causes MSR outlet temperature to go up. Attachment F contains instructions tothrottle the RSLLV to prevent large temperature mismatches on the Low Pressure Turbine inlets.B. Incorrect. Fully closing the RSLLV will isolate steam to the 2nd stage heating coil for the MSR causing Low PressureTurbine inlet temperature to go to low and would cause a temperature mismatch.C. Incorrect. Low pressure turbine inlet temperature would go up, not go down.D. Incorrect. Low pressure turbine inlet temperature would go up, not go down.

References:

OP-2106.009, Turbine Generator Operations, Rev 071, Att. F step 4.0 page 86 of 143STM 2-16, Reheat Steam, Rev 8 section 3.3.1.3 pages 5 and 6, simplified drawing page 17Source: NEWRev: 2Rev Date:1/30/2014 4:13:22Search039000A20510CFR55:41.5 / 43.5 / 45.3 / 45.

Tier: 2Group: 1Author:SimpsonL. Plan: OBJQID #: 51 64Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 30-Jan-14Historical Comments:Rev. 1: changed distractors to better match K/A per NRC comments. (mwf 1/30/14)Rev. 2: Updated notes. (mwf 1/30/14) 65Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 29-Jan-14Bank:1976Safety Function 7System Number 073System Title:Process Radiation Monitoring (PRM) System K/A K1.01Description:Knowledge of the physical connections and/or cause-effect relationships between the PRM System and thefollowing systems: - Those systems served by PRMsRO Imp: 3.6SRO Imp: 3.9Lic Level:

RDifficulty:

2Taxonomy: HQuestion:In accordance with OP-2104.014, Supplement 1, Unit 2 Liquid Radwaste Release Permit, placing the selector switch forProcess Liquid radiation monitoring instrument 2RITS-2330 in ___________ would cause its meter output to exceed thedump permit high alarm setpoint and close the 2T-69B tank isolation valves, 2CV-2330A and /or 2CV-2330B. A. HV (High Voltage) B. PULSE CAL C. CHECK SOURCE D. LEVEL CALAnswer:B. Correct Notes:The LRW/BMS Process Radiation Monitor, 2RITS-2330, provides an automatic closure of 2CV-2330A and/or 2CV-2330B.This automatic feature occurs on a high alarm that is determined by the Unit 2 Liquid Radwaste Release Permit (OP-2104.014, Supp 1). Going to PULSE Cal will raise the detector radiation output above the alarm setpoint causing the valves togo closed. Testing of this interlock will prevent discharging liquid waste above the design limits.

References:

OP-2104.014, LRW and BMS Operations, Rev 054, supplement 1 section 7.0 steps 7.3 and 7.4STM 2-62, Radiation Monitoring System, Rev 20, section 2.2.6.1 page 20STM 2-52, Liquid Radwaste / Boron management System, Rev 17, simplified LRW/BMS drawing page 35Source:NRC Bank QID #1538Rev: 1Rev Date:1/29/2014 11:33:4Search073000K10110CFR55:41.2 to 41.9 / 45.7 to 4Historical Comments:QID #1538 used on the 2008 NRC ExamRev 1: changed to incorporate NRC comments. (mwf 1/29/14)

Tier: 2Group: 1Author:fosterL. Plan:A2LP-RO-RMON OBJ 9QID #: 52 66Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 29-Jan-14Bank:1977Safety Function 4System Number 076System Title:Service Water System (SWS)

K/A A3.02Description:Ability to monitor automatic operation of the SWS, including: - Emergency heat loadsRO Imp: 3.7SRO Imp: 3.7Lic Level:

RDifficulty:

4Taxonomy: HQuestion:Consider the following: - Unit 2 has tripped from 100% power due to a LOCA - Pressurizer pressure has lowered to 1400 psiaService Water ______________ be aligned to Containment Coolers and _______________ be aligned to Spent Fuel Pool HeatExchanger. A. would; would B. would; would not C. would not; would D. would not; would notAnswer:B. Correct Notes:B. Correct. Pressurizer pressure of 1400 psia causes SIAS and CCAS. CCAS aligns Service Water to the Containment Coolers and SIAS isolates Service Water to the SFP Heat Exchanger.A. Incorrect. Service Water is isolated to SFP Heat Exchanger during a SIAS.C. Incorrect. Service Water is aligned to Containment Coolers during a CCAS and isolated to the SFP Heat Exchanger during a SIAS.D. Incorrect. Service Water is aligned to the Containment Coolers during a CCAS.

References:

STM 2-42, Service Water & Auxiliary Cooling Water System Training Manual, Rev. 36, pages 76 and 77Source: NEWRev: 1Rev Date:1/29/2014 2:19:32Search076000A30210CFR55:41.7 / 45.5Historical Comments:Rev 1: changed to better align with K/A per NRC comments. (mwf 1/29/14)

Tier: 2Group: 1Author:fosterL. Plan:A2LP-RO-ESPTA OBJ 11QID #: 53 67Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 29-Jan-14Bank:1984Safety Function 5System Number 028System Title:Hydrogen Recombiner and Purge Control Syste K/A A2.03Description:Ability to (a) predict the impacts of the following malfunctions or operations on the HRPS and (b) based onthose predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions oroperations: - The hydrogen air concentration I excessof limit flame propagation or detonation with resultingequipment damage in containmentRO Imp: 3.4SRO Imp: 4.0Lic Level:

RDifficulty:

3Taxonomy: HQuestion:The Hydrogen analyzers are placed in service within _______ minutes of the beginning of an accident to ensure arepresentative sample is obtained. A DETONATION inside the containment building is likely to occur if hydrogenconcentration reaches ____ % A. 70; 4 B. 70; 18 C. 90; 4 D. 90; 18Answer:B. Correct Notes:The Hydrogen analyzers have a 20 minute transport time from when started to when an representative air stream is beingsampled. Actions in the EOPs (LOCA, ESD, Functional Recovery) required the start of the analyzers within 70 minutes forthis reason. 4% hydrogen concentration is right at the flammability limit inside containment. At 18% hydrogen concentrationa detonation would occur.

References:

STM-2-06, Containment Combustible Gas Control System, Rev 12, section 1.5 pages 5 and 6 and section 4.2 page 24Source:NRC BANK QID #1487Rev: 1Rev Date:1/29/2014 4:26:45Search028000A20310CFR55:41.5 / 43.5 / 45.3 / 45.Historical Comments:NRC BANK QID #1487 not used on any previous NRC ExamRev. 1, replaced Violent with detonation (mwf 1/29/14)

Tier: 2Group: 2Author:fosterL. Plan:A2LP-RO-CONH2 OBJ 2&4QID #: 60 75Form ES-401-5 Written Exam Question Worksheet

Question Number:

63_R 0 (NRC recommendations

)

Revised Question:

Given the following:

Unit 2 has tripped due to a loss of condenser vacuum A consistent 55°F/hour cooldown has been established over the last hour on the DOWNSTREAM atmosphere dump valves with SDBCS in automatic The SDBCS is in its normal at

-power alignment Annunciator 2K12 A

-8 "IA Pressure HI/LO" comes into alarm Instrument Air header pressure is reading 0 psig NO operator actions are taken The RCS cooldown limit _____(1)_____ be exceeded due to _____(2)_____. A. Would; the downstream atmosphere dump valves failing open B. Would; the upstream atmosphere dump valves failing open C. Would not; the downstream atmosphere dump valves failing closed D. Would not; the upstream atmosphere dump valves failing closed Proposed Answer:

__C___ Comments: Recommend deleting the word DOWNSTREAM to remove the cueing that made this question unsat. Recommend adding a statement about SDBCS being in its normal at

-power alignment to provide information to the candidates about status of the upstream ADV's.

Data for 2014 NRC RO/SRO Exam 29-Jan-14Bank:1987Safety Function 4System Number 041System Title:Steam Dump System (SDS) and Turbine Bypass K/A A3.01Description:Ability to monitor automatic operation of the SDS, including: - RCS T-ave. meter (cooldown rate)RO Imp: 3.2SRO Imp: 3.2Lic Level:

RDifficulty:

2Taxonomy: FQuestion:Consider the following: - Unit 2 has tripped due to a loss of condenser vacuum - A consistent 55°F/hour cooldown has been established over the last hour on the DOWNSTREAM atmosphere dump valves with SDBCS in automatic - Annunciator 2K12 A-8 "IA PRESSURE HI/LO" comes into alarm - Instrument Air header pressure is reading 10 psig and trending down - NO operator actions are takenThe RCS cooldown limit ____________ be exceeded due to ________________________________ . A. would; the downstream atmosphere dump valves failing open B. would; the upstream atmosphere dump valves failing open C. would not; the downstream atmosphere dump valves failing closed D. would not; the upstream atmosphere dump valves failing closedAnswer:C. Correct Notes:The downstream atmosphere dump valves fail closed on a loss of Instrument Air stopping the cooldown and the upstreamatmosphere dump valves do fail open on a loss of Instrument Air but are normally manually isolated from the Main Steamheader, therefore would not affect the RCS.

References:

Tech Spec 3.4.9, Pressure/Temperature LimitsSTM 2-23, Steam Dump & Bypass Control System, Rev 16, section 1.2 pages 1 and 2 , section 1.2.2 pages 4 and 5, section4.0 page 31OP-2203.021, Loss of instrument Air AOP, Rev 015, Attachment "A", page 18 of 108OP-2203.012L, Annunciator Corrective Actions, 2K12 window A-8, Rev 036, page 85 of 116Source: NEWRev: 1Rev Date:1/29/2014 12:07:2Search041000A30110CFR55:41.7 / 45.5Historical Comments:Rev. 1, reworded per NRC comments (mwf 1/29/14)

Tier: 2Group: 2Author:fosterL. Plan:A2LP-RO-SDBCS OBJ 20QID #: 63 78Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 31-Jan-14Bank:1987Safety Function 4System Number 041System Title:Steam Dump System (SDS) and Turbine Bypass K/A A3.01Description:Ability to monitor automatic operation of the SDS, including: - RCS T-ave. meter (cooldown rate)RO Imp: 3.2SRO Imp: 3.2Lic Level:

RDifficulty:

2Taxonomy: FQuestion:Consider the following: - Unit 2 has tripped due to a loss of condenser vacuum - A consistent 55°F/hour cooldown has been established over the last hour on the atmosphere dump valves with SDBCS in automatic - The SDBCS is in its normal at-power alignment - MSIVs are open - Annunciator 2K12 A-8 "IA PRESSURE HI/LO" comes into alarm - Instrument Air header pressure is reading 10 psig and trending down - NO operator actions are takenThe RCS cooldown limit ____________ be exceeded due to ________________________________ . A. would; the downstream atmosphere dump valves failing open B. would; the upstream atmosphere dump valves failing open C. would not; the downstream atmosphere dump valves failing closed D. would not; the upstream atmosphere dump valves failing closedAnswer:C. Correct Notes:The downstream atmosphere dump valves fail closed on a loss of Instrument Air stopping the cooldown and the upstreamatmosphere dump valves do fail open on a loss of Instrument Air but are normally manually isolated from the Main Steamheader, therefore would not affect the RCS.

References:

Tech Spec 3.4.9, Pressure/Temperature LimitsSTM 2-23, Steam Dump & Bypass Control System, Rev 16, section 1.2 pages 1 and 2 , section 1.2.2 pages 4 and 5, section4.0 page 31OP-2203.021, Loss of instrument Air AOP, Rev 015, Attachment "A", page 18 of 108OP-2203.012L, Annunciator Corrective Actions, 2K12 window A-8, Rev 036, page 85 of 116Source: NEWRev: 2Rev Date:1/30/2014 5:23:07Search041000A30110CFR55:41.7 / 45.5Historical Comments:Rev. 1, reworded per NRC comments (mwf 1/29/14)Rev. 2, changed wording based on NRCcomments [mwf 1/30/14]

Tier: 2Group: 2Author:fosterL. Plan:A2LP-RO-SDBCS OBJ 20QID #: 63 78Form ES-401-5 Written Exam Question Worksheet Question 64_R0 (NRC recommendations

) Revised Question:

Consider the following:

Unit 2 is operating at 97% power OP-2106.009, Supplement 3, Turbine Generator Valve Stroke Test surveillance is in progress OP-2106.009 directs placing first stage pressure feedback in service because first stage pressure feedback ____(1)____. If first stage pressure feedback is NOT placed in service, when stroking a high pressure turbine control valve closed the reactor coolant system temperature initially ____(2)____. A. (1) will open the other high pressure turbine control valves to compensate for the closure of the tested high pressure turbine control valve (2) increases B. (1) will open the other high pressure turbine control valves to compensate for the closure of the tested high pressure turbine control valve (2) remains the same C. (1) will lock the other high pressure turbine control valves in place and uses steam bypass valves to compensate for closure of the tested high pressure turbine control valve (2) increase s D. (1) will lock the other high pressure turbine control valves in place and uses steam bypass valves to compensate for closure of the tested high pressure turbine control valve (2) remains the same Comments: Per procedure 2106.009, first stage pressure feedback opens the other high pressure turbine control valves to maintain turbine load NEAR pre

-test values. Due to stroke time, the opening of the other high pressure turbine control valves is slightly delayed. Therefore the RCS temperature will initially increase due to the lower steam demand versus steam supply, resulting in less heat transfer in the steam generators and a high reactor coolant system temperature. This makes answer A correct. Distractor B is incorrect but plausible if the candidate does not take into account the delayed response of the other high pressure turbine control valves. Distractors C and D are incorrect because first stage pressure feedback opens the other control valves, not steam dumps, but is plausible because the procedure has instructions for using steam dumps to maintain the power level constant while reducing turbine load.

Data for 2014 NRC RO/SRO Exam 30-Jan-14Bank:1988Safety Function 4System Number 045System Title:Main Turbine Generator (MT/G) System K/A K1.06Description:Knowledge of the physical connections and/or cause-effect relationships between the MT/G System and thefollowing systems: - RCS, during steam valve testRO Imp: 2.6SRO Imp: 2.6Lic Level:

RDifficulty:

3Taxonomy: HQuestion:Consider the following: - Unit 2 is operating at 97% power - OP-2106.009, Supplement 3, Turbine Generator Valve Stroke Test surveillance is in progressOP-2106.009 directs placing first stage pressure feedback in service because first stage pressure feedback______________. If first stage pressure feedback is NOT placed in service, when stroking a high pressure turbine controlvalve CLOSED the RCS temperature initially ______________. A. will open the other high pressure turbine control valves to compensate for the closure of the tested high pressure turbine control valve; increases B. will open the other high pressure turbine control valves to compensate for the closure of the tested high pressure turbine control valve; remains the same C. will lock the other high pressure turbine control valves in place and uses steam bypass valves to compensate for closure of the tested high pressure turbine control valve; increases D. will lock the other high pressure turbine control valves in place and uses steam bypass valves to compensate for closure of the tested high pressure turbine control valve; remains the sameAnswer:A. Correct Notes:A. Correct. Per procedure OP-2106.009, first stage pressure feedback opens the other high pressure turbine control valves tomaintain turbine load NEAR pre-test values. Due to stroke time, the opening of the other high pressure turbine control valvesis slightly delayed. Therefore the RCS temperature will initially increase due to the lower steam demand versus steam supply,resulting in less heat transfer in the steam generators and a high RCS temperature.B. Incorrect. Plausible if the candidate does not take into account the delayed response of the other high pressure turbinecontrol valves.C. Incorrect. First stage pressure feedback opens the other control valves, not steam dumps but is plausible because theprocedure has instructions for using steam dumps to maintain the power level constant while reducing turbine load.

References:

OP-2106.009, Turbine Generator Operations, Rev 071, Supplement 3 pages 110, 112, 115, 116, and 119 of 143Source: NEWRev: 1Rev Date:1/30/2014 4:29:11Search045000K10610CFR55:41.2 to 41.9 / 45.7 to 4 Tier: 2Group: 2Author:fosterL. Plan:A2LP-RO-TURBC OBJ 32QID #: 64 79Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 30-Jan-14Historical Comments:Rev. 1: changed question based on NRC feedback. (mwf 1/30/14) 80Form ES-401-5 Written Exam Question Worksheet Question Number:

6 6_R 0 (NRC recommendations

)

Comments: Remove the open reference to make this a closed reference question. The question is then no longer a direct look

-up and becomes SAT.

Data for 2014 NRC RO/SRO Exam 29-Jan-14

References:

EN-OP-115, Conduct of Operations, Rev 014, Attachment 9.1 page 1 of 1 [PROVIDED to STUDENT]Historical Comments:Bank:1990Safety FunctionSystem NumberGENERICSystem Title:Generic K/A2.1.7Description:Conduct of Operations - Ability to evaluate plant performance and make operational judgments based onoperating characteristics, reactor behavior, and instrument interpretation.RO Imp: 4.4SRO Imp: 4.7Lic Level:

RDifficulty:

2Taxonomy: FQuestion:Per OP-1015.021, ANO-2 EOP/AOP User's Guide, what demarkation is used in the Emergency Operating Procedures toindicate corrected parameter values for harsh containment environmental conditions? A. Asterick beside the paramater value B. Solid black square beside the parameter value C. Parenthesis around the parameter value D. Brackets around the paramater valueAnswer:D. Correct Notes:D. Correct. Per OP-1015.021, ANO-2 EOP/AOP User's Guide, Brackets are used to indicate corrected parameter values for harsh containment environment conditions.A. Incorrect. Asterick is used to indicate a continuous action step in the EOPs.B. Incorrect. A solid black square is used to indicate a floating step in the EOPs.C. Incorrect. Parenthesis are used around component numbers in the EOPs.

References:

OP-1015.021, ANO-2 EOP/AOP User's Guide, Rev. 11, page 34 of 73Source: NEWRev: 1Rev Date:1/29/2014 4:54:24Search194001210710CFR55:41.5 / 43.5 / 45.12 / 45Historical Comments:Rev. 1, rejected original K/A 2.1.7 due to being an SRO duty. Replaced with K/A 2.1.7 and new question. (mwf 1/29/14)

Tier: 3Group: 1Author:fosterL. Plan:A2LP-RO-EAOP OBJ 2QID #: 66 82Form ES-401-5 Written Exam Question Worksheet Question Number:

6 6_R 1 (NRC recommendations

)

Comments: Correct spelling of the words "demarcation," "asterisk" and "parameter" Per OP-1015.021, ANO

-2 EOP/AOP User's Guide, what demarkation is used in the Emergency Operating Procedures to indicate corrected parameter values for harsh containment environmental conditions?

A. Asterick beside the paramater value D. Brackets around the paramater value Submit corrections as Rev 2

Data for 2014 NRC RO/SRO Exam 30-Jan-14Bank:1990Safety FunctionSystem NumberGENERICSystem Title:Generic K/A2.1.7Description:Conduct of Operations - Ability to evaluate plant performance and make operational judgments based onoperating characteristics, reactor behavior, and instrument interpretation.RO Imp: 4.4SRO Imp: 4.7Lic Level:

RDifficulty:

2Taxonomy: FQuestion:Per OP-1015.021, ANO-2 EOP/AOP User's Guide, what demarcation is used in the Emergency Operating Procedures toindicate corrected parameter values for harsh containment environmental conditions? A. Asterisk beside the parameter value B. Solid black square beside the parameter value C. Parenthesis around the parameter value D. Brackets around the parameter valueAnswer:D. Correct Notes:D. Correct. Per OP-1015.021, ANO-2 EOP/AOP User's Guide, Brackets are used to indicate corrected parameter values for harsh containment environment conditions.A. Incorrect. Asterick is used to indicate a continuous action step in the EOPs.B. Incorrect. A solid black square is used to indicate a floating step in the EOPs.C. Incorrect. Parenthesis are used around component numbers in the EOPs.

References:

OP-1015.021, ANO-2 EOP/AOP User's Guide, Rev. 11, page 34 of 73Source: NEWRev: 2Rev Date:1/30/2014 2:43:08Search194001210710CFR55:41.5 / 43.5 / 45.12 / 45Historical Comments:Rev. 1, rejected original K/A 2.1.7 due to being an SRO duty. Replaced with K/A 2.1.7 and new question. (mwf 1/29/14)Rev. 2: corrected misspellings per NRC comments. (mwf 1/30/14)

Tier: 3Group: 1Author:fosterL. Plan:A2LP-RO-EAOP OBJ 2QID #: 66 82Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 29-Jan-14Bank:1991Safety FunctionSystem NumberGENERICSystem Title:Generic K/A2.1.19Description:Conduct of Operations - Ability to use plant computers to evaluate system or component status.RO Imp: 3.9SRO Imp: 3.8Lic Level:

RDifficulty:

3Taxonomy: FQuestion:Consider the following: - Unit 2 has tripped from 100% power - Annunciator 2K04 G-9 "MSSV VALVE OPEN" is in alarmThe CRS would direct the CBOT to determine which Main Steam Safety Valve is open by using the _________________screen on the ______________ . A. Inadequate Core Cooling (ICC); Safety Parameters Display System (SPDS) B. Primary to Secondary Heat Transfer (PSHT); Safety Parameters Display System (SPDS) C. Inadequate Core Cooling (ICC); Plant Monitoring System (PMS) D. Main Steam mimic; Plant Monitoring System (PMS)Answer:A. Correct Notes:A. Correct: ICC on SPDS mimics the RCS and Secondary system to the MSIVs and the MSSVs will change colors to show if open or notB. Incorrect: does not have MSSV statusC. Incorrect: ICC on PMS mimics the RCS and Secondary system to the MSIVs (similar to SPDS) but the MSSVs do not change colorsD. Incorrect: does not have MSSV status

References:

STM 2-76, Safety Parameter Display System (Common Unit), Rev 11, section 2.3.7 page 22Source: NEWRev: 1Rev Date:1/22/2014 1:34:09Search194001211910CFR55:41.10 / 45.12Historical Comments:Rev. 1: changed based on NRCcomments [mwf 1/22/13]

Tier: 3Group: 1Author:fosterL. Plan: A2LP-RO-SPDS OBJ 5QID #: 67 83Form ES-401-5 Written Exam Question Worksheet Question 67

_R 1 (NRC recommendations

) Comments: The K/A selected (2.1.19) makes it difficult to write a non

-system specific question as the K/A requires ability to evaluate system status using the plant computer. If the question has not already been reworked, recommend rejecting this K/A and selecting another K/A from Section 2.1 (Conduct of Operations) to replace it.

If KA is rejected, ensure ES

-401-4 and outline are updated accordingly.

One possible KA replacement is KA 2.1.21, Ability to verify a controlled procedure copy RO 3.5/SRO3.6

(Possible new question

)

Consider the following:

- A job is in progress that will last several weeks

- The procedure has been verified at the start of the job

- A p re-job brief has been completed for all participants How often is the procedure required to be verified/validated to be current?

A. each shift B. once a day C. every 7 Days

D. only prior to start of the j ob I believe the correct answer is C, need to verify in 1000.6 Control of Procedures (we do not have that electronically). Provide reference once question is approved.

All of the distractors are creditable base on common sense and normal frequency of evolutions conducted at power plants Note: This was originally sent as NRC recommendations to Q67_R0, but you had submitted R1 to the question before you received our comments. We edited our original recommendations and now this document is NRC recommendations to Q67_R1.

Question 69

_R 0 (NRC recommendations

) Recommend replacing current question with the following revision to remove the reverse logic and make it more operationally valid.

Proposed Question:

Which of the following procedure changes would qualify as a change in procedure INTENT?

A procedure revision _______________ .

A. to correct a typo that would send the performer to the wrong procedure section if followed. B. that asks that a detailed component location be added to the existing procedure to aid in locating the component in a high radiation area.

C. to reword the "purpose" section of the procedure to make it more descriptive but does not allow performance of a new or unrelated function.

D. request that would delete a required hold point in the original procedure. Correct Answer: D Reference 1000.006 page 5 section 4.9.2

Data for 2014 NRC RO/SRO Exam 29-Jan-14Bank:1993Safety FunctionSystem NumberGENERICSystem Title:Generic K/A2.2.6Description:Equipment Control - Knowledge of the process for making changes to procedures.RO Imp: 3.0SRO Imp: 3.6Lic Level:

RDifficulty:

2Taxonomy: FQuestion:Which one of the following is NOT an example of a procedure INTENT change? A. Minor alterations to the purpose for clarification B. Reducing the margin to nuclear safety C. Deleting a portion of the acceptance criteria D. Changing the scope of the procedureAnswer:A. Correct Notes:OP-1000.006, Procedure Control step 4.9.1 minor changes to the purpose section of a procedure is permitted as long as it doesnot allow the procedure to accomplish a function it was not intended for. B, C, and D are Incorrect, per the procedure, all aredefinitions of an INTENT change

References:

OP-1000.006, Procedure Control, Rev 065, step 4.9Source:Modified NRC Bank QID #40Rev: 1Rev Date:1/22/2014 10:30:2Search194001220610CFR55:41.10 / 43.3 / 45.13Historical Comments:NRC Bank QID #40 used on 1998 NRC ExamRev. 1: added procedure noun name to notes Tier: 3Group: 1Author:fosterL. Plan:ASLP-RO-PRCON OBJ 1QID #: 69 85Form ES-401-5 Written Exam Question Worksheet Question 70

_R 0 (NRC recommendations

) Revised Question:

You have been assigned a task that has been classified as an IPTE (Infrequently Performed Tests or Evolutions).

IAW EN-OP-116, Infrequently Performed Tests or Evolutions procedure, during an IPTE brief, ALL of the items on the IPTE Pre Job Checklist (i.e. Tech. Specs., TRM, ODCM, Fire Protection, FME, etc-) should be discussed _________ they are applicable to the evolution. Likewise, an IPTE Post Job Brief Checklist ______ required to be performed for ALL infrequently performed tasks and evolutions.

A. only if; is B. whether or not; is C. only if; is not D. whether or not; is not Correct answer: A Comments: EN-OP-116 states that items on the pre

-job checklist SHOULD be discussed, not that they are REQUIRED to be discussed. Recommend editing the stem as above to bring it into alignment with the procedure.

Data for 2014 NRC RO/SRO Exam 29-Jan-14Bank:1994Safety FunctionSystem NumberGENERICSystem Title:Generic K/A2.2.7Description:Equipment Control - Knowledge of the process for conducting special or infrequent tests.RO Imp: 2.9SRO Imp: 3.6Lic Level:

RDifficulty:

2Taxonomy: FQuestion:You have been assigned a task that has been classified as an IPTE (Infrequently Performed Tests or Evolutions).IAW EN-OP-116, Infrequently Performed Tests or Evolutions procedure, during an IPTE brief, ALL of the items on the IPTEPre Job Checklist (i.e. Tech. Specs., TRM, ODCM, Fire Protection, FME, etc...) should be discussed _____________ theyare applicable to the evolution. Likewise, an IPTE Post Job Brief Checklist ________ required to be performed for ALLinfrequently performed tasks and evolutions. A. only if; is B. whether or not; is C. only if; is not D. whether or not; is notAnswer:A. Correct Notes:As described in procedure which makes B, C, and D incorrect.

References:

EN-OP-116, Infrequently Preformed Tests or Evolutions, Rev 012, section 5.3, page 16 of 35 and section 5.2.5, page 14 of 35Source: NEWRev: 1Rev Date:1/29/2014 3:22:33Search194001220710CFR55:41.10 / 43.3 / 45.13Historical Comments:Rev. 1, reworded stem to include the work 'should' to more closely align with the procedure wording. (mwf 1/29/14)

Tier: 3Group: 1Author:fosterL. Plan:ASLP-RO-PRCON OBJ 16QID #: 70 86Form ES-401-5 Written Exam Question Worksheet

Question 71

_R0 (NRC recommendations

) Comments: The K/A selected (2.2.42) makes it difficult to write a non

-system specific question when the K/A references the use of system parameters to make a determination, requiring system specific knowledge. If the question has not already been reworked, recommend rejecting this K/A and selecting another K/A from Section 2.2 (Equipment Control) to replace it.

One possible replacement K/A: 2.2.35 Ability to determine the Technical Specification Mode of Operation RO 3.6/SRO 4.5 (NEW) Given the following conditions Reactor power is 0% on Power Range NI's Tcold is 218 F Keff - .90 The plant -. A. is currently in Mode 5, Cold Shutdown

. B. is currently in M ode 4 , Hot Shutdown

. C. will enter Mode 5 when average coolant temperature is reduced to <

210 F. D. will enter Mode 6 when average coolant temperature is reduced to <= 150 F

. Correct Answer

B Explanations:

A. Is credible because you are close to transitioning to mode 5 at <= 200 F B. Correct C. Credible because 210 F is close to the mode change value of 200 degrees D. Credible as mode 6 is achieved when avg temp drops below 140 degrees not 150 degrees

Data for 2014 NRC RO/SRO Exam 29-Jan-14Bank:1995Safety FunctionSystem NumberGENERICSystem Title:Generic K/A2.2.43Description:Equipment Control - Knowledge of the process used to track inoperable alarms.RO Imp: 3.0SRO Imp: 3.3Lic Level:

RDifficulty:

2Taxonomy: FQuestion:Consider the following: - An annunciator is comeing in and out of alram a distraction to the Control Room staff - The CRS has declared it a Nuisance Alarm - The Shift Manager has given permission to pull the annunciator card - OP-1015.001, Conduct of Operations, section 10.0 is being implmentedConcurrence from the _________________ must be obtained to ensure that pulling the annunciatorcard has no effect on continued system operability and a _________________________________is required to be installed on the pulled annunciator card stored inside the annunciator panel? A. System Engineer; Equipment Out of Service or Caution tag B. System Engineer; Work Incomplete or Temporary Services and Equipment tag C. Shift Technical Advisor; Equipment Out of Service or Caution tag D. Shift Technical Advisor; Work Incomplete or Temporary Services and Equipment tagAnswer: D. Shift Technical Advisor; Work Incomplete or Temporary Services and Equipment tag Notes:A and B are incorrect because the Shift Technical Advisor (STA) performs the system operability not the system engineer.The system engineers technical knowledge may be relied upon to make the appropriate operability call- but the finaldetermination will be made by the STA. A and C are incorrect because there are no Equipment Out of Service Tags, and aCaution Tag is a specific tag, not a generic tag as called for in the procedure. According to OPS expectations, TemporaryServices and Equipment (TSE) Tags should be used but the procedure still calls for Work Incomplete Tags or other genericidentification tag.

References:

OP-1015.001, Conduct of Operations, Rev 100, steps 10.1.1 (B) and 10.1.4 (A)Source:NRC BANK QID #1706Rev: 1Rev Date:1/23/2014 3:26:15Search194001224310CFR55:41.10 / 43.5 / 45.13Historical Comments:NRC Bank QID #1706 used on the 2009 NRC ExamRev. 1, replaced K/A and replaced question. (mwf 1/29/14)

Tier: 3Group: 1Author:fosterL. Plan:ASLP-RO-OPSPR OBJ 4QID #: 71 87Form ES-401-5 Written Exam Question Worksheet

Data for 2014 NRC RO/SRO Exam 31-Jan-14Bank:1995Safety FunctionSystem NumberGENERICSystem Title:Generic K/A2.2.43Description:Equipment Control - Knowledge of the process used to track inoperable alarms.RO Imp: 3.0SRO Imp: 3.3Lic Level:

RDifficulty:

2Taxonomy: FQuestion:Consider the following: - An annunciator is coming in and out of alarm, causing a distraction to the Control Room staff - The CRS has declared it a Nuisance Alarm - The Shift Manager has given permission to pull the annunciator card - OP-1015.001, Conduct of Operations, section 10.0 is being implementedConcurrence from the _________________ must be obtained to ensure that pulling the annunciatorcard has no effect on continued system operability and a(n) _________________________________is required to be installed on the pulled annunciator card stored inside the annunciator panel. A. System Engineer; Equipment Out of Service or Caution tag B. System Engineer; Work Incomplete or Temporary Services and Equipment tag C. Shift Technical Advisor; Equipment Out of Service or Caution tag D. Shift Technical Advisor; Work Incomplete or Temporary Services and Equipment tagAnswer: D. Shift Technical Advisor; Work Incomplete or Temporary Services and Equipment tag Notes:A and B are incorrect because the Shift Technical Advisor (STA) performs the system operability not the system engineer.The system engineers technical knowledge may be relied upon to make the appropriate operability call- but the finaldetermination will be made by the STA. A and C are incorrect because there are no Equipment Out of Service Tags, and aCaution Tag is a specific tag, not a generic tag as called for in the procedure. According to OPS expectations, TemporaryServices and Equipment (TSE) Tags should be used but the procedure still calls for Work Incomplete Tags or other genericidentification tag.

References:

OP-1015.001, Conduct of Operations, Rev 100, steps 10.1.1 (B) and 10.1.4 (A)Source:NRC BANK QID #1706Rev: 2Rev Date:1/23/2014 3:26:15Search194001224310CFR55:41.10 / 43.5 / 45.13Historical Comments:NRC Bank QID #1706 used on the 2009 NRC ExamRev. 1, replaced K/A and replaced question. (mwf 1/29/14)Rev. 2, corrected spelling, made changes based on NRC comments [mwf 1/30/14]

Tier: 3Group: 1Author:fosterL. Plan:ASLP-RO-OPSPR OBJ 4QID #: 71 87Form ES-401-5 Written Exam Question Worksheet Question 7 2_R0 (NRC recommendations

) Revised Question:

Consider the following:

Unit 2 has tripped from 100% power A 20 gpm tube leak in "B" Steam Generator occurs upon trip OP-2203.038, Primary to Secondary Leakage AOP, is being implemented CRS has directed the IAO to perform OP

-2202.010, Standard Attachments, Attachment 19, Control of Secondary Contamination

To prevent an inadvertent radiological release, OP

-2202.010, Attachment 19, Initial Actions would direct _________.

A. aligning Steam Generator Blowdown to the SU/BD DIs B. starting all available Auxiliary Building Exhaust fans (2VEF

-8s) C. securing the Turbine Building sumps to the Unit 1 Oily Water Separator D. isolating the discharge flowpath from the Unit 1 Oily Water Separator to the lake Comments: In the original version, distractor A could also be considered correct as there are words about coordinating with chemistry to align S/G blowdown as part of the long term actions. By adding the words "Initial Actions", to the stem, it makes distractor A incorrect, and leaves C as the only correct answer.

Data for 2014 NRC RO/SRO Exam 29-Jan-14Bank:1996Safety FunctionSystem NumberGENERICSystem Title:Generic K/A2.3.11Description:Radiological Controls - Ability to control radiation releases.RO Imp: 3.8SRO Imp: 4.3Lic Level:

RDifficulty:

3Taxonomy: HQuestion:Consider the following: - Unit 2 has tripped from 100% power - A 20 gpm tube leak in "B" Steam Generator occurs upon the trip - OP-2203.038, Primary to Secondary Leakage AOP, is being implemented - The CRS has directed the IAO to perform OP-2202.010, Standard Attachment 19, Control of Secondary ContaminationTo prevent an inadvertent radiological release, the initial actions of Standard Attachment 19 would direct_______________________________________ . A. aligning Condensate Flow to the 2T-94B DI B. starting all available Auxiliary Building Exhaust fans (2VEF-8s) C. securing the turbine building sumps to the Unit 1 Oily Water Separator D. isolating the discharge flowpath from the Unit 1 Oily Water Separator to the lakeAnswer:C Correct Notes:Att. 19 directs securing the Turbine building sump pumps to prevent an inadvertent release and to monitor a release throughthis flowpath

References:

OP-2203.038, Primary to Secondary Leakage AOP, Rev 014, step 7 page 4 of 32EOP-2203.038, Primary to Secondary Leakage Tech guide, Rev 014, step 7 page 10 of 33OP-2202.010, Standard Attachments, Rev 022, Attachment 19 pages 61 thru 64 of 204Source:NRC Bank QID #1681Rev: 1Rev Date:1/29/2014 3:31:44Search194001231110CFR55:41.11 / 43.4 / 45.10Historical Comments:NRC Bank QID #1681 used on the 2009 NRC ExamRev. 1, reworded distractor A to make incorrect. Reworded questions stem based on NRC comments. (mwf 1/29/14)

Tier: 3Group: 1Author:fosterL. Plan: A2LP-RO-APSEC OBJ 5&9QID #: 72 88Form ES-401-5 Written Exam Question Worksheet Question 7 3_R0 (NRC recommendations

) Revised Question:

Consider the following:

Unit 2 is in Mode 6 "A" SDC train is in service RCS cleanup is in progress following hydrogen peroxide addition WCO is investigating a noise in the room and calls for assistance CRS has sent the CBOT into the Auxiliary Building to help the WCO CBOT has been informed that the current measured dose rate in the "A" ESF pump room is 700 mr em/hour The "A" ESF pump room would be posted as a ____________ and, due to the posting for this area, Radiation Protection (RP) Personnel CONTINUOUS coverage ______ required for the CBOT. A. High Radiation Area; is B. High Radiation Area, is not C. Locked High Radiation Area, is D. Locked High Radiation Area, is not

Comments: Technical Specification 6.7.1.e Administration Controls, requires that for HRA entry, the dose rate must be determined and entry personnel knowledgeable, or be continuously escorted by RP. By rewording the stem slightly, it removes the confusion as to whether the CBOT had been informed of the current dose rate in the "A" ESF pump room.

Data for 2014 NRC RO/SRO Exam 29-Jan-14Bank:1997Safety FunctionSystem NumberGENERICSystem Title:Generic K/A2.3.13Description:Radiological Controls - Knowledge of radiological safety procedures pertaining to licensed operator duties,such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities,access to locked high-radiation areas, aligning filters, etc.RO Imp: 3.4SRO Imp: 3.8Lic Level:

RDifficulty:

2Taxonomy: FQuestion:Consider the following: - Unit 2 is in Mode 6 - "A" SDC train is in service - RCS cleanup is in progress following Hydrogen peroxide addition - General area dose rate in the "A" ESF pump room is 700 mr/hour - The WCO is investigating a noise in the room and calls for assistance - The CRS has sent the CBOT into the Auxiliary Building to help the WCO - The CBOT is knowledgable about the dose rates in the "A" ESF pump roomThe "A" ESF pump room would be posted as a __________________ and, due to the posting for this area, RadiationProtection (RP) Personnel CONTINUOUS coverage _______ required for the CBOT. A. High Radiation Area; is B. High Radiation Area; is not C. Locked High Radiation Area; is D. Locked High Radiation Area; is notAnswer:B. Correct Notes:The room should be posted as a High Radiation Area due to the dose rate is <1000 mrem. A High Radiation area has a doserate >100 to <1 rem. Access to a High Radiation area does not required continuous RP coverage

References:

Tech Spec 6.7.1, Administration ControlsEN-RP-100, Radiation Worker Expectations, Rev 8, section 5.3 [18] page 12 of 38EN-RP-101, Access Control for Radiologically Controlled Areas, Rev 8, section 3.0 [16] and [17] page 8 of 43Source:Modified NRC Bank QID #1782Rev: 1Rev Date:1/29/2014 3:38:46Search194001231310CFR55:41.12 / 43.4 / 45.9 / 45Historical Comments:NRC Bank QID #1782 used on 2011 NRC ExamRev. 1; removed the word "Area" from the stem after the first blank (repeated word). Added information to stem as suggestedby NRC comments. (mwf 1/29/2014)

Tier: 3Group: 1Author:fosterL. Plan:ASLP-RO-RADP OBJ 7QID #: 73 89Form ES-401-5 Written Exam Question Worksheet Question 7 4_R 1 (NRC recommendations

) Revised Question:

Abnormal Operating Procedures (AOPs) and Emergency Operating Procedures (EOPs) will give direction to "GO TO" another AOP, EOP or Normal Operating Procedure (NOP).

Which of the following describes the term "GO TO

?"

A. Complete the controlling procedure and then enter the procedure you were directed to "GO TO" B. Immediately exit the controlling procedure and then enter the procedure that you were directed to "GO TO

" C. Continue with the controlling procedure and perform the procedure that you are direct to "GO TO" in conjunction with it D. Immediately enter and complete the procedure you were directed to "GO TO" then return and complete the controlling procedure Answer: B (changed from C)

Comments: The original distractor D required STA concurrence and was not plausible. The revised distractor is more plausible in that operators might believe that they need to return to the original procedure after completing the GOTO procedure. This makes the revised distractor D plausible but incorrect.

Data for 2014 NRC RO/SRO Exam 29-Jan-14Bank:1998Safety FunctionSystem NumberGENERICSystem Title:Generic K/A2.4.5Description:Emergency Procedures/Plan - Knowledge of the organization of the operating procedures network for normal,abnormal, and emergency evolutions.RO Imp: 3.7SRO Imp: 4.3Lic Level:

RDifficulty:

2Taxonomy: FQuestion:Abnormal operating procedures (AOPs), and Emergency operating procedures (EOPs) will give direction to "GO TO" anotherAOP, EOP or normal operating procedure (NOP).Which of the following describes the term "GO TO"? A. Continue with the controlling procedure and perform the procedure that you are directed to "GO TO" in conjunction with it B. Complete the controlling procedure and then enter the procedure that you were directed to "GO TO" C. Immediately exit the controlling procedure and then enter the procedure that you were directed to "GO TO" D. Exit the controlling procedure when plant conditions allow, then enter the procedure that you were directed to "GO TO"Answer:C. Correct Notes:ANO-2 EOP/AOP User Guide uses the term "GO TO" to depart from the current procedure or step in the procedure and entereither another step in the current procedure or a different procedure altogether. It is used when the current procedure or step isnot working and will help the implementer with plant conditions and direct entry into a procedure that will help.

References:

OP-1015.021, ANO-2 EOP/AOP User Guide, Rev 011, section 4.4 page 3 of 73 , and section 4.40.10 page 11 of 73Source:Modified ANO Bank QID #ANO-OPS2-13018Rev: 1Rev Date:1/29/2014 3:33:44Search194001240510CFR55:41.10 / 43.5 / 45.13Historical Comments:ANO Bank QID #ANO-OPS2-13018Rev. 1, reworded D distractor to make more credible based on NRC comments. (mwf 1/29/14)

Tier: 3Group: 1Author:fosterL. Plan:A2LP-RO-ESPTA OBJ 3QID #: 74 90Form ES-401-5 Written Exam Question Worksheet Question 7 4_R 1 (NRC recommendations

) Revised Question:

Abnormal Operating Procedures (AOPs) and Emergency Operating Procedures (EOPs) will give direction to "GO TO" another AOP, EOP or Normal Operating Procedure (NOP).

Which of the following describes the term "GO TO

?"

A. Complete the controlling procedure and then enter the procedure you were directed to "GO TO" B. Immediately exit the controlling procedure and then enter the procedure that you were directed to "GO TO

" C. Continue with the controlling procedure and perform the procedure that you are direct to "GO TO" in conjunction with it D. Immediately enter and complete the procedure you were directed to "GO TO" then return and complete the controlling procedure Answer: B (changed from C)

Comments: The revised distractor is more plausible than exiting a procedure simply based on plant conditions.

Re-order distractors from shortest to longest.

Note: We had sent recommendations to Q74_R0 but you submitted R1 prior to receiving our recommendations. These recommendations are to R1.

Question 7 5_R0 (NRC recommendations

) Revised Question:

Consider the following:

Unit 2 is operating at 100% power An Annunciator check is being performed for the shift turnover checklist Alarm panels 2K01 through 2K07 do not alarm OP-2203.042, Loss of Annunciators AOP, has been entered In accordance with OP-2203.042, the operators would ______. A. maintain steady state plant conditions

. B. perform a one (1) hour rapid plant shutdown

. C. perform a two (2) hour normal plant shutdown

. D. trip the plant and enter the SPTA's

.

Comments: The original question asked what the CRS would do, which does not provide a good legal basis for the question and answers, so the revised question ties the answers to what the procedure would direct based on the initial conditions, which provides the necessary legal basis.

Data for 2014 NRC RO/SRO Exam 29-Jan-14Bank:1999Safety FunctionSystem NumberGENERICSystem Title:Generic K/A2.4.32Description:Emergency Procedures/Plan - Knowledge of operator response to loss of all annunciators.RO Imp: 3.6SRO Imp: 4.0Lic Level:

RDifficulty:

3Taxonomy: HQuestion:Consider the following - Unit 2 is at 100% power - No annunciators will alarm on Annunciator panels 2K01 thru 2K12 - OP-2203.042, Loss of Annunciators AOP, has been enteredPer OP-2203.042, the required action is to _______________. A. immediately commence a plant shutdown due to the inability to monitor the plant B. maintain steady state plant conditions due to the inability to monitor the plant C. immediately commence a plant shutdown due to the loss of COLSS D. maintain steady state plant conditions due to the loss of COLSSAnswer:B. Correct Notes:2K01 thru 2K12 are all the annunciators on the front panels.B. Correct: Plant maneuvers are not recommended or required without remote monitoring capability (annunciators) steady state plant operation is preferred.A. Incorrect: An immediate plant shutdown is not directed by the AOP. A plant maneuver could be required per Tech Specs, but not in this case.C. Incorrect: An immediate plant shutdown is not directed by the AOP. A plant maneuver could be required per Tech Specs, but not in this case.D. Incorrect. The AOP does require the plant to be maintained at steady state plant conditions, but COLSS is not lost, just the ability to continuously monitor COLSS. The required action is for the operators to continuously monitor COLSS on the plant computer.

References:

OP-2203.042, Loss of Control Room Annunciators AOP, Rev 006, step 3 page 2 of 20AOP-2203.042, Loss of Control Room Annunciators Tech Guide, Rev 005, step 3 page 6 of 12Source: NEWRev: 1Rev Date:1/29/2014 4:23:41Search194001243210CFR55:41.10 / 43.5 / 45.13Historical Comments:Rev. 1, reworded question and distractors to make all choices more credible per NRC comments. (mwf 1/29/14)

Tier: 3Group: 1Author:fosterL. Plan: A2LP-RO-PANN OBJ 8QID #: 75 91Form ES-401-5 Written Exam Question Worksheet Question 7 5_R 1 (NRC recommendations

) Revised Question:

Consider the following:

- Unit 2 downpower is planned for surveillance testing

- Annunciator check is being performed for the shift turnover checklist

- Alarm panels 2K01 through 2K07 do not alarm - OP-2203.042, Loss of Annunciators AOP, has been entered In accordance with OP-2203.042, the operators would ________. The fault __________ propagate to other alarm panels.

A. not perform the downpower; could B. not perform the downpower; could not C. use alternate indications to perform the downpower; could D. use alternate indication to perform the downpower; could not Answer: A Comments: The original question asked what the CRS would do, which does not provide a good legal basis for the question and answers, so the revised question ties the answers to what the procedure would direct based on the initial conditions, which provides the necessary legal basis. Also, by altering the stem to include a downpower, it provides the opportunity to test the applicants on whether or not the downpower could continue, which the AOP does not allow, except in the case of exceeding Technical Specification limits.

Since the downpower is for a surveillance, there is no indication of exceeding a Technical Specification limit, so the downpower would not be performed. The procedure does allow operators to downpower using alternate indications if a limit is exceeded, so this makes distractors C and D plausible but incorrect. The second piece is a caution from the AOP, which states that fault may propagate from 2K01 through 2K12, making answer A correct. Distractor B is plausible if the applicant cannot remember if the alarms are all on the same circuit.

Data for 2014 NRC RO/SRO Exam 30-Jan-14Bank:2000Safety Function 3System Number 009System Title:Small Break LOCA K/AEA2.06Description:Ability to determine and interpret the following as they apply to a small break LOCA: - Whether PZR waterinventory loss is imminentRO Imp: 3.8SRO Imp: 4.3Lic Level:

SDifficulty:

3Taxonomy: HQuestion:(REFERENCE PROVIDED)Consider the following: - Unit 2 is operating at 100% power - "C" HPSI pump (2P-89C) is OOS for maintenance - "C" CCP (2P-36C) is aligned to Green - ATC reports Containment parameters are trending up (pressure, temperature, radition, and humidity) - Pressurizer level is 60% - Volume Control Tank (VCT) level is 72%3 minutes later: - Pressurizer level is 59% - VCT level is 71%Unit 2 now trips due to a Loss of Offsite Power (LOOP) - Annunciator 2K08 C-2 "ENGINE/EXCITER SHUTDOWN" for #1 EDG is in alarm - CBOT reports "B" HPSI pump is running without discharge pressure - RCS Leakrate does not change post tripBased on conditions above, the Reactor Coolant System (RCS) inventory (Pressurizer level) ________ recover (trend up) andafter performing SPTAs, the CRS would diagnose entry into _________________________________. A. would; OP-2203.016, Excess RCS Leakage B. would; OP-2202.003, Loss of Coolant Accident C. would not; OP-2203.016, Excess RCS Leakage D. would not; OP-2202.003, Loss of Coolant AccidentAnswer:B. Correct Notes:The leakrate is based on 55.3 gallons per percent in the pressurizer x 1% change in level = 55.3 gallons 33.8 gallons perpercent in the VCT x 1% change in level = 33.8 gallons, 55.3 + 33.8 = 89.1 gallons / 3 minutes (time frame the leakrate datawas taken) = 29.7 gallon/minutes RCS leakage. SIAS would be actuated due to the RCS leakage and with the loss of offsitepower (LOOP) and the #1 EDG not supplying the bus (exciter shutdown) only Green Train components will be available formakeup sources. With the "C" HPSI (swing) pump OOS and the failure of the "B HPSI pump the 2 CCPs (with a capacity of44 gpm each) would be available to makeup to the Pressurizer (the "B" LPSI pump would be running but RCS pressure wouldSource: NEWRev: 1Rev Date:1/30/2014 8:54:44Search000009A20610CFR55:41.7 / 41.10 / 43.5 / 45 Tier: 1Group: 1Author:fosterL. Plan:A2LP-RO-ELOCA OBJ 6QID #: 76 92Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 30-Jan-14be to high for injection (RCS makeup > RSC leakage) therefore Pressurizer level would trend up at approximately 1% /minute. With a leakrate of 29.7 gpm entry conditions for OP-2203.016, Excess RCS Leakage. Exhibit 8 will direct the CRS todiagnose LOCA due to a RCS leak with a LOOP.A. Incorrect. Pressurizer level would be trending up, but it is incorrect to diagnose Excess RCS leakage AOP. Per Exhibit 8 ofStandard Attachments, when an AOP is combined with a LOOP, the associated EOP is diagnosed, which is the LOCA EOP.Plausible because the Excess RCS Leakage AOP could be diagnosed coming out of Standard Post Trip ActionsB. Correct. Pressurizer level would be recovering and per Standard Attachments Exhibit 8, Excess RCS Leakage AOP plus aLOOP EOP results in a diagnosis of the LOCA EOP.C. Incorrect. Per the calculation above, Pressurizer level would be recovering not going down. Plausible because the candidatecould calculate the wrong leakrate.D. Incorrect. Per the calculation above, Pressurizer level would be recovering not going down. Plausible because the candidatecould calculate the wrong leakrate.

References:

[PROVIDED] OP-2305.002, Reactor Coolant System Leak Detection, Rev 024 Exhibit 1 page 39 of 54OP-2203.012H, Annunciator Corrective Actions, 2K08 window C-2, Rev 037, page 15 of 50OP-2202.010, Standard Attachments, Rev 022, Exhibit 8 page 193 of 204Historical Comments:Rev. 1; changed second bullet pump noun name to match pump number (when from "A" to "C") fourth bullet, added radiation to the list of parameters trending up (based on validator comments), corrected leakrate number in notes from 89.2 to 89.1 (calculation iwas correct) and added CCP capicity of 44 gpm. Updated notes to show why each distractor is plausible but incorrect. (mwf 1/30/14) 93Form ES-401-5 Written Exam Question Worksheet

Data for 2014 NRC RO/SRO Exam 30-Jan-14Bank:2001Safety Function 4System Number 040System Title:Steam Line Rupture K/A2.4.2Description:Emergency Procedures/Plan - Knowledge of system set points, interlocks and automatic actions associatedwith EOP entry conditions.RO Imp: 4.5SRO Imp: 4.6Lic Level:

SDifficulty:

4Taxonomy: HQuestion:Consider the following: - Unit 2 has tripped from 100% power - RCS pressure is 1800 psia and lowering - Containment pressure is trending up - Containment High Range Radiation Monitors are in alarm and rising - Containment Low Range Radiation Monitors are reading 10 mr/hr and stable - 'A' SG level is 18% - 'B' SG level is 20% - 'A' SG pressure is 730 psia and lowering - 'B' SG pressure is 900 psia and slowly lowering - Assume no operator actions have been takenThe CRS would diagnose _________________ and EFW would be aligned to ____________. A. OP-2202.003, Loss of Coolant Accident EOP, 'B' SG only B. OP-2202.003, Loss of Coolant Accident EOP, 'A' and 'B' SGs C. OP-2202.005, Excess Steam Demand EOP, 'B' SG only D. OP-2202.005, Excess Steam Demand EOP, 'A' and 'B' SGsAnswer:C. Correct Notes:A. Incorrect. LOCA EOP would not be diagnosed in this scenario because the Containment Low Range Radiation Monitorsare reading normal and stable and 'A' SG pressure is lowering. The Containment High Range Radiation Monitors are in alarmand rising, which could distract the applicant, but the coaxial cables for these radiation monitors have been susceptible tothermally induced currents which make them read false high during an ESD. Plausible because all the other indications areconsistent with a LOCA.B. Incorrect. LOCA EOP would not be diagnosed in this scenario because the Containment Low Range Radiation Monitorsare reading normal and stable and 'A' SG pressure is lowering. The Containment High Range Radiation Monitors are in alarmand rising, which could distract the applicant, but the coaxial cables for these radiation monitors have been susceptible tothermally induced currents which make them read false high during an ESD. Plausible because all the other indications areconsistent with a LOCA.Source:Modified NRC Bank QID #1566Rev: 1Rev Date:1/30/2014 8:46:17Search000040240210CFR55:41.7 / 45.7 / 45.8 Tier: 1Group: 1Author:fosterL. Plan: A2LP-RO-COLSS OBJ 17QID #: 77 94Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 30-Jan-14C. Correct. ESD EOP diagnosis is correct based on lowering RCS pressure, Containment Low Range Radiation Monitorsstable, and 'A' SG pressure trending down. MSIS actuates at 751 psia. Both Steam Generators will be fed by EFW until 751psia is reached. At that point, the EFAS initiation logic would isolate EFW flow to the affected SG 'A'. SG 'B' would continueto be fed by EFW.D. Incorrect. ESD EOP diagnosis is correct based on lowering RCS pressure, Containment Low Range Radiation Monitorsstable, and 'A' SG pressure trending down. MSIS actuates at 751 psia. Both Steam Generators will be fed by EFW until 751psia is reached. At that point, the EFAS initiation logic would isolate EFW flow to the affected SG 'A'. SG 'B' would continueto be fed by EFW. So what makes this distractor incorrect is that 'A' SG would not be fed with pressure less than 751 psia.Plausible because 'A' SG would be fed until 751 psia is reached and then it would be isolated by the EFAS initiation logic.

References:

STM 2-19-2, EFW & AFW Systems, Rev. 35, Section 2.3.3.1, page 22STM 2-62, Radiation Monitoring System, Rev. 21, Section 2.1.2, page 11OP-2202.005, ESD EOP, Rev. 014, Entry Conditions, page 1 of 41OP-2202.003, LOCA EOP, Rev. 014, Entry Conditions, page 1 of 67Historical Comments:NRC Bank QID #1566, used on the 2008 NRC ExamRev. 1: Rewrote questions to change from Overcooling AOP to ESD EOP per NRC comments to better match K/A. (mwf1/30/14)95Form ES-401-5 Written Exam Question Worksheet

Data for 2014 NRC RO/SRO Exam 30-Jan-14Bank:2002Safety Function 6System Number 055System Title:Loss of Offsite and Onsite Power (Station Black K/AEA2.01Description:Ability to determine and interpret the following as they apply to a Station Blackout: - Existing valvepositioning on a loss of instrument air systemRO Imp: 3.4SRO Imp: 3.7Lic Level:

SDifficulty:

2Taxonomy: HQuestion:Consider the following: - Unit 2 is operating at 100% power - Alternate AC Diesel Generator (AACDG) is OOS for maintenance - A Loss of Offsite Power (LOOP) now occurs - Upon the trip neither Emergency Diesel Generator (EDG) is running - IAO is unable to start either EDG - SPTAs are completeCRS would diagnose entry into ___________________________ and Reactor Coolant Pump (RCP) Controlled Bleedoff(CBO) Flow would be aligned to the _________________________. A. OP-2202.007, Loss of Offsite Power EOP; Quench Tank (QT) B. OP-2202.007, Loss of Offsite Power EOP; Volume Control Tank (VCT) C. OP-2202.008, Station Blackout EOP; Quench Tank (QT); D. OP-2202.008, Station Blackout EOP; Volume Control Tank (VCT)Answer:C. Correct Notes:The student should recognize a Station Blackout is in progress (due to the LOOP, AACDG OOS and neither EDG starting)The CRS would diagnose the Station Blackout EOP using Standard Attachments Exhibit 8, Diagnosis Flow Chart. Withoutpower to the non-vital buses, there would be no Instrument Air pressure and the CBO flowpath to the VCT would isolate(valves fail close) which will align CBO to the QT through the CBO relief valve.A. Incorrect. Because neither EDG could be started during SPTAs and the AAC DG is unavailable, both 2A3 and 2A4 are de-energized. This meets the entry conditions for the SBO EOP. Plausible because a LOOP does exist in the stem of the question.B. Incorrect. Because neither EDG could be started during SPTAs and the AAC DG is unavailable, both 2A3 and 2A4 are de-energized. This meets the entry conditions for the SBO EOP. Plausible because a LOOP does exist in the stem of the question.C. Correct. Because neither EDG could be started during SPTAs and the AAC DG is unavailable, both 2A3 and 2A4 are de-energized. This meets the entry conditions for the SBO EOP. Without power to the non-vital buses, there would be noInstrument Air pressure and the CBO flowpath to the VCT would isolate (valves fail close) which will align CBO to the QTthrough the CBO relief valve.Source: NEWRev: 1Rev Date:1/30/2014 8:55:45Search000055A20110CFR55:41.7 / 41.10 / 43.5 / 45 Tier: 1Group: 1Author:fosterL. Plan:A2LP-RO-ESPTA OBJ 17QID #: 78 96Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 30-Jan-14D. Incorrect. Without power to the non-vital buses, there would be no Instrument Air pressure and the CBO flowpath to theVCT would isolate (valves fail close) which will align CBO to the QT through the CBO relief valve. Plausible because CBO isaligned to the VCT prior to the power failure and the power failure results in CBO being realigned to the QT.

References:

STM 2-04, Chemical and Volume Control System, Rev 29, section 2.1 page 21 and simplified drawing page 62OP-2202.010, Standard Attachments, Rev 022, Exhibit 8 page 193 of 204Historical Comments:Rev 1: Changed Taxonomy from "F" to "H", swapped order of question/answers, added relief valve to flowpath of CBO to theQT. [mwf 1/27/14]

97Form ES-401-5 Written Exam Question Worksheet

Data for 2014 NRC RO/SRO Exam 30-Jan-14Bank:2003Safety Function 6System Number 058System Title:Loss of DC Power K/A AA2.03Description:Ability to determine and interpret the following as they apply to the Loss of DC Power: - DC loads lost;impact on ability to operate and monitor plant systemsRO Imp: 3.5SRO Imp: 3.9Lic Level:

SDifficulty:

4Taxonomy: HQuestion:Consider the following: - Unit 2 is operating at 100% power - 2D02 Green Battery disconnect has been opened for maintenance - Battery charger, 2D-32B, is in service - Now 2D-32B the output breaker trips openThe CRS would diagnose entry into ______________________________ and Pressurizer level would be maintained bycycling a Coolant Charging Pump (CCP) due to ______________ letdown isolation valve failing closed. A. OP-2202.001, Standard Post Trip Action EOP; 2CV-4820-2, inside containment B. OP-2202.001, Standard Post Trip Action EOP; 2CV-4823-2 outside containment C. OP-2203.037, Loss of 125V DC AOP; 2CV-4820-2, inside containment D. OP-2203.037, Loss of 125V DC AOP; 2CV-4823-2, outside containmentAnswer:D. Correct Notes:With the Green Battery disconnected from its bus [2D02] the battery charger is supplying all green DC loads. When thechargers breaker trips open, a loss of green DC will occur. The unit will stay on line and the Loss of DC AOP would beentered. The outside containment letdown isolation valve [2CV-4823-2] is air operated and the air supply is controlled by agreen DC solenoid. When green DC is lost, the valve will fail closed isolating letdown and cause Pzr level to be maintained bycycling CCPs.A. Incorrect. The Unit does not trip automatically nor is it an action required by the AOP to trip the Reactor and go to SPTAsupon a loss of Green DC. Plausible because a loss of Green DC does automatically open 2 trip circuit breakers but this doesnot cause a Reactor trip.B. Incorrect. The Unit does not trip automatically nor is it an action required by the AOP to trip the Reactor and go to SPTAsupon a loss of Green DC. Plausible because a loss of Green DC does automatically open 2 trip circuit breakers but this doesnot cause a Reactor trip.C. Incorrect. The Loss of DC AOP is entered but the Letdown Isolation valve inside containment does not automatically closeupon a loss of Green DC. Plausible because letdown does isolate on a loss of Green DC, but it is the Letdown Isolation valveoutside containment that closes not the valve inside containment.Source: NEWRev: 1Rev Date:1/27/2014 9:47:18Search000058A20310CFR55:41.7 / 41.10 / 43.5 / 45 Tier: 1Group: 1Author:fosterL. Plan:A2LP-RO-ED125 OBJ 11QID #: 79 98Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 30-Jan-14D. Correct. With the Green Battery disconnected from its bus [2D02] the battery charger is supplying all green DC loads.When the chargers breaker trips open, a loss of green DC will occur. The unit will stay on line and the Loss of DC AOPwould be entered. The outside containment letdown isolation valve [2CV-4823-2] is air operated and the air supply iscontrolled by a green DC solenoid. When green DC is lost, the valve will fail closed isolating letdown and cause Pzr level tobe maintained by cycling CCPs.

References:

OP-2203.037, Loss of 125V DC AOP, Rev 009, entry page 1 of 57, section 3 step 2.A. page 33 of 57OP-2203.037, Loss of 125V DC Tech Guide, Rev 009, section 3 step 2entry page 45 of 75STM 2-04, Chemical and Volume Control System, Rev 29, section 2.1.5 page 6 and simplified drawing on page 62STM 2-32-5, 125Vdc Electrical Distribution, Rev 19, section 2.7.2 page 15Historical Comments:Rev. 1; changed wording of stem. Added clarification in note section. Added STM 2-04 to the references for 2CV-4823-2 andSTM 2-32-5 for modifications to the DC bus. Updated notes. [wmf 1/27/14]

99Form ES-401-5 Written Exam Question Worksheet

Data for 2014 NRC RO/SRO Exam 30-Jan-14Bank:2004Safety Function 4System Number 062System Title:Loss of Nuclear Service Water K/A2.1.32Description:Conduct of Operations - Ability to explain and apply system limits and precautions.RO Imp: 3.8SRO Imp: 4.0Lic Level:

SDifficulty:

3Taxonomy: HQuestion:Service Water Systems Operations procedure, OP-2104.029, has Limits and Precautions associated with the EmergencyCooling Pond (ECP) Level and Temperature Tech Spec 3.7.4.1.Tech Spec 3.7.4.1 Bases, a MINIMUM indicated ECP level of ____ feet, based on soundings and includes measurement,calculation and other uncertainties (equivalent to 0.15 ft), ensures an adequate heat sink based on worst case initial conditionsduring a simultaneous shutdown of Unit 1 and emergency shutdown of Unit 2 following a Unit 2 LOCA.Also, Operator action ________ credited to initiate makeup to ECP upon a loss of Dardanelle Reservoir to maintain theminimum water volume required for a 30 day supply of cooling water to safety related components without exceeding theirdesign basis temperature. A. 5.2; is B. 5.2; is not C. 5.5; is D. 5.5; is notAnswer:A. Correct Notes:Aligns with T.S. 3.7.4.1 bases for the minimum indicated ECP level of 5.2 feet. This requirement is based on soundings andincludes measurement, calculation and other uncertainties (equivalent to 0.15 ft) to ensure a minimum contained watervolume of 70 area-feet crediting operator action to initiate makeup to ECP upon loss of Dardanelle Reservoir. The additionalwater added to the ECP during the time between first swapping the returns to the ECP and then later swapping the suctions tothe ECP will maintain the ECP >70 area-feet and provide adequate supply of water for a 30 day supply of cooling water toECCS components to operate without exceeding their design base temperature.

References:

OP-2104.029, Service Water Systems Operations, Rev 096, section 5.0 step 5.25 and 5.26 page 8 of 312Tech Spec 3.7.4.1, ECP Level and Temperature requirementsTech Spec Bases B3.7.4.1, ECP Level and Temperature requirementsOPS-B31, Unit 2 outside AO Logs, Rev 46, ECP Level reading, page 9Source: NEWRev: 1Rev Date:1/27/2014 10:21:2Search000062213210CFR55:41.10 / 43.2 / 45.12Historical Comments:Rev. 1; changed rev number for OP-2104.029, verified no impct on question [mwf 1/27/14]

Tier: 1Group: 1Author:fosterL. Plan: A2LP-RO-SWACW OBJ 13&15QID #: 80 100Form ES-401-5 Written Exam Question Worksheet

Data for 2014 NRC RO/SRO Exam 30-Jan-14Bank:2005Safety Function 6System Number 077System Title:Generator Voltage and Electric Grid Disturbanc K/A2.2.36Description:Equipment Control - Ability to analyze the effect of maintenance activities, such as degraded power sources,on the status of limiting conditions for operations.RO Imp: 3.1SRO Imp: 4.2Lic Level:

SDifficulty:

3Taxonomy: HQuestion:[REFERENC PROVIDED]Consider the following: - Unit 2 is operating at 100% power - #2 EDG is out of service for its 18 month overhaul - The Unit 2 control room has just been informed that Startup #2 (SU2) Transformer is InoperableWhat action, listed below, is required FIRST? A. Restore at least one of the inoperable sources to OPERABLE status B. Demostrate the operability of the remaining AC circuit C. Demonstrate the operability of #1 EDG D. Place the Unit in HOT STANDBYAnswer:B. Correct Notes:T.S. 3.8.1.1 covers a varity of combinations of loss of power sources. Action 'c' covers a loss of an offsite source (SU2) alongwith the #2 EDG being unavailable due to planned maintenance. 3.8.1.1.c.1. required performance of OP-2107.001, ElectricalSystem Operation, Supp. 4 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least every 8 hours0.333 days <br />0.0476 weeks <br />0.011 months <br /> thereafter.A. Incorrect: The stated condition is not outside T.S.3.8.1.1 LCOC. Incorrect: If an offsite power source was inoberable first, then a EDG became unavailable, then within 8 hours oberalbility of the remaining EDG would have to be demonstrateD. Incorrect: No requirements to place the Unit in HOT STANDBY within 72 hours3 days <br />0.429 weeks <br />0.0986 months <br />

References:

T.S. 3.8.1.1, Electrical Systems Modes 1-4Source:ANO Bank QID #ANO-OPS2-7035Rev: 1Rev Date:1/30/2014 9:42:33Search000077223610CFR55:41.10 / 43.2 / 45.13Historical Comments:ANO Bank QID #ANO-OPS2-7035Rev. 1: Changed the wording of the distractors to match Tech Spec action statement wording. Incorporated NRC commentsand reworded distractor C per NRC comments. (mwf 1/30/14)

Tier: 1Group: 1Author:fosterL. Plan:A2LP-RO-EDHVD OBJ 9QID #: 81 101Form ES-401-5 Written Exam Question Worksheet Comments on Q 81_R1 There are a couple follow

-on comments:

1) Text was added indicating that this question will now have a reference provided (the word REFERENCE is misspelled, by the way).

The reference needs to be clearly identified on the Worksheet and needs to be sent to NRC (if we don't already have it) so we can review it prior to accepting the question as satisfactory. The reference will also need to be included in the revised question file when the exam is submitted again.

2) On answer B, revise it to say "Demonstrate the operability of the remaining offsite AC circuit." The word "offsite" is used in the Technical Specifications text (LCO 3/4.8.1, Action c.1).

3) There are still some minor edits that were identified on the worksheet we sent to you as comments for R0 on January 26 th.

Data for 2014 NRC RO/SRO Exam 30-Jan-14Bank:2006Safety Function 1System Number 005System Title:Inoperable/Stuck Control Rod K/A2.2.22Description:Equipment Control - Knowledge of limiting conditions for operations and safety limits.RO Imp: 4.0SRO Imp: 4.7Lic Level:

SDifficulty:

2Taxonomy: FQuestion:After realignment of an Inoperable Control Element Assembly (CEA), OP-2203.003, CEA Malfunction AOP, directsmaintaining Reactor power constant for at least one hour prior to performing a power escalation.Per the CEA Malfunction Tech Guide, the reason for this one hour hold is _______________________ . A. to allow ASI to stabilize prior to performing the power escalation after realignment of the CEA B. to prevent pellet-cladding interactions caused by the redistribution of core power from the misaligned CEA C. to prevent exceeding the COLSS ASI operational limit of +/- 0.27 when performing the power escalation after realignment of the CEA D. to prevent exceeding the Tech Spec limits on Azimuthal Tilt (Az Tilt) caused by the redistribution of core power from the misaligned CEAAnswer:B. Correct Notes:Per the AOP tech guide, reactor power is maintained constant for at least one hour to prevent pellet-clad interactions causedby the redistribution of core power from the misaligned Control Element Assembly (CEA)

References:

OP-2203.003, CEA Malfunction AOP, Rev 020, step 33 page 13 of 27AOP-2203.003, CEA Malfunction Tech Guide, Rev 020, step 33 page 27 of 34Source:ANO Bank QID #ANO-OPS2-6094Rev: 1Rev Date:1/30/2014 9:43:14Search000005222210CFR55:41.5 / 43.2 / 45.2Historical Comments:ANO Bank QID #ANO-OPS2-6094Rev. 1; changed order of answers per NRC comment and corrected other wording per NRC comments. [mwf 1/30/14]

Tier: 1Group: 2Author:fosterL. Plan:A2LP-RO-ACEA OBJ 2QID #: 82 102Form ES-401-5 Written Exam Question Worksheet Comments on Q 8 2_R1 The changes made addressed BTL's markups. It is satisfactory from that perspective.

The question is SRO level of knowledge, but it isn't clear how this ties to the K/A statement.

The question doesn't appear to test knowledge of the LCO's or Safety Limits. If applying the AOP is implementing a Surveillance Requirement driven by the LCO Action Statement for one CEA inoperable, then the tie could be established. With the given references, this isn't clear.

If the tie to the KA can be established, enhance the Notes and submit as R2.

Data for 2014 NRC RO/SRO Exam 30-Jan-14Bank:2007Safety Function 1System Number 024System Title:Emergency Boration K/A AA2.01Description:Ability to determine and interpret the following as they apply to the Emergency Boration: - Whether boronflow and/or MOVs are malfunctioning, from plant conditionsRO Imp: 3.8SRO Imp: 4.1Lic Level:

SDifficulty:

3Taxonomy: HQuestion:Consider the following: - Unit 2 is operating at 100% power - Annunciator 2K12 B-2 "HEADER PRESS LO" for the Coolant Charging Pumps (CCPs) comes into alarm - Annunciator 2K12 B-3 "HEADER FLOW LO" for the CCPs comes into alarm - Volume Control Tank (VCT) level is 58% and lowering - The WCO reports a rupture in the CCP suction header downstream of the RWT supply valve, 2CV-4950-2 and check valve - OP-2203.036, Loss of Charging AOP, has been entered and the CRS directs tripping the Unit - The ATC reports 3 CEAs did not fully insert on the trip and reactor power is 0.2% and steady - SPTAs have been completedThe CRS would diagnose _____________________________ and Emergency Boration would be accomplished by______________________________________________ . A. OP-2202.009, Functional Recovery EOP; aligning CCP discharge to the #1 HPSI header B. OP-2202.009, Functional Recovery EOP; lowering RCS pressure and starting a HPSI pump C. OP-2203.032, Emergency Boration AOP; aligning CCP discharge to the #1 HPSI header D. OP-2203.032, Emergency Boration AOP; lowering RCS pressure and starting a HPSI pumpAnswer:B. Correct Notes:With the given conditions entering Functional Recovery and depressurizing the RCS to allow using HPSI to emergency borateis correct. The location of the charging suction header rupture is unisoable from the rest of the system rendering all CCPsincapable of adding inventory to the RCS. With >1 CEA not fully inserted and reactor power >.1% and stable requires theaddition of boron to meet shutdown margin. The Emergency Boration AOP does contain direction to depressurize and use aHPSI pump but it is not addressed on the exhibit 8 as an option to enter post SPTAs with the reactivity safety function notmet. Standard Attachment Exhibit 1, Emergency Boration, would have been attempted during SPTA's, but would have nothave been successful. Emergency Boration AOP is not one of the procedures that can be diagnosed coming out of SPTAs.

References:

OP-2203.012L, Annunciator Corrective Actions, 2K12 window B-2, Rev 044 page 18 of 116OP-2203.012L, Annunciator Corrective Actions, 2K12 window B-3, Rev 044, page 36 of 116OP-2203.036, Loss of Charging AOP, Rev 011, step 8, contingency 8.2) page 7 of 24Source:NRC Bank QID #1569Rev: 1Rev Date:1/30/2014 9:55:36Search000024A20110CFR55:41.7 / 41.10 / 43.5 / 45 Tier: 1Group: 2Author:fosterL. Plan:A2LP-RO-EFRP OBJ 4QID #: 83 103Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 30-Jan-14OP-2202.010, Standard Attachments, Rev 022, Exhibit 8 page 193 of 204OP-2202.009, Functional Recovery, Rev 017, entry section step 11.A page 10 of 45OP-2202.009, Functional Recovery, Rev 017, section RC, Reactivity Control Decision Tree page 1 of 11 and section RC-3step 4 contingency columeOP-2202.001, Standard Post Trip Actions EOP, Rev. 014, Step 3.C (Contingency), page 3 of 19OP-2202.010, Standard Attachments, Exhibit 1, Emergency Boration, Rev. 022, page 179 of 204Historical Comments:NRC Bank QID #1569 used on the 2008 NRC ExamRev. 1: changed RWT to CCP suction from 2CV-4850-2 to 4950-2, added check valve to location, added simiplified drawingof CVCS to show location of break. Incorported NRC comments into notes and references. [mwf 1/27/14]

104Form ES-401-5 Written Exam Question Worksheet Comments on Q 8 3_R1 From S. Hedger

The markups provided by BTL have been addressed.

IF the question is written to the correct K/A (see below), it is satisfactory.

If ES-401-2, Revision 2, is the written exam outline of record, then this question is not written to the K/A in the outline.

- For Tier 1, Group 2, in the SRO section, there is an outline selection for 024 Emergency Boration, G 2.4.41, Knowledge of the emergency action level thresholds and classifications.

- The proposed question is written to 024 Emergency Boration, AA2.01, Ability to determine and interpret the following as they apply to the Emergency Boration:

Whether boron flow and/or MOVs are malfunctioning, from plant conditions

Either the K/A was rejected and should be justified with a newer revision to the exam outline, or the question provided does not meet the K/A statement.

From B. Larson

The ES-401-4, Record of Rejected KAs, Rev 1, does have an entry for changing the KA for this question. It states "There is not an E

-Plan associated with Emergency Boration. Selected 024 AA 2.01 as the replacement K/A."

If the 401

-4 entry is correct, then R1 is sat for the examiner review.

Data for 2014 NRC RO/SRO Exam 30-Jan-14Bank:2008Safety Function 5System Number 069System Title:Loss of Containment Integrity K/A2.1.1Description:Conduct of Operations - Knowledge of conduct of operations requirements.RO Imp: 3.8SRO Imp: 4.2Lic Level:

SDifficulty:

2Taxonomy: FQuestion:Consider the following: - Unit 2 is in Mode 4 and heating up - Control Board panel walkdowns are being performed in preparations to enter Mode 3 - CBOT reports Containment Purge system isolation valves are open with keys insertedThe required action to comply with Tech Spec, 3.6.1.6 and restore Containment Purge system to an Operable status would beto verify Containment Purge isolation valves closed with keys removed within the maximum allowed time of______________________ because, per the Tech Spec bases, the valves have not demonstrated capability of being closedduring a ______________________ inside Containment . A. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; Loss of Coolant Accident (LOCA) B. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; Excess Steam Demand (ESD) C. 2 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br />; Loss of Coolant Accident (LOCA) D. 2 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br />; Excess Steam Demand (ESD)Answer:A. Correct Notes:Technical Specification 3.6.1.6 requires all three Containment Purge Isolations in the supply and exhaust ducts to remainclosed and keys removed during modes 1-4. These valve are only opened in Modes 5 and below to ensure ContainmentIntegrity is maintained in Modes 1-4. Per T.S. Bases, Purge valves are required to be closed with keys removed due to thevalves have not demonstrated capability of being closed during a LOCA

References:

Technical Specification 3.6.1.6, Containment Ventilation System and BasesSource: NEWRev: 1Rev Date:1/22/2014 10:40:2Search000069210110CFR55:41.10 / 45.13Historical Comments:Rev. 1, reworded question statement and changed distractors to make all of them credible per NRC comments. (mwf 1/30/14)

Tier: 1Group: 2Author:fosterL. Plan:A2LP-RO-CVENT OBJ 15QID #: 84 105Form ES-401-5 Written Exam Question Worksheet Comments on Q 8 4_R1 From S. Hedger:

In Revision 1 to the question, the K/A statement has changed. It changed from 069 Loss of Containment Integrity, K/A A2.02, to K/A G2.1.1. In looking at this, and Question 83, I suspect that a swap of the A2 and G K/As for these was completed. However, it this isn't something that has been negotiated, it is captured here for follow up.

The question has been revised to test an additional area of knowledge that is SRO

-only in nature. Therefore, this is now a SRO

-only question. There is no justification for the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> time requirement being plausible, but it is better than the previous options. It is satisfactory.

From B. Larson:

ES-401-4, Record of Rejected KAs, Rev 1, does NOT contain an entry for changing the KA for this question. The change from an A2 to a Generic affects the Category Points for Tier 1, Group 2. Without a more detailed review, it appears as if now there is only 1 question for Tier 1, Group 2 which is not acceptable. Note 1 on the ES

-401-2 form states "Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines." This need s to be resolved.

Data for 2014 NRC RO/SRO Exam 30-Jan-14Bank:2009Safety Function 4System Number A11System Title:RCS Overcooling K/AEA2.1Description:Ability to determine and interpret the following as they apply to the (RCS Overcooling): - Facility conditionsand selection of appropriate procedures during abnormal and emergency operationsRO Imp: 2.9SRO Imp: 3.3Lic Level:

SDifficulty:

3Taxonomy: HQuestion:Consider the following: - Unit 2 has tripped due to a rupture in the EH system - SPTAs have been completed - IAO reports steam in the Turbine building basement - "A" S/G pressure is 900 psia and slowly trending down - "B" S/G pressure is 890 psia and slowly trending downThe CRS would diagnose entry into ______________________ and direct ________________________ . A. OP-2203.011, RCS Overcooling AOP; closing the Main Steam Isolation Valves (MSIVs) B. OP-2203.011, RCS Overcooling AOP; actuating Main Steam Isolation Signal (MSIS) C. OP-2202.005, Excess Steam Demand EOP; closing the Main Steam Isolation Valves (MSIVs) D. OP-2202.005, Excess Steam Demand EOP; actuating Main Steam Isolation Signal (MSIS)Answer:A. Correct Notes:A. Correct: OP- 2202.010, Standard Attachment diagnostics will direct entry into RCS Overcooling AOP unless the overcooling is excessive causing a Main Steam Isolation signal, then the Excess Steam demand EOP would be entered.B. Incorrect: Entry conditions are met and actuating MSIS is directed in step 2 if S/G pressure is below the MSIS setpoint, but S/G pressures are above the MSIS setpoint.C. Incorrect: the entry conditions for ESD are not met per the dianositic flow chart (exhibit 8) due to the MSIS setpoint has not been reached (<751 psia) closing the MSIVs is not directedD. Incorrect: the entry conditions for ESD are not met per the dianositic flow chart (exhibit 8) due to the MSIS setpoint has not been reached (<751 psia) actuating MSIS is directed in step 5.

References:

OP-2202.010, Standard Attachments, Rev 022, exhibit 8 page 193 of 204OP-2203.011, RCS Overcooling AOP, Rev 005, Entry Conditions page 1 of 9 and step 3 page 2 of 9AOP-2203.011, RCS Overcooling Tech Guide, Rev 005 Entry Conditions page 3 of 15 and step 3 page 6 of 15Source:Modified NRC BANK QID #0522Rev: 1Rev Date:1/30/2014 10:03:1Search00CA11A20110CFR55:41.7 / 41.10 / 43.5 / 45Historical Comments:NRC Bank QID #0522 used on 2005 NRC ExamRev. 1: NRC editorial comments (mwf 1/30/14)

Tier: 1Group: 2Author:fosterL. Plan:A2LP-RO-ACOOL OBJ 1&3QID #: 85 106Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 30-Jan-14 107Form ES-401-5 Written Exam Question Worksheet

Data for 2014 NRC RO/SRO Exam 30-Jan-14Bank:2010Safety Function 7System Number 012System Title:Reactor Protection System K/A A2.03Description:Ability to (a) predict the impacts of the following malfunctions or operations on the RPS and (b) based onthose predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions oroperations: - Incorrect channel bypassingRO Imp: 3.4SRO Imp: 3.7Lic Level:

SDifficulty:

3Taxonomy: FQuestion:[REFERENCE PROVIDED]Consider the following: - Unit 2 is operating at 100% power - Channel 1 Pressurizer (PZR) pressure transmitter (NR), 2PT-4601-1, has failed LOW - CBOT bypasses ONLY point 5 (PZR pressure - HIGH)Failure of another PZR pressure (NR) transmitter would cause a Reactor trip on ____________. This trip could of beenprevented by applying Tech Spec 3.3.1.1 _______________ to bypass additional points in Channel 1. A. Linear Heat Rate (LPD) and Departure form Nucleate Boiling Ratio (DNBR); Action 2 B. Linear Heat Rate (LPD) and Departure form Nucleate Boiling Ratio (DNBR); Action 3 C. Pressurizer pressure LOW; Action 2 D. Pressurizer pressure LOW; Action 3Answer:A. Correct Notes:With one channel failed low (PZR pressure channel 1) LPD and DNBR will also be in a tripped condition on channel 1.T.S.3.3.1.1 action b requires points 3, 4, and 5 in either tripped or bypass within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Without placing points 3 and 4 inbypass for channel 1 the reactor trip logic is in a 2 out of 4 logic with 1 point already tripped, therefore it would only take 1,more PZR pressure channel to fail low (which would also trip LPD and DNBR for that channel) to cause a reactor trip.

References:

T.S. 3.3.1.1 (PROVIDED to STUDENT]STM 2-63, Reactor Protection System, Rev 11, section 6.2.1, pages 41 and 42STM 2-03, Reactor Coolant System, Rev 22, section 2.2.5.1, page 17STM 2-63, Reactor Protection System, Rev 11, section 4.3.5 page 24STM 2-65-1, Core Protection Calculator System, Rev 17, section 2.2.3 page 6 and section 2.4.6 page 15Source: NEWRev: 1Rev Date:1/30/2014 10:16:5Search012000A20310CFR55:41.5 / 43.5 / 45.3 / 45.Historical Comments:Rev. 1: NRC editorial comments, added STM 2-63 and STM 2-65-1. (mwf 1/30/14)

Tier: 2Group: 1Author:fosterL. Plan: A2LP-RO-RPS OBJ 10QID #: 86 108Form ES-401-5 Written Exam Question Worksheet

Data for 2014 NRC RO/SRO Exam 30-Jan-14Bank:2011Safety Function 2System Number 013System Title:Engineered Safety Features Actuation System (K/A2.2.22Description:Equipment Control - Knowledge of limiting conditions for operations and safety limits.RO Imp: 4.0SRO Imp: 4.7Lic Level:

SDifficulty:

2Taxonomy: FQuestion:Pressurizer Code Safety Tech Spec 3.4.3 LCO is based on preventing the RCS from being pressurized above its Safety Limitof _____________ psia with a loss of Main Turbine Generator and no reactor trip until the first Reactor Protection System(RPS) setpoint is reached and the Steam Dump Bypass Control System (SDBCS) _______ operation. A. 2500; in B. 2750; in C. 2500; not in D. 2750; not inAnswer:D. Correct Notes:D. Correct: During operations, the combine relief capacity of the code safeties is sufficient to limit RCS pressure to within its safety limit of 2750 psia assuming the reactor does not trip before the first RPS reactor trip setpoint is reached and without the SDBCS in operations (T.S. 3.4.3 bases)A. Incorrect: 2500 psia is the code safety setpoint not the safety limit setpoint and the setpoint is based on the assumption the reactor does not trip before the first RPS reactor trip setpoint is reached and SDBCS is not in operation.B. Incorrect: 2750 psia is the safety limit setpoint but assumes the reactor does not trip before the first RPS reactor trip setpoint is reached and SDBCS is not in operation.C. Incorrect: 2500 psia is the code safety setpoint not the safety limit setpoint

References:

T.S 3.4.3, Safety Valves Operating and basesSource: NEWRev: 1Rev Date:1/30/2014 10:18:5Search013000222210CFR55:41.5 / 43.2 / 45.2Historical Comments:Rev. 1: Rev. 1: NRC editorial comments, added explanation to the notes section Tier: 2Group: 1Author:fosterL. Plan:A2LP-RO-RCS OBJ 16QID #: 87 109Form ES-401-5 Written Exam Question Worksheet

Data for 2014 NRC RO/SRO Exam 30-Jan-14Bank:2012Safety Function 5System Number 026System Title:Containment Spray System (CSS)

K/A2.1.20Description:Conduct of Operations - Ability to interpret and execute procedure steps.RO Imp: 4.6SRO Imp: 4.6Lic Level:

SDifficulty:

2Taxonomy: HQuestion:Consider the following: - Unit 2 is operating at 100% power - I&C is performing maintenance in 2C-39, the Engineered Safety Features Auctuation System (ESFAS) actuation cabinet - Annunciator 2K07 D-1 "CSAS ACT" alarms - Containment pressure 14.7 psia - Containment temperature 112°FThe CRS would enter _______________________________ and would direct _____________________ . A. OP-2202.001, Standard Post Trip Actions EOP; securing all Reactor Coolant Pumps (RCPs) B. OP-2202.001, Standard Post Trip Actions EOP; placing the "A" Spray Pump (2P-35A) in Pull to Lock (PTL) C. OP-2203.041, Inadvertant CSAS AOP; secure all Reactor Coolant Pumps (RCPs) D. OP-2203.041, Inadvertant CSAS AOP; place the "A" Spray Pump (2P-35A) in Pull to Lock (PTL)Answer:B. Correct Notes:the Inadvertant Spray Actuation will cause a reactor trip and SPTAs will verify spray is not needed and direct placing the "A"Spray pump in PTL. Pre power uprate, an Inadvertant CSAS would have the operators trip the unit and secure the RCPs. Onlythe 'A' Spray pump inadvertently starts in this scenario. 'B' Spray pump is not running.

References:

OP2202.001, Standard Post Trip Action EOP, Rev 014, step 9.B page 16 of 19Source: NEWRev: 1Rev Date:1/30/2014 10:37:5Search026000212010CFR55:41.10 / 43.5 / 45.12Historical Comments:Rev. 1: Rev. 1: NRC editorial comments. Changed Difficulty from 3 to 2. (mwf 1/30/14)

Tier: 2Group: 1Author:fosterL. Plan:A2LP-RO-ELOCA OBJ 6QID #: 88 110Form ES-401-5 Written Exam Question Worksheet

Data for 2014 NRC RO/SRO Exam 30-Jan-14Bank:2013Safety Function 4System Number 061System Title:Auxiliary / Emergency Feedwater (AFW) Syste K/A A2.04Description:Ability to (a) predict the impacts of the following malfunctions or operations on the AFW System and (b)based on those predictions, use procedures to correct, control, or mitigate the consequences of thosemalfunctions or operations: - pump failure or improper operationRO Imp: 3.4SRO Imp: 3.8Lic Level:

SDifficulty:

3Taxonomy: HQuestion:Consider the following: - Unit 2 has tripped due to a disturbance on the Grid - 500kV and the 161kV lines are de-energized - Both Emergency Diesel Generators (EDGs) are running - Annunciator 2K08 B-3 "2A3 L.O. RELAY TRIP" is in alarm - #1 EDG feeder to 2A3 (2A308) is open - Annunciator 2K05 A-9 "2P7A TURB OVERSPEED TRIP" is in alarm - "A" Steam Generator (S/G) level is 223" [WR] and trending down - "B" Steam Generator (S/G) level is 123" [WR] and trending down - SPTAs are completeThe CRS would enter __________________________ EOP and the first mitigation strategy directed by the chosen procedure to remove Reactor Coolant System (RCS) heat is ___________________________ . A. OP-2202.006, Loss of Feedwater; resetting "A" EFW pump (2P-7A) and feeding S/Gs B. OP-2202.006, Loss of Feedwater; energizing 2A3 with the #1 EDG and feeding S/Gs with the "B" EFW pump (2P-7B) C. OP-2202.009, Functional Recovery; energizing 2A1 with AACDG and feeding the S/Gs with the Auxiliary Feedwater pump (2P-75) D. OP-2202.009, Functional Recovery; implement Once Through CoolingAnswer:A. Correct Notes:A. Correct: The Loss of Feedwater EOP would be diagnosed after completion of SPTAs, not Functional Recovery, because there is only one event in progress. Step 12 in the LOF EOP will direct restoring feedwater and the feedwater sources are listed in the preferred order ("B" EFW, "A" EFW, AFW, MFP, COND, Once Through Cooling) Step 12.B. directs establishing feed with "A" EFW pump using Standard Attachment 54 which will direct re-setting the overspeed trip device and restoring feed at <150 gpm.B. Incorrect: The Loss of Feedwater EOP would be diagnosed after completion of SPTAs, not Functional Recovery, because there is only one event in progress. Energizing 2A3 with the #1 EDG and feeding S/Gs with "B" EFW pump (2P-7B) but the "B" EFW pump is unavailable because 2A3 is locked out.C. Incorrect: The Loss of Feedwater EOP would be diagnosed after completion of SPTAs, not Functional Recovery, because there is only one event in progress. Energizing 2A1 with AACDG and feeding S/GsSource: NEWRev: 1Rev Date:1/30/2014 10:39:5Search061000A20410CFR55:41.5 / 43.5 / 45.3 / 45.

Tier: 2Group: 1Author:fosterL. Plan:A2LP-RO-EFW OBJ 10QID #: 89 111Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 30-Jan-14 with Auxiliary Feedwater pump (2P-75) is directed in both LOF EOP and Functional Recovery, but it is not the preferred pump and Functional would reset the "A" EFW pump first also.D. Incorrect: The Loss of Feedwater EOP would be diagnosed after completion of SPTAs, not Functional Recovery, because there is only one event in progress. S/G levels do not meet Once Through Cooling criteria.

References:

OP-2203.012H, Annunciator Corrective Actions, 2K08 window B-3, Rev 037, page 26 of 50OP-2203.012E, Annunciator Corrective Actions, 2K05 window E-9, Rev 039, page 77 of 86OP-2202.006, Loss of Feedwater EOP, Rev 010, step 12 page 5 of 25OP-2202.010, Standard Attachment, Rev 022, Att. 54 step 6.A page 2 of 3 and step 9 page 3 of 3EOP-2202.006, Loss of Feedwater Tech Guide, Rev 009, step 12 page 19 of 62Historical Comments:Rev. 1: Changed wording of question and added notes based on NRC comments. [mwf 1/30/14]

112Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 31-Jan-14Bank:2013Safety Function 4System Number 061System Title:Auxiliary / Emergency Feedwater (AFW) Syste K/A A2.04Description:Ability to (a) predict the impacts of the following malfunctions or operations on the AFW System and (b)based on those predictions, use procedures to correct, control, or mitigate the consequences of thosemalfunctions or operations: - pump failure or improper operationRO Imp: 3.4SRO Imp: 3.8Lic Level:

SDifficulty:

3Taxonomy: HQuestion:Consider the following: - Unit 2 has tripped due to a disturbance on the Grid - 500kV and the 161kV lines are de-energized - Both Emergency Diesel Generators (EDGs) are running - Annunciator 2K08 B-3 "2A3 L.O. RELAY TRIP" is in alarm - #1 EDG feeder to 2A3 (2A308) is open - Annunciator 2K05 A-9 "2P7A TURB OVERSPEED TRIP" is in alarm - "A" Steam Generator (S/G) level is 223" (WR) and trending down - "B" Steam Generator (S/G) level is 123" (WR) and trending down - "A" S/G pressure is 1020 psia and slowly lowering - "B" S/G pressure is 1010 psia and slowly lowering - RCS pressure is 2100 psia and slowly rising - SPTAs are completeThe CRS would diagnose entry into __________________________ EOP and the first mitigation strategy directed by the chosen procedure to remove Reactor Coolant System (RCS) heat is ___________________________ . A. OP-2202.006, Loss of Feedwater EOP; resetting "A" EFW pump (2P-7A) and feeding S/Gs B. OP-2202.006, Loss of Feedwater EOP; energizing 2A3 with the #1 EDG and feeding S/Gs with the "B" EFW pump (2P-7B) C. OP-2202.005, Excess Steam Demand EOP; resetting "A" EFW pump (2P-7A) and feeding S/Gs D. OP-2202.005, Excess Steam Demand EOP; energizing 2A3 with the #1 EDG and feeding S/Gs with the "B" EFW pump (2P-7B)Answer:A. Correct Notes:A. Correct: The Loss of Feedwater EOP would be diagnosed after completion of SPTAs, not ESD EOP, because there is not an ESD in progress. Step 12 in the LOF EOP will direct restoring feedwater and the feedwater sources are listed in the preferred order ("B" EFW, "A" EFW, AFW, MFP, COND, Once Through Cooling) Step 12.B. directs establishing feed with "A" EFW pump using Standard Attachment 54 which will direct re-setting the overspeed trip device and restoring feed at <150 gpm.B. Incorrect: The Loss of Feedwater EOP would be diagnosed after completion of SPTAs, not ESD,Source: NEWRev: 2Rev Date:1/31/2014 8:22:59Search061000A20410CFR55:41.5 / 43.5 / 45.3 / 45.

Tier: 2Group: 1Author:fosterL. Plan:A2LP-RO-EFW OBJ 10QID #: 89 111Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 31-Jan-14 because there is only one event in progress. Energizing 2A3 with the #1 EDG and feeding S/Gs with "B" EFW pump (2P-7B) but the "B" EFW pump is unavailable because 2A3 is locked out.C. Incorrect: The Loss of Feedwater EOP would be diagnosed after completion of SPTAs, not ESD, because a LOF event in progress.D. Incorrect: Incorrect: The Loss of Feedwater EOP would be diagnosed after completion of SPTAs, not ESD, because a LOF event in progress.

References:

OP-2203.012H, Annunciator Corrective Actions, 2K08 window B-3, Rev 037, page 26 of 50OP-2203.012E, Annunciator Corrective Actions, 2K05 window E-9, Rev 039, page 77 of 86OP-2202.006, Loss of Feedwater EOP, Rev 010, step 12 page 5 of 25OP-2202.010, Standard Attachment, Rev 022, Att. 54 step 6.A page 2 of 3 and step 9 page 3 of 3EOP-2202.006, Loss of Feedwater Tech Guide, Rev 009, step 12 page 19 of 62Historical Comments:Rev. 1: Changed wording of question and added notes based on NRC comments. [mwf 1/30/14]Rev. 2: Changed distractors based on NRC comments via telephone conversation with Kelly. (mwf 1/31/14) 112Form ES-401-5 Written Exam Question Worksheet

Data for 2014 NRC RO/SRO Exam 30-Jan-14Bank:2014Safety Function 6System Number 064System Title:Emergency Diesel Generator (ED/G) System K/A A2.01Description:Ability to (a) predict the impacts of the following malfunctions or operations on the ED/G System and (b)based on those predictions, use procedures to correct, control, or mitigate the consequences of thosemalfunctions or operations: - Failure modes of water, oil, and air valvesRO Imp: 3.1SRO Imp: 3.3Lic Level:

SDifficulty:

2Taxonomy: HQuestion:Consider the following: - Unit 2 is operating at 100% power - A 3 gpm RCS leak has been detected - A Loss of Offsite Power now occurs - SPTAs have been entered - Annunciator 2K09 D-1 "POTENTIAL ENGINE FAILURE" comes into alarm for #2 Emergency Diesel Generator (EDG) - IAO has been dispatched and reports local alarm is "SERVICE WATER PRESSURE LO" - IAO reports Scavenging Air Temperature is 160°F and rising - ATC reports both lights above the #2 EDG Service Water supply, 2CV-1504-2, are outAt the end of SPTAs, 2A4 Vital bus __________ be energized and the CRS would enter ______________________________

. A. would; OP-2202.003, Loss of Coolant Accident EOP B. would not; OP-2202.003, Loss of Coolant Accident EOP C. would; OP-2203.016, Excess RCS Leakage AOP in conjunction with OP-2202.007, Loss of Offsite Power EOP D. would not; OP-2203.016, Excess RCS Leakage AOP in conjunction with OP-2202.007, Loss of Offsite Power EOPAnswer:B. Correct Notes:With both lights above the #2 EDG Service Water supply, 2CV-1504-2, out coupled with Scavenging Air Temperature is160°F and rising and low Service Water pressure, indicates the EDG cooling water supply valve has failed to fully open (2CV-1504-2 is a MOV and fails AS-IS). #2 EDG would be secured during SPTAs due to indications of no service water available.The Excess RCS Leakage AOP entry conditions are meet prior to the plant trip but it is not design to handle a Loss of OffsitePower. Per the EOP/AOP User guide, if in the Excess RCS Leakage AOP with a LOOP, then go to the LOCA EOP.

References:

OP-2202.001, Standard Post Trip Actions EOP, Rev 014, step 4.G page 5 of 19EOP-2202.001, Standard Post Trip Actions Tech Guide, Rev 012, step 4.G page 11 of 42OP-1015.021, ANO-2 EOP/AOP User Guide, Rev 011, section 5.1.2, page 14 of 73Source: NEWRev: 1Rev Date:1/30/2014 10:41:0Search064000A20110CFR55:41.5 / 43.5 / 45.3 / 45.

Tier: 2Group: 1Author:fosterL. Plan:A2LP-RO-ESPTA OBJ 2&11QID #: 90 113Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 30-Jan-14STM 2-42, Service Water & Auxiliary Cooling Water Systems, Rev 36, section 3.5.8 page 35Historical Comments:Rev. 1: Rev. 1: NRC editorial comments. Deleted information from notes section. Aded STM 2-42 to references. (mwf1/30/14)114Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 31-Jan-14Bank:2014Safety Function 6System Number 064System Title:Emergency Diesel Generator (ED/G) System K/A A2.01Description:Ability to (a) predict the impacts of the following malfunctions or operations on the ED/G System and (b)based on those predictions, use procedures to correct, control, or mitigate the consequences of thosemalfunctions or operations: - Failure modes of water, oil, and air valvesRO Imp: 3.1SRO Imp: 3.3Lic Level:

SDifficulty:

2Taxonomy: HQuestion:Consider the following: - Unit 2 is operating at 100% power - A 3 gpm RCS leak has been detected - A Loss of Offsite Power now occurs - SPTAs have been entered - Annunciator 2K09 D-1 "POTENTIAL ENGINE FAILURE" comes into alarm for #2 Emergency Diesel Generator (EDG) - IAO has been dispatched and reports local alarm is "SERVICE WATER PRESSURE LO" - IAO reports Scavenging Air Temperature is 160°F and rising - ATC reports both lights above the #2 EDG Service Water supply, 2CV-1504-2, are outThe CRS would direct securing #2 EDG due to the Service Water supply _______________. The CRS would diagnose entryinto __________________. A. MOV failing AS-IS; OP-2202.003, Loss of Coolant Accident EOP B. AOV failing CLOSED; OP-2202.003, Loss of Coolant Accident EOP C. MOV failing AS-IS; OP-2203.016, Excess RCS Leakage AOP in conjunction with OP-2202.007, Loss of Offsite Power EOP D. AOV failing CLOSED; OP-2203.016, Excess RCS Leakage AOP in conjunction with OP-2202.007, Loss of Offsite Power EOPAnswer:A. Correct Notes:With both lights above the #2 EDG Service Water supply, 2CV-1504-2, out coupled with Scavenging Air Temperature is160°F and rising and low Service Water pressure, indicates the EDG cooling water supply valve has failed to fully open (2CV-1504-2 is a MOV and fails AS-IS). #2 EDG would be secured during SPTAs due to indications of no service water available.The Excess RCS Leakage AOP entry conditions are meet prior to the plant trip but it is not design to handle a Loss of OffsitePower. Per the EOP/AOP User guide, if in the Excess RCS Leakage AOP with a LOOP, then go to the LOCA EOP.

References:

OP-2202.001, Standard Post Trip Actions EOP, Rev 014, step 4.G page 5 of 19EOP-2202.001, Standard Post Trip Actions Tech Guide, Rev 012, step 4.G page 11 of 42OP-1015.021, ANO-2 EOP/AOP User Guide, Rev 011, section 5.1.2, page 14 of 73Source: NEWRev: 2Rev Date:1/31/2014 8:12:56Search064000A20110CFR55:41.5 / 43.5 / 45.3 / 45.

Tier: 2Group: 1Author:fosterL. Plan:A2LP-RO-ESPTA OBJ 2&11QID #: 90 113Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 31-Jan-14STM 2-42, Service Water & Auxiliary Cooling Water Systems, Rev 36, section 3.5.8 page 35Historical Comments:Rev. 1: Rev. 1: NRC editorial comments. Deleted information from notes section. Aded STM 2-42 to references. (mwf1/30/14)Rev. 2: Incorporated NRC comments based on phone conversation. Changed first half of question and changed distractors.(mwf 1/31/14) 114Form ES-401-5 Written Exam Question Worksheet

Data for 2014 NRC RO/SRO Exam 30-Jan-14Bank:2015Safety Function 1System Number 001System Title:Control Rod Drive System K/A A2.18Description:Ability to (a) predict the impacts of the following malfunctions or operations on the CRDS and (b) based onthose predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions oroperations: - Incorrect rod stepping sequenceRO Imp: 3.2SRO Imp: 3.8Lic Level:

SDifficulty:

4Taxonomy: HQuestion:[REFERENCE PROVIDED]Consider the following: - Unit 2 is in Mode 2 with a Reactor startup in progress - "A" and "B" Shutdown Banks are fully withdrawn - CEA Reg Groups are being withdrawn in Manual Sequential modeWhile the ATC is withdrawing CEAs by holding the Shim switch in "WITHDRAW" position he notes: - Reg Groups 1 and 2 have reached the fully withdrawn position - Reg Group 3 is at 102" and withdrawing - Reg Group 4 is at 10" and withdrawing - Reg Group 5 is at 10" and withdrawing - Annunciator 2K10 E-1 "REG GROUP OUT OF SEQUENCE" comes into alarm - Reactor is subcriticalControl Element Assembly (CEA) motion would be stopped _____________ and basedon OP-2203.012J, 2K10 E-1 ACA, the CRS would direct inserting Regulating Group 5 CEAsin manual __________________ mode to clear the alarm. A. automatically; sequential B. manually; sequential C. automatically; group D. manually; groupAnswer:C. Correct Notes:C. Correct: CEAs are monitored for proper overlap during rod withdrawal. If proper overlap is not maintained, the alarm [Reg Group Out of Sequence] would alert the operations staff and CEA motion is automatically stopped [system interlock when withdrawing CEAs in Manual Sequential Mode] The CRS would use ACA guidance to recommence CEA motion in either manual group or manual individual mode.A. Incorrect: CEA motion is stopped automatically but manual sequential is only used for CEA withdrawalSource: NEWRev: 1Rev Date:1/30/2014 1:29:23Search001000A21810CFR55: 43.6 Tier: 2Group: 2Author:fosterL. Plan:A2LP-RO-CEDM OBJ 14&15QID #: 91 115Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 30-Jan-14 not insertion.B. Incorrect: CEA motion is stopped automatically not manually. Manual sequential mode is only used for CEA withdrawal not insertion.D. Incorrect: CEA motion is stopped automatically not manually.

References:

OP-2203.012J, Annunciator Corrective Actions, 2K10 window E-1 Rev 039, pages 9 and 10 of 84 [PROVIDED toSTUDENT]STM 2-02, Control Element Drive Mechanism Control System, Rev 21, section 4.2.1.4 page 27Historical Comments:Rev. 1: Updated based on NRC comments. Changed 10CFR55 reference to 43.6. (mwf 1/30/14) 116Form ES-401-5 Written Exam Question Worksheet Question 9 1_R1 (NRC recommendations)

Revised Question:

Consider the following:

Unit 2 is in Mode 2 with a Reactor startup in progress "A" and "B" Shutdown Banks are fully withdrawn CEA Reg Groups are being withdrawn in Manual Sequential mode While the ATC is withdrawing CEAs by holding the Shim switch in "WITHDRAW" position he notes: Reg Groups 1 and 2 have reached the fully withdrawn position Reg Group 3 is at 102" and withdrawing Reg Group 4 is at 10" and withdrawing Reg Group 5 is at 10" and withdrawing Annunciator 2K10 E

-1 "REG GROUP OUT OF SEQUENCE" comes into alarm Reactor is subcritical CEA motion would be stopped automatically and the CRS would use procedure ___________ which initially directs the operators to ___________.

A. OP-2203.003, CEA Malfunctions AOP; insert Reg Group 5 CEA's in Manual Group to clear the alarm B. OP-2203.003, CEA Malfunctions AOP; ensure rod motion has stopped and notify I&C to perform troubleshooting on CEA Reg Group 5 C. OP-2105.009, CEDM Control System Operation; insert Reg Group 5 CEA's in Manual Group to clear the alarm D. OP-2105.009, CEDM Control System Operation; ensure rod motion has stopped and notify I&C to perform troubleshooting on CEA Reg Group 5 Answer: C Comments: Previous comment was that the question did not ask an SRO level of knowledge, so the proposed revision above changes the stem and answers to make the applicant choose the procedure that would be used to make the question SRO level. Per alarm response procedure OP-2203.012J, if the alarm is in due to improper reg group overlap, the direction is to reposition the group to clear the alarm using OP

-2105.009, making answer C correct. The use of the CEA Malfunction AOP as a response to this event is plausible because of the groups getting out of sequence. However, this is not listed as an entry condition to the AOP, therefore distractor A and B are plausible but incorrect. Notifying I&C to perform troubleshooting is listed as a step in the AOP, making distractors B and D plausible but incorrect. Troubleshooting would likely be performed due to the sequence problem, but it is not listed in the procedure, and would be performed after the operators insert Reg Group 5 to clear the alarm.

Data for 2014 NRC RO/SRO Exam 30-Jan-14Bank:2016Safety Function 7System Number 016System Title:Non-Nuclear Instrumentation System (NNIS)

K/A2.1.7Description:Conduct of Operations - Ability to evaluate plant performance and make operational judgments based onoperating characteristics, reactor behavior, and instrument interpretation.RO Imp: 4.4SRO Imp: 4.7Lic Level:

SDifficulty:

2Taxonomy: HQuestion:Consider the following: - Unit-2 is operating at 100% power - Annunciator 2K12 G-5 "VCT 2T4 LEVEL LO LO" comes into alarm - 2LIS-4857, VCT level on 2C09 reads 68% - 2LR-4857, VCT chart recorder on 2C09 reads 68% and steady - It has been determined 2LT-4861 has failed low - RCS Tave 578°F and trending down - Pressurizer level is 59% and trending down slowlyThe Control Room staff would determine there is a ______________________ event in progress and the CRS would initiateactions referencing ____________________________________ . A. dilution; EN-OP-115, Conduct of Operations B. boration; EN-OP-115, Conduct of Operations C. dilution; EN-OP-111, Operational Decision Making Issue (ODMI) Process D. boration; EN-OP-111, Operational Decision Making Issue (ODMI) ProcessAnswer:B. Correct Notes:Due to the false low VCT level signal, CV-4873-1, VCT outlet, would automatically close and 2CV-4950-2, CCP suctionsource from the RWT would automatically open aligning an Emergency Boration flowpath to the RCS. Once aligned, reactortemperature will trend down, reactor power will maintain somewhat constant due to steam demand not changing (MTG iscontrolled in manual). The CRS should recognize this and secure CCPs (or take manual control of the VCT and RWT valvesand realign CCP suction to the VCT) referencing EN-OP-115, Conduct of Operations, Section 5.4, Manual Control ofAutomatic Systems.A. Incorrect. Based on the above note, there is a boration in progress, not a dilution.B. Correct. Based on the above note, there is a boration in progress and the CRS would use the guidance in EN-OP-115 tomanual control of the failed automatic system and restore the proper suction source to the Charging Pumps.C. Incorrect. Based on the above note, there is a boration in progress, not a dilution.D. Incorrect. There is a boration in progress, but EN-OP-111 does not contain the guidance to take manual control of anautomatic system that is malfunctioning. Plausible because the operators will use the guidance in EN-OP-111 to create anODMI for this malfunction, but that will be performed at a later time.Source: NEWRev: 1Rev Date:1/30/2014 1:27:33Search016000210710CFR55:41.5 / 43.5 / 45.12 / 45 Tier: 2Group: 2Author:fosterL. Plan:A2LP-RO-CVCS OBJ 4&8QID #: 92 117Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 30-Jan-14

References:

OP-2203.012L, Annunciator Corrective Actions, 2K12 window G-5, Rev 044, page 58 of 116STM 2-04, Chemical and Volume Control system, Rev 29, section 2.1.21.1 page 19 and simplified drawing page 63EN-OP-115, Conduct of Operations, Rev. 014, Section 5.4, page 23 of 89Historical Comments:Rev. 1: Rev. 1: NRC editorial comments. Changed Difficulty from 3 to 2. Changed distractors based on NRC comments. (mwf1/30/14)118Form ES-401-5 Written Exam Question Worksheet

Data for 2014 NRC RO/SRO Exam 30-Jan-14Bank:2017Safety Function 8System Number 034System Title:Fuel Handling Equipment System (FHES)

K/A K4.01Description:Knowledge of Fuel Handling System design feature(s) and/or interlock(s) which provide for the following: -Fuel protection from binding and droppingRO Imp: 2.6SRO Imp: 3.4Lic Level:

SDifficulty:

2Taxonomy: FQuestion:Tech Spec 3.9.6, Refueling Machine Operability requires Refueling Machine (Main Bridge) to have a minimum liftingcapacity of ______________ and have overload cut offs.Per Tech Spec 3.9.6, the bases for these requirements is to ensure that the machine has sufficient load capacity to lift a fuelassembly, and the overloads ensure that _________________ is(are) protected from excessive forces. A. 2000; core internals B. 3750; core internals C. 2000; refueling machine D. 3750; refueling machineAnswer:B. Correct Notes:B. Correct: T.S. 3.9.6 limit and bases require the Refueling Machine to have a minimum lifting capacity of 3750 pounds andthe overloads protect the core internals from excessive lifting forces.A. Incorrect: 2000 pounds is T.S. 3.9.7, Crane Travel-Spent Fuel Pool Building, limit for loads carried over irradiated fuel in the SFPC. Incorrect: 2000 pounds is T.S. 3.9.7, Crane Travel-Spent Fuel Pool Building, limit for loads carried over irradiated fuel in the SFPD. Incorrect: 3750 pounds is the correct max weight per T.S. 3.9.6 but the limit is not based on protecting the refueling machine. T.S. bases states max limit is designed to protect the core internals.

References:

T.S 3.9.6, Refueling Machine and basesSTM 2-51-1, Main Refueling Bridge & Reactor Bldg. Fuel Handling Equip., Rev 11, section 1.1 pages 1 and 2, section 2.2.6pages 18 and 19Source: NEWRev: 1Rev Date:1/30/2014 12:26:4Search034000K40110CFR55: 43.2Historical Comments:Rev. 1: Replaced with SRO only question based on NRC comments. (mwf 1/30/14)

Tier: 2Group: 2Author:fosterL. Plan:A2LP-SRO-TS OBJ 5QID #: 93 119Form ES-401-5 Written Exam Question Worksheet Question 93_R1 (NRC recommendations)

Revised Question:

Technical Specification (TS) 3.9.6, Refueling Machine Operability requires the Refueling Machine (Main Bridge) to have a MINIMUM lifting capacity of __________

pounds and have overload cut offs.

Per TS 3.9.6, the bases for these requirements is to ensure that the machine has sufficient load capacity to lift a fuel assembly, and the overloads ensure that the __________ is (are) protected from excessive forces.

A. 2000; core internals B. 3750; core internals C. 2000; refueling machine

D. 3750; refueling machine Comments: Capitalized minimum for emphasis. Added units in the first sentence. Added minor editorial changes for clarity.

Comments - 2/18/2014 Q93 - file contains 2 Rev 0's, both with the same Rev Date: (10/22/2013). The question is clearly different on each rev. The one worksheet with Rev 0 written on top of the worksheet was the version that was submitted with the Draft Exam. That would make one of the Rev 0's actually Rev 1, and then Rev 1 would be Rev 2. In addition, we have comments we sent on Rev 1 (which is probably actually Rev 2).

Data for 2014 NRC RO/SRO Exam 30-Jan-14Bank:2018Safety FunctionSystem NumberGENERICSystem Title:Generic K/A2.1.39Description:Conduct of Operations - Knowledge of conservative decision making practices.RO Imp: 3.6SRO Imp: 4.3Lic Level:

SDifficulty:

3Taxonomy: HQuestion:In accordance with EN-OP-115, Conduct of Operation, which of the following would be considered aNON-conservative decision making practice? A. Reducing reactor power after a loss of the plant computer B. Re-energizing a Vital switchgear during an EOP after a potential fire on the bus C. An implementation plan being changed due to degrading trends D. Validating available information prior to taking any time critical actionsAnswer:B. Correct Notes:Based on EN-OP-115, Conduct of Operation, section 5.3 which describes the thought process utilized for making conservativedecisions. Re-energizing a deranged electrical bus, even during implementation of an EOP, would not be a prudent actionwithout having the bus inspected first.

References:

EN-OP-115, Conduct of Operation, Rev 014, section 5.3 page 22 of 89Source: NEWRev: 1Rev Date:1/30/2014 11:17:5Search194001213910CFR55:41.10 / 43.5 / 45.12Historical Comments:Rev. 1: corrected editorial NRC comments. This is an SRO topic that is taught in ASLP-SRO-OC. (mwf 1/30/14)

Tier: 3Group: 1Author:fosterL. Plan:ASLP-SRO-OC OBJ 3QID #: 94 120Form ES-401-5 Written Exam Question Worksheet Question 9 4_R1 (NRC recommendations)

Revised Question:

In accordance with EN

-OP-115, Conduct of Operation, which of the following would be considered a NON

-conservative decision making practice?

A. Reducing Reactor power after a loss of the plant computer B. Validating available information prior to taking any time critical actions C. Re-energizing a vital switchgear during an EOP after a potential fire on the bus D. Consulting an off-shift system engineer before taking action in response to an unexpected system response Comments: Need to edit Rev 1 distractor C (now distractor D) to make it more plausible.

(Above is a possible replacement distractor)

Re-order distractors from shortest to longest, make two minor edits.

Data for 2014 NRC RO/SRO Exam 30-Jan-14Bank:2019Safety FunctionSystem NumberGENERICSystem Title:Generic K/A2.1.1Description:Conduct of Operations - Knowledge of conduct of operations requirements.RO Imp: 3.8SRO Imp: 4.2Lic Level:

SDifficulty:

3Taxonomy: HQuestion:Consider the following: - Unit 2 is operating at 100% power - A Loss of Stator Water Cooling has occurred - Main Turbine Generator (MTG) runback is in progressThe CRS would perform the Reactivity Brief as directed by _____________________________ and the brief__________________________ commencement of boration or CEA insertion. A. COPD-030, ANO Reactivity Management Program; must be performed prior to B. COPD-030, ANO Reactivity Management Program; can be performed after C. COPD-032, Transient Conduct of Operations; must be performed prior to D. COPD-032, Transient Conduct of Operations; can be performed afterAnswer:D. Correct Notes:COPD-032 contains guidance for briefs requirements during transients [section 20.0, step 20.3 page 28 of 41]. COPD-030,ANO Reactivity Management Program, Section 5.0, Step 5.5 statest that the required controls for planned reactivityevolutions are not applicable during AOP conditions.

References:

COPD-032, Transient Conduct of Operations, Rev 003 section 6.0 page 10 of 41 and 20.0 page 28 of 41COPD-030, ANO Reactivity Management Program, Rev. 006, Section 5.0, Step 5.5Source:NRC Bank QID #1711Rev: 1Rev Date:1/30/2014 11:27:5Search194001210110CFR55:41.10 / 45.13Historical Comments:NRC Bank QID #1711 not used on a NRC ExamRev. 1: Added COPD-030 as a reference. Added clarifying info in the notes. Clarified stem and distractors to ensure only oneanswer correct per NRC comments. (mwf 1/30/14)

Tier: 3Group: 1Author:fosterL. Plan:A2LP-RO-ARCSA OBJ 5QID #: 95 121Form ES-401-5 Written Exam Question Worksheet

Data for 2014 NRC RO/SRO Exam 30-Jan-14Bank:2020Safety FunctionSystem NumberGENERICSystem Title:Generic K/A2.2.14Description:Equipment Control - Knowledge of the process for controlling equipment configuration or status.RO Imp: 3.9SRO Imp: 4.3Lic Level:

SDifficulty:

3Taxonomy: FQuestion:During an off-normal event (AOP or EOP entered), plant configuration control ____________ required to be maintained byuse of the normal eSOMS program. A review of the AOP or EOP is required to be performed ____________ exiting the AOPor EOP to ensure correct plant configuration. A. is; prior to B. is; after C. is not; prior to D. is not, afterAnswer:C. Correct Notes:A. Incorrect. OP-1015.021 step 9.1.6 on page 47 of 73 states that it is not required to maintain configuration with the normalconfiguration control means.B. Incorrect. OP-1015.021 step 9.1.6 on page 47 of 73 states that it is not required to maintain configuration with the normalconfiguration control means.C. Correct. OP-1015.021 step 9.1.6 on page 47 of 73 states that it is not required to maintain configuration with the normalconfiguration control means. COPD-032, step 12.1 on page 22 of 41 states that prior to exiting, configuration control will bere-established.D. Incorrect. OP-1015.021 step 9.1.6 on page 47 of 73 states that it is not required to maintain configuration with the normalconfiguration control means. COPD-032, step 12.1 on page 22 of 41 states that prior to exiting, configuration control will bere-established.

References:

OP-1015.021, ANO-2 EOP/AOP User Guide, Rev. 011, Step 9.1.6, page 47 of 73COPD-032, Transient Conduct of Operations, Rev. 003, Step 12.1, page 22 of 41Source: NEWRev: 1Rev Date:1/30/2014 11:38:1Search194001221410CFR55:41.10 / 43.3 / 45.13Historical Comments:ANO Bank QID #ANO-OPS2-11280Rev. 1: reworded stem and distractors to make all plausible.

Tier: 3Group: 1Author:fosterL. Plan:A2LP-RO-ESPTA OBJ 3QID #: 96 122Form ES-401-5 Written Exam Question Worksheet NRC recommendation to Q96_R1 Question: 96 During an off

-normal event involving the use of AOP(s) and/or EOP(s), plant configuration control is not required to be maintained by use of the normal eSOMS program. However, according to OP

-1015.021, ANO

-2 AOP/EOP User Guide, a review of the AOP(s) and/or EOP(s) is required to be performed ____________ exiting the AOP(s) and/or EOP(s) to ensure correct plant configuration.

A. prior to B. immediately after C. within one shift of D. within 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> of Answer: A. Correct

Data for 2014 NRC RO/SRO Exam 30-Jan-14Bank:2021Safety FunctionSystem NumberGENERICSystem Title:Generic K/A2.2.17Description:Equipment Control - Knowledge of the process for managing maintenance activities during power operations,such as risk assessments, work prioritization, and coordination with the transmission system operator.RO Imp: 2.6SRO Imp: 3.8Lic Level:

SDifficulty:

3Taxonomy: HQuestion:[REFERENCE PROVIDED]Consider the following: - Unit 2 is operating at 100% power - 2P-35A, "A" Spray pump, is OOS for maintenance - Annunciator 2K04 K-2 "ESF PROCESS SYSTEM INOP" is in alarm - The lights are OUT for 2CV-1510-2, Service Water to Containment Fan Coolers 2VSF-1C/D - IAO reports 2B63-E5, 480 VAC vital breaker for 2CV-1510-2, Service Water inlet to Containment Coolers is tripped - The EOOS computer program has been taken out of service by the Safety Analysis GroupWhich of the following Risk Categories would apply to these conditions? A. Green; Minimal Risk B. Yellow; Acceptable Risk C. Orange; High Risk D. Red; Unacceptably High RiskAnswer:C. Correct Notes:COPD-024 Attachment 2 Table 7 on page 33 of 101 designates this configuration (1 containment spray train and onecontainment cooling train) as a ORANGE risk level.

References:

COPD 24, Risk Assessment Guidelines, Rev. 048, Attachment 2, Table 7 page 33 of 101COPD 24, Risk Assessment Guidelines, Rev. 048, Section 9.2, page 19 of 101OP-2203.012D, Annunciator Corrective Actions, 2K04 window K-2, Rev 036, page 23 of 94Provide COPD 24 Attachment 2 [PROVIDED to STUDENT]Source: NEWRev: 1Rev Date:1/30/2014 1:30:07Search194001221710CFR55:41.7 / 41.10 / 43.5 / 45Historical Comments:Rev. 1: clarified notes and references based on NRC comments. (mwf 1/30/14)

Tier: 3Group: 1Author:fosterL. Plan:ASLP-RO-MNTC OBJ 13QID #: 97 123Form ES-401-5 Written Exam Question Worksheet

Data for 2014 NRC RO/SRO Exam 30-Jan-14Bank:2022Safety FunctionSystem NumberGENERICSystem Title:Generic K/A2.3.14Description:Radiological Controls - Knowledge of radiation or contamination hazards that may arise during normal,abnormal, or emergency conditions or activities.RO Imp: 3.4SRO Imp: 3.8Lic Level:

SDifficulty:

2Taxonomy: FQuestion:The following plant conditions exist: - A Site Area Emergency has been declared - You are the Shift Manager and still have Emergency Direction and Control - The TSC and EOF is still in the activation process - You have waived Federal 10CFR20 TEDE dose limit for a plant worker and directed him to perform an emergency repair to a valuable piece of plant equipmentWhich of the following is the maximum emergency TEDE dose you can authorize the plant worker to receive in accordancewith OP-1903.033, Protective Action Guidelines for Rescue/Repair and Damage Control Teams, if he is directed to performthis emergency repair? A. 5 Rem B. 10 Rem C. 25 Rem D. 50 RemAnswer:B. Correct Notes:Per OP-1903.033, Protective Action Guidelines for Rescue/Repair and Damage Control Teams, the limit to perform anemergency repair to a valuable piece of plant equipment is 10 Rem.

References:

OP-1903.033, Protective Action Guidelines for Rescue/Repair and Damage Control Teams, Rev. 023, section 6.0, page 5 of 15Source: NEWRev: 1Rev Date:1/30/2014 12:42:2Search194001231410CFR55: 43.4Historical Comments:Rev. 1: replaced question due to overlap with A8 administrative JPM. (mwf 1/30/14)

Tier: 3Group: 1Author:fosterL. Plan:ASLP-RO-EPLAN OBJ 4QID #: 98 124Form ES-401-5 Written Exam Question Worksheet NRC recommendation for Q98_R1

Question: 98

________ radiation from Kr

-85 gas is a significant hazard in an accident involving spent fuel.

A. Alpha B. Beta C. Gamma D. Neutron Answer: B. Correct

Reference:

Procedure 1905.001, Emergency Radiological Controls, Rev 19, Page 5, Step 6.1.6 KA - Radiological Controls

- Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.

Data for 2014 NRC RO/SRO Exam 30-Jan-14Bank:2023Safety FunctionSystem NumberGENERICSystem Title:Generic K/A2.4.14Description:Emergency Procedures/Plan - Knowledge of general guidelines for EOP usage.RO Imp: 3.8SRO Imp: 4.5Lic Level:

SDifficulty:

2Taxonomy: HQuestion:Consider the following: - An event has occurred on Unit 2 - OP-2202.009, Functional Recovery EOP, entry section has been completed with the following status: - Reactivity - SATISFIED - Maintenance of Vital Aux (DC) - SATISFIED - Maintenance of Vital Aux (AC) - SATISFIED - RCS Inventory Control - CHALLENGED - RCS Pressure Control - CHALLENGED - RCS/Core Heat Removal - SATISFIED - Containment Isolation - JEOPARDIZED - Containment Temp/Press Control - JEOPARDIZEDWhich list is the correct order the CRS would address each safety function? A. Reactivity, Maintenance of Vital Aux (DC), Maintenance of Vital Aux (AC), RCS/Core Heat Removal, RCS Inventory Control, RCS Pressure Control, Containment Isolation, Containment Temp/Press Control B. RCS Inventory Control, RCS Pressure Control, Containment Isolation, Containment Temp/Press Control, Reactivity, Maintenance of Vital Aux (DC), Maintenance of Vital Aux (AC), RCS/Core Heat Removal C. Reactivity, Maintenance of Vital Aux (DC), Maintenance of Vital Aux (AC), RCS/Core Heat Removal, Containment Isolation, Containment Temp/Press Control, RCS Inventory Control, RCS Pressure Control D. Containment Isolation, Containment Temp/Press Control, RCS Inventory Control, RCS Pressure Control, Reactivity, Maintenance of Vital Aux (DC), Maintenance of Vital Aux (AC), RCS/Core Heat RemovalAnswer:D. Correct Notes:After completing the entry section, the Functional Recovery procedure will prioritize safety functions in an order of mostendangered (jeopardized) With the above conditions the student should determine: Reactivity is SAT; Maintenance of VitalAux (DC) SAT; Maintenance of Vital Aux (AC) SAT; RCS Inventory Control CHALLENGED; RCS Pressure ControlCHALLENGED; RCS/Core Heat Removal SAT; Containment Isolation JEPORIDIZED; Containment Temp/Press ControlSource: NEWRev: 1Rev Date:1/30/2014 12:31:4Search194001241410CFR55:41.10 / 45.13 Tier: 3Group: 1Author:fosterL. Plan:A2LP-RO-EFRP OBJ 3QID #: 99 125Form ES-401-5 Written Exam Question Worksheet Data for 2014 NRC RO/SRO Exam 30-Jan-14JEPORIDIZED.

References:

OP-2202.009, Functional Recovery, Rev 015, entry section step 13.C., page 15 of 43OP-2202.009, Functional Recovery, Rev 015, Success Path Tracking Page, page 28 of 28EOP-2202.009, Functional Recovery Tech Guide, Rev 014, step 13.C., page 20 of 372OP-1015.021, ANO-2 EOP/AOP User Guide, Rev 011, section 5.7, pages 20 and 21 of 73OP-1015.021, ANO-2 EOP/AOP User Guide, Rev 011, Attachment A, page 50 of 73Historical Comments:Rev. 1: Rejected K/A 2.4.23 and replaced with K/A 2.4.14. (mwf 1/30/14) 126Form ES-401-5 Written Exam Question Worksheet

Response Comments for Draft Exam 2 February 17, 2014 comments SRO Exam 1. Q77 - question is no longer a MODIFIED, it is NEW. Update and submit Rev 2 with explanation added for Rev 2. Changed to NEW question and changed to Rev 2.

2. Q78 - there are two copies of Rev 1, and they have different "Notes" and different Rev Dates. Change the Rev 1 dated 1/30/2014 to Rev 2 and add a description of Rev 2 to the Historical Comments. Changed the Rev. 1 dated 1/30/14 to Rev 2 and updated historical comments.

3. Q81 - For "B" change "circuit" to "circuits." This was identified but missed.

Changed "circuits" to "circuit" and changed to Rev 3.

4. Q84 - need to verify the Revision numbers. There are two Rev 1's with different answers. (Pages 2 and 3 of 10). How is it possible to have 2 different sets of answers yet the Rev Date blocks are identical?

Deleted one of the Rev 1's.

5. Q85 - There are two Rev 1's with different Rev Dates. Is Rev 1 dated 1/30/2014 actually Rev 2? If so, update and add comment in the Historical Comments. Updated to Rev 2 and added historical comments.

6. Q93 - we sent Recommendations to Rev 1: no Rev 2 was returned.

Deleted Rev. 1 dated 10/22/13. Created new Rev. 2 incorporating NRC comments.

Notes: 1. On several questions, the second page of the latest revision of worksheet is out of place - it's been the last page of the file. Caused by the way the pdf documents were merged together. Are in the correct order in our book and will be in next electronic transmission.

2. Have your team start looking at the RO questions, starting with Q1, and check all files for proper revision numbers (so we can track the pedigree of each question) and check that the worksheet pages are in the proper order (first page or two of the file should be the worksheet for the latest rev of the question, and then previous rev(s) worksheets.

RO questions 1-50 are completed and are starting on 50-75.

3. Files should be in chronological order - for example: If the K/A was changed for Rev 0 question, then file should be Rev 1 (new question), Rev 1 reference material, then Rev 0 question, then Rev 0 reference material. As we are completing step 2 above, we are copying the reference material and putting it with each rev in chronological order.

4. Make sure we accurately identify all questions that were used on last 2 NRC exams, and all questions with "Reference Provided." We have went back and identified all questions that were on the past 2 NRC exams and all questions with Reference Provided.

February 18, 2014

SRO Exam (continued)

1. Q88 - file is missing Rev 0 worksheet. We have the Rev 0 worksheet ready to scan when next electronic document is sent.

2. Q89 - file has 2 Rev 1's, dated 1/22 and 1/30. At first glance, I don't see any differences between the two worksheets. Either ensure they are the same and delete one of them (and then change Rev 3 to Rev 2) or find out if they are different, then change one of them to Rev 2 (with a comment as to what was changed in Historical Comments). Also, the second page of the Rev 3 worksheet was the last page of the file. Deleted Rev 1 dated 1/22. Will correct order of scanned documents when next electronic doc is sent.

3. Q90 - second page of Rev 2 worksheet was the last page of the file. Will correct the order of scanned docs when next electronic doc is sent.

4. Q91 - confirm NO reference provided. File has 2 Rev 1's dated 1/22 and 1/30. The only difference I see is that the one dated 1/30 has a Rev 1 entry in the Historical Comments section. Either ensure they are the same and delete one of them (leave Rev 2 as Rev 2) or find out if they are different, then change one of them to Rev 2 (with a comment as to what was changed in Historical Comments) and then change Rev 2 to Rev 3. Also, the second page of the Rev 2 worksheet was the last page of the file. Deleted Rev 1 dated 1/22. 5. Q92 - second page of Rev 1 worksheet was the last page of the file. Will correct order of scanned docs when next electronic doc is sent.

6. Q93 - [file contains 2 Rev 0's, both with the same Rev Date: (10/22/2013). The question is clearly different on each rev. The one worksheet with Rev 0 written on top of the worksheet was the version that was submitted with the Draft Exam. That would make one of the Rev 0's actually Rev 1, and then Rev 1 would be Rev 2. In addition, we have comments we sent on Rev 1 (which is probably actually Rev 2).] - comments sent to Clay via email. Deleted Rev. 1 dated 10/22/13. Created new Rev. 2 incorporating NRC comments. 7. Q94 - (Rev 2 is a new question based on a new K/A. Was this K/A discussed with NRC examiner? We had sent comments on Rev 1 to make the question acceptable - why was the K/A changed? Also, the notes for Rev 2 in the Historical Comments section doesn't identify that a new K/A was selected. Was this new K/A added to the written exam outline and included on the ES-401-4, Record of Rejected K/A's?) This question is Q95, not Q94. We need Rev 2 of Q94. Also, there are 2 Rev 1's in the file, dated 1/22 and 1/30. The one dated 1/30 has a note in Historical Comments and the other doesn't.

Questions 94 and 95 corrected in Exam bank. Kept Rev 1 dated 1/30.

8. Q96 - file has 2 Rev 2's, appear to be the same. File has 2 Rev 1's, dated 1/30 and 1/22, and questions are clearly different. Need to resolve revision status with remarks updated accordingly in the Historical Comments section. Deleted Rev 1 dated 1/22. This question was never submitted.

9. Q98 - file is missing Rev 1 and Rev 0. Will include all rev's when next electronic doc is sent. 10. Q99 - page 2 of worksheet was the last page in the file. Correct order in book, will be in correct order when next electronic doc is sent.

11. Q100 - page 2 of worksheet was the last page in the file. Also, file is missing Rev 1 worksheet. Will include rev 1 in next electronic doc sent. Correct order in book, will be correct order when next electronic doc is sent.

12. Q83- Incorporated Rev 0 changes. No changes needed per Rev 1 comments from Larson and Hedger.

Question Technical Review RO Draft Written Exam 2 February 20, 2014

1. Q 4 a. Rev 0 was Unsat due to K/A mismatch. How does question address operational implication of natural circ? See R0 comments.

2. Q7 a. Rev 0 identified question as Unsat since part 2 of all answers are unique. That is still true on Rev 3. What value is there in asking part 1 of the question?

b. Why did you put "on a Main Steam Isolation Signal (MSIS)" back into all answers? 3. Q 10 a. First bullet in stem

- refers to 80 gpm tube le ak, then next bullet says SG Tube Rupture. Would it be more accurate to call the 80 gpm leak a rupture?

4. Q11 a. In stem, the word "Demand" is misspelled (Deman).

b. In stem, the step in 2202.005 is 14, not 12. I have Rev 14 of the EOP. It is step 12 in the ESD Tech Guide, which is Rev 13. I'm guessing the EOPs and the ir Tech Guides are kept at the same revision so update question stem to step 14 and update References EOP

-2202.005 Basis Document to Rev 14.

c. Since the question is referencing a step in 2202.005, add 2202.005 to References.

d. Also, since the step is in quotation marks, change to "WHEN RCS T C less than 510°F, THEN reduce number of running RCPs as follows:"

e. Also, delete "Emergency Operating Procedure" after "step 14 of-"

f. Change Taxonomy from H to F. LOD is still 4.

g. In Notes, should be "greater th an three" 5. Q12 a. How did validation go for this question? I'm wondering what the value of the 2 nd part of the answer is since all answers are different for part 1.

b. In stem, change "RCS cooling-" to "RCS heat removal-" c. Also, change "Pump" to "pump" after Condensate.

d. Should we add as last bullet "CRS has entered OP

-2202.009, Functional Recovery EOP"?

6. Q 14 a. Recommend deleting "ONE (1)" in your database

- no revision required.

7. Q15 a. For "A" - should be status light (not lights)

b. For "B" - should be status light (not lights)

c. For "C" - should be status lights (not light)

February 21, 2014

1. Q17 a. Since question was replaced, change Taxonomy to F, LOD = 3.

2. Q18 a. Arrange answers shortest to longest: A

-B-C-D becomes D

-B-C-A. In short, swap A and D. Correct answer stays the same.

3. Q19 a. Arrange answers shortest to longest: A

-B-C-D becomes B

-C-A-D. Correct answer becomes "C" instead of "B"

4. Q20 a. Arrange answers shortest to longest: A

-B-C-D becomes A-D-B-C. Correct answer becomes "D" instead of "B"

5. Q 21 a. I'm crying Uncle on this question. I'm not convinced you can't write a question using the other K/A, but given the circumstances-On this question, answers A and D are marginally plausible.

Make sure ES

-401-2 and 4 get updated.

6. Q 22 a. Historical Comments state Rev 1 is due to correcting formatting

- I don't see any change. What changed?

7. Q24 a. Editorial edits:

- Second bullet: Delete "The", capitalize "Room" and "Cooling Tower"

- Stem: after "-at a MINIMUM, a(n) ________" vice just "a"

b. Recommend adding additional Notes to your database

- not required

8. Q 25 a. Rev 2 note says "Changed distractors and notes." What changed in the distractors?

b. Minor edit in stem

- third bullet, delete "The" Revision not required.

9. Q 26 a. Since no revision was submitted based on Examiner comments, I conclude you feel R0 meets the intent of the K/A

- yes? b. For "C" and "D"

- what is a Pressurizer High Point vent valve? Do they exist? What is the reference for them?

c. What reference identifies the location of the ECCS vent valves being on Panel 2C09? d. Why is Panel 2C336

-1 plausible?

e. Arrange answers shortest to longest: A

-B-C-D becomes C

-D-A-B. Correct answer becomes "C" instead of "A"

f. Third bullet

- delete first word "The"

10. Q27 a. This is an SRO

-only question (see p. 8 of Clarification Guidance for SRO

-only Questions). Removing "The CRS would diagnose" from the stem doesn't change the knowledge required. Revised the question to keep the same bullets (except that the SG tube leak is a rupture at 75 gpm), but ask what procedure would be entered (the operational implication is that two events requires entry into the FRP which is RO level knowledge). LOD=2, but it is what it is. A: SGTR EOP, B: ESD EOP, C: LOCA, D: FRP.

b. 2 nd bullet - change 0.12 to 75; change leak to rupture

c. 3 rd bullet - lower case "pressure, temperature and humidity"

d. 4 th bullet - capitalize "Monitors"

Rev 2 Question Technical Review RO Draft Written Exam 2 February 21, 2014

1. Q17 a. Since question was replaced, change Taxonomy to F, LOD = 3.

2. Q18 a. Arrange answers shortest to longest: A

-B-C-D becomes D

-B-C-A. In short, swap A and D. Correct answer stays the same. 3. Q19 a. Arrange answers shortest to longest: A

-B-C-D becomes B

-C-A-D. Correct answer becomes "C" instead of "B"

4. Q20 a. Arrange answers shortest to longest: A

-B-C-D becomes A-D-B-C. Correct answer becomes "D" instead of "B"

5. Q 21 a. I'm crying Uncle on this question. I'm not convinced you can't write a question using the other K/A, but given the circumstances-On this question, answers A and D are marginally plausible.

Make sure ES

-401-2 and 4 get updated.

6. Q 22 a. Historical Comments state Rev 1 is due to correcting formatting

- I don't see any change. What changed?

7. Q24 a. Editorial edits:

- Second bullet: Delete "The", capitalize "Room" and "Cooling Tower"

- Stem: after "-at a MINIMUM, a(n) ________" vice just "a"

b. Recommend adding additional Notes to your database

- not required 8. Q 25 a. Rev 2 note says "Changed distractors and notes." What changed in the distractors?

b. Minor edit in stem

- third bullet, delete "The" Revision not required.

9. Q 26 a. Since no revision was submitted based on Examiner comments, I conclude you feel R0 meets the intent of the K/A

- yes? b. For "C" and "D"

- what is a Pressurizer High Point vent valve? Do they exist? What is the reference for them?

c. What reference identifies the location of the ECCS vent valves being on Panel 2C09? d. Why is Panel 2C336

-1 plausible? e. Arrange answers shortest to longest: A

-B-C-D becomes C

-D-A-B. Correct answer becomes "C" instead of "A"

f. Third bullet

- delete first word "The"

Rev 2 10. Q27 a. This is an SRO

-only question (see p. 8 of Clarification Guidance for SRO

-only Questions). Removing "The CRS would diagnose" from the stem doesn't change the knowledge required. Revised the question to keep the same bullets (except that the SG tube leak is a rupture at 75 gpm), but ask what procedure would be entered (the operational implication is that two events requires entry into the FRP which is RO level knowledge). LOD=2, but it is what it is. A: SGTR EOP, B: ESD EOP, C: LOCA, D: FRP.

b. 2 nd bullet - change 0.12 to 75; change leak to rupture

c. 3 rd bullet - lower case "pressure, temperature and humidity

" d. 4 th bullet - capitalize "Monitors"

Rev 3 Question Technical Review RO Draft Written Exam 2 February 21, 2014

1. Q28 a. My notes show this question was identified as Unsat due to LOD=1. Even the Notes section states this is applying generic fundamentals (and the ref material is Generic Fundamentals training material), which isn't allowed on our exam. Do you have a Bank question for this K/A?

If not, I suggest a question where a malfunction of RCPs causes flow imbalance between SGs.

2. Q29 a. Changed LOD=3, recommend deleting "The" in third bullet. Revision not required. 3. Q 30 a. Notes say Rev 2

- corrected formatting of question. What changed?

b. Recommend deleting "The" from fourth bullet in database. Rev not required.

4. Q 32 a. Rev 0 comment

- how does this question meet both parts of K/A?

b. Any reason to not identify OP

-2203.018, Inadvertent SIAS AOP in the stem?

c. Arrange answers from shortest to longest: A

-B-C-D to B-D-C-A. Correct answer changes from "A" to "B"

d. Delete "The" from third bullet

e. In "B" and "C", capitalize "Containment Building"

f. In "D", lower case "pumps" following "Spray"

5. Q 33 a. Rev 1 states "based on NRC comments"

- I don't see that anything changed?

b. Third bullet

- lower case "pressure" c. Fourth bullet

- lower case "level"

d. Stem - add "in accordance with OP

-2103.007, Quench Tank and Reactor Drain Tank OPS" after "-to the Quench Tank is from ____ and" so make it the only correct answer. Explanation for "A" says it's possible to go to Containment Sump but not procedurally driven so need to remove all possibilities for appeals.

e. Stem -replace the word "drained" with "vented" to match procedure.

f. Explanations for "C" and "D" don't address part 2 of the answer.

6. Q35 a. Swap "C" and "D" so answers go from A

-B-C-D to A-B-D-C. Correct answer remains the same

- "B" b. Change LOD=3

7. Q36 a. Historical Comments, Rev 2 states "corrected formatting of question" What changed? b. Recommend deleting "The" in second bullet, and capitalize "Heater" after Backup in stem, and change LOD=3 in your database

- no revision required.

8. Q37 a. Arrange answers from A

-B-C-D to C-B-A-D. This changes correct answer from "C" to "A"

9. Q38 a. Arrange answers from A

-B-C-D to B-C-D-A. This changes correct answer from "A" to "B"

Rev 4 Question Technical Review RO Draft Written Exam 2 February 2 3, 2014 1. Q 43 a. Rev 2 - Notes say "With no operator action, SG levels would continue to rise until the HLO setpoint of 82% level was reached. At that point, the HLO signal goes around the Master controller and straight to the individual component controllers-" Is this correct? The answer "C" says operator action IS required to prevent a HLO from occurring. If the HLO signal "goes around the Master controller, why is operator action required? Also, OP-2106.007 says if the controller is in manual, HLO signals can NOT perform their function.

b. Is the stem correct to say "prevent a HLO from occurring" or should it say "minimize moisture carryover?"

2. Q 44 a. Is it normal for 2P-75 to be running for the conditions given in the stem (startup completed, raising power, current power 5%

and trending up)? If so, when is 2P

-75 procedurally secured?

b. "A" - Part 1 states the FCS will automatically raise 1B speed and SG levels will be maintained at setpoint, but part 2 says to place 1B in service- how can part 1 be true if 1B isn't in service? Not plausible

. Also, the Notes for "A" discuss 2P

-75, not raising 1B speed. Why not use a 2x2 question format? Part 1 is either automatically maintain SG levels at setpoint OR require manual operator action to restore SG levels to setpoint. Part 2 is either place "B" Main Feedwater pump (2P-1B) in service OR attempt to restart "A" Main Feedwater pump (2P

-1A). (This is what the Examiner proposed to Revision 1.)

3. Q45 a. Comment to Rev 1 wasn't addressed: What is significance of 15 minutes after trip? Is it a carryover from Rev 0? If left in the question, does it have the possibility of confusing the applicants?

b. Comment to Rev 1 wasn't addressed: Why is 150 gpm plausible for "A" and "C

?" 4. QQ47 a. For you database

- recommend putting "bus" at end of stem and remove from each answer, adding commas after bus in "A" and "B" (like "C" and "D"), and Notes should identify at least one major load for each distractor. Rev not required. b. Adding the voltage of the bus could be considered cueing (applicant could reduce incorrect choices by half just knowing RCPs are 6900 V). Revision not required. c. Not just related to this question, but why did you remove question numbers from the ES-401-2? How do you relate a K/A to a specific question?

5. Q48 a. Changed LOD=3 and Taxonomy changed to H. No revision required.

6. Q49 a. Comments were provided on Rev 1

- we re they addressed? Comments:

The change did not address the concern.

The basis for the proposed correct answer says that the loss of 125 VDC control power prevents any "remote manual operations." Based on Answer C's wording, Rev 4 "local manual means" must be available as the only option for operating the affected breakers.

When the wording of distracter B is reviewed, it says "Breakers would be able to be operated remotely.." Is operating a breaker by "local manual means," considered "remotely?" An applicant could argue if this is vague that operating the breaker by local manual means can be completed outside the Control Room, so it is "remote." If there is a specific site definition for "remotely" that will ensure that distracter B is not correct, it needs to be documented in the question notes. If there isn't a basis, the next best thing would be to modify distracter B to say "Breakers would be able to be manually operated remotely,.

." The goal is to have all the terms clear so that there is no room to argue that there are two correct answers.

b. Answers are adequate, but more complicated than necessary for LOD=2 knowledge.

c. If the question or format is changed, then swap "C" and "D" for shortest to longest. This will change right answer from "C" to "D"

7. Q 50 a. Comments on Rev 0 said Bank, not Mod Bank. Why still Mod Bank?

8. Q52 a. Change Taxonomy from H to F. Rev not required.

9. Q53 a. Update database: LOD=3, add "the" to stem "be aligned to the Spent Fuel-" Revision not required.

10. Q55 a. Add "greater than" to post

-RAS flow per LOCA EOP, step 22.C. Should read "-and greater than

_____ gpm post RAS."

11. Q56 a. Arrange answers from A

-B-C-D to B-C-A-D. This changes correct answer from "B" to "C"

b. Change taxonomy from H to F.

c. In stem, change "- the following set s of conditions-"

12. Q57 a. Arrange answers from A

-B-C-D to B-D-C-A. Correct answer remains "C"

13. Q58 a. Change taxonomy from H to F.

b. Prefer shortest to longest, not longest to shortest.

c. Rev not required.

14. Q59 a. Update your database: second bullet, annunciator alarm in all caps; third and fourth bullet, "Level" is "level." No rev required.

15. Q60 a. How does this question address either part of the K/A? Predicting the impacts (detonation

- which is given in the stem) and no procedure is referenced in the stem or identified as a Reference.

b. Notes section doesn't address why 90 minutes is plausible, other than 20 + 70 = 90. Why is 90 min important.

Rev 4 16. Q 61 a. Third part of all answers (supply/exhaust fan trips 10 seconds later) is not required as it offers no discriminatory value. 2 x 2 format.

b. Change taxonomy to H

c. Question is Bank, not Modified.

17. Q62 a. In stem: Capitalize "Monitors," and "Control Room"

b. Arrange shortest to longest: A

-B-C-D to C-D-A-B. Would change correct answer from "B" to "D"

c. Rev not required.

18. Q63 a. LOD = 3 b. First bullet: Capitalize "Condenser"

c. Second bullet: Capitalize "Atmospheric Dump Valves"

d. Fourth bullet: delete "The"

e. Rev not required

19. Q66 a. K/A mismatch

- How does knowing what symbol is used for Harsh Containment conditions equate to evaluating plant performance and making operational judgments based on operating characteristics, reactor behavior and instrument interpretation?

20. Q67 a. Ensure ES-401-3 and -4 get updated.

21. Q70 a. LOD=3, rev not required.

22. Q71 a. LOD=3 b. Delete "The" from 2 nd and 3 rd bullets c. Based on last sentence of Notes section, is a PIF required?

d. Revision not required.

23. Q72 a. Co uld reword stem to eliminate all bullets, but not wrong as is.

"To prevent an inadvertent radiological release during implementation of OP

-2203.038, Primary to Secondary Leakage AOP, the initial actions of -"

b. Taxonomy is F, not H

c. Delete "The" from 4 th bullet d. Question is Modified Bank

e. "A" - aligning Condensate flow to 2T-94B-DI f. "B" - are the fans 2VEF

-8s or 2VEF

-8S? g. "C" - securing Turbine Building Sump pumps to Unit 1 Oily Water Separator (seems more accurate to secure a Sump pump than to secure a Sump)

h. "D" - isolating discharge flowpath from Unit 1 Oily Water Separator to Lake

i. Recommend adding Notes to identify why distracters are plausible

j. Rev not required unless "C" is changed by adding the word "pump"

24. Q73 a. LOD=3 b. Could delete first 3 bullets, but not wrong as is

c. 3 rd bullet: "Hydrogen Peroxide"

d. 4 th bullet: "General area dose rate in "A" pump room-"

e. 5 th bullet: Delete "The"

f. 6 th bullet: Delete "CRS has sent CBOT into Auxiliary Building to help WCO"

g. "CBOT is knowledgeable about dose rates in "A" ESF pump room"

h. Stem: Delete "The" and lower case "personnel"

Question Technical Review SRO Draft Written Exam 2 Generic Question:

1. Why do most of the SRO-only questions have RO lesson plans identified?

Are there SRO lesson plan numbers available?

1. Q76 a. Will a 1% change in PZR level cause a change in Letdown? Concern is that the PZR level control system will automatically adjust to a lowering level so the info in the question stem would not be accurate. PZR level would not be 59% in 3 minutes if the level control system responds as designed.

b. The value used for Volume vs Level for the PZR is not correct. Per the ref, it is 53.5 gal/%, not 55.3. This affects the leakrate calculation (29.1 gpm vs 29.7) but doesn't affect the correct answer since it is still within the capacity of available CCP's. c. The Notes section states "SIAS would be actuated due to the RCS leakage"

- is this true? With two available CCPs (B & C) after the Reactor trip, how will pressure lower enough to initiate an SIAS with only a 29.1 gpm leak?

d. Explanation for "C" is incorrect

- the second half should state that is it plausible because the applicant may not recognize Excess Leakage plus LOOP is LOCA EOP. 2. Q: 88 a. Question on Rev 0 asked why just "A" spray pump since procedure says "both."

Note on Rev 1 says "Only the "A" Spray pump inadvertently starts in this scenario. "B" Spray pump is not running." How does the applicant know this?

3. Q: 90 a. This is the second question that tests Excess RCS Leakage AOP combined with a LOOP = LOCA EOP.

4. Q92 a. Not having a procedure for this event could be an Appendix B violation. Make sure this gets submitted for evaluation after the exam is completed.

Does ANO still think this question should be used on the written exam?

5. Q95 a. Comment on Rev 0 stated COPD

-030 could be correct and identified page 10, Section 4.5, 11 th bullet. Rev 1 Notes says COPD

-030 not correct but identified Section 5, Step 5.5. What about Section 4.5, 11 th bullet since it specifically identifies "transients?" Could the applicant argue this bullet also makes Answer B as correct? Also, recommend adding the applicable AOP to the Notes section to directly relate given conditions in the stem do constitute entry into an AOP, thus making COPD

-030, Step 5.5 more applicable.

6. Q98 a. FYI - changed LOD to 4. Also, Notes don't appear to have been updated. No revision required but updates should be made to your database

. 7. Q99 a. FYI - changed LOD to 3. No revision required.

8. Q100 a. Second bullet

- Rev 0 identified "Owners" should be "Owner" but not corrected. If okay with ANO, no revision is required but you should correct in your database.